ML20084N241

Rev 0 to Drill Scenario 4B

ML20084N241
Person / Time
Site:	Indian Point
Issue date:	05/16/1984
From:	CONSOLIDATED EDISON CO. OF NEW YORK, INC.
To:
References
PROC-840516, NUDOCS 8405160399
Download: ML20084N241 (120)

Text

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4 CONSOLIDATED EDISON COMPANY OF NEW YORK INDIAN POINT UNIT NO. 2 DRILL SCENARIO NO. 4B REV. O O

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(_/ CONSOLIDATED EDISON COMPANY OF NEW YORK INDIAN POINT UNIT NO. 2 DRILL SCENARIO NO. 4B REV. O TABLE OF CONTENTS Section I. Introduction II. Objectives III. Drill Scenario IV. Messages V. Observer / Controller Instructions VI. Plant Status Log rm VII. Radiological / Meteorological Log v)

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VIII. Radiological Information IX. Logistics

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l r^% CONSOLIDATED EDISON COMPANY OF NEW YORK

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INDIAN POINT UNIT NO. 2 DRILL SCENARIO NO. 4B REV. O I. INTRODUCTION Tha purpose of this drill is to demonstrate Con Edison's capability to effectively implement the Indian Point Unit No. 2 Site Emergency Plan and Procedures.

To assist the drill Observer / Controllers in the conduct and evaluation of the drill, this document has been prepared. It contains all the information and data necessary to properly conduct the drill in an efficient and coordinated manner and is broken down as follows:

Section II objectives -

this section defines the drill objectives.

Section III Drill Scenario -

this section describes the Indian . Point _ Unit NO. 2 postulated sequence of events occurring which will require the onsite emergency f-s response organizations to respond. For each event

( / described, the anticipated results of the participants are also detailed. These results should be used as a guide in evaluating the drill. However, it should be noted that the results observed may vary from those stated and should be evaluated on a case-by-case bas'is with respect to applicable procedures.

Section IV Messages -

this section contains copies of the drill messages which will be utilized to control the progress of the drill scenario.

Section V Observer / Controller Instructions - this section provides general instructions to the drill Observers and Controllers in the conduct of the drill.

Also included is evaluation criteria for evaluating the responses of the drill participants.

Section VI Plant Status Log -

this section contains time-related information (non-radiological) concerning plant conditions, which corresponds to the development of the drill scenario.

Section VII Radiological / Meteorological Log -

this section contains time-related plant radiological and meteorological data which corresponds to the qlh development of the drill scenario.

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SCENARIO NO. 4B REV. O Section VIII Radiological Information - this section contains time-related radiological information in the l

) following categories:

o Primary Coolant Activity o Containment Activity o Release Path Activity i o Plant Radiation Levels o Facility Radiation Levels o Reuter-Stokes Readings o Plume Monitoring Data & Figures o Offsite TLD Readings o Post Accident Samples o

Pose Accident Offsite Contamination LevelsSection IX Logistics - this section contains information and direction for the handling of peripheral items related to the day of the drill.

o Food for participants o Access lists o

Methods of identification of players, controllers, observers, visitors, etc.

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/ ) CONSOLIDATED EDISON COMPANY OF NEW YORK INDIAN POINT UNIT No. 2 DRILL SCENARIO NO. 4B REV. O II. OBJECTIVES A. Emergency Operations. Facilities and Resources

1. Demonstrate the adequacy of the staffing and setting up as appropriate of emergency response facilities as well as demonstrating the adequacy of space and habitability for management of radiological emergency at:

o Control Room (CR) o Technical Support Center (TSC) o Operational Support Center (OSC) o Emergency Operations Facility (EOF) o Emergency News Center (ENC) limited to 4 Irving Place

2. Evaluate the adequacy of access control and security for emergency response facilities.

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k 3. Demonstrate the Indian Point communication capabilities among the Control Room (CR),

Technical Support Center (TSC). Emergency Operations Facility (EOF) and Operations Support Center (OSC).

4. Demonstrate emergency communications capability among the Counties, the State and Indian Point including the Radiological Emergency Communications System (RECS-Hot Line).

5. Demonstrate the ability of Indian Point to coordinate, control and deploy radiological monitorinr, teams via the respective field communications system.

B. Alertina and Mobilisation of Officials and Staff

1. Demonstrate the ability of Indian Point staff to classify actual or potential emergencies in accordance with Indian Point Emergency Plan Implementation Procedures as tot o Notification of Unusual Event,

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Alert Site Area Emergency, General Energency.

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SCENARIO NO. 4B REV. O

2. Demonstrate the capability of Indian Point to f'd- } notify the State, local and Federal levels of government in accordance with Federal guidance and established protocols.

3. Demonstrate the capability to communicate technical information among Indian Point, the State, and Counties. The extent of the interface with the offsite authorities will be limited because of the reduced level of participation. Indian Point will also demonstrate communicating with the NRC via the NRC Hot Line.

4. Demonstrate the capability of Indian Point to notify and activate emergency response personnel.

C. Emergency Operations Management

1. Evaluate the adequacy and capability of implementation of the Indian Point radiological emergency plans.

2. Demonstrate the emergency response capabilities of Indian Point.

t~ 3. Demonstrate the capability of Indian Point to implement their radiological emergency preparedness plans in a manner satisfying NRC acceptance criteria.

4. Demonstrate the ability of key emergency personnel at Indian Point to initiate and coordinate timely and effective decisions with respect to a radiological emergency and clearly demonstrate "who is in charge."

5. Demonstrate that there is effective organizational control (direction and control) and integrated radiological emergency response including deployment of field monitors, and receipt and analysis of field data.

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l SCENARIO NO. 4B REV. O gg D. Accident Assessment dj -

1. Demonstrate the ability of Indian Point to receive and assess radiological data from field teams in accordance with the emergency plan i implementation procedures. ..

2. Demonstrate the ability of Indian Point to calculate dose projections, compare the projections to the Protective Action Guides (PAGs) and determine appropriate protective actions. i

3. Demonstrate the activation, operations and reporting procedures of Indian Point field monitoring teams. Indian Point teams will be dispatched within and beyond the site boundary. >

E. Actions to Protect the Public

1. Demonstrate the capability of emergency personnel to identify requirements, assess and  !

implement procedures for reentry. l F. Health, Medical and Exposure Control Measures

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1. Demonstrate Indian Point employee account-ability following the requirements of the Emergency Plan Implementing Procedures.

2. Demonstrate the decision process for limiting exposure of emergency workers.

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CONSOLIDATED EDISON COMPANY OF NEW YORK 1

3 INDIAN POINT UNIT NO. 2 DRILL SCENARIO NO. 4B REY. O i

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i III. DRILL SCENARIO

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i. Initial Conditions 4 Con Ed Indian Point Unit No. 2 has been

operating at full power for 60 days. All plant j parameters are normal and stable. The i containment is being pressure relieved via the i normal path.

j Narrative Summary A tremor is felt in the Control Room. No alarm 2

annunciation is indicated and the Unit continues to operate wth no interruptions. The Unit No. 3 Watch Supervisor notifies the Unit No. 2 Control Room that

{ two amber lights on the Peak Shock Annunciatior are J lit.

After analysis of the accelerometer, the. Unit No. 3

Watch Supervisor notifies the Unit No. 2 Control Room the horizontal and vertical indication is large enough to declare an ALERT.

4 i Approximately 100 individuals have been previously l designated to participate in assembly / accountability.

} After accountability has been performed non-players will be dismissed from the drill and returned to their normal work locations, i

Later Rod Cluster Control Assembly (RCCA), Bank D.

i is ejected from the reactor core resulting in.a small loss-of-coolant accident (LOCA). The reactor and

{ turbine both trip, i

As reactor coolant system (RCS) pressure and

, temperature decrease, Safety Injection is j initiated. One of the three High Pressure Safety Injection Pumps (#21) fails to start, the 4

other two operate normally. On receipt of the-

! containment isolation signal, the two pressure i

relief valves outside containment fail to close.

, The inside valve does close, however, securing i containment pressure relief.

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SCENARIO NO. 4B REV. O The LOCA causes a " Site Area Emergency" to be declared.

(-] The motor-driven auxiliary feedwater pumps start

(_/ normally and begin to provide feedwater to the steam generators. At this time, an offsite electrical power disturbance causes a loss of all offsite power. In response to this, Emergency Diesel Generators Nos. 21, 22 and 23 all start normally. Vital loads are properly sequenced onto the emergency power supply except both motor-driven auxiliary feedwater pumps fail to start.

No. 22 Auxiliary Boiler Feed Pump and No. 22 High Pressure Safety Injection Pumps are out on Limiting Condition for Operation (LCOs) for corrective mainten-ance. This results in no feedwater being supplied to the steam generators and only one High Pressure Safety Injection Pump in operation. At this point, a

" General Emergency" should be declared. All steam generators boil dry resulting in a loss of the primary heat sink for the reactor. RCS temperature and pressure rapidly increase because only one HPSI pump supplying water to the core in a natural circulation mode is insufficient to remove decay heat. All power operated relief valves (PORVs) fail to open at the prescribed pressure.

Consideration may be given to opening the reactor head vent valves for a cooling path but this flow would be inadequate for core cooling. Due to the loss of heat

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sink and loss of bleed capability through the PORV, steam-blanketing of the core results in the Control Room receiving indications of fuel damage.

Subsequently, indications in the Control Room indicate the remaining closed containment Pressure Relief Valve (PCV-1192) fails OPEN. Initial attempts to close all valves fail.

Control Room instrumentation indicates high radiation levels in the plant ventilation system. Radiogas monitors indicate significant releases are occurring.

Eventually, the problem with the motor driven auxiliary feedwater pumps is corrected and the pumps are started.

Feedwater flow is restored to the steam generators.

Maintenance ~ teams manage to repair and close valve PCV-1191 of the Containment pressure relief system.

This action terminates the release from the plant.

Operations continue in.a long-term cooling mode to cold shutdown.

The exercise will last approximately seven (7) hours.

Duration of the radiological release will be 1-1/2 I hours. The exercise will be completed after the 4)7' release is terminated and the plant is in.a controlled and stable condition. A Recovery phase will not be demonstrated.

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l r SCENARIO NO. 4B REV. 0 1 i

DETAILED SCENARIO TIME LINE INITIATING MESSAGE

, TIME NUMBER EVENT

SUMMARY

1 T = 08:00 1 Initial Conditions established.

I j T = 08:10 2 A tremor is felt in the Control

. Room. No alarm annunciation is l indicated. Unit continues to operate with no interruptions.

T = 08:15 3 Unit No. 3 Watch Supervisor calls i to say that they felt the tremor j and two-(2) amber _ lights lit on the Peak Shock Annunciation. He will call back as soon as the ground acceleration indication has been

, analyzed. Unit No. 3 will remain on the line until the evaluation is completed.

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(() ANTICIPATED RESULTS Senior Watch Supervisor (SWS)

-Follows " Abnormal Operating Procedure A-42.

-Declares a Notification of Unusual Event because of NUE Initiating Condition No. 13(a).

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-Fills out " Emergency Notification Fact Sheet, Part I."

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-Directs the " Communicator" to make the appropriate notifications in accordance with IP-10.2.

T = 08:25 3A The SWS should declare an NUE at i

this time'and initiate appropriate i

actions and notifications if not l already done.

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i SCENARIO NO. 4B REV. 0 f:(~)T 8

DETAILED SCENARIO TIME LINE INITIATING MESSAGE l TIME NUMBER EVENT

SUMMARY

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I T = 08:45 4 Unit No. 3 Watch Supervisor calls to say that the evaluation of the accelerometer indicates a 0.11 g i horizontal and 0.04 vertical displacement. He also indicates that Unit No. 3 will remain on the line.

ANTICIAPTED RESULTS Senior Watch Supervisor (SWS)

-Declares an ALERT and directs the

CR0 to sound the Site Emergency j Assembly Alarm. Declaration of ALERT is because of Initiating Condition 17(a).

j -Mobilizes emergency personnel.

-Fills out " Emergency Notification Fact Sheet, Part I."

-Directs.the " Communicator" to make appropriate notifications in accordance with IP-1002.

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SCENARIO NO. 4B REV. O DETAILED SCENARIO TIME LINE INITIATING MESSAGE TIME NUMBER EVENT

SUMMARY

Plant Operations Manager (POM)

Reports to the Control Room and discusses the emergency, plant status, initiating conditions and classification with the SWS.

Meets Offsite Rad Assessment Director (ORAD) and TSC personnel at the SWS office. Assigns

,' individuals to fill the positions of ORAD and TSC Manager.

Assumes Emergency Director (ED) position.

Discusses protective actions with ORAD. None Required.

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Evaluates possiblility of taking the Unit off the line

l Shift Technical Advisor (STA) l Assists SWS and POM with system j information.

$ Offsite Radiological Assessment Director (0 RAD)

- Obtains two (2) onsite monitors, four (4) offsite monitors-and one (1) communicator before or after 1

reporting to the EOF as conditions dictate. '

- Activates EOF and lists personnel 5

on status board.

i' - Starts to activate personnel too fill all positions at the EOF, except for the ED.

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SCENARIO NO. 4B REV. O DETAILED SCENARIO TIME LINE e INITIATING

'k, MESSAGE TIME NUMBER EVENT

SUMMARY

Chief Accountability Officer (CAO)

Set up operation at the OSC (i* 10?.3) and performs accountability for the site.

- Assigns reporting personnel to waiting areas within the-OSC.

- Assigns personnel to repair teams.

- Has status boards maintained.

Technical Support Center Manager (TSC Managegl,

- Activates TSC and mobilizes personnel (IP-1035).

- Provides technical support to SWS and POM.

Evaluates plant data.

T= 08:55 4A The SWS should declare an ALERT at this time and initiate appropriate actions and notificatione if not already done.

ANTICIPATE RESULTS Senior Watch Supervisor (SWS)

- Confers with the POM to discuss the message from the Unit No. 3 Watch Supervisor.

- Tells the POM that the inspection team

.has not reported back yet.

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l i l SCENARIO No. 4B REV. O t

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DETAILED SCENARIO TIME LINE  :

i I INITIATING ,

MESSAGE i TIME NUMBER EVENT

SUMMARY

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T = 09:10 5 The damage survey team reports no

! evidence of damage to plant structures or

equipment.  ;

4 Plant Operations Manager (POM) i i

Decides to maintain the operating status I

of the Unit.

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T = 09

10 6 If the site accountability has been

(or later) completed, the POM (ED) is notified

but within I hr. that all personnel not assigned to 1

of time ordered a facility (EOF, TSC, OSC, CR) may i return to their normal duties.

otherwise defer the message to the i appropriate time.

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SCENARIO NO. 4B REV. O DETAILED SCENARIO TIME LINE

\ INITIATING i

~'b~ MESSAGE TIME NUMBER EVENT

SUMMARY

T = 09:10 7 Rod Cluster Control Assembly (RCCA), Bank "D" has been ej ected from the Reactor core, resulting in

, a small loss-of-coolant accident (LOCA).

The reactor and turbine both " trip" on high power. The steam dump system activates and functions normally.

As RCS temperature and pressure decrease, Safety Inj e c tion initiates. One of the three High Pressure Safety injection Pumps (No. 21) fails to start; the other two operate normally. On receipt of the Containment isolation sig-nal, the two pressure relief valves outside Containment fail to close

% (PCV-1191 and PCV-1192). -The in-side valve (PCV-1190) does_close

[ however, securing containment purge. The motor-driven auxiliary feedwater pumps start normally'and provide flow to the-steam gener-

.ators. Control Room indicators are as follows:

o Pressurizer Low Pressure:and-Level o Reactor. Trip o Turbine Trip o Safety Injection-ANTICIPATED RESULTS Control Room Operator (CRO)

- Refers-to Emergency Procedures.

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SCENARIO NO. 4B REV. O DETAILED SCENARIO TIME LINE INITIATING d(

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) MESSAGE TIME NUMBER EVENT

SUMMARY

Senior Watch Supervisor (SWS)

- Discusses plant / emergency status with the POM, including the need for RCS and VC samples.

Plant Operations Manager (POM)

- Discusses and reviews plant status, emergency action levels, initiating conditions and emergency classification with SWS and TSC Manager.

- Declares a SITE AREA EMERGENCY because of Initiating Condition No. 1.

- Fills out " Emergency Notification Fact Sheet, Parts I and III".

- Direct the " Communicator" to make appropriate notifications in

! accordance with IP-1002.

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- Notify individual who will take over Emergency Director duties at EOF.

Give appropriate instructions to Security Supervisor.

- Direct in-plant radiglogical monitoring. Initiate a security fence survey.

- Direct ORAD to initiate a site perimeter survey.

Direct actions to mitigate emergency conditions.

Turn over control of the emergency to the Emergency Director upon his arrival at the EOF.

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SCENARIO NO. 4B REV. O DETAILED SCENARIO TIME LINE

< /~' INITIATING s MESSAGE TIME NUMBER EVENT

SUMMARY

Radiation Protection Technician (RPT)

Provides radiological control for the Control Room, including set up of Step-Off Pad and "frisker" at entrance from turbine floor to SWS office; or as directed by the SWS.

Perform surveys requested by SWS ,

or POM.

Evaluate PRM-ARM instrumentation.

- Determine status of controlled area evacuation, and report to SWS.

- Maintain Log Book.

Offsite Radiological Assessment (O Director (ORAD)

- Check information obtained from TSC.

- Perform necessary dose projections. Determine-recommended Protective Actions using IP-1013. Review these with ED or POM. No release is

. occurring yet; however, Protective Action recommendations could require " consideration" of evacuation of a 2 mile radius and 5 miles in the three' downwind sectors, and sheltering in the remainder of the 10 mile EPZ. No offsite Protective Actions recommendation at this time is also acceptable.

Confer with Dose Assessment H.P.

and dispatch offsite monitoring teams co specified. environmental r- ' sampling / survey points if there

. (, has been a release, s.

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SCENARIO NO. 4B REV. O DETAILED SCENARIO TIME LINE e INITIATING l

( MESSAGE l TIME NUMBER EVENT

SUMMARY

- Initiate mobilization of the f

complete EOF staff, with the exception of the Emergency Director, if not already done.

- Fill out " Emergency Notification Fact Sheet, Part II" (Form 30b) and confer with the Emergency Director.

TSC Manager

- Transmit plant data to EOF.

Investigate failure of High Pressure Safety Injection Pump No. 21 to start, and failure of PCV-1191 and PCV-1192 to close.

- Support Control Room and maintenance activities.

-[ OSC Coordinator

- Repair teams may (or may not) be sent out to manually start Safety Injection Pump No. 21, and close PCV-1191 and PCV-1192.

Emergency Director (ED)

Report to the EOF and assume overall direction and control of the emergency from the POM.

- Discuss potential actions with POM and ORAD.

- Evaluate conditions and declare'a Site Area Emergency-if not already done.

- A precautionary recommendation to SHELTER in the two:(2) mile radius and five (5) mile downward could also be considered.-

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- No offsite Protective Action recommendation at this time is-t, also acceptable.

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SCENARIO NO. 4B REV. O DETAILED SCENARIO TIME LINE

/"] INITIATING bd MESSAGE TIME NUMBER EVENT

SUMMARY

If required ensure offsite authorities are notified of recommended Protective Actions.

Survey Team Health Physicist (STHP)

- Check equipment availability.

