ML20062J228

From kanterella
Jump to navigation Jump to search
Consolidated Edison Co of Ny Indian Point Unit 2,Drill Scenario 1993
ML20062J228
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 07/23/1993
From:
CONSOLIDATED EDISON CO. OF NEW YORK, INC.
To:
Shared Package
ML100430423 List:
References
NUDOCS 9308020173
Download: ML20062J228 (145)
v • d • e


Text

..

s .

CONDOLIDATED EDIBON COMPANY OF NEW YORK INDIAN POINT UNIT NO. 2 DRILL BCENARIO NO. 1993 4

___N_30BOholYb w .

O I CONBOLIDATED EDISON COMPANY OF NEW YORK INDIAN POINT UNIT NO. 2 DRILL BCENARIO NO. 1993 TADLE OF CONTENTB i

Bection I. Introduction )

i II. Objectives III. Exercise Scenario IV. Messages and Controller Field Reports V. Observer / Controller Instructions 1

( VI. Plant Status Log VII. Radiological / Meteorological Log VIII. Radiological Information i

IX. Logistics 1

l l

I

a a CONSOLIDATED EDISON COMPANY OF NEW YORK INDIAN POINT UNIT NO. 2 DRILL SCENARIO NO.1993

1. INTRODUCTION The purpose of this exercise is to demonstrate Con Edison's capability to effectively implement the Indian Point Unit No. 2 Site Emergency Plan and Procedures and the interface with New York State and the counties of Westchester, Rockland, Orange and Putnam.

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

IgntLon 11 Qblectives - this section defines the licensee exercise objectives.

Section ill Exercise Scenario - this section describes the Indian Point Unit No. 2 postulated sequence of events occurring which will require the onsite emergency response organizations to respond. For each event described, the-anticipated responsive actions of the participants are also detailed. These anticipated actions may be used as a guide in evaluating the exercise. However, it should be noted that the results observed may vary from those stated and should be evaluated on a case-by-case basis with respect to applicable procedures.

Sepflon IV Messages - this section contains copies of the exercise messages and Centroller Field Reports which will be utilized to control the progress of the exercise scenario.

Section V Observer / Controller Instructions - this section provides general instructions to the exercise Observers and Controllers in the conduct of the exercise. Also included are evaluation criteria for evaluating the response of the exercise participants.

Eggtlon VI Plant Status Log - this section contains time-sequenced information (non-radiological) concerning plant conditions, which corresponds to the development of the exercise scenario.

1-1

-~ ,

SCENARIO NO.1993 Section Vil Radiological / Meteorological Log - this section contains time-sequenced plant radiological and meteorological data which corresponds to the development of the exercise scenario.

Section Vill Radiological Mormatiom - this section contains time-sequenced radiological information in the following categories as required by the scenario:

+ Primary Coolant Activity

+ Containment Activity

+ Release Path Activity

+ Plant Radiation Levels

+ Reuter-Stokes Readings

+ Plume Monitoring Data & Figures

+ Offsite TLD Readings

+ Post Accident Samples

+ Post Accident Offsite Contamination Levels

+ Medical Emergency Data Section IX Logistics - this section contains information and direction for the handling of peripheral items related to the drill, including:

+ Food for participants

+ Access lists

+

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

1-2

o e CONSOLIDATED EDISON COMPANY OF NEW YORK INDIAN POINT UNIT NO. 2 DRILL SCENARIO NO.1993 OBJECTIVES Our objectives are to demonstrate the licensee's:

1. ability to identify emergencies through the four (4) classifications utilizing the EAL tables.
2. ability to notify to offsite authorities within 15 minutes of the initial (NUE) declaration and again at the closecut.
3. ability to activate the emergency organization as delineated in Section 5 of the Emergency Plan. This includes completing Level 11 within 60 minutes.
4. ability to activate the EOF, CCR, TSC, OSC, ENC, CIG, and CRC.

NOTE: State / Counties are not participating.

5. ability to communicate between offsite monitoring teams and 'icensee facilities.
6. ability to transmit data from the TSC to the EOF.
7. ability to deploy offsite and onsite radiological monitoring teams.
8. ability to deploy inplant radiological monitoring teams.
9. ability to receive and assess radiological data.
10. ability to complete assembly and accountability of site personnel within 30 minutes.

(no evacuation of site personnel will be demonstrated and there will be no activation of the alert notification [ siren] system).

11. command and control at the emergency response facilities.
12. ability to changeover responsibility for the airection and control of the emergency force from the Senior Watch Supervisor to the Plant Operations Manager and then to the Emergency Director.
13. ability of facility staff to perform their specified emergency plan job function in an efficient manner.
14. site access control and security measures to ensure there are no delays to the .

passage of EOF emergency personnel to the EOF.

15. ability to perform dose projections and determine recommended protective actions, if applicable.
16. personnel radiological exposure control capabilities for emergency personnel.
17. ability to brief the media in an accurate, coordinated, and timely manner.

NOTE: State / Counties are not participating.

18. ability to plan for a shift change.
19. ability to de-escalate the emergency and declare the recovery stage. (Recovery Center will not be activated).

i

, e e CONSOLIDATED EDISON COMPANY OF NEW YORK INDIAN POINT UNIT NO. 2 DRILL SCENARIO NO.1993 lit. DRILL SCENARIO Initial Conditions The Indian Point Unit 2 Nuclear Generating Station has been at full power for 177 days. A severe thunderstorm watch was declared at 0630. All plant parameters are normal and stable. A routine vapor containment (VC) building pressure relief is in progress. Equipment out of service for corrective maintenance are 22 Safety injection (SI) pump and 22 Auxiliary Boiler Feed Pump. Umiting Condition of Operation (LCO) action statements are in effect for both of these pieces of equipment.