Perform field survey at EOF; including set-up of TRITON in accordance with IP-1041, and set-up of SAM-2/RD-22 and RM-14/HP-210 Counter and Air Sampler in accordance with IP-1020.

- Obtain two ( 2 )' H a n d'i - T a l k i e s from Security.

- Assign film badges and dosimeters.

- Set-up FRISKER and Step-off Pad at upper and lower entrance of EOF.

- Perform appropriate surveys approximately every 30 minutes.

Follow and maintain personnel exposure and contamination control for all personnel.

- Confer with ORAD and dispatch onsite field survey teams and receive data. Place field survey readings on Site Map.

T = 09:25 8 The Emergency Director should

declare a SITE ~ AREA EMERGENCY and initiate appropriate actions and notifications if it'has not already been done.

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SCENARIO No. 4B REV. O DETAILED SCENARIO TIME LINE l

M INITIATING

(. MESSAGE TIME NUMBER EVENT

SUMMARY

T= 09:40 9 RCS cooldown is taking place and the reactor is in a stable condition. The Charging Pumps and Safety Injection have stabilized RCS pressure at 1200 psig, and are continuing to p_rovide makeup for coolant lost through the RCCA LOCA.

RCS Tavg is constant at 500 F.

It is estimated that cooldown of the RCS will take approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

Radiation monitors R-2, R-7, R-ll and R-12 ALARM.

ANTICIPATED RESULTS Control Room' Operator (CRO)

- Review Abnormal Operating f O Instructions A-19.A and A-19.B.

Area Radiation Monitors - High Radiation and High Activity -

Containment Air Particulate Monitor R-ll and/or Containment Radiogas Monitor R-12.

Senior Watch Supervisor (SWS)

- Discuss plant / emergency status with POM.

Radiation Protection Technician (RPT)

- Perform surveys if requested by SWS and POM.

- Evaluate PRM-ARM instrumentation.

, - Obtain Protected Area Fence Survey, if directed by-the SWS or POM.

Maintain Log Book.

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SCENARIO NO. 4B REV. O DETAILED SCENARIO TIME LINE l

/ INITIATING 6- MESSAGE TIME NUMBER EVENT

SUMMARY

T= 10:10 10 A disturbance in the offsite electric power system grid causes a loss of all offsite power. Power transfers to the emergency bus.

Diesel Generators Nos. 21, 22 and 23 all start normally. Vital loads are properly sequenced onto the emergency power supply except for both motordriven Auxiliary Feedwater Pumps, and No. 22 High Pressure Safety Injection Pump fails to start. No feedwater is being supplied to the Steam Generators, and only one High Pressure Safety Injection Pump is 1

in operation.

Indications to the operator are as follows:

("% o 6900 Volt Station Auxiliary

( Breakers trip.

o 480 Volt Switchgear Motor trips.

o Emergency Diesel Generators Nos.

21, 22 and 23 start.

o Auxiliary Feedvater Pumps Nos.

21 and 23 fail to start.

o HPSI 22 fails to start.

ANTICIPATED RESULTS Control Room Operator (CRO)

- Review Abnormal Operating Instruction A-4, " Loss of Outside Power."

Report any accident condition changes to SWS or STA, and maintain Log Book.

Senior Watch Supervisor (SWS)

Inform and confer with the POM.

rw 3, Plant Operations Manager (POM)

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(;< - Confers with the SWS snd then with ED.

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SCENARIO NO. 4B REV. O DETAILED SCENARIO TIME LINE INITIATING 1h_'/f' } MESSAGE TIME NUMBER EVENT

SUMMARY

- Direct the OSC Coordinators to form a repair and corrective action team (per IP-1011) to check the status of the auxiliary feed pumps and SI pumps.

Direct the OSC Coordinators to send a Chem Tech to obtain a RCS sample.

- Direct the OSC Coordinators to send a Chem Tech to obtain a containment air sample.

Offsite Radiological Assessment Director (ORAD)

- Check information obtained from TSC.

Perform necessary dose projections. Determine fO k

recommended Protective Actions using IP-1013. Review these with the ED. Protective Actions may at this time include evacuation of a two (2) mile radius and sheltering in the remainder of the ten (10) mile EPZ.

No change in Protective Action recommendations at this time is not acceptable.

Till out " Emergency Notification Fact Sheet, Part II" and confer with the Emergency Director.

Dose Assessment Health Physicist (DAHP)

Calculate proj ected of f site exposures at the Site Boundary, 2 miles, 5 miles and 10 miles.

Discuss results with ORAD.

Check recommended Protective Os' Actions (IP-1013).

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SCENARIO NO. 4B REV. O DETAILED SCENARIO TIME LINE

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INITIATING MESSAGE TIME NUMBER EVENT

SUMMARY

- Project future survey / sampling points.

TSC Manager

- Transmit plant data to EOF.

Support Control Room and maintenance activities.

Emergency Director-(ED)

Obtain latest prognosis from POM.

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Evaluate conditions and declare a General Emergency because major parts of-Initiating Conditions 3, 4a, 4b & 4d and associated Emergency Action Levels have been satisfied and plantiparameters indicate worsening conditions.

{~ - Discuss Protective Actions with the ORAD. Protective Action recommendations should include:

o Evacuation in a 2 mile radius, o Sheltering for the remainder of the 10 mile EPZ.

- No change in Protective Action recommendations at this time is.

acceptable if the above recommendation had been given.for the SAE.

i- - Fills out " Emergency Notification Fact Sheet, Part I" and has >

Technical Advisor (TA) complete Part III. Part II not requirad' because there is no release to the environment.

.Have offsite authorities notified.

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I SCENARIO NO. 4B REV. O i

DETAILED SCENARIO TIME LINE A INITIATING i

\.\- ~ MESSAGE TIME NUMBER EVENT

SUMMARY

T = 10:25 11 The Emergency Director should declare a GENERAL EMERGENCY and initiate appropriate actions and notifications if it has not al-ready been done.

t T= 10:25 12 Attempts to load the gas turbine generators are unsuccessful, i

T= 10:25 13 All Steam Generators boil dry, resulting in the loss of the primary heat sink for the Reactor.

ANTICIPATED RESULTS Control Room Operator (CRO)

- Report any accident. condition changes to SWS or STA, and maintain Log Book.

(~ Senior Watch Supervisor (SWS)

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Inform and confer with the.POM.

l T= 10:35 14 The Power-Operated Relief Valves (PORVs) fail to OPEN at the prescribed pressure.

ANTICIPATED RESULTS Control Room Operator (CRO)

Report any accident condition ,

changes to SWS or STA, and maintain Log Book.

Senior Watch Supervisor (SWS)

- Inform and confer with-the POM.

T= 10:40 15 Due to loss of heat sinks and loss of bleed capability through the PORVs, the Control Room is alerted to potential fuel cladding failure by the following:

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o Area Monitor'High Radiation Alarm vge o Failed fuel-monitor-indicates high activity III-17

SCENARIO NO. 4B REV. O DETAILED SCENARIO TIME LINE f INITIATING j

% MESSAGE i TIME NUMBER EVENT

SUMMARY

ANTICIPATED RESULTS Control Room Operator (CRO)

- Review Abnormal Operating Instruction A-20, "High Activity /

Reactor Coolant System."

- Report any accident condition changes to SWS or STA, and maintain Log Book.

Senior Watch Supervisor-(SWS)

Inform and confer with the POM.

Plant Operations Manager (POM)

- Direct OSC Coordinators to send a Chem Tech to obtain a RCS sample.

Note: The taking and counting of rO

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this sample may be simulated.

controller is to hand the team the The data after they have arrived at the sample site.

Offsite Radiological Assessment Director (ORAD)

- Check information obtained from the TSC.

- Perform necessary dose p roj ec tions . Determine recommended Protective Actions using IP-1013. Review these with ED. 'Offsite Protective Actions should be increased at this time.

- Project future survey / sampling points.

Dose Assessment Health Physicist (DAHP)

Calculate projected offsite

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) exposures at the Site Boundary,' 2' g ,. miles, 5 miles and 10 m'les.

Discuss with' ORAD. l l

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SCENARIO NO. 4B REV. O DETAILED SCENARIO TIME LINE INITIATING s#}

lyr MESSAGE TIME NUMBER EVENT

SUMMARY

i Check recommended Protective 1 Actions (IP-1013). j l

- Project future survey / sampling l points.

Emergency Director (ED)

- Discuss Protective Actions with the ORAD, POM and TSC Manager.

Protective Action recommendations should be increased at this time to include.

o Evacuation out to 10 miles in Sectors 4, 5, and 6.

o Evacuation out to 5 miles for remaining sectors.

o Sheltering for the remainder of the 10 mile EPZ.

- Fills out " Emergency Notification

% ,/ Fact Sheet, Part I" and has l -

Technical Advisor (TA) complete Part III. Part II is not required because there is no release to the environment.

- Has offsite authorities notified.

1 T= 11:10 16 The Control Room annunciators indicate that the remaining closed Containment Pressure Relief Valve

-(PCV-1190) has failed in the OPEN position. Initial attempts to close'all valves-fail.

T= 11:15 17 Control Room radiation. monitors indicate high levels in the plant-ventilation system. ARM R-13.and R-14 both ALARM.

ANTICIPATED RESULTS Control Room Operator (CRO) '

Follow Abnormal Operating O'

l 7- Instructions A-19.C, "High l L, i . Activity Plant-Vent Particulate ,

Monitor R-13 and/or Plant Vent- R Radiogas Monitor R-14.

III-19

i

. -s- SCENARIO NO. 4B REV. O 4

DETAILED SCENARIO TIME LINE f("'g INITIATING i hs) MESSAGE TIME NUMBER EVENT

SUMMARY

- Report any accident condition changes to SWS or STA, and maintain Log Book.

Senior Watch Supervisor (SWS)

- Inform and confer with the POM.

Plant Operations Manager (POM)

Direct OSC Coordinators to send a Chem Tech to obtain a plant vent sample.

Direct in-plant radiological monitoring.

- Direct actions to mitigate release.

-- Confer with ED and TSC Manager.

'- - Authorize emergency personnel exposure in accordance with IP-1038.

Offsite Radiological Assessment <

Director (ORAD)

- Check-information obtained from-TSC.

- Fill out " Emergency Notification Fact Sheet, Part II" and confer with the Emergency Director.

- Perform necessary dose proj ec tions . Determine recommended-Protective Actions using IP-1013. Review these with-

-ED.

- Confer with Dose Assessment H.P.

and dispatch offsite monitoring teams to specified environmental survey / sampling points.

j .

v III-20

,, 3 SCENARIO NO. 4B REV. 0 DETAILED SCENARIO TIME LINE I

INITIATING

,( MESSAGE TIME NUMBER EVENT

SUMMARY

f Request information from MIDAS

. operator on weather forecast.

1 i - Review new plant release and survey data, and compare predicted offsite exposure rates with survey team measured and/or Reuter-Stokes field readings,

i. - Proj ect future-survey / sampling

points.

Survey Team Health Physicist (STHP)

Continue to perform appropriate surveys approximately every 30

minutes; including EOF. field survey, air sampling and counting i

inside. EOF, etc.

I Continue updating personnel-i exposure records and maintain

!('- exposure and contamination >

control for all personnel at.the EOF.

i Confer with ORAD and dispatch j onsite field survey teams and i

receive data. Place field 1 survey

) readings on Site Map.

4 Dose Assessment Health Physicist ,

! (DAHP)

J Receive,. evaluate and relate to ORAD offsite survey team data.

Begin to detect elevated offsite l

radiation = levels.. '

- Calculate offsite exposures at.

! the Site Boundary,:2. miles, 5 miles and 10 miles. Discuss results with ORAD.

i - Obtain fromfMIDAS Operator the Reuter-Stokes SENTRI-readings.

Review and compare with predicted-i g-7s j . and/or measured offsite exposure-g ,i. .. r a t e s . Recommend to 0 RAD i

redirecting monitoring teams to l

resolve any discrepancies.

g III-21

SCENARIO NO. 4B REV. O DETAILED SCENARIO TIME LINE INITIATING MC' MESSAGE TIME NUMBER EVENT

SUMMARY

- Project future survey / sampling points.

Emergency Director (ED)

- Obtain latest prognosis from POM.

Discuss Protective Actions with the ORAD, Plant Operations Manager and TSC Manager.

Fills out " Emergency Notification Fact Sheet, Part I" and has the ORAD complete Part II and the TA Part III.

- Has offsite authorities notified.

l TSC Manager

- Transmit plant data to EOF.

l - Develop plans for closing PCV-1192.

- Support Control Room and.

maintenance activities..

OSC Coordinators I

- Form a Repair and Corrective Action team (s) (per IP-1011) to check the status of the exhaust 4

valves.

Form team to obtain plant vent sample.

1

I s

III-22

SCENARIO NO. 4B REV. O i

DETAILED SCENARIO TIME LINE j, INITIATING E_ MESSAGE TIME NUMBER EVENT

SUMMARY

T= 11:40 18 The wind has shifted from 270 degrees to 225 degrees. This message will only be used if the MIDAS. Computer has not been preprogrammed with :he scenario data.

Offsite Rad Assessment Director (ORAD)

Request plume update from MIDAS Operator.

Review new plant release and survey data and compare predicted offsite exposure rates with survey team measured and/or Reuter- Stokes field readings.

- Perform necessary dose projections. Determine recommended Protective Actions (O using IP-1013. Review these-with

, the Emergency Director.

i Protective Actions should at this time be expanded to include evacuation of Sector 2 and 3 as

! well.as 4, 5 and 6 out to 10

, . miles.

- Fill out " Emergency Notification Fact Sheet, Part II" and confer r with the Emergency Director.

' Survey Team Health Physicist (STHP)

-- Continue to perform. appropriate surveys approximately every-30

, minutes;1 including EOF field survey, air _ sampling, and counting inside EOF, etc.

- Continue updating personnel. ]

exposure records and maintain

- exposure and contamination ~ l I

control for all personnel.

III-23

SCENARIO NO. 4B REV. O DETAILED SCENARIO TIME LINE

< INITIATING

.h MESSAGE TIME NUMBER EVENT

SUMMARY

Confer with ORAD and dispatch onsite field survey teams and receive data. Place field survey readings on Site Map.

Dose Assessment Health Physicist (DAHP)

- Receive, evaluate and relate to ORAD offsite survey team data.

Begin to detect elevated offsite radiation levels in new downwind sectors.

- Calculate offsite. exposures at the Site Boundary, 2 miles, 5 miles and 10 miles. Discuss results with ORAD.

Obtain from MIDAS Operator the Reuter-Stokes SENTRI Readings.

Review and compare with predicted

[O and/or measured offsite exposure rates. Recommend to ORAD redirecting monitoring teams to resolve any discrepancies.

Proj ect future survey / sampling points.

e Emergency Director (ED)

Immediately notify the offsite authorities of the wind change.

Obtain last prognosis from POM.

Discuss Protective Actions with the ORAD. Protective Action recommendations should be expanded to include:

o Evacuation of Sectors 2 and 3 as well as 4, 5 and 6 out to 10 miles.

m

.O f

III-24

SCENARIO NO. 4B REV. O DETAILED SCENARIO TIME LINE 4 INITIATING

';. MESSAGE TIME NUMBER EVENT

SUMMARY

Fill out " Emergency Notification Fact Sheet, Part I" and have ORAD complete Part II and the TA 4

Part III.

Have offsite authorities notified via telecopier.

T= 12:40 19 Maintenance teams have closed PCV-1191. The radioactive release from the plant is terminated.

ANTICIPATED RESULTS Senior Watch Supervisor Inform and confer with the POM.

Emergency Director (ED)

- Have Communicator inform offsite authorities that release has been terminated.

Evaluate offsite dose rates.

- Discuss. downgrading the emergency to a Site Area Emergency with the TSC Manager, ORAD and Plant Operations Manager.

Offsite Radiological Assessment Director (ORAD)

- Continue to monitor and assess.

the plume. Begin to consider recovery actions.

v O

III-25

SCENARIO NO. 4B REV. O DETAILED SCENARIO TIME LINE r" INITIATING

(~ TIME MESSAGE NUMBER EVENT

SUMMARY

TSC Manager

- Determine core damage from previous Reactor Coolant samples.

T= 12:55 20 Maintenance teams have repaired motor-driven Auxiliary Feedwater Pump #21. Feedwater flow may be restored to the Steam Generators.

ANTICIPATED RESULTS Maintenance Team Leader

- Reports back to OSC Coordinators that Auxiliary Feedwater Pump No.

21 is repaired.

OSC Coordinators

- Report to POM that Auxiliary Feedwater Pump No. 21 is repaired.

3 (- Plant Operations Manager Informs the SWS and directs him to restore feedwater flow to the steam generators.

T= 13:25 21 It is now 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> later, the plant is in a stable condition.

Maintenance teams have repaired

, auxiliary feed pump #23 and have cloeed PCV-1192. Offsite power has been restored and the plant is Jn a controlled cooldown.

ANTICIPATED RESULTS Emergency Director (ED)

- Discussion plant situation with POM and TSC Manager.

Downgrades the emergency to ALERT.

(

) -

Notifies the offsite authorities.

III-26

)

SCENARIO NO. 4B REV. O  !

DETAILED SCENARIO TIME LINE i i

j

) INITIATING MESSAGE TIME NUMBER EVENT

SUMMARY

, T= 14:10* 22 Two (2) days have passed. The

(*Two days plant is now in a safe and

later stable condition (i.e., core is cooled and radioactive release is terminated).

ANTICIPATED RESULTS Emergency Director (ED)

- Discuss declaration of the  !

j Recovery phase with the ORAD, TSC

, Manager, Plant Operations Manager and Recovery Manager.

Offsite Rad Assessment Director (ORAD)

} -

Initiate radiological checkout of j Recovery Center.

jO -

Perform Post-Accident Environmental Sampling and Counting in accordance with q IP-1004.

l Perform Offsite Contamination

Checks in accordance with IP-1039.

) -

Continue, as necessary, radiological checking and t decontamination of vehicles in accordance with IP-1009.

Estimate the total population dose within the 10 mile EPZ in accordance with IP-1036.

T= 15:10 23 All Exercise-activities are terminated.

All reports, logs, data and other  :

pertinent material will be l collected at this time by an  ;

Observer / Controller.

5 O.

8,) l k~

III-27

l

. CONSOLIDATED EDISON COMPANY OF NEW YORK INDIAN POINT UNIT NO. 2 DRILL SCENARIO NO. 4B REV. O IV. MESSAGES TO: ALL EXERCISE PARTICIPANTS

(

FROM: ALL LOCATIONS i

TIME: T = 08:00 or earlier 1 ,

j MESSAGE: EXERCISE GROUND RULES -

All Exercise participants are required to observe the following Exercise Ground Rules for the entire duration of the Exercise. If you have any questions, ask your Exercise Controller for clarification at this time.

1. Ensure that all communications indicate that this is only an exercise. Make a positive statement that this is an exercise-related message at the beginning and

! end of all messages or conversations.

If

{'- communication lines are kept open for

~

1 extended periods, periodically repeat the 3

caution. This is especially critical when transmitting messages over communication facilities that are monitored by

{ non-Consolidated Edison personnel.

2. Take no actions that affect unit or non-exercise related operations.

3. Take immediate action (s) to restore safe operation, if an unsafe condition exists.

Ignore exercise situation if actual safety becomes a concern.

l 4. Use only the information provided.in accordance with the exercise ground rules or derived from approved procedures. Do not improvise information. Provide the actual outside temperature and precipitation conditions, when applicable.-

a. Controllers will provide appropriate information at the location where that information would normally be available

,s (e.g., Reactor status at the Control y Room, dose rate readings with' field teams, meteorological information:at Control Room or EOF).

-IV-1

CONSOLIDATED EDISON COMPANY OF NEW YORK INDIAN POINT UNIT NO. 2 DRILL SCENARIO NO. 4B REV. O IV. MESSAGES TO: ALL EXERCISE PARTICIPANTS FROM: ALL LOCATIONS TIME: T = 08:00 or earlier MESSAGE: EXERCISE GROUND RULES All Exercise participants are required to observe the following Exercise Ground Rules _for the entire duration of the Exercise. If you have anyLquestions, ask your Exercise Controller for clarification at this. time.

1. Ensure that all communications indicate that this is only an exercise. Make a positive statement that this is an exercise-related message at the beginning and O '

end of all messages or conversations.- If communication lines are kept open for extended periods, periodically repeat the caution. This is especially critical when transmitting messages over communication facilities that are monitored by non-Consolidated Edison personnel.

2. Take no actions that affect unit or non-exercise related operations..

3.- Take immediate action (s) to' restore safe operation, if an unsafe condition exists.

Ignore exercise situation if actual safety becomes a concern.

4. Use only the information provided in accordance with the' exercise ground rules or derived from approved procedures. -po not improvise information. Provide the actual outside temperature and precipitation conditions, when applicable.

a. Controllers will provide appropriate 3 information at the location where that '

information1would normally be available (e.g., Reactor' status at the Control

{,O.

, Room,-dose rate readings with field teams, meteorological information-at-Control Room or EOF).-

IV-1 I I

j

.  : SCENARIO NO. 4B REV. 0 l

b. Only selected parameters and readings i will be provided. The selected '

._ information will be sufficient to make decisions in accordance with Con Edison plans and procedures.

c. DO NOT BECOME OVERLY CONCERNED WITH THE MECHANICS 0F THE REACTOR OR THE CAUSE OF THE ACCIDENT. THIS EXERCISE IS DESIGNED TO TEST CON EDISON PLANS AND PROCEDURES AND IS NOT CONCERNED WITH BRAINSTORMING THE PROBABILITY, FEASIBILITY OR DETAILED MECHANICS OF THE SIMULATED ACCIDENT.

d. There will be a Con Edison Observer /

Controller at each important location. Controllers will provide information and clarification on which actions are to be simulated or are outside the scope of this exercise in order to keep the exercise progressing in accordance with the scenario.

Observer / Controllers will also observe all aspects of the exercise to prepare an in-house evaluation of plans, procedures and training.

C')

! (_/ 5. Be sure that the Con Edison Observer /

Controller is aware of your actions (actual or simulated).

6. Make all required notifications. All notifications outside the Company will be for information only.

7. If samples inside or outside the site are deemed necessary, they will actually be collected, if possible, and their analysis conducted or simulated, if directed by a Controller. Observer / Controllers will accompany the survey teams, both onsite and offsite.

8. This exercise is conducted to evaluate our plans and procedures. The exercise is also a training vehicle for members of the Con Ed ,

Emergency Response Organization to practice working together and with outside organizations. Please make note of any improvements in any area that you observe as a participant and submit them to the

. s Observer / Controller at the conclusion of the t

kj i exercise.

x, IV-2

. _ . - - . . . - - _ _ _ = - . - - - .

I

• t I l

l SCENARIO NO. 4B REV. O

{)

9. If, during any part of the exercise, you are having trouble accomplishing your required duties, confusion arises, or clarification is necessary, ask your Controller. Controller assistance or clarification does not necessarily imply failure on your part. Your Controller will know the limitations of information he can provide you, and will assist you only to the extent necessary.

P G

i L

lY v

IV-3

SCENARIO NO. 4B REV. O

<w

'U 4

TO: SENIOR WATCH SUPERVISOR LOCATION: CONTROL ROOM TIME: T = 08:00

MESSAGE

NO. 1 This is a Drill i

~

Con Ed Indian Point Unit No. 2 has been operating at full power for 60 days. All plant parameters are normal and stable. The Containment is

'- being pressure relieved. No. 22 ABFP and No. 22 HPSI pump are out on LCOs.for corrective maintenance.

l This is a Drill i

O u

i IV-4

SCENARIO NO. 4B REV. O

o e

k 1-TO: SENIOR REACTOR OPERATOR i

j LOCATION: CONTROL ROOM TIME: T = 08:10 -

1 '

t l MESSAGE: NO. 2 l

4

~

4 i

This is a Drill l I

4 A tremor is felt in the Control Room. No alarm annunciation is

-( indicated. Unit continues to operate with no interruptions .

1:

i .

i i

t I

This is a Drill 6

5 t-I E

4 i

I J

\ ,,

i

IV-5 k

e - r , ,+7 , . , . , , . - - + w.-. ,,--,n,, , - . - , , - - , , , - . . . - , , . . . , ,,,---,n,,.,.,.,m -,-e n .n.s ,.-, . - _ , , . . . + - - , - , , , , , . . . . - .

. s i 4

< ~

SCENARIO NO. 4B REV. O 1

. ~.

i s

c s

TO:- . SENIOR REACTOR OPERATOR LOCATION: ,

' CONTROL ROOM u TIME: T =.08:15 '~-

MESSAGE

NO. 3

, s s o_.

Nw

, T h i's i s - a Drill s i

_. _ x , . . , . . ~

The Unit No. 3 Watch Supervisor calls-to .

, ~

sai that they felt the tremor and.two (2) amber lights'lic on'the Nak Shock Annunciator. He will

'~

call back-as'soon as thefground acceleration indication has been analyzed. Unit No.23'will remain on

$hyfline until the evaluation is s

completed.

4 -~s j - _

! x - ,

m

" 'This'is a Drill 4 ., N'# "-  %

x . ,

e

% :e ,

T

.g 4 e

f

* 4 ..

4

• -r

'_ 41 ' '.'

y me a x

xv-6

+-

I

' .n * ~ - - s. .._. l "K -,

.4.. , ,..

.,K , , _ . . - _ .- . ~ . . . _ . . .- .

l l

SCENARIO NO. 4B REV. O  ;

l O

TO: SENIOR WATCH SUPERVISOR LOCATION: CONTROL ROOM TIME: T = 08:25 if the SWS has not declared an NUE MESSAGE: No. 3A This is a Drill You should declare a NUE at this time. Initiate the appropriate

{ )- actions and notifications.

This is a Drill i

1

'l O

IV-7 ._

SCENARIO NO. 4B REV. 0 l \-

f-TO: SENIOR WATCH SUPERVISOR LOCATION: CONTROL ROOM 4

] TIME: T= 08:45 4

.i MESSAGE: NO. 4 4

This is a Drill The Unit No. 3 Watch Supervisor calls to say that the evaluation of 4

the accelerometer indicates a 0.11g horizontal and 0.04 vertical l

l {I \ displacement. He also indicates that Unit No. 3 will remain on line.

This is'a' Drill m*-

t-f

j. -

I -

t i

~ +

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l . Q: ,.

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l, ~. ~

q .

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r., -

j 3 --j y.+ (_- ~.IV-8 l

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p . . , _ . , , . - , , - . . . , - - . . . , m.,.

--,-.-,.gg, _

. . . - . - _ - _ . . . - - - - , - ~ .

i

! SCENARIO NO. 4B REV. 0 1

i TO: SENIOR WATCH SUPERVISOR LOCATION

• CONTROL ROOM TIME: T = 08:55 if the SWS has not declared an ALERT l

MESSAGE: NO. 4A I

l f

This is a Drill O You should declare an ALERT at this time. -Initiate the appropriate actions and notifications.

This is a Drill

+

_a IV-9

- _ - - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ~ _ _ _ _ _

SCENARIO NO. 4B REV. 0 3

1 1-l l

4 TO: SENIOR WATCH SUPERVISOR i

^

l i

4 LOCATION: CONTROL ROOM TIME: T= 09:10 i

j MESSAGE: No. 5

?

i This is a Drill i,

1 4

4 1

i.

j The damage survey team reports no ~ evidence of damage.to plant i.

structures or equipment.

l I

i -

1 - This is a Drill 1

I i l

1 e

?

i l

L,0

, i~?

i' .IV-10' 2

-..-g - . , - , ,,are-, , _ , , y-,w,-..m, - _ , . , w. w , ..,,w .,...,-,w . . , - . , e-,,,_ . , . , ,,w,, y ,,

l.

1 SCENARIO NO. 4B REV. O LO l.

TO: PLANT OPERATIONS MANAGER i i LOCATION: CONTROL ROOM i

i. TIME: T= 09:10 or when accountability has been completed. .

+

MESSAGE NO. 6 1

J 1-

'This is a Drill I

e k-e All personnel not assigned to a-facility (EOF, TSC,.OSC, CR) may t

, return - to their normal duties. .

3 o

j~

f l This'is a Drill i

i I

i .

4 W

4 f

8 1

g. <

IV-11

• g.- a w-. -

ye-W yr % g-% -t phv---+a-*, ..-g, y. 9 *geep. y .a ,,g.,-ww.4,, - tw g- y-g 9. ,s ,q.*wggy--%-.g,r--mg-,wsp*=y w.p

r. p p. ,e ,-+-g-e y p.e +-

SCENARIO NO. 4B Rev. O

\

'L ,,/

TO: SENIOR WATCH SUPERVISOR ,

I LOCATION: CONTROL ROOM TIME: T = 09:10 MESSAGE: NO. 7 This is a Drill Rod Cluster Control Assembly (RCCA), Bank "D" has been ej ected from the reactor core, resulting in a small LOCA.

l The Reactor " trips" on high power level.followed by a Turbine Trip.

I

! As RCS temperature and pressure decrease, Safety Injection initiates.

One of the three High Pressure Safety Injection Pumps (No. 21) fails to start; the other two operate normally. On receipt of the containment isolation signal, the two pressure relief valves outside Containment fail to close (PCV-1191 and PCV-1192).. The inside valve (PCV-1190) does cl'ose however, securing Containment purge. The motor-driven auxiliary feedwater pumps start normally and provide flow to the Steam Cenerators.

Indications are as follows:

Reactor Trip Turbine Trip Pressurizer Low Pressure and Level Safety Injection This is a Drill e.

IV-12

-. , +

i

, SCENARIO NO. 4B Rev. 0 l

0 t

TO: EMERGENCY DIRECTOR LOCATION: EMERGENCY OPERATIONS FACILITY TIME: T = 09:25 if the Plant Operations Manager has not already declared an S.A.E.

l MESSAGE: NO. 8 This is a Drill i

) You should declare a SITE AREA EMERGENCY at this time. ' Initiate i appropriate actions and notifications.

i This is a Drill i

i i

i a

,1 O

e IV-13

SCENARIO NO. 4B Rev. O O

TO: SENIOR WATCH SUPERVISOR LOCATION: CON' TROL ROOM TIME:' T = 09:40

MESSACE: NO. 9 This is a Drill RCS cooldown is taking place and the Reactor is in a stable condition.

The Charging Pumps and Safety Injection have stabilized RCS pressure at 1200 psig, and are continuing to provide makeup for coolant lost rO

\ '

through the RCCA LOCA. RCS Tavg is constant at 500*F.

It is estimated that cooldown of the RCS will take approximately.3 J

hours.

Radiation monitors R-2, R-7, R-11 and R-12 ALARM.

i i

This is a Drill a

f"

.XJ

, %:/

IV-14'

SCENARIO NO. 4B Rev. O TO: SENIOR WATCH SUPERVISOR LOCATION: CONTROL ROOM TIME: T= 10:10 MESSAGE: NO. 10 This is a Drill

~

A disturbance in the offsite electric power system grid causes a loss of all offsite power. Power transfers to the emergency bus. Vital

((\-

loads are properly sequenced onto the emergency power supply except for both motor-driven Auxiliary Feedwater Pumps, and No. 22 High Pressure Safety Injection Pump fails to start. No feedwater being supplied to the Steam Generators, and only one High Pressure Safety Injection Pump is in operation.

Diesel Generators Nos. 21, 22 and 23 all start normally.

Indications are as follows:

6900 Volt Station Auxiliary Breakers trip 480 Volt Switchgear Motor trips Emergency Diesel Generators Nos. 21, 22 and 23 start Auxiliary Feedwater Pumps Nos. 21 and 23 fail to start High Pressure Safety Injection Pump No. 22 fails to start This is a Drill LO o

IV-15

I l

SCENARIO NO. 4B Rev. 0 10 TO: EMERGENCY DIRECTOR LOCATION: EMERGENCY OPERATIONS FACILITY '

TIME: T= 10:25 if the Emergency Director has not already declared a General Emergency.

MESSAGE: NO. 11 This is a Drill A GENERAL EMERGENCY should be declared at this time. Initiate appro-lO

\ priate actions and notifications.

This is a Drill H

i s ..

IV-16

SCENARIO NO. 4B Rev. 0 iLO

,i 1

i 1

TO: SENIOR WATCH SUPERVISOR LOCATION: CONTROL ROOM

) TIME: T= 10:25 (only when attempt is made) j MESSAGE: NO. 12 i

i i..; This is a Drill i

l' Attempts to parallel the Gas Turbine Generators to the electrical i-j- buses are unsuccessful.

8 i

i 1

i This is a Drill i

J I.

+ ,

4 L

i

!. I i

t IV-17 i

i.

- - , , , . , . + . . . , , . . - , + , , . , . -

w.,,, e , , . - . ., . , , -

, ,, ,. - . , . . , , , , . . . . , . , - s ae,.w~

, . . . - ~ . - . . - . . . . - - - ~ - _ - . - - - - - . _ . - _ . . ~ . - . . . - - . - . . - . . . . . . . . . - . . .

i 1

1 SCENARIO NO. 4B Rev. 0 e

.I

• l l' 4 l t i

i, 4 1

1 1

TO

SENIOR WATCH SUPERVISOR LOCATION: CONTROL ROOM i

TIME

T= 10:25 r

!~

t MESSAGE: NO. 13  !

4 1

i 1

i i i  !

i This is a Drill I i I i

i f

I i i

l

.((

All Steam Generators boil dry.

i i

J i

i i

' This is a Drill i

i

[

l s l . e.

-l .'

m IV-18 I:

L ,,.. c.___ . . _ . . . - _ . , , . _ . - . _ _ _ . _ , _ _ - - _ _ . _ _ _ . _ . . _ _ . _ _ _ . _ _ _ _ . . . . _ _ . . _ _ .

- . . . .. . , _ _ _ . . . . . . _ . - _ . . _ - -. .. - .. . . . _ _ _ = _ . . . _ - _ _ _ . . . .. - .- ... . , _ . _ - _ _ - _

SCENARIO NO. 4B Rev. 0 1

i

J 5

4 TO :' SENIOR WATCH SUPERVISOR 1 LOCATION: CONTROL-ROOM l 1 TIME: T= 10:35 t

. MESSAGE: NO. 14 1

4

$ This is a Drill i

i i

i t

i The Power-Operated Relief Valves (PORVs) fail to OPEN at the pre- t i scribed pressure.

I (.

t i

J s

I-This is'a Drill i

i i '

t t

i ,

i

.I i

i i

i I i

1 t yr*.- ,

1

1 1

IV.-19 Y

,a.m-- -r,v.w.-e. ,.4 w -m . l r -se + - n -, .,e ,e,-, .,<..a '. .w m , + .u-,..,.,wm-,se ,--.-,--..-e-w, *, --r - n w w . e-e-- -r,, -,e vm-w~- -, ~ , - - ~ ev.-~nw

_- . . . _ _. - - . . . . . _ . - . . . . . . -. ._- . _ _ . .= . . _. _ _ _ _ - - - -

\

l SCENARIO NO. 4B Rev. 0 l I l 1 .

l l-

\

v 4 I i

TO: SENIOR WATCH SUPERVISOR j LOCATION: CONTROL ROOM TIME: T= 10:40 MESSAGE: No. 15 i

i i

This is a Drill i

I i

i Indications are as follows:

j o Area Monitor High Radiation Alarm o Failed fuel monitor indicates high activity '

]

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]- This is a Drill i

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IV-20 1

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.. _ ~ -. - .. ._-.- ... .. . . . - . . . - - - - . . - _ _ . . - _ . . - _ _ - . - . - - . . _ _ - .

SCENARIO NO. 4B Rev. O

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I

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i

! TO: SENIOR WATCH SUPERVISOR LOCATION: CONTROL ROOM TIME: T= 11:10

! MESSAGE: NO. 16 i

Ye This is a Drill i i

i i '

! Control Room annunciators indicate that the remaining closed

{ Containment Pressure Relief Valve (PCV-1190) has failed in the OPEN '

position. Initial attempts to close all valves fail.

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1-IV-21

{ SCENARIO NO. 4B Rev. 0 1.

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! TO: SENIOR WATCH SUPERVISOR LOCATION: CONTROL ROOM 1

1 TIME: T= 11:15 l MESSAGE: NO. 17 i

h j This is a Drill 1

' ARM R-13 and R-14 Alarm.

This is a Drill i

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i I

,O, IV-22 i

. _ . . . . . - . - . ~ . - - - . . . . - - .- _. .- - -. . - - -

4 SCENARIO NO. 4B Rev. O I

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1 4

i l TO: MIDAS OPERATOR -

l LOCATION: EMERGENCY.0PERATIONS FACILITY 3

TIME: T= 11:40 This message should not be issued if the i MIDAS has been preprogrammed with scenario l Met conditions.

1 MESSAGE: NO. 18 i

i l This is a Drill 1

l The wind has shifted from 270-degrees to 225 degrees.

1 4

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This is a Drill 1

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1 SCENARIO NO. 4B Rev. O

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j TO: SENIOR WATCH SUPERVISOR 1

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! LOCATION: CONTROL ROOM l

j TIME: T= 12:40 i

j MESSAGE: NO. 19 i

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l This is a Drill i

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k j Maintenance teams manage to close PCV-1191. The radioactive release i* ~

j from the plant is terminated. ,

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This is a Drill '

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SCENARIO !!O. 4B Rev. O O

TO: MAINTENANCE TEAM LEADER LOCATION: AUX FEEDWATER PUMP NO. 21 TIME: T= 12:55 MESSAGE: NO. 20 This is a Drill

( Your team has completed repair of the motor-driven Auxiliary Feedwater Pump No. 21.

This is a Drill l

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IV-25 9

- . . . - .-. . . . _ . . - -- .. - - . - . ..~. - - . - . - - . . - . _ . - . _ . . - - _ . - .

SCENARIO NO. 4B Rev. O  ;

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i i TO: PLANT OPERATIONS MANAGER l'

i LOCATION: CONTROL ROOM i ,

l TIME: T= 13:25 I i- ,

j MESSAGE: NO. 21 i

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This is a Drill l

i It is now 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> later, the plant is in a stable condition, mainte-

nance teams have repaired auxiliary feed pump #23 and have closed I

4 PCV-1192. Offsite power has been restored and the plant'is in a l

,. controlled cooldown.

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F This is a Drill 4

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TO: PLANT OPERATIONS MANAGER i

LOCATION: CONTROL ROOM TIME: T= 14:10 (two days later)  ;

MESSAGE: NO. 22

(

This is a Drill l

1 i

! Two (2) days have passed. The plant is now in a safe and stable condition (i.e., core is cooled and radioactive release is i

j terminated).