Narrative Summary A tornado is observed by Operations touching down near Charles Point. .

When the Central Control Room (CCR) is notified, a Notification of Unusual Event (NUE) will be declared based on the indian Point Unit 2 Emergency Plan NUE event Table item SD, Natural Phenomena.

The Central Control Room Operator will attempt to secure the in progress VC pressure relief when VC pressure reaches the desired value. Upon securing the pressure relief, Valve PCV-1190 (the inside VC pressure relief Valve) closes, while PCV-1191 and PCV-1192 (the outside VC pressure relief valves) remain open.  :

A loss of #21 Main Boiler Feed Pump occurs with an ensuing automatic 3 turbine runback. Reactor Coolant System (RCS) pressure increases to the '

Power Operated Relief Valve (PORV) set point resulting in a PORV actuation. As pressure drops, the PORV's close, but pressure continues to i decrease. The Pressurizer Relief Tank (PRT) pressure, level, and temperature increase, indicating that either the PORV's have not fully closed or a Safety Valve is open. The acoustic monitor confirms the Safety Valve .l is open causing a Small Break Loss of Coolant Accident (SBLOCA). A j reactor trip occurs on low RCS pressure. RCS pressure continues to  !

decrease resulting in a Safety injection. As PRT pressure increases the I rupture disc blows by design resulting in excessive Reactor Coolant System i Leakage. An Alert will be declared on a Reactor Coolant System barrier  !

breach as confirmed by RCS leakage into the VC at a rate of greater than l 100 gpm.

Ill-1 l

te .

SCENARIO NO.1993 While the CCR operators are responding to the Safety injection a loss of offsite power occurs. Diesel Generators 21 and 22 tie on to their respective 480 volt buses. Diesel Generator 23 output breaker fails to close causing 480 volt Bus 6A to remain de-energized, After resetting Si and Containment isolation Phase A, as directed by procedure, an electrical fault results in PCV-1190 opening creating a direct pathway from containment to atmosphere. A site area emergency will be declared based on a second barrier breach confirmed by a failure of the Containment isolation function.

The ongoing small break LOCA results in voids in the Reactor Vessel. The Reactor Vessel Level Indicating System (RVLIS) shows a continued decreases in Reactor Vessel Level. After the core is uncovered, increasing radiation levels in the VC ind_icate the potential for fuel failure. An RCS sample is provided to the CCR indicating greater than 28 uci/cc. Increasing radiation levels in the VC are indicated on the R25 radiation monitoring. A general emergency will be declared based on the failure of a third barrier, the fuel, as indicated by the RCS sample.

Restoration of plant equipment begins with a re-energization of Bus 6A and the restoration of Safeguards equipment. An instrument and control technician installs an electricaljumper which causes Valve PCV-1190 to go closed and terminate the release. A time warp occurs in which the Reactor Core will be considered in a safe condition with no further potential releases of radioactive material to the environment. The Emergency Director will close out the emergency and declare the commencement of the recovery stage at which time the drill will terminate.

Ill-2

SCENARIO NO. 1993 TORNADO TOUCHING BREACH DOWN 1 MILE 1 BARRIER 1190 OPEN FROM PLANT PRT RUPTURES V.C.

NUE ALERT SAE 0730 0800 0857 0915 0935 1035 1055 1230 1355 1400 1415 LOSS RX LOSS GE INITIAL RELEASE TWO DRILL OF TRIP OF THIRD CONDITION STOPS DAY TIME ENDS MBFP OFFSITE BARRIER WARP POWER (CLAD)

III - 3

SCENARIO NO.1993 DETAILED SCENARIO TIME LINE INITIATING MESSAGE NUMBER TIME EVENT

SUMMARY

T = 07:30 1 initial conditions are:

- Operating for 177 days at full power.

- A severe thunderstorm alert was declared at 0630.

- Plant parameters are stable and normal.

- All Gas Turbine are running a/c AOI-28.0.7.

- Equipment out on LCO are #22 Si Pump and #22 Aux.

Boiler Feed Pump.

- Pressure relief in progress.

T = 08:00 A - Tornado is seen by NPO touching down at Charles Point.

ANTICIPATED RESMJ.IS Control Room Ooerator

- Continue in A-28.0.7 and IP-1032.

Senior Watch Suoervisor

- Declares an NUE due to Table SD. Any tornado observed within one mile of site.

i l

l 111- 4

e .

SCENARIO NO.1993 DETAILED SCENARIO TIME LINE INITIATING MESSAGE NUMBER TIME EVENT

SUMMARY

Fills out Radiolog: cal F.mergency Data Form Part 1.

Direct the communicator to make appropriate notification with IP-1002.

T - 08:30 2 CCR Operators stop pressure relieving.

- Valve No.1190 closes but valves No.1192 and No.1192 stay open.

ANTICIPATED RESULTS Control Room Ooerator T = 08:45 B - Send NPO to investigate why valves No.1190 and No.1192 didn't close.

N NMO

'?L2f4 A""A " "e*"

l l l l l l l l l l l I I I l

=.  :. ~ .a;,. . = - " = = ,

l 111- 5 l

SCENARIO NO.1993 DETAILED SCENARIO TIME LINE INITIATING MESSAGE NUMBER TIME EVENT

SUMMARY

T = 08:57 3 - Loss of 21 MBFP occurs.

- RCS pressure increases to open PORV resulting in PORV activation.

- As pressure drops PORV close but pressure decrease does not stop.

- PRT pressure and level increase.

- Acoustic Monitor indicates Safety Valve still open.

ANTICIPATED RESULTS Central Control Room Operator

- Make sure