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This is a Drill 4

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SCENARIO NO. 4B Rev. 0 1

O 4

TO: ALL EXCERCISE PARTICIPANTS LOCATION: CONTROL ROOM TIME: T= 15:10

MESSAGE

NO. 23 This is a Drill f

All Exercise activities are terminated. All participants should report back to their individual staging (or assembly) areas, i

f All reports, logs, data and other pertinent material will be collected at this time by an Observer / Controller.

j This is a Drill 1

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IV-28 l f

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l SCENARIO NO. 4B REV. O CONSOLIDATED EDISON COMPANY OF NEW YORK

( INDIAN POINT UNIT NO. 2 r DRILL SCENARIO NO. 4B REV.0 V. OBSERVER / CONTROLLER INSTRUCTIONS A. Exercise Control Organization Exercise Observer / Controllers shall be appointed in order to control, observe, and later critique exercise activities. The title " Observer / Controller" is used to designate either a single, or dual function during the exercise. Observers will be assigned to watch exercise activities as they occur. They will provide no input or active involvement or direction to any participants during the exercise. Their only function is to quietly observe in order to later help develop a representative critique of exercise participants' actions. Controllers will be assigned to various " key" locations in order to actively control the progress of the exercise. They will input Control and Contingency Messages at the appropriate times and provide any necessary interpretation to exercise participants. Controllers will be the only ones who can answer participants' questions. They will also function as Observers to help evaluate performance; thus ,

Observer / Controllers. The designation below of Observer /

Controller will mean either Observer, Controller, or Observer and Controller. The " Chief Controller" is the lead exercise manager-(or controller)-and will be located in the Control Room. Prior to the exercise. Observer / Controller instructions will be provided in order to familiarize all Observer / Controllers with the entire scope of the exercise, and answer any specific 3 questions.- Table A provides a listing of all exercise Observers and Controllers, their locations and phone numbers.

B. Exercise Control Instructions

1. All Controllers.shall be pre.-positioned at least one' hour ~

prior to the first message time.

2. Prior to exercise commencement, all Controller communica-tions will be tested to ensure 1 satisfactory exercise control.

3. All Controllers will comply with' instructions from the Chief Controller.

4. Each Controller will have copies of the messages controlling  !

the progress of the exercise scenario. Messages shall'be  ;

delivered by the Controller at the appropriate times, to-the

~

i designated individual (s). If the response of exercise-

= participants necessitates the use of-a contingency message, V-1

I SCENARIO NO. 4B REV. O I

rs j( ) the situation should be discussed with the Drill Controller prior to issuance of the message.

i Controllers will use the following techniques to control the exercise in accordance with the scenario.

a. Control Messages - Control messages provide information to the participants and/or cause the participants to take action needed to keep the exercise moving smooth-ly. The Controller will give a hard copy of the control message to the designated participant at the l specified. time. Simultaneously, the Controller will

. provide the essential information verbally. The Controller will follow through and clarify the message l by answering-questions to ensure that the participants d-do not read extraneous meaning into the message.

Controller will not tell participants.what action they are expected to take.

l

b. Contingency Messages - Contingency messages will be-

used only if participants fail to take the major l actions expected from the control messages by the time j designated. Controllers will give the contingency

] message to the designated participant and explain in as i

much detail as necessary what actions the participant is expected to perform. Contingency messages are;used 4

(- to keep the exercise on schedule, though their use may indicate inadequate plan implementation.

c. Control Information - Controllers ~ for Health Physics and Environs Field Teams will provide instrument 4

readings and other information to team members verbally

when they request it by performing the measurements,

, etc. Controllers will refer to their current-location and the applicable time.periodsto obtain requested _ data from the appropriate tables.

d. Control Guidance - Controllers will provide verbal 3 guidance to participants to keep the exercise oriented to the pre-arranged scope and scenario. Controllers ,

j will direct participants to simulate certain-actions j

that are outside the immediate scope of the' exercise'at the time participants announce their intention to perform the action. Observer / Controllers will note that the participants simulated the action. Partici- ,

, pants must request information that is not automat - l l ically provided from participants at other locations. -

~

Controllers will steer participants away from types of j

=

information that are outside the exercise scope.to avoid bogging the exercise down.in a1 guest for'informa-i fs_/

p tion that Controllers do not possess and have no intention of providing.

V V-2

o 1

SCENARIO NO. 4B REV. O l

O NOTE: All messages controlling the progress of the 43/ exercise scenario are noted with a number.

5. All Controllers shall synchronize their watches to ensure that messages are delivered at the proper time. Times on messages are real time.

6. Each Controller will have copies of time-related plant and radiological parameters (data) corresponding to the develop-ment of the exercise scenario. This information should be issued, only upon request or when required, to the appropriate exercise participants by either the Control Room Drill Controller, or Controllers accompanying the radiological monitoring or inplant health physics personnel.

7. Controllers shall not provide information to the exercise participants regarding scenario development or resolution of problem areas encountered. The exercise participants are expected to obtain information through their own organiza-tions and exercise their own j udgemencs in determining response actions and resolving problems.

8. Any. inquiries originating from the general public, as a result of exercise activities, will be referred to a Controller. An explanation will consist only of stating that a practice drill is underway at the plant and all events are simulated (i.e., not real).

9. Some exercise participants may insist that certain parts of the scenario are unrealistic. The Drill Controller has the sole authority to clarify any questions regarding scenario content.

10. Each Observer / Controller should use the Log Sheet contained at the end of this section to take detailed notes regarding the progress of the exercise and the responses of the exercise participants at their respective assigned lo-cations. Each Observer / Controller should carefully. note the arrival and departure times for exercise participants, the times at which major activities or milestones occur, and problem areas encountered. Observer /Contro11ers' comments should consider the evaluation elements set forth in Section B, " Exercise Evaluation Criteria." All notes taken.should be retained for the purposes of reconstructing the exercise chronology and preparing-a written critique of the exercise.

11. The exercise is tentatively scheduled to:end as' indicated in-the last message. Instructions for reassembly of the Observer / Controller team will be.giventat that time.

NOTE:

In the event of a real emergency during the fs exercise, the exercise may be immediately ter-

\ g. minated by the Drill. Controller, if' deemed appro-priate.

V

-- .. . _ . _ - - . = . - -

SCENARIO NO. 4B REV. 0

-B. Exercise Evaluation Criteria Observer / Controllers shall familiarize themselves with the duties and action requirements of the personnel they are monitoring.

Certain generic evaluation points are to be considered for all locations / participants, as appropriate. These include:

1. Notification, alerting and mobilization of emergency re-sponse personnel.

2. Adequate communications capabilities among onsite and s

, offsite emergency response facilities and personnel.

3. Timely activation of emergency facilities and teams.

I 4. Clear and appropriate direction and control of all exercise

activities.

i

5. Emergency procedures are followed. In some cases they should be referred to during accomplishment of specific duties; e.g., dose assessment.

6. Overall adequacy of the scenario to test the various emer-gency preparedness plans and procedures.

), 7. Benefit of the exercise co'its participants.

43

! The following guidelines provide basic evaluation criteria which

, must be addressed by the Observer / Controller in order to effec-

! tively critique the exercise. Evaluation criteria are grouped

according to exercise activity location and' individual (or team) functions.

I I

NOTE: Specific exercise performance must be compared directly with company emergency procedures. Therefore, indi-viduals assigned as Observer / Controllers shall.be cognizant of the respective procedures and all actions

! that shall-be carried out by the participants they l observe.

After completion of.the' drill, and before the end of the next normal working day. .the Chief Controller shall hold a verbal

critique, where all~ Observer / Controllers shall discuss their observations and any noted. shortcoming, and present their rec-ommendations to improve performance and emergency preparedness.

Critique-comments will be requested from all participants at the conclusion of the exercise.

1. Control Room O

, ,g_,/ Prior to initiating the exercise, the Drill Controller will'  !

\', confer with the Senior. Watch Supervisor (SWS) in order to identi- I fy any ongoing operational or maintenance activities that-should i

V-4 .

^1

l SCENARIO NO. 4B REV. O not be interrupted._ Those personnel engaged in these activities OS, will be notified that they are to disregard any exercise-related announcements or activities. Emphasis should be made, however, that in the event of a real emergency the exercise may be ter -

ainated and station announcements will specify "THIS IS NOT A DRILL" such that instructions should be followed by all personnel.

The-Observer / Controller shall. observe the action of all personnel assigned to the Control Room and all personnel who report to the Control Room for assignment. In addition, he will pay special attention to the following:

o Use of map and overlays, o Placement of calls to NRC, NYS and Counties.

o Notification, alerting and mobilization of emergency re-sponse personnel, including calling-in off-duty personnel.

o Operations handling of accident conditions if appropriate.

o Instructions given to Search and Rescue' teams, Repair and Corrective Action teams, and H.P. and Chem. Techs by the Senior Watch Supervisor (SWS).

o Does the SWS handle the emergency by directing his people or

{O trying to do the work.htmself, o Is the time. frame of actions by the SWS reasonable enough.

o Deportment of all personnel in the Control Room.

The following procedures are to be used~1n the evaluation:

IP-1001 Mobilization _of Onsite Emergency Organization IP-1002 Emergency Notification and Conaunication IP-1003 Planned Discharge of Containment ~ Atmosphere During Accident Conditions IP-1007 Determination of the Magnitude of Release and Exposure-Rate IP-1010 Search.and Rescue-Teams IP-1011 Repair and Corrective Action IP-1013 Recommendation of' Protective Actions for Offsite i Population IP-1016 Obtaining Meteorological Data IP-1020 Airborne Iodine -'131 Determination Using SAM-2/RD or RM-14/RP-210 IP-1021 Manual Update and Readout of' Proteus Plant Parineter, Data

-IP-1026 Operation of the NAWAS Conaunication System IP-1037 Obtaining Offsite Reuter-Stokes Monitor Data

_ .: s IP-1038 Emergency Personnel! Exposure 1,/

V-5 L __

SCENARIO NO. 4B REV. O g IP-1043 ;0peration of the NYS Radiological Emergency

' ~

Communications System (RECS)

IP-1047 Obtaining Offsite Exposure Rates from MIDAS Via Control j s

Room ASCII Terminal.

Plus7 Immediate Action Procedures for SWS, CRO, WATCH HP, POM ,

2. Technical Support Center The Observer / Controller should observe the following:

o Timely activation s

,o A minimum of four qualified persons manning the center.

o-

. Field survey performed.

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~ ~

Noble gas monitor set up.

~~ o , " F r i s k e r" 's e t_ up. ,

o , Work performed in professional manner.

, o Pho~nes are plugged in and direct lines to Control Room, NRC, and EOF are checked out.

) The following procedures are to be used in the evaluation:

IP-1020 Airborne Iodine - 131 Determination Using SAM-2/RD-22 or:AM-14/HP-210 IP-1021 Manual Update and Readout of Proteus Plant Parameter Data IP-1035 Technical Support Center IP-1041 Use of:the, Triton to Monitor Noblegas 3.f Operations control-benter (OCC) s The Observer /Conerni_lar should observe the.following:

,c ' Timely initiat' ion of a call to the paging service company.

m v '% h o Adequate *commuhic'ations,-including how problems with.the radio'and. telephones are handled. Message handling and communicat' ion logging proc'e,dures.

c' Verification call to Indian' Point Unit-No. 2 Control Room 4 ,

. x' f o r au thentic,ity - O f eme rgency.

s ,,, ,,2

• o- Preparation rec'pr'dt.of personnel'who have called in.

- vc ..

The following procedure'is to be used in the~ evaluation '

N. ,

,I,P7 1002 Emergency Notification and Communication

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• SCENARIO NO. 4B REV. 0

4. Assembly Area The Observer / Controller should observe the following:

o Do they seek out their section or department accountability officer, generally stay together as a group and remain orderly?

o Were Assembly Area radiation surveys performed and results recorded? This will depend on whether there is an SAE or GE classification and releases to the environment.

o Is there documentation of accountability and is it under-standable to others.

The following procedure is to be used in the evaluation:

IP-1027 Site Personnel Accountability and Evaluation

5. Operational Support Center The Observer / Controller should observe the following:

o Is there documentation of accountability and is it under-standable to others?

o Do the personnel awaiting assignment remain orderly?

o Were radiation surveys performed and recorded?

o Receipt of request to form teams.

o Handling the assignment of team members.

The following procedures are to be used in the evaluation.

IP-1020 Airborne Iodine -

131 Determination using SAM-2/RD-22 or RM-14/HP-210 IP-1023 Operational Support Center IP-1027 Site Personnel Accountability and Evacuation IP-1041 Use of the Triton to Monitor Noblegas.

6. Emergency Operations Facility This is the command post for the interface with offsite author-ities and it should seen so to the Observer / Controller.

Look for the following things:

b gj,)

<x o The Emergency Director is in command of the EOF.

o -The ORAD is in control of the radiological assessment activities, and reports results and recommendations to the Emergency Director in a timely and efficient manner.

V-7

/

_ SCENARIO NO. 4B REV. 0 f o Any extra pnrsonnel, spectators and those awaiting orders are quietly standing out of the way.

i o The H.P. or_ support personnel are performing duties in a time 2y and efficient manner and reporting results to either the Emargency Director or ORAD.

l o Instrumentation deployed in the EOF is placed in a l non-interfering position. l l

o Adequate communications, including how problems with the I radio and telephone are handled. Message handling and communications logging procedures.

o Radioactive release ratas, whole body and thyroid exposures to the offsite population are . calculate,d quickly after the receipt"of data from the Control Room or the offsite moni-toring team (s).

o Prompt notification to the NRC, NYS and Counties of exposure data and changes to site meteorological conditions.

o The Emergency Director assigns, whehe possible, his routine calls to someone else thereby leaving himself free to command the action.

A, o Data forms filled out and tu rned in to the ORAD / Health k _/ Physicist.

o Time)y deployment of teams.

o'~ A central point for receipt' of radio. logical monitoring data is designated and adequate communications with field teams demonstrated.

o Demonstrate ability'to assess plant conditions, rec 3assify

,the incident (if appropriate), develop timely protective action recommendations,.or communicate with offsite author-ities in'an' accurate and" timely manner.

o Demonstrate ability to control radiological monitoring field teams for "p lume-t ra c king ," and , ingestion pathway monitor-ing. f' o jDemonstrate ability to develop recommendations for recovery j gud re-entry activities.

o Demonstrate ability to provide radiation exposure control for emergency workers.. ,.

(~'N . Th( following procedures are tc/;be used in the evaluation:

L) '

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(_f IP-1002, Emergency Norpiication'and Communication IP-1003 ?lanned Dischargajof~ Containment Atmosphere During

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. y_8 h l_ 1 Y .

SCENARIO NO. 4B REY. 0

()

Yd/ IP-1004 Accident Conditions Post Accident Offsite Environmental Surveys, Sampling and Counting IP-1005 Use of SAM-2/RD-22 to Determine Thyroid Burdens IP-1006 Site Perimeter Surveys IP-1007 Determination of the Magnitude of Release and Exposure Rate IP-1013 Recommendation of Protective Actions for Offsite Population IP-1016 Obtaining Meteorological Data IP-1020 Airborne Iodine - 131 Determination Using SAM-2/RD-22 or RM-14/HP-210 IP-1021 Manual Update and Readout of Proteus Plant Parameter Data IP-1029 Emergency Closeout / Class Reduction Written Summary to Authorities IP-1036 Estimation of Population Dose Within the 10 Mile Emergency Planning Zone IP-1037 Obtaining Offsite Reuter-Stokes Monitor Data IP-1038 Emergency Personnel Exposure IP-1041 Use of Triton to Monitor Noblegas IP-1043 Operation of the NYS Radiological Emergency Communications System (RECS)

IP-1048 Deescalation of Emergency and Initiation of Recovery Pins Immediate Action Procedures for ED, TA, ORAD, DAHP, STHP,

{(~' MIDAS, EOF COMM, EOF CLERK

7. Security Building (s) or Security Control Points -

It is to be noted that all normal practices, such as sign-out and use of the hand and foot monitor and the portal monitor, are to be accomplished unless the H.P. Technician gives other directions because of radiological conditions. The Observer / Controller will pay special attention to the above along with the following:

o Timely activation or establishment of control ptirt o No one is wearing Anti-C clothing when leaving the site.

o All alarms from monitoring equipment or computer card terminals are acknowledged.  !

The following procedures are to be used in the evaluation:

l IP-1017 Issuance and Use of Radiological Equipment Stored in the Command Guard House r

8. Onsite Monitoring Teams Onsite monitoring teams will normally be assigned field survey l A("T l

s ,) work onsite, outside of the protected area fence, and at the g_f Service' Center building complex. Check on the following items:

l l

I o V-9

SCENARIO NO. 4B REV. O y o Received KI dose (simulated) from ORAD if required.

}

NOTE: Do not actually take the KI Dose.

o They have a dosimeter and film badge.

o They have a charcoal filter respirator when leaving the building complex to perform a survey.

o Radio check performed before leaving the EOF parking lot.

o Field readings taken along the route to the designated area.

Simulated field data will only be available at designated monitoring points, o Work performed in a professional manner.

o Data forms filled out as appropriate and turned in to the ORAD / Health Physicist.

The following procedures are to be used in the evaluation:

IP-1006 Site Perimeter Surveys IP-1008 Personnel Radiological Check and Decontamination IP-1009 Radiological Check and Decontamination of Vehicles

(~N IP-1014 Radiological Check of Equipment Before it leaves the Site

{ IP-1028 Onsite (out of plant) Field Surveys

9. Offsite Monitoring Teams The Observer / Controller should observe the following items:

o Received Ki dose (simulated) from ORAD if. required.

J NOTE: Do not actually take the KI dose.

o Operational check performed on survey instruments, sample counter and sample pump before l'eaving the EOF parking lot, o Equipment check-off performed.

o Assignment of badges and dosimeters before leaving the EOF parking lot.

o Charcoal cartridge respirator made available before leaving EOF. lot.

o. Survey instrument made ready to take field readings.

("}

lJ o Radio check-out by communication to EOF beforeLleaving.

YJ' V-10

. SCENARIO NO. 4B REV. O fr~g o Beta and gamma field surveys p rformed on the way to sample b/ point.

1 o Sampling and field surveys performed at sample location. l o Instrument calibration performed and samples counted.

o Air sampling started.

The following procedures are to be used in the evaluation:

IP-1004 Post Accident Offsite Environmental Surveys, Sampling and Counting IP-1006 Site Perimeter Surveys IP-1008 Personnel Radiological Check and Decontamination IP-1009 Radiological Check and Decontamination of Vehicles IP-1015 Mobilization and Operational Procedure for Offsite l Monitoring Teams - Immediate Response.

IP-1020 Airborne Iodine - 131 Determination using SAM-2/RD-22 or RM-14/HP-210 IP-1039 Offsite Contamination Checks

10. Radiation Protection Technician (RPT)

The Observer / Controller should observe the following:

f% RPT follows his instructions indicated under his discipline

[q,/

o tab during radiological emergencies.

o RPT fallows instructions from SWS or OSC coordinator.

o RPT performs survey as indicated using appropriate instrumentation.

o RPT performs duties during medical emergency as indicated in IP-1012.

The following procedures are tc be used in the evaluation:

IP-1010 Search and Rescue Teams IP-1011 Repair and Corrective Action IP-1012 Onsite Medical Emergency IP-1020' Airborne Iodine -

131 Determination Using SAM-2/RD-22 or RM-14/HP-210 IP-1042 In-Plant Radiological Surveys and. Sampling HPP-6.4 Decontamination HPI-6.41 Personnel Decontamination

~Plus Immediate Action Procedure WATCH H.P.

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I i

SCENARIO NO. 4B REV. O

11. - Chemistry Technician The Observer / Controller should observe the following:

o Chemistry Technician follows Chemistry Procedures as appropriate, o Samples are actually collected and counted, as indicated by the scenario, o Results of sample counting (simulated and real) are transmitted to the SWS or OSC Coordinator as appropriate.

The following procedures are to be used in the evaluation:

IPC-E-001 Post Accident Sampling and Analysis of Reactor Coolant IPC-E-002 Post Accident Sampling and Analysis of the Vapor Containment Atmosphere IPC-E-003* Post Accident Sampling and Analysis-of Plant Discharges for Noblegas, Radioiodines and Particulates.

12. Maintenance Repair Team The Observer / Controller should observe the following:

.O . o Response and repair time.

o Proper equipment brought to perform the work.

o Maintenance Repair Team members follow H.P. Technician's instructions.

?

. o Radiological precautions taken.

.i The following procedures are to be used in the evaluation.

IP-1010 Search and Rescue Teams.

IP-1011 Repair and Corrective Action IP-1023 Operational Support Center i

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V .

SCENARIO NO. 4B REV. O TABLE A 1984 ANNUAL DRILL - CONTROLLER /0BSERVER

)

POSITION LOCATION INDIVIDUAL TELEPHONE:

q-Chief Controller CCR R. Sondike

- Controller CCR G. Lewis Observer (SWS/POM) CCR R. Colanero

Observer (Communicator) CCR V. Megluevich

, Observer (H.P.) CCR E. Nestor

, Observer (Chem) .

CCR S. Profeta

! Backup Controller / Observer T. Cotter i Backup Controller / Observer W. Thompson Backup Controller / Observer T. Gildersleeve

' Controller . TSC N. Hartmann

_ Observer TSC Observer TSC' Observer (CAO) OSC B. Barbalich.

Observer (Team) OSC J. Daly-i Observer (Team) OSC .F. Gross Observer (Team) OSC H. Whitteborn Observer (53 el

Confer Rm) OSC H. Dietrich

, Controller .

EOF ~ G. H. Liebler

. Observer (ED/0 RAD) EOF H. Sanders

\

Observer (Communicator) EOF Observer (Onsite Team) EOF T. Hanovich Observer (Offsite Team) - EOF H..Gordon-4 -

- Observer (Offsite Team) EOF E. Savoca Observer (Assembly) Simulator J.- Sedlacek.

Observer (Assembly) Construction A. Donnegan Observer (Assembly) Maint.-Load. Well- M. DiGenova.

Observer (Assembly) M.O. Bldg - Crouse- A. Tom j Observer (Assembly) U-l Turb. F1. Off.

I Observer (Security) CGH Observer-(Security) River! Gate .

. L..Rocco Observer'(Security NSB Control'Pt. M. Skotzko Controller / Observer- - 0CC

- Observer ~ CRC W. Piatek-i 7

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SCENARIO NO. 4B REV. O CONSOLIDATED EDISON COMPANY OF NEW YORK INDIAN POINT UNIT NO. 2

(.

EMERGENCY PREPAREDNESS EXERCISE OBSERVER / CONTROLLER LOG SHEET Neme: Date:

Location:

TIME _0BSERVATION/ COMMENT

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l V-14 i

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. (U U u PLANT STATUS LOG SCENARIO NO. 4B REV. O PARAMETER TIME 08:00 08:15 08:45 09:00 09:10 09:11 09:12 09:13 Racetor Shutdown N N N N N N Y Y

.(Y/N)

NIS Power Range (%) 100,4 0 NIS In;erim. Range 100_4 2x10 2x10 100_4 2x10 100_4 2x10 100_4 2x10 2x10 80 _4 2x10 -5 10 SS

1. 35 (Amps)

~4 -4 -4 -0 ~4 NIS Interim. Range 2x10 2x10 2x10 2x10 2x10~ 2x10 2x10 -5 10

-5

1. 36 (Amps)

NIS Source Range N/A N/A N/A N/A N/A N/A N/A N/A

1. 31 (CPM)

NIS Source Range N/A N/A N/A N/A N/A N/A N/A N/A

1. 32 (CPM)

RCS Incor T/C 575 575 575 575 575 573 545 545 (Center) (*F)

RCS Incore T/C 575 575 575 575 575 573 545 545 (Highest) (*F)

RCS Pressure (PSIC) 2235 2235 2235 2235 2000 1900 1750 1675 RCS Avg. Temp. (*F) 549 549 549 549 549 549 545 545 RCS Cold Leg Temp. 523 523 523 523 523 525 545 545

(*F)

SAT . Meter Margin (*F)~ 76 76 76 76 60 55 58 68 RCP in Service (Y/N) Y Y Y Y Y Y Y Y Pressurizer Level (%) 25 25 25 25 15 15 14 14 Racctor Vessel Level 100 100 100 100 100 100 100 100

(%)

S/G Levels #21 (%) 45. 45 45 45 45 45 0 2

1. 22 45 45 45 45 45 45 0 2

1. 23 45 45 45 45 45 45 0 2

1. 24 45 45 45 45 45 45 0 2 S/G Press #21 (PSIG) 650 650 650 650 750 750 850 900

1. 22 650 650 650 650 750 750 850 900

1. 23 650 650 650 650 750 750 850 900

1. 24 650 650 650 650 750 750 850 900 VC Pressure (PSIG) 0 0 0 0 0 0.5 1 1

.VC Temperature (*F) 116 116 116 116 117 118 119 120 VC Sump Level Elev. O. 0 0 0 0 0 40.5 40.5 (ft.)

VC Hydrogen (%) 0 0 0 0 0 0 0 0 Aux. F. W. Flow (GPM) 0 0 0 0 0 0 400 400 RWST Level (ft.) 36 36 36 36 36 36 36 36 Condensate Storage 40 40 40 40 40 40 40 40 Tank Level (ft.)

VI-1

PLANT STATUS LOG SCENARIO NO. 4B REV. 0 PARAMETER TIME 09:14 09:15 09:20 09:25 09:40 09:55 10:10 10:15 ,

Reactor Shutdown Y Y Y Y Y Y Y Y (Y/N)

NIS Power Range (%) 0 0 0 _3g 0 _3g p gg gi NIS Interim. Range 7x10

-6 4x10

-6 0 _7 2x10 10 99 5x10 5x10 10 10 g

7x10 ~0 -6 -1 ~II ~I

~

NIS n ra Range 4x10 2x10 10~ 5x10 5x10~ I 10 10

1. 36 (Amps)

NIS Source Range N/A N/A N/A N/A 10,000 10,000 5,000 2,000 1

1. 31 (CPM)

NIS Source Range N/A N/A N/A N/A 10,000 10,000 5,000 2,000

1. 32 (CPM)

RCS.Incor T/C 544 543 525 500 500 500 550 560 (Center) (*F)

RCS Incore T/C 544 543 525 500 500 500 550 570 (Highest) (*F)

RCS Pressure (PSIG) 1650 1625 1500 1200 1200 1200 1200 1200 RCS Avg. Temp. (*F) 544 543 525 500 500 500 550 540 RCS Cold Leg Temp. 544 543 525 500 500 500 550 540

(*F)

SAT Meter Margin (*F) 64 63 71 67 67 67 17 7 RCP in Service (Y/N) Y Y Y Y Y Y Y Y Pressurizer Level (%) 14 13 14 24 25 25 25 25 Reactor' Vessel-Level 100 100 100 100 100 100 100 100

~(%)

S/C Levels'#21 (%) 5 7 7 6 7 7 7 5

1. 2 2. 5 7 7 6 7 7 7 5

1. 23 5 7 7 6 7 7 7 5

1. 24 5 7 7 6 7 7 7 5 S/G Press #21 (PSIG) 1000 1000 970 1000 950 950 950 950

1. 22 1000 1000 970 1000 950 950 950 950

1. 23 1000 1000 970 1000 950 950 950 950

1. 24 1000 1000 970 1000 950 950 950 950 VC Pressure (PSIC). 2 2 2 3 4 4 5 6 VC" Temperature (*F) 121 122 127 126 127 127 128 129 VC Sump Level Elev. '40.5 40.5 42.9 42.9 42.9 42.9 42.9 42.9 (ft.)

VC Hydrogen (%) 0 0 0 0 0 0 0 0

' Aux. F. W. Flow (CPM) 400 400 400 400 400 400 0 0 RWST Level (ft.) 36 36 36 35 35 35 35 35 Condensate Storage 39 38 38 37 36 36 36 36 Tank Level (ft.)

VI-2

PLANT STATUS LOG SCENARIO NO. 4B REV. O PARAMETER TIME 10:20 10:25 10:30 10:35 10:40 10:55 11:10 11:25 Reactor Shutdown Y Y Y Y Y Y Y Y (Y/N). -

NIS. Power Range (%) O gg g gg p gg g gg p gg p gg p gg g gg NIS Interim. Range '10 10 10 10 10 10 10 10 0-11 ~II -11 ~I ~I ~I ~

NIS nt a Range 10- 10 10 10 10 10 10

1. 361(Amps)

NIS Source. Range 1,000 500 200 100 100 100 100 100

1. 31 (CPM)

, NIS Source _ Range 1,000 500 200 100 100 100 100 100

-#32 (CPM)

RCS Incor T/C 565' 570 620 640 660 680 680 680 (Center) (*F)

RCS Incore T/C 575 575 630 650 670 690 700 800 (Highest) (*F)

RCS Pressure-(PSIC) 1200 2100 2300 2400 2400 2400 2400 2400 RCS Avg. Temp. (*F) 540 540 600 615 High High High High RCS Cold Leg Temp. 540 540 600 600 600 600 600 600

.(*F)

' SAT Meter Margin (*F) 7 102 55 12 0 0 0 0 RCP in Service (Y/N) N N N N N N N N Pressurizer Level (%) -25 25 25 25 0 0 0 0 Reactor Vessel Level 100 100 100 100 90 40 30 40

(%)

S/G Levels #21 (%) 2 0 0 0 0 0 0 0

1. 22 2 0 0 0 0 0 0 0

.#23 2 0 0 0 0 0 0 0

1. 24 2 0 0 0 0 0 0 0 S/G Press #21 (PSIG) 860 0 0 0 0 0 0 0

1. 22 860 0 0 0 0 0 0 0

1. 23 860 0 0 0 0 0 0 0

1. 24 860 0 0 0 0 0 0 0

.VC Pressure (PSIG) 6 7 7 8 8 8 7 8 VC Temperature (*F) 130 130 130 130 130 130 130 130 VC. Sump Level ~Elev. 42.9 42.9 42.9 42.9 42.9 42.9 42.9 42.9 (ft.)

VC Hydrogen;(%)' O O O O O O 0.4 0.6 Aux.'F. W.-. Flow (GPM) ~ 0 0 0 0 0 0 0 0 RWST, Level (ft.) 34 34 34 34 33 33 33 32 Condensate Storage 36 36 36 36 36 36 36 36 TankLLevel (ft.),

VI-3

D :D 0 PLANT STATUS LOG SCENARIO NO. 4B REV. O PARAMETER TIME 11:40 11:55 12:10 12:25 12:40 12:55 13:10 13:25 Raactor Shutdown Y Y Y Y Y Y Y Y (Y/N)

'NIS. Power Range (%) g gg 0 0 0 3y O g3 O gg O gg O 33 g g3 NIS Interim. Range 10 10 10 10 10 10 10 10 NI a Range 10

-11 10-11 -II -II -II -II -II -II nt 10 10 10 10 10 10

1. 36 (Amps)

NIS Source Range 100 100 100 100 100 100 100 100

1. 31 (CPM)

NIS Source. Range 100 100 100 100 100 100 100 100

1. 32 (CPM)

RCS Incor T/C 680 680 680 680 680 680 680 575 (Center) (*F)

RCS Incore T/C 900 1000 1000 1000 1000 1000 1000 600 (Highest) (*F)

RCS Pressure (PSIG) 2400 2400 2400 2400 2400 2400 2400 1400 RCS Avg. Temp. (*F) High High High High High High High 400 RCS Cold Leg Temp. 600 600 600 600 600 600 600 400

(*F)

SAT Meter Margin (*F) 0 0 0 0 0 0 0 187 RCP in Service (Y/N) N N N N N N N Y Pressurizer Level (%) 0 0 0 0 0 0 0 25 Racetor-Vessel Level 45 60 70 75 80 80 85 90

(%)

S/G Levels #21 (%) 0 0 0 0 0 5 5 45

1. 22 0 0 0 0 0 5 5 45

1. 23 0 0 0 0 0 0 0 45

1. 24 0 0 0 0 0 0 0 45 S/G Press #21 (PSIC) 0 0 0 0 0 600 600 250

1. 22 0 0 0 0 0 600 600 250

1. 23 0 0 0 0 0 0 0 250

1. 24 0 0 0 0 0 0 0 250 VC Pressure (PSIC) 7 8 8 8 8 8 8 0 VC Temperature (*F) 130 130 130 130 130 130 130 130 VC Sump Level Elev. 42.9 42.9 42.9 42.9 42.9 42.9 42.9 42.9 (ft.)

VC Hydrogen (%) 0.8 1.0 1.0 1.0 1.0 1.0 1.0 0 Aux. F. W. Flow (GPM) 0 0 0 0 0 200 200 400 RWST Level (ft.) 32 32 32 31 31 31 31 25 ccndensate Storage 36 36- 36 36 36 36 36 36

' Tank Level (ft.)

VI-4

PLANT STATUS LOC SCENARIO NO. 4B REV. O i

PARAMETER TIME 13:40 13:55 14:10 Racctor Shutdown Y Y Y (Y/N)

NIS Power Range (%) O g7 O gg O gg

.NIS Interim. Range 10 10 10

1. 35 (Amps)

.NIS Interim. Range -11 10-11 -11 10 10

1. 36 (Amps)

NIS Source Range 100 100 20

1. 31-(CPM)

NIS Source Range 100 100 20

'f32 (CPM)

RCS'Incor T/C 555 535 190 (Center) (*F)

RCS'Incore T/C 580 560 190-(Highest) (*F)

'RCS Pressure (PSIC) 1400 1400 0 RCS Avg. Temp. (*F) 380 360 180' RCS Cold Leg Temp. 380 360 180

(*F)

SAT Meter Margin (*F) 187 187 32 RCP in Service (Y/N) Y~ Y N Pressurizer Level'(%) 25 25 25 Reactor Vessel Level 100 100 100

.(%)

S/G Levels #21 (%) 45 45 45

1. 22 45 45 45

1. 23 45 45 45

1. 24 45 45 45 S/G Press #21-(PSIG) '195 150 0

1. 22 195' 150 0

1. 23' 195 150 0

1. 24 195 150 0 "VC-Pressure (PSIC) 0 0 0 VC Temperature'(*F) 130 130 130 VC_ Sump Level Elev. 42.9 42.9 42.9.

(ft.)

VC Nydrogen (%) 0 0 'O Aux, F. W. Flow (GPM) 400 400 400 RWST Level (ft.) 25 25 10 Condensate. Storage 36 36 30 Tank Level (ft.)

VI-5

f L [

PLANT STATUS LOG SENARIO NO. 4B REV. O PARAMETER TIME PARAMETER TIME 08:00 08:00 Offsite Power Available 138KV 0 Service Water Pumps #21 0 13.8KV 0 (Essential Header) #22 0

'Energency D/Gs #21 S #23 S

1. 22 S #24 S

1. 23 S #25 0

' SIS Pumps #21 S #26 0

1. 22 S. Component Cool Heat Exchf21 0

1. 23 S #22 0 RHR Pumps #21 S RHR Heat Exchanger #21 S

1. 22 S #22 S Charging Pumps #21 0 Hydrogen Recombiner #21 S

1. 22 S #22 S

1. 23 S VC Isolation (A/B) NO Containment Spray Pumps #21 S Exceptions

1. 22 S Containment Purge in Recirculation Pumps #21 S Progress

1. 22 S High Head SIS Flow #21 (GPM) 0 Cocponent Cooling Pumps #21 0 #22 (GPM) 0

1. 22 0 #23 (GPM) 0

1. 23 S #24 (GPM) 0 Aux Component. Cooling Pumps #21 S Low Head SIS Flow #21 (GPM) 0

1. 22- S #22 (GPM) 0 Aux Boiler Feed Pumps .#21 S #23 (GPM) 0

1. 22 S #24 (GPM) 0

1. 23 S Accumulator Level #21 (%) 52 Fan Cooler Units #21 0 #22 (%) 52

1. 22 0 #23 (%) 52

1. 23 0 #24 (%) 52

1. 24 0 BIT Level (%) 64

1. 25 0 BIT Pressure (PSIG) 90 Legend: O. = . Operating O/S = Out cf Service <

S = Standby.

Vl-6

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l PLANT STATUS LOG SCENARIO NO. 4B REV. 0 l PARAMETER TIME PARAMETER TIME __

09:12 09:12 Offsite Power Available 138KV 0 Service Water Pumps #21 0 13.8KV 0 (Essential Header) #22 0 Ecorgency D/Gs #21 0* #23 S

1. 22 0* #24 S

1. 23 0* #25 0 SIS Pumps #21 0/S* #26 0

1. 22 0* Component Cool Heat Exchf21 0

1. 23 0* #22 0 RHR Pumps #21 S RHR Heat Exchanger #21 S

1. 22 S #22 S Cherging Pumps #21 O Hydrogen Recombiner #21 S

1. 22 S #22 S

1. 23 S VC Isolation (A/B) YES*

Containment Spray Pumps #21 S Exceptions

!22 S PCV-1191 & 1192 Fail to Close Racirculation Pumps #21 S PCV-Il90 Closes

1. 22 S High Head SIS Flow #21 (GPM) O Ccaponent Cooling Pumps #21 0 #22 (CPM) 0

1. 22 0 #23 (CPM) 0

1. 23 S #24 (GPM) 0 Aux Component Cooling Pumps #21 S Low Head SIS Flow #21 (GPM) 0

1. 22 S #22 (GPM) 0 Aux Boiler Feed Pumps. #21 0*

1. 22 0/S* #24 (%) 0

1. 23- 0* Accumulator Level #21 (%) 52 Fcn Cooler Units #21 0 #22 (%) 52

1. 22 0 #23 (%) 52

1. 23 0 #24 (%) 52

1. 24 0 BIT Level (%) 64

1. 25 0 BIT Pressure (PSIG) 90 Legend: 0 = Operating O/S = Out of Service S = Standby

• = Change on status from previous log.

VI-7

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go. -

o PLANT STATUS LOG D

SCENARIO NO. 4B REV. O PARAMETER TIME PARAMETER TIME 09:20 09:20 Offolte Power Available 138KV 0 Service Water Pumps #21 0 13.8KV 0 (Essential Header) #22 0 Eastgency D/Gs #21 0 #23 S

1. 22 0 #24 S

1. 23 0 #25 0 SIS Pumps' #21 0/S #26 0

1. 22 0 Component Cool Heat Exchi21 0

1. 23 0 #22 0 RHR Pumps #21 S RHR Heat Exchanger #21 S

1. 22 S #22 S Charging Pumps #21 0 Hydrogen Recombiner #21 S

1. 22 S #22 S

1. 23 S VC Isolation (A/B) YES Containment Spray Pumps #21 S Exceptions

$22 S PCV-Il91 & 1192 Open Recirculation Pumps #21 S PCV-Il90 Closed

1. 22 S High Head SIS Flow #21 (GPM) 100*

Ccaponent Cooling Pumps #21 0 #22 (GPM) 100*

1. 22 0 #23 (GPM) 100*

1. 23 S #24 (GPM) 100*

Aux Component Cooling Pumps #21 S Low Head SIS Flow #21 (CPM) 0

1. 22 S #22 (GPM) 0 Aux Boiler Feed Pumps #21 0 #23 (GPM) 0

1. 22 0/S #24 (GPM) 0

1. 23 0 Accumulator Level #21 (%) 52 Fan Cooler Units #21 0 #22 (%) 52

1. 22 0 #23 (%) 52

1. 23 0 #24 (%) 52 724 0 BIT Level (%) 10*

1. 25 0 BIT Pressure (PSIG) 15*

Legend: 0 = Operating O/S = Out of Service S -. Standby

• =- Change on status from previous log.

VI-8

( .

PLANT STATUS LOG SCENARIO NO. 4B REV. O PARAMETER TIME PARAMETER TIME 09:25 09:25 Offaite Power Available 138KV 0 Service Water Pumps #21 0 13.8KV 0 (Essential Header) #22 0 Ecorgency D/Gs #21 0 #23 S

1. 22 0 #24 S

1. 23 0 #25 0 SIS Pumps #21 0/S #26 0

1. 22 0 Component Cool Heat Exchf21 0

1. 23 0 #22 0 RHR Pumps #21 S RHR Heat Exchanger #21 S

1. 22 S #22 S Chorging Pumps #21 O Hydrogen Recombiner #21 S

1. 22 S #22 S

1. 23 S VC Isolation (A/B) YES Conteinment Spray Pumps #21 S Exceptions

1. 22 S PCV-1191 & 1192 Open Recirculation Pumps #21 S PCV-1190 Closed

1. 22 S High Head SIS Flow #21 (GPM) 175*

Component Cooling Pumps #21 0 #22 (GPM) 175*

1. 22 0 #23 (GPM) 175*

1. 23 S #24 (GPM) 175*

Aux Component Cooling Pumps #21 S Low Head SIS Flow #21 (GPM) 0 l #22 S #22 (GPM) 0 i Aux Boiler Feed Pumps #21 0 #23 (GPM) 0 l #22 0/S #24 (GPM) 0 l #23 0 Accumulator Level #21 (%) 52 l Fan Cooler Units #21 0 #22 (%) 52 l #22 0 #23 (%) 52 l #23 0 #24 (%) 52

1. 24 0 BIT Level (%) 10

1. 25 0 BIT Pressure (PSIG) 15 l

Legend: 0 = Operating O/S = Out of Service l S = Standby

• = Change on status from previous log.

Vl-9 l

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PLANT STATUS LOG SCENARIO NO. 4B REV. O PARAMETER TIME PARAMETER TIME 10:10 10:10 Offaite Power Available 138KV 0/S* Service Water Pumps #21 0 13.8KV 0/S* (Essential Header) #22 0 Ecorgency D/Gs #21 0 #23 S

1. 22 0 #24 S

1. 23 0 #25 0 SIS' Pumps #21 0/S #26 0

1. 22 0/S Component Cool Heat Exchf21 0

1. 23 0 #22 0 RHR Pumps #21 S RHR Heat Exchanger #21 S

1. 22 S #22 S Charging Pumps #21 O Hydrogen Recombiner #21 S

1. 22 S #22 S

1. 23 S VC Isolation (A/B) YES Containment-Spray Pumps #21 S Exceptions

1. 22 S PCV-Il91 & 1192 Open Recirculation Pumps #21 S PCV-1190 Closed

1. 22 S High Head SIS Flow #21 (GPM) 75*

Cooponent Cooling Pumps #21 0 #22 (GPM) 75*

1. 22 0 #23 (GPM) 75*

1. 23 S #24 (GPM) 75*

Aux Component Cooling Pumps #21 S Low Head SIS Flow #21 (GPM) 0

1. 22 S #22 (GPM) 0 Aux Boiler Feed Pumps #21 0/S* #23 (GPM) 0

1. 22 0/S #24 (GPM) 0

1. 23 0/S* Accumulator Level #21 (%) 52 Fan Cooler Units #21 0 #22 (%) 52

1. 22 0 #23 (%) 52

1. 23 0 #24 (%) 52

1. 24 0 BIT Level (%) 10

1. 25 0 BIT Pressure (PSIG) 15

~Lsgend: 0 = Operating O/S = Out of Service S = Standby -

• = Change on status from previous log. i VI-10

)

PLANT STATUS LOG SCENARIO NO. 4B REV. O PARAMETER TIME PARAMETER TIME 10:25 10:25 Offsite Power Available 138KV 0/S Service Water Pumps #21 0 13.8KV O/S (Essential Header) #22 0 E=orgency D/Gs #21 0 #23 S

1. 22 0 #24 S

1. 23 0 #25 0

, SIS Pumps #21 0/S #26 0

1. 22 0/S Component Cool Heat Exchf21 0

1. 23 0 #22 0 RHR Pumps #21 S RHR Heat Exchanger #21 S

1. 22 S #22 S Charging Pumps #21 0 Hydrogen Recombiner #21 S

1. 22 S #22 S

1. 23 S VC Isolation (A/B) YES Containment Spray. Pumps #21 S Exceptions

1. 22 S PCV-Il91 & 1192 Open Rocirculation Pumps '#21 S PCV-1190 Closed

1. 22 S High Head SIS Flow #21 (GPM) 0*

Co=ponent Cooling Pumps #21 0 #22 (GPM) 0*

1. 22 0 #23 (GPM) 0*

1. 23 S #24 (GPM) 0*

Aux Component Cooling Pumps #21 S Low Head SIS Flow #21 (GPM) 0

1. 22 S #22 (GPM) 0 Aux Boiler Feed. Pumps #21 0/S #23 (GPM) 0

1. 22 0/S #24 (GPM) 0

1. 23 0/S Accumulator Level #21 (%) 52 Fan Cooler Units #21 0 #22 (%) 52

1. 22 0 #23 (%) 52

1. 23 0 #24 (%) 52

1. 24 0 BIT Level (%) 10

1. 25 0 BIT Pressure (PSIG) 15 Legend: 0 = Operating O/S = Out of Service S = Standby

• = Change on status from previous log.

VI-ll

~ _ _

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O O PLANT STATUS LOG SCENARIO NO. 4B REV. O PARAMETER TIME PARAMETER TIME 11:10 11:10 Offsite Pcwer Available 138KV 0/S Service Water Pumps #21 0 13.8KV O/S (Essential Header) #22 0 Easrgency D/Gs #21 0 #23 S

1. 22 0 #24 S

1. 23 0 #25 0 SIS Pumps #21 0/S #26 0

1. 22 0/S Component Cool Heat Exchf21 0

1. 23 0 #22 0 RHR Pumps #21 S RHR Heat Exchanger #21 S

1. 22 S #22 S Charging Pumps #21 O Hydrogen Recombiner #21 S

1. 22 S #22 S

1. 23 S VC Isolation (A/B) N0*

Containment-Spray rumps #21 S Exceptions

1. 22 S PCV-1190, 1191 & 1192 Open Recirculation Pumps #21 S

1. 22 S High Head SIS Flow #21 (GPM) O Couponent Cooling Pumps #21 0 #22 (GPM) 0

1. 22 0 #23 (GPM) 0

1. 23 S #24 (GPM) 0 Aux Component ~ Cooling Pumps #21 S Low Head SIS Flow #21 (GPM) 0

1. 22 S #22 (GPM) 0 Aux Boiler Feed Pumps #21 0/S #23 (GPM) 0

1. 22 0/S #24 (GPM) 0

1. 23 0/S Accumulator Level #21 (%) 52

~Fcn Cooler Units #21 0 #22 (%) 52

1. 22 0 #23 (%) 52

1. 23 0 #24 (%) 52

1. 24 0 BIT Level (%) 10

.#25 0 BIT Pressure (PSIG) 15 Lagend: 0 = Operating.

0/S = Out of Service S- = Standby

• = Change on status from previous log.

VI-12

(

PLANT STATUS LOG SCENARIO NO. 4B REV. O PARAMETER TIME PARAMETER TIME 12:40 12:40 Offsite Power Available 138KV 0/S Service Water Pumps #21 0 13.8KV 0/S (Essential Header) #22 0 Exorgency D/Gs #21 0 #23 S

1. 22 0 #24 S

1. 23 0 #25 0 SIS Pumps #21 0/S #26 0

1. 22 0/S Component Cool lle a t Exchl21 0

1. 23 0 #22 0 RHR Pumps #21 S RHR Heat Exchanger #21 S

1. 22 S #22 S Charging Pumps #21 0 liydrogen Recombiner #21 S

1. 22 S #22 S

1. 23 S VC Isolation (A/B) YES*

Containment Spray Pumps #21 S Exceptions

1. 22 S PCV-1190 & 1192 Open Racirculation Pumps #21 S PCV-1191 Closed

1. 22 S liigh llead SIS Flow #21 (GPM) 0 Cenponent Cooling Pumps #21 0 #22 (GPM) 0

1. 22 0 #23 (GPM) 0

1. 23 S #24 (CPM) 0 Aux Component Cooling Pumps #21 S Low Head SIS Flow #21 (GPM) 0

1. 22 S #22 (GPM) 0 Aux Boiler Feed Pumps #21 0/S #23 (GPM) 0

1. 22 0/S #24 (GPM) 0

1. 23 0/S Accumulator Level #21 (%) 52 Fen Cooler Units #21 0 #22 (%) 52

1. 22 0 #23 (%) 52

1. 23 0 #24 (%) 52

1. 24 0 BIT Level (%) 10

1. 25 0 BIT Pressure (PSIG) 15 L9gond: 0 = Operating O/S = Out of Service S = Standby

• = Change on status from previous log.

VI-13

CO "O O PLANT STATUS LOG SCENARIO NO. 4B REV. O PARAMETER TIME PARAMETER TIME 12:55 12:55 Offsite Power Available 138KV O/S Service Water Pumps #21 0 13.8KV 0/S (Essential Header) #22 0 Energency D/Gs #21 0 #23 S

1. 22 0 #24 S

1. 23 0 #25 0 SIS Pumps #21 0/S #26 0

1. 22 0/S Component Cool Heat Exchf21 0

1. 23 0 #22 0 RHR Pumps #21 S RHR Heat Exchanger #21 S

1. 22 S' #22 S Charging Pumps #21 0 Hydrogen Recombiner #21 S

1. 22 S #22 S

1. 23 S VC Isolation (A/B) YES Containment Spray Pumps #21 S Exceptions

$22 S PCV-Il90 & 1192 Open Rocirculation Pumps #21 S PCV-Il91 Closed

1. 22 S High Head SIS Flow #21 (GPM) 0 Component Cooling Pumps #21 0 #22 (GPM) 0

1. 22 0 #23 (GPM) 0

1. 23 S #24 (GPM) 0 Aux Component Cooling Pumps #21 S Low Head SIS Flow #21 (GPM) 0

1. 22 S #22 (GPM) 0 Aux Boiler Feed Pumps #21 0* #23 (GPM) 0

1. 22 0/S #24 (GPM) 0

1. 23 0/S Accumulator Flow #21 (%) 52 Fan Cooler Units #21 0 #22 (%) 52

1. 22 0 #23 (%) 52

1. 23 0 #24 (%) 52

1. 24 0 BlT Level (%) 10

1. 25 0 BIT Pressure (PSIG) 15 Legend: 0 . -- Operating 0/S = Out of Service S = Standby

• = Change'on status from previous log.

VI-14

~

PLANT STATUS LOG SCENARIO NO. 4B REV. O PARAMETER TIME PARAMETER TIME 13:25 13:25 Offsite Power Available 138KV 0* Service Water Pumps #21 0 13.8KV 0* (Essential Header) #22 0 E=orgency'D/Gs #21 0 #23 S

1. 22 0 #24 S

1. 23 0 #25 0 SIS Pumps #21 0/S #26 0

1. 22 0/S Component Cool Heat Exchl21 0

1. 23 0 #22 0 RHR Pumps #21 S RHR Heat Exchanger #21 S

1. 22 S #22 S Charging Pumps #21 0 Hydrogen Recombiner #21 S

1. 22 S #22 S

1. 23 S VC Isolation (A/B) YES*

Centainment Spray Pumps #21 S Exceptions

1. 22 S PCV-Il90 Open

'Rocirculation Pumps #21 S PCV-Il91 & 1192 Closed

1. 22 S High Head SIS Flow #21 (GPM) 50*

Cooponent Cooling Pumps #21 0 #22 (GPM) 50*

1. 22 0 #23 (GPM) 50*

1. 23 S #24 (GPM) 50*

Aux Componenc Cooling Pumps #21 S Low Head SIS Flow #21 (GPM) 0

1. 22 S #22 (CPM) 0 Aux Boiler Feed Pumps #21 0 #23 (GPM) 0

1. 22 0/S #24 (GPM) 0

1. 23 0* Accumulator Level #21 (%) 52 Fen Cooler Units- #21 0 #22 (%) 52

1. 22 0 #23 (%) 52

1. 23 0 #24 (%) 52

1. 24 0 BIT Level (%) 10

, #25 0 BIT Pressure (PSIG) 15 Legend: 0. = Operating

O/S = Out of Service S = Standby

• = Change on status from previous log.

VI-15

,{ e PLANT STATUS LOG SCENARIO NO. 4B REV. O PARAMETER TIME PARAMETER TIME 14:10 14:10 Offolte Power Available 138KV 0 Service Water Pumps #21 0 13.8KV O (Essential Header) #22 0 Ecorgency D/Gs #21 S* #23 S

1. 22 S* #24 S

1. 23 S* #25 0 SIS Pumps #21 0/S #26 0

1. 22 0/S Component Cool Heat Exchf21 0

1. 23 S* #22 0 RHR Pumps #21 S RHR Heat Exchanger #21 0*

1. 22 S #22 0*

Charging Pumps #21 0 Hydrogen Recombiner #21 S

1. 22 0* #22 S

1. 23 S VC Isolation (A/B) YES Containment Spray Pumps #21 S Exceptions

. #22 S PCV-Il90 Open Racirculation Pumps #21 0* PCV-1191 & 1192 Closed

1. 22 S High Head SIS Flow #21 (GPM) 0*

4 Cocponent Cooling Pumps #21 0 #22 (GPM) 0*

1. 22 0 #23 (GPM) 0*

4

1. 23 S #24 (GPM) 0*

Aux Component Cooling Pumps #21 0* Low Head SIS Flow #21 (GPM) 400*

1. 22 0* #22 (CPM) 400*

Aux Boiler Feed Pumps #21 0 #23 (GPM) 400*

1. 22 0/S #24 (CPM) 400*

1. 23 0 Accumulator Level #21 (%) 52 Fen Cooler Units #21 0 #22 (%) 52

1. 22 0 #23 (%) 52

1. 23 0 #24 (%) 52

1. 24 0 BIT Level (%) 0*

1. 25. O BIT Pressure (PSIG) 0*

Legend: 0 = Operating O/S = Out of Service S = Standby

• = Change on status from previous log.

VI-16

(D "O RADIOLOGICAL / METEOROLOGICAL LOG

's SCENARIO NO. 4B REV. O PARAMETER TIME 08:00 08:15 08:45 09:00 09:10 09:11 09:12 R-1 CCR mR/hr 0.1 0.1 0.1 0.1 0.1 0.1 0.1 R-2 VC 80' mR/hr 1 1 1 1 1 2 4 R-4 Chrg. Pump mR/hr 1 1 1 1 1 1 1 R-5 F.S.B. mR/hr 0.2 0.2 0.2 0.2 0.2 0.2 0.2 R-6 Sample Rm mR/hr 2 2 2 2 2 2 2 R-7 VC Seal Table mR/hr 5 5 5 5 5 8 12 R-8 Drum Sta, mR/hr 0.5 0.5 0.5 0.5 0.5 0.5 0.5 R-10 Stm Line Penet mR/hr 0 0 0 0 0 0 0 R-ll VC Part CPM 37,000 37,000 37,000 37,000 37,000 N/A N/A R-12 VC Gas CPM 3,000 3,000 3,000 3,000 3,000 N/A N/A R-13 Vent Part CPM 1,500 1,500 1,500 1,500 1,500 1,500 1,500 R-14 Vent Gas CPM 1,800 1,800 1,800 1,800 1,800 1,800 1,800 R-15 Air Ejector CPM 200 200 200 200 200 200 N/A R-16 F.C. Water CPM 1,300 1,300 1,300 1,300 1,300 1.300 1,300 R-17 Comp. Cool CPM 400 400 400 400 400 400 400 R-18 Liquid Waste CPM 6,000 6,000 6,000 6,000 6,000 6,000 6,000 R-19 S/G B.D. CPM 500 500 500 500 500 500 500 R-23 F.C. Water CPM 1,900 1,900 1,900 1,900 1,900 1,900 1,900 R-25 VC Hi-Rge R/hr 0 0 0 0 0 0 0 R-26 VC Hi-Rge R/hr 0 0 0 0 0 0 0 R-27 Vent Monitor uCi/cc 0 0 0 0 0 0 0 R-27 Vent Flow Rate CFM 45,000 45,000 45,000 45,000 45,000 45,000 45,000 R-27 Vent Dis Rate uC1/sec 0 0 0 0 0 0 0 Main Steam #21 Rad Mon CPM 250 250 250 250 250 250 250

1. 22 275 275 275 275 275 275 275

1. 23 300 300 300 300 300 300 300

1. 24 285 285 285 285 285 285 285 Vant Flow Rate CFM 45,000 45,000 45,000 45,000 45,000 45,000 45,000 6 6 6 Main Steam Exh Lbs/Hr 3x 10 3x 10 3x 10 3x 10 6 3 x 10 6

2.4 x 10 6

0 Air Ej ector CFM (osasured value) N/A N/A N/A N/A N/A N/A N/A METEOROLOGICAL Wind Speed (meters /sec) 6.8 6.8 6.8 6.8 6.8 6.8 6.8 Wind Direction (degrees) 270 270 270 270 270 270 270 Porquill Stability Category D D D D D D D VII-l

RADIOLOGICAL / METEOROLOGICAL LOG SCENARIO NO. 4B REV. O PARAMETER TIME 09:13 09:14 09:15 09:20 09:25 09:40 09:55 R-1 CCR mR/hr 0.1 0.1 0.1 0.1 0.1 0.1 0.1 R-2 VC 80' mR/hr 7 8 10 10 11 13 13 R-4 Chrg. Pump mR/hr 1 1 1 1 1 1 1 R-5 F.S.B. mR/hr 0.2 0.2 0.2 0.2 0.2 0.2 0.2 R-6 Sample Re mR/hr 2 2 2 2 2 2 2 R-7 VC Seal Table mR/hr 13 15 17 18 20 22 22 R-8 Drum Sta, mR/hr 0.5 0.5 0.5 0.5 0.5 0.5 0.5 R-10 Stm Line Penet mR/hr 0 0 0 0 0 0 0 R-11 VC Part CPM N/A N/A N/A N/A N/A N/A N/A R-12 VC Gas CPM N/A N/A N/A N/A N/A N/A N/A R-13 Vent Part. CPM 1,500 1,500 1,500 1,500 1,500 1,500 1,500 R-14 Vent Gas CPM 1,800 1,800 1,800 1,800 1,800 1,800 1,800 R-15 Air Ejector CPM N/A N/A N/A N/A N/A N/A N/A R-16 F.C. Water CPM 1,300 1,300 1,300 1,300 1,300 1.300 R-17 Comp. Cool CPM 1.300 400- 400 400 400 400 400 400

.R-13 Liquid Waste CPM 6,000 6,000 6,000 6,000 6,000 6,000 6,000 R-19 S/G B.D. CPM 500 500 500 500 500 500 500 R-23 F.C. Water CPM 1,900 1,900 1,900 1,900 1,900 1,900 1,900 R-25 VC Hi-Rge R/hr 0 0 0 0 0 0 0 R-26 VC Hi-Rge R/hr 0 0 0 0 0 0 0 R-27 Vent Monitor uCi/cc 0 0 0 0 0 0 0 R-27 Vent Flow Rate'CFM 45,000 45,000 45,000 45,000 45,000 45,000 45,000 R-27 Vent Dis Rate uCi/sec 0 0 0 0 0 0 0 Main Steam #21 Rad Mon CPM 250 250 250 250 250 250 250

1. 22 275 275 275 275 275 275 275

1. 23 300 300 300 300 300 300 300

1. 24 285 285 285 285 285 285 285 Vent Flow Rate CFM 45,000 45,000 45,000 45,000 45,000 45,000 45,000 Mein Steam Exh Lbs/Hr 0 0 0 0 0 0 0 Air Ejector CFM (coasured value) N/A N/A N/A N/A N/A N/A N/A METEOROLOGICAL Wind Speed (meters /sec) 6.8 6.8 6.8 6.8 6.8 6.8 6.8 Wind Direction (degrees) 270 270 270 270 270 270 270 Pecquill Stability Category D D D- D D D D 4

VII-2

RADIOLOGICAL / METEOROLOGICAL LOC SCENARIO NO. 4B REV. O PARAMETER TIME 10:10 10:15 10:20 10:25 10:30 10:35 10:40 R-1 CCR mR/hr 0.1 0.1 0.1 0.1 0.1 0.1 0.1 R-2 VC 80' mR/hr 14 15 16 17 17 18 19 R-4 Ch'rg. Pump mR/hr .

I 1 1 1 1 1 1 R-5 F.S.B. mR/hr 0.2 0.2 0.2 0.2 0.2 0.2 0.2 R-6 Sample Rm mR/hr 2 2 2 2 2 2 2 R-7 VC Seal Table mR/hr 23 25 28 31 34 36 38 R-8 Drum Sta. mR/hr 0.5 0.5 0.5 0.5 0.5- 0.5 0.5 R-10 Sem Line Penet mR/hr 0 0 0 0 0 O_ 0 R-11 VC Part CPM N/A N/A N/A N/A N/A N/A N/A R-12 VC Gas CPM- N/A N/A N/A N/A N/A N/A N/A R-13 Vent Part CPM 1,500 1,500 1,500 1,500 1,500 1,500 1,500 R-14 Vent Gas CPM 1,800 1,800 1,800 1,800 1,800 1,800 1,800 R-15 Air Ej ec tor CPM N/A N/A N/A N/A N/A N/A N/A R-16 F.C. Water CPM 1,300 1,300 1,300 1,300 1,300 1,300 1,300

.R-17: Comp. Cool CPM 400 '400 400 400 400 400 400 R-18 Liquid Waste CPM 6,000 6,000 6,000 6,000 6,000 6,000 6,000 R-19 S/G B.D. CPM 500 500 500 500 500 500 500 R-23 F.C. Water CPM 1,900 1,900 1,900 1,900 1,900 1,900 1,900 R-25 VC Hi-Rge R/hr 0 0 0 0 0 0 0 '

R-26 VC Hi-Rge R/hr 0 0 0 0 0 0 0 R-27 Vent' Monitor uCi/cc 0 0 0 0 0 0 0 R-27 Vent Flow Rate CFM 45,000 45,000 45,000 45,000 45,000 45,000 45,000 R-27 Vent Dis Rate uCi/sec 0 0 0 0 0 0 0 Main Steam #21 Rad Mon CPM 250 250 250 250 250 250 250

1. 22 275 275 275 275 275 275 275

1. 23 300 300 300 300 300 300 300

1. 24 285 285 285 285 285 285 285 Vont Flow Rate CFM 45,000 45,000 45,000 45,000 45,000 45,000 45,000 Main Steam Exh Lbs/Hr 0 0 0 0 0 0 0 Air, Ejector CFM (coasured value) N/A N/A N/A N/A N/A N/A N/A METEOROLOGICAL Wind Speed (meters /sec) 6.8 6.8 6.8 6.8 6.8 6.8 6.8 Wind Direction'(degrees) 270 270 270 270 270 270 270 Pasquill Stability Category D D D D D D D VII-3

[ .  ;

RADIOLOGICAL / METEOROLOGICAL LOG SCENARIO ho. 4B REV. 0

.s * '1 PARAMETER . TIME 10:55 _ 11:10 11:25 11:40 11:55, 12:10 12:35

/ . ,

, /

R-1 CCR mR/hr

^

. ' , - ~, ,

0.1 0.1 0.1 ' O .1, 0.1 0.1 0 .' 1 R-2 VC 80' mR/hr ,

< , 20 1000 0FFSCALE OFFSCALE ,0FFSCALE ;OFFSCALE OFFSCALE R-4 Chrg. Pump mR/hr r - n, .

1 1 1 1 1

, 1 1.

R-5 F.S.B. mR/hVE- 0.2 0.2 0.2 0.2 0. 2 ' 'O . 2 0.2 R-6 Sample Rm mR/hr 2 2 2 2 2  ; 2 2 R-7 VC Seal Table mR/hr ,39 0FFSCALE OFFSCALE OEFSCALE OFFSCALE ~ OFFSCALE OFFSCALE R-8 Drum Sta. mR/hr 0.5 0.5 0.5 u t S' 0:5- 0.5 0.5 R-10 Stm Line Penet mR/hr 'O '

O 15 e50 '

300 .

300 ' . 300 R-11 VC Part CPM , N/A N/A N/A N/A N/A N/A '

N/A R-12 VC Gas CPM N/A , N/A N/A N/A N/A N/A #/A ,

, R-13 Vent Part CPM 1,5 0 0< OFFSCALE OFFSCALE OFFSCALE OFFSCALE OFFSCALE OFFSCALE R-14 Vent Gas CPM 1,800 0FFSCALE OFFSCALE',OFFSCALE OFFSCALE OFFSCALE /SFFSCALE R-15 Air Ejector CPM N/A N/A N/A N/A N/A' R/A

' M/A R-16 F.C. Water CPM 1,300 1 ,.3 0 0 j 1,300 1,300 ,', 1,300 1.,300 1,300 R-17 Comp. Cool CPM , .4 0 0 "400 400 400 ' 400- 400 R-18 Liquid Waste CPM j 6,000 6.000 ; 6,000 l 6,0G0 6,000 6[400000 ,

6,'000 Ril9 S/G B.D. CPM 500 500 500 f 500 500 500 500 Wajter CTM-

~

R '23 F.C. it,900 1,900 1,900 1,900 l',900 1/, 9 0 0 ~' 1,900 ,

R-25 VC Hi-Rge R/hr 0 '

1.0 40 190 870 880 900 K-26 VC Hi-Rge R/hr 0 /'

1. 9 - 60 250 1,000 1,000 1,000

.R-27 Vent Monitor uCi/cc 0' ',' 47 47 3 47 57 62 208 R-2 7 'Ve n't Flow Rate CFM 45,000 ' 45,g00 45,000 9

45,000 45,000 45,000 45,00g 9

R22.7 Veit t Yh.3d, Rate uCi/sec 0, c10 10 10 1.2x10 9 1.3x10 9

4.4x10 TMain Sfaafif2f 2ad Mon CPM  ! ' '

250 , '4 ~

250 250 250 250 '250 250 ,

, <?[f2,2(J ',

275- 275 275 275 2'75 275 275

,, #23 ', l 300 e 300 300 300 300 300 300

1. 24 'a -

285 285 285 285 285 285 285 Vent Flow Rate CFM 45,000 45,000 45,000 45,000 45,000 45,000 45,000 Main Steam Exh Lbs/Hr 0 0 0 0 0 0 0 Air-Ejector CFM (consured value) N/A N/A N/A N/A N/A N/A N/A METEOROLOGICAL Wind Speed (meters /sec) 6.8 6.8 6.8 6.8 6.8 6.8 6.8 Wind Direction (degrees) 270 270 270 225 225 225 225 Pesquill Stability Category D D D D D D D VII-4

RADIOLOGICAL / METEOROLOGICAL LOG SCENARIO NO. 4B REV. O PARAMETER TIME 12:40 12:55 13:10 13:25 13:40 13:55 14:10 R-1 CCR mR/hr 0.1 0.1 0.1 0.1 0.1 0.1 0.1 R-2 VC 80' mR/hr OFFSCALE OFFSCALE OFFSCALE OFFSCALE OFFSCALE OFFSCALE OFFSCALE R-4 Chrg. Pump mR/hr 1 1 1 1 1 1 1 R-5 F.S.B. mR/hr 0.2 0.2 0.2 0.2 0.2 0.2 0.2 R-6 Sample Rm mR/hr 2 2 2 2 2 2 2 R-7 VC Seal Table mR/hr OFFSCALE OFFSCALE OFFSCALE OFFSCALE OFFSCALE OFFSCALE OFFSCALE R-8 Drum Sta, mR/hr 0.5 0.5 0.5 0.5 0.5 0.5 0.5 R-10 Stm Line Penet mR/hr 300 300 300 200 200 200 50 R-Il VC Part CPM N/A N/A N/A N/A N/A N/A N/A R-12 VC Gas CPM N/A N/A N/A N/A N/A N/A N/A R-13 Vent Part CPM 1,500 1,500 1,500 1,500 1,500 1,500 1,500 R-14 Vent Gas CPM 1,800 1,800 1,800 1,800 1,800 1,800 1,800 R-15 Air Ej ector CPM N/A N/A N/A N/A N/A N/A N/A R-16 F.C. Water CPM 1,300 1,300 1,300 1,300 1,300 1,300 1.300 R-17 Comp. Cool CPM 400 400 400 400 400 400 400 R-18 Liquid Waste CPM 6,000 6,000 6,000 6,000 6,000 6,000 6,000 R-19 S/G B.D. CPM 500 500 500 500 500 500 500 R-23 F.C. Water CPM 1,900 1,900 1,900 1,900 1,900 1,900 1,900 R-25 VC lii-Rge R/hr 900 900 900 700 700 700 2 R-26 VC 111-Rge R/hr 1,000 1,000 1,000 800 800 800 5 R-27 Vent Monitor uCi/cc 0 0 0 0 0 0 0 R-27 Vent Flow Rate CFM 45,000 45,000 45,000 45,000 45,000 45,000 45,000 R-27 Vent Dis Rate uCi/sec 0 0 0 0 0 0 0 Mcin Steam #21 Rad Mon CPM 250 250 250 250 250 250 250

1. 22 275 275 275 275 275 275 275 f23 300 300 300 300 300 300 300

1. 24 285 285 285 285 285 285 285 Vont Flow Rate CFM 45,000 45,000 45,000 45,000 45,000 45,000 45,000 Main Steam Exh Lbs/Hr 0 0 0 0 0 0 0 Air Ejector CFM (acasured value) N/A N/A N/A N/A N/A N/A N/A METEOROLOGICAL Wind Speed (meters /sec) 6.8 6.8 6.8 6.8 6.8 6.8 3.4 Wind Direction (degrees) 225 225 225 225 225 225 90 Pecquill Stebility Category D D D D D D A VII-5

-- _---_m__.- -_ _ . __ __ __

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lm'. ? . CONSOLIDAIED' EDISON COMPANY OF NEW YORK f

e IND I AN ,;,

• POINT UN-IT NO . 2

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i. DRILL S CENARIO NO. 4B REV. O

~ ,

, , . f ,

- ,VIII RAD I'3 LOG IC A L INFORMATION 4 ,

TAB A T1BLE; f: Primdry Coolan.t Activity

'> j _

TAB B;T.ABLE,2: Containment Activity

< ~

f T AE.i. C ,TA BL E 3: Release Path, Activity

^* TAB D, TABLE 4: Plant Radiation Levels 3

TAB E TABLE 5: Facility Radiation Levels

' TAB F TA3LE 6: Reuter-Stokes Readings TAB G TABL5'7 6 Plume Monitoring Data & Figures tab H TABLE 8: Offsite TLD Readings 4

TAB I TABLE 9: Post Accident Samples L -

r TAB J TABLE 10: Post Accident Offsite Contami-

/

nation Levels

. ^

l/

4

' TAB K TABLE 11: Medical _ Emergency Data c.

b

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g A f N .

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, , . - . , . . ,. ,r.

SCENARIO NO. 4B REV.0 TABLE 1

)

PRIMARY COOLANT ACTIVITY 08:00 hrs. 10:40 hrs. 11:10 hrs. 11:40 hrs.

Nuclide uC1/ml uC1/ml uC1/ml uC1/ml

~I ~1 1-131 2.3x10 5.6x10 ~I 1.0 8.1

-2 132 8.2x10 8.2x10 1.5 11.7

~I 133 3.2x10 1.2 2.3 17.6

-2 134 4.3x10 1.4 2.5 19.8

~I 135 1.3x10 1.1 2.1 16.1 Xe-133 20.0

_1 76.2 145.7 1,130 133m 2.6x10 22.1 42.3 330

-1 135 4.7x10 24.6 47.0 370

-2 135m 3.3x10 12.3 23.5 180

-2 138 4.5x10 17.2 32.9 260 Kr-85 2.5 4.7 40.0 85m 2.6x10[f 260 1.5x10- 17.2 32.9 87 8.5x10_21 29.5 56.4 440 88 2.6x10 44.2 84.6 660

! Te-132 2.5x10[2 1.0x10[3 1.8x15[f 1.4

_1 Cs-134 1.7x15 9.2x10 1.7x10~ 1.3x10 -2

-2 137 3.0x10 4.6x10 -3 8.4x10 6.5x10

-3 -3 -3 -2 138 5.1x10 4.6x10 8.4x10 6.5x10 ~

-5 -2 ~I

) Ce-144 2.9x10 6.9x10 1.3x10 9.8x10 v -4 ~I -1 Le-140 1.2x10 1.4x10 2.5x10 2.0

~I ~I 3.3x10 '

~

Ba-140 1.3x10 2.4x10 1.9 Data to be provided to Chemistry personnel I hour after the sample is obtained.

i i

R v

f.

-VIII-2

SCENARIO NO. 4B REV.0

[ TABLE 1 (Continued) e PRIMARY COOLANT ACTIVITY 12:10 hrs. 12:40 hrs. 14:10 hrs.*

Nuclide uCi/ml uC1/ml uC1/ml

~I I-131 14.0 17.0 1.8x10 132 20.4 25.6 2.6x10[

133 134 30.5 34.3 38.4 43.2 3.8.10_f 4.3x10 7

~1 135 28.0 35.2 3.5x10 Xe-133 1,960 2,480 24.8 133m 570 720 7.2-135 640 800 8.0 135m 320 400 4.0 138 450 560 Kr-85 70.0 80.0 5.6 8x10

_7 85m 450 560 5.6 87 760 960 9.6 88 1,140 1,440 14.4

-2 Te-132- 2.5 3.1 Cs-134

_7 -1 3.1x10_3 2.3x10_1 2.8x10,1 2.9x10 -3 137 1.1x10 ~

1.4x10 ~

1.4x10 138 1.1x10 1.4x10 1.4x10[3

, Ce-144 1.7 2.1 2.1x10 Le-140 -2 3.4 4.3 4.3x10 l

{V. Ba-140 3.3 4.1 4.1x10

~

Data to be provided.co Chemistry personnel I hour after the sample is obtained.

. *Two (2) days later i

l I

l l

v l.i VIII-3

SCENARIO NO. 4B REV.0 l

l TABLE 2 l CONTAINMENT ACTIVITY 09:40 hrs 10:40 hrs 11:40 hrs 12:40 hrs 14:10*

Nuclide uC1/cc uCi/cc uCi/cc uC1/cc uC1/cc

-3 -2 -1 -3 I-131 9.5x10 -

5.6x10 -2 8.1.10--1 1.8x10

-1 1.8x10

-3 132 1.4x10 8.2x10 1.2x10 2.6x10 2.6x10

-2 -1 -1 -I -3

( 133 2.1x10 1.2x10 1.8x10 3.8x10 3.8x10

-3

-2 -1 -I -I

134 2.3x10 1.4x10 2.0x10 4.3x10 4.3x10

-2 -1 -1 -I -3 l 135 1.9x10 1.1x10 1.6x10 3.5x10 3.5x10

-1 Xe-133 6.7x10 7.63 113 248 2.48

-I 133m 1.9x10 2.21 33 72 0.72

-1 135 2.2x10 2.46 37 80 0.80

-I 135m 1.1x10 1.23 18 40 0.40 138 1.5x10[ 1.72 26 56 0.56 Kr-85 85m 2.2x10_f 1.5x10_g 0.25 1.72 4

26 8

56 0.08 0.56 1

87 2.95 44 96 0.96 88 2.6x10_7 3.9x10 4.43 66 144 1.44

-3 -2 -2 -2 -4 Te-132 1.7x10- 1.0x10 1.4x10 3.1x10 3.1x10

-4 Cs-134 1.5x10 9.2x10 -4 1.3x10

-3 2.8x10

-3 2.9x10 -5

-5 - -

-5 137 7.6x10 4.6x10 1.4x10 1.4x10 138 7.1x10

-5 4.6x10 6.5x10 6.5x10

'4 1.4x10

-3 1.4x10

-5

-3 -3 -3 -2 -4 q Ce-144 1.1x10

-3 6.9x10

-2 9.8x10

-2 2.1x10

-2 2.1x10

-4 A/ La-140 2.3x10

-3 1.4x10

-2 2.0x10

-2 4.3x10 -2 4.3x10 -4 12 Ba-140 2.2x10 1.3x10 1.9x10 4.1x10 4.2x10 l

Data to be provided to Chemistry personnel I hour after the sample is obtained.-

• Two (2) days later O

v .

VIII-4

SCENARIO NO. 4B REV.0

. ) TABLE 3 RELEASE PATH ACTIVITY l

RELEASE PATH MEASUREMENT METHOD TIME RADIATION LEVELS PLANT VENT VENT CONTACT METHOD 4 11:11 0.01 R/hr 11:11 380 R/hr 11:25 680 R/hr 6 11:40 0FFSCALE >10 mR/hr

> 12 : 4 0 0.10 R/hr PLANT VENT CHEMISTRY SAMPLE 11:11 Noble Gases 47.1 uCi/cc I-131/5.18 x 10[ uCi/cc I-132/7.54 x 10 uCi/cc I-133/1.13 x 10[3 uci/cc I-134/1.27 x 10 -3 uCi/cc I-135/1.04 x 10 uCi/cc 11:40 Noble Gases /367.2 uC1/cc I-131/4.04 x 10~ uC1/cc I-132/5.87 x 10[3 uCi/cc

(( ) I-133/8.81 x 10 -3 uC1/cc I-134/9.91 x 10 -3 uCi/cc I-135/8.07 x 10 uci/cc 12:10 Noble Gases /635.6 uC1/cc

-3 I-131/7.00 x 10 -2 uC1/cc I-132/1.02 x 10 -2 uC1/cc I-133/1.53 x 10 -2 uC1/cc I-134/1.72 x 10 -2 uCi/cc I-135/1.40 x 10 uC1/cc 12:30' Noble Gases /743.9 uC1/cc I-131/8.18 x 10[32 uC1/cc I-132/1.19 x 10 -2 uCi/cc I-133/1.79 x 10 -2 uC1/cc ,

I I-134/2.01 x 10 -2 uC1/cc I-135/1.64 x 10 uCi/cc NOTE: Vent contract reading provided to Rad-Prot Tech. Chemistry data available'30-minutes after the sample is taken.

VIII-5 I

i l

SCENARIO NO. 4B REV.0 TABLE 4 PLANT RADIATION LEVELS

~

1

(_/ LOCATION TIME RADIATION LEVELS General Vicinity of " stuck" < 11 : 10 Background Containment Pressure Relief 11:11 40 R/hr Valve PCV-1191 11:40 60 R/hr 12:10 90 R/hr 12:25 135 R/hr 12:45 2 R/hr Security Fence 09:10 4 1 mR/hr 10:40 3 mR/hr 11:10 >1 R/hr Aux Feed Pump No. 21 Radiation fields as measured SI Pumps Radiation fields as measured RCS Chemistry Sample 10:40 3.5 R/hr @ Contact 75 mR/hr @ 3' 11:10 7 R/hr @ Contact 140 mR/hr @ 3' 11:40 13 R/hr @ Contact 270 mR/hr @ 3' 12:10 10 R/hr @ Contact 430 mR/hr @ 3'

{'g 12:40 27 R/hr @ Contact g_) 600 mR/hr @ 3' 14:10 2.7 R/hr @ Contact 60 mR/hr @ 3' Plant Vent Chemistry Sample 11:11 780 mR/hr @ Contact 50 mR/hr @ 3' 11:40 2.6 R/hr @ Contact 96 mR/hr @ 3' 12:10 4.4 R/hr @ Contact 166 mR/hr @ 3' 12:30 5.2 R/hr @ Contact 195 mR/hr'@ 3' VC Chemistry Sample 10:40 1.2 R/hr @ Contact 100 mR/hr @ 3' 11:40 2.0 R/hr @ Contact 158 mR/hr @ 3' 12:40 4.4 R/hr @ Contact 300 mR/hr @ 3' NOTE 1: All loose contamination and airborne concentrations are j ) actual levels detected.

(.

NOTE 2: Data to be supplied to Rad Prot Tech at the locations after the survey is performed.

VIII-6

SCENARIO NO. 4B REV.0 -

l

) TABLE 5 FACILITY RADIATION LEVELS 1 METER HEIGHT READING 10 ft. AIR SAMPLE LOCATION TIME B +Y Y BKGD IODINE PART mR/hr mR/hr CPM CPM CPM Emergency All 41.0 41.0 200 200 200 Operation Times Facility (EOF)

Operational All 41.0 ( 1. 0 200 200 200 Support Times Center (OSC)

Technical All < 1. 0 < 1. 0 200 200 200 Support Times Center (TSC)

Control Room All < 1. 0 < 1. 0 200 200 200 (CR) Times Emergency All < 1. 0 < 1. 0 200 200 200 t

(()

~

News Center (ENC)

Times 4

Recovery All < 1. 0 < 1. 0 200 200 200 j Center (RC) Times a

d NOTE: Data to be supplied to Rad Protection Technician after the survey is completed.

~

O VIII-7 I

l

s

'O TO 'O i

SCENARIO NO. 4B REV.0 TABLE 6 REUTER-STOKES READINGS mR/hr TIME 1 2 3 4 5 6 7 8 9 10 11 4,11:18 <1 41 -41 <1 <1 41 41 <1 el- <1 <1 l'l:25 41 <1 3,000 50 11:40 .35 3,000 1,000 20 11:55 4,100 41 <1 <1 12:10 5,200 12:25 6,100 ,

12:40 12,100 12:55 20 13:00 <1 VIII-8

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' I; ; li Illi ii; lIl ;I  :!

SCENARIO NO. 4B REV.0 TABLE 7 PLUME MONITORING DATA-SECTORS 2 THRU 6 EMERGENCY / FIXED SAMPLE SITE NO. OR 1 METER HEIGHT READING 10 FT AIR SAMPLE DATA CENTERING DIRECTION B +Y Y BKGD IODINE PART TIME NO. DEG MILES mR/hr mR/hr CPM CPM CPM ALL TIMES 2 1-10 4 1 41 200 200 200 11:40 45 2 4 1 4 1 200 200 200 11:48 45 .2 1.600 1,460 200 860 200 11:55 45 2 1,770 1,600 200 870 200 12:10 45 2 1,750 1,590 200 980 200 12:25 45 2 1,800 1,650 200 1,045 200

.12:40 45 2 6,000 5,370 200 3,060 200 712:48 45 2 4 1 4 1 200 200 200 12:00 45 5 430 395 200 365 200 12:10 45 5 475 430 200 364 200 12:25 45 5 450 415 200 394 200 12:40 45 5 675 600 200 410 200 12:55 45 5 1,650 1,450 200 913

213:00 200s 45 5 <1 4 1 200 200 200" 12:20 45 10 180 160 200 260 200 12:25 45 10 185 170 200 262 200 12:40 45 10 190 175 200 278 200 12:55 45 10 220 205 200 285 200 13:10 45- 10 645 595 200 486 200

>13:20 45 10 4 1 41 200 200 200 11:44 3 1 3,790 3,500 200

• 2,400 200 11:55 3 1 5,080 4,200 200 2,550 200 12:15 3 1 6,280 5,800 200 2,350 200 12:25 3 1 7,150 6,600 200 3,000 200 12:40 3 1 23,500 21,500 200 5,480 200

. > 12 : 4 4 3 1 4 1 41 - 200 200 200 NOTE: Plume Center Line Direction Is Given In Degrees. The Emergency Or Fixed Sample Sites Are Indicated By Sector No. And Mile Distance.

VIII-10

SCENARIO NO. 4B REV.0 TABLE 7 (Continued)

PLUME MONITORING DATA-SECTORS 2 THRU 6 EMERGENCY / FIXED SAMPLE SITE NO. OR 1 METER HEIGHT READING 10 FT AIR SAMPLE DATA TIME CENTERING DIRECTION NO. DEC B +y y BKGD IODINE PART MILES mR/hr mR/hr CPM CPM CPM 11:47 3 2 1,570 1,460 200 850 200 11:55 3 2 1,700 1,540 200 880 200 12:10 3 2 1,740 1,590 200 1,000 200 12:25 3 2 2,620 2,500 200 1,040 200 12:40 3 2 7,000 5,370 200 3,000 200 712:47 3 2 4 1 4 1 200 200 200 11:52 3 3 1,100 1,000 200 650 200 12:10 3 3 1,240 1,100 200 660 200 12:25 3 3 1,450 1.300 200 12:40 780 200 3 3 3,000 2,350 200 712:52 1,150 200 3 3 4 < 1 200 1 200 200 ,

11:55 3 4 780 720 200 525 200 12:10 3 4 820 740 200 540 200 12:25 3 4 830 750 200 600

• 200 12:40 3 4 840 760 200 620 200 12:55 3 4 1,000 860 200 650 200

>13:00 3 4 < 1 <1 200 200 200 12:04 3 6 350 320 200 330 200 12:10 3 6 370 340 200 340 200 12:25 3 6 360 330 200 340 200 12:40 3 6 380 350 200 350 200 12:55 3 6 620 550 200 400 200

> 13:04 3 6 < 1 <1 200 200 200 NOTE:. Plume Center Line Direction'Is Given In Degrees. The Emergency Or Fixed Sample Sites Are Indicated By Sector No. And Mile Distance.

VIII-11

{

f/ i SCENARIO NO. 4B REV.0 TABLE 7 (Continued)

PLUME MONITORING DATA-SECTORS 2 THRU 6 EMERGENCY / FIXED SAMPLF SITE NO. OR 1 METER HEIGHT READING 10 FT AIR SAMPLE DATA CENTERING DIRECTION B +y T BKGD IODINE PART TIME NO. DEC MILES mR/hr mR/hr CPM CPM CPM 12:19 3 10 185 175 200 260 200 12:25 3 10 190 180 200 262 200 12:40 3 10 200 190 200 270 200 12:55 3 10 240 220 200 280 200

~13:10 3 10 625 595 200 470 200

> 13: 19 3 10 4 1 < 1 200 200 200 11:14 4 1 4 1 <1 200 200 200 11:25 4 1 2 2 200 201 200 11:40 4 1 5,080 4,200 200 2,500 200 11:45 4 1 5,750 5,000 200 3,010 200 11:50 4 1 4 3 200 210 200

• >11:55 4 1 < 1 <1 200 200 200 11:10 90 2 < 1 41 200 200 200 11:19 90 2 1,350 1,200 200 750 200 11:25 90 2 1,425 3,300 200 760 200 11:40 90 2 1,370 1,250 200 745 200

.>11:55 90 2 < 1 41 200 200 200 11:31 90 5 350 310 200 325 200 11:40 90 5 390 320 200 340 200 11:45 90 5 55 50 200 25 200

) 12:00 90 5 < 1 <1 200 200 200 ALL TIMES 90 10 <1 < 1 200 200 200 11:16 5 2 3,050 2,500 200 1,045 200 11:25 5 2 3,800 3,000 200 1,240 200 11:40 5 2 4,000 3,300 200 1,300 200

~>11:45 5 2 < 1 4 1 200 200 200 NOTE: Plume Center Line Direction Is Given In Degrees. The Emergency Or Fixed Sample Sites Are Indicated By Sector No. And Mile Distance.

VIII-12

q) O O SCENARIO NO. 4B REV.0 TABLE 7 (Continued)

PLUME MONITORING DATA-SECTORS 2 THRU 6 EMERGENCY / FIXED SAMPLE SITE NO. OR 1 METER HEIGHT READING 10 FT AIR SAMPLE DATA CENTERING DIRECTION B +y g BKGD IODINE PART TIME NO. DEG MILES mR/hr mR/hr CPM CPM CPM 11:24 5 4 480 450 200 365 200 11:40 5 4 480 400 350 200 200

>11:45 5 4 < 1 4 1 200 200 200 11:35 5 6 240 220 200 285 11:40 200 5 6 350 300 200

> 11:45 330 200 5 6 A 1 <1 200 200 200 ALL TIMES 5 10  % 1 < 1 200 200 200 ALL TIMES 6 1-10 < 1 4 1 200 200 200 NOTE: Plume Center Line Direction Is Given In Degrees. The Emergency Or Fixed Sample Sites Are Indicated By-Sector No. And Mile Distance.

VIII-13

SCENARIO NO. 4B REV.0 TABLE 7 (Continued)

PLUME MONITORING DATA-SITE BOUNDARY SEGMENTS (mR/hr)

WIND 1 2 3 4 5 6 TIME 11:00 DIR B + )( Y B+ 7 ( B+ Y Y B+ 7 Y B+ T ( B+ T T 270 4 1 4 1 4 1 4 1 4 1 <1 4 1 < 1 4 1 4 1 41 4 1 11:10 270 4 1 <1 12 10 1,320 1,200 14,200 12,900 1,320 1,200 12 10 11:20 270 < 1 <1 12 10 1,320 1,200 14,200 12,900 1,320 1,200 12 10 11:30 270 < 1 <1 12 10 1,320 1,200 14,200 12,900 1,320 1,200 12 10 11:40 225 14,200 12,900 1,340 1,200 650 600 <1 <1 4 1 4 1 < 1 4 1 11:50 225 14,200 12,900 1,340 1,200 12 10 < 1 <1 4 1 <1 4 1 4 1 12:00 225 14,200 12,900 1,340 1,200 12 10 < 1 <1 4 1 4 1 4 1 4 1 12:10 225 18,500 16,800 1,750 1,600 18 15 < 1 <1 4 1 41 4 1 4 1 12:20 225 18,500 16,800 1,750 1,600 19 15 < 1 <1 c1 4 1 < 1 4 1 12:30 225 62,400 56,700 6,150 5,000 56 50 .<1 <1 41 41 4 1 < 1 12:40 225 5,500 5,000 65 50 6 5 <1 41 ( 1 41 4 1 4 1

> 12:50 225 <1 41 < 1 <1 4 1 <1 <1 41 41 41 4 1 ( l All other segments <l mR/hr at ALL TIMES PLUME MONITORING DATA-SITE BOUNDARY SEGHENTS AIR SAMPLES (CPM)

WIND 1 2 3 4 5 6 TIME DIR IODINE PART IODINE PART IODINE PART IODINE PART IODINE PART IODINE PART 11:00 270 200 200 200 200 200 200 200 200 200 200 200 200 11:10 270 200 200 210 200 750 200 6,500 200 750 200 210 200 11:20 270 200 200 210 200 750 200 6,550 200 750 200 210 200 11:30 270 200 200 210 200 750 200 6,540 200 750 200 208 200 11:40 225 7,800 200 750 200 300 200 200 200 200 200 200 200 11:50 225 7,900 200 750 200 210 200 200 200 200 200 200 200 12:00 225 8,000 200 800 200 205 200 200 200 200 200 200 200 12:10 225 8,450 200 820 200 200 200 200 200 200 200 200 200 12:20 225 8,600 200 840 200 200 200 200 200 200 200 200 200 12:30 225 28,600 200 2,800 200 200 200 200 200 200 200 200 200 12:40 225 2,800 200 280 200 200 200 200 200 200 200 200 200

> 12 : 5 0 225 200 200 200 200 200 200 200 200 200 200 200 200 Counter BKGD and other segments 200 CPM at ALL TIMES VIII-14

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/ !il V111-l7 L-

1 SCENARIO NO. 4B REV.0 TABLE 8 0FFSITE TLD READINGS i

MILE MILE SECTOR RING MREM SECTOR RING MREM 1 1 9 1

> 5 5 10 10 1 2 1 6 10 1 5 1 5 10 10 i 3 1 6,200 11 1

! 5 4,300 5 j 10 10 4 1 12 1 5 5 i 10 10 5 1 5,600 13 1 5 92 5 10 10 6 1 14 1 5 5

! 10 10 7 1 15 1 5 5 4

10 10 J

8 1 16 1

. 5 5 l 10 10 i

NOTE:- Data to be supplied-to Offsite Radiological

Assessment Director.

l 9 .

u VIII-18 i

i

.- _, , - , - . , . , . - ,,- .n - ,, , , - - - , - r - . , -~c --,.

l SCENARIO'NO. 4B REV.0 l

I A '\ TABLE 9 l b

POST ACCIDENT SAMPLES SAMPLE SECTOR TIME TIME ISOTOPES RADIOACTIVE MEDIUM MILE TAKEN COUNT IDENTIFIED CONCENTRATION

• SOIL 5-2 1400 1800 I-131 0.039 I-133 0.085 I-135 0.039 SOIL 5-2 1400 Il) 1800 I-131 0.031

^

I-133 0.040 SOIL 5-2 1400( ) 1800 I-131 0.026 SOIL 5-5 1400 1800 I-131 0.007

! I-133 0.015 I-135 0.010 SOIL 5-5 1400 fI) 1800 I-131 0.004 I-133 0.005 i SOIL '5-5 1400(2) 1800 I-131 0.001 SOIL 5-10 1400 1800 I-131 0.001 I-133 0.002 I-135 0.002 SOIL 5-10 1400(1) 1800 NONE

,

• SOIL = uCi/kg Water =

uCi/ liter Vegetation = uCi/g dry weight NOTE 1: one day later NOTE 2: two. days later NOTE 3: Data to be provided to Offsite Radiological Assessment Director after samples have been collected and processed.

e,.-

VIII-19

SCENARIO NO. 4B REV.0

) TABLE 9(Continued)

POST ACCIDENT SAMPLES 4

SAMPLE SECTOR TIME TIME ISOTOPES RADIOACTIVE MEDIUM MILE TAKEN COUNT IDENTIFIED CONCENTRATION

• SOIL 3-2 1400 1800 I-131 0.252 I-133 0.549 I-135 0.503 SOIL 3-2 1400(1) 1800 1-131 0.132 I-133 0.268 SOIL 3-2 1400(2) 1800 I-131 0.006 SOIL 3-5 1400 1800 I-131 0.044 I-133 0.096 I-135 0.088 SOIL 3-5 1400(I) 1800 I-131 0.020 I-133 0.044 SOIL 3-5 1400(2) 1800 I-131 0.004

}

SOIL 3-10 1400 1800 I-131 0.006 I-133 0.014 I-135 0.013 SOIL 3-10 1400(1) 1800 NONE

• SOIL = uCi/kg Water =

uCi/ liter Vegetation = uCi/g dry weight NOTE 1: one day later NOTE 2: two days later NOTE 3: Data to be provided to Offsite Radiological Aseessment Director after samples have been collected and processed.

4 O

o VIII-20

SCENARIO NO. 4B REV.0 TABLE 10 1 (

POST ACCIDENT OFFSITE CONTAMINATION' LEVELS i

! SECTOR SMEAR CHECK RESULTS-CPM I MILE 1400 HRS 1500 HRS (1) 1500 HRS (2)  ;

5-SB 0FFSCALE (50K) 21,500 450 )

5-2 28,200 4,500 300 <

5-5 4,950 650 30 l 5-10 700 BKGD BKGD 3-SB 0FFSCALE (50K) 0FFSCALE (50K) 4,400 i 3-2 0FFSCALE (50K) 31,700 450 3-5 31,700 5,000 300 3-10 4,500 BKGD BKGD 4

O NOTE 1: Time represents one (1) day later 2: Time represents two (2) days'later 3: Data to be provided to Offsite Radiological Assessment Director after checks are simulated.

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l . . SCENARIO No. 4B REV.0 1

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O CONSOLIDATED EDISON COMPANY OF NEW YORK INDIAN POINT UNIT NO. 2 DRILL SCENARIO NO. 4B REV. O IX. LOGISTICS A. Drill Size There will be a full scale activation of the following facilities.

Control Room Technical Support Center Operational Support Center Emergency Operations Facility B. Participation Assembly and accountability will be limited to A approximately 100 personnel from Nuclear Power who will be designated and instructed before the drill that they are participants. After accountability has been completed, personnel not participating as players, controllers or observers will be permitted to return to their normal work locations.

C. Arm Band Use The following arm band color coding will be used during the drill.

Green - Controller Red - Observer White - Player Blue - NRC (available if they desire them)

D. Access Lists Access lists-will only be prepared for the EOF for use by the Security Guard assigned to that post.

All other Nuclear Power personnel not partici-pating will be directed by their Department r~s7 ' Managers to refrain from entering the TSC and OSC

- (,/ areas. Non drill participants'rcquiring entry to the Control Room will be directed to contact the

.SWS assigned to the watch.

IX-1

SCENARIO No. 4B REV. O O.*

s E. Lunch Lunch will be provided to all players, observers and controllers at their respective facilities in order that the drill can continue without interruptions.

F. Critique The Chief Controller will hold a critique at 0800

. hours on May 10, 1984 at the Simulator Cafeteria.

All controllers and observers shall attend.

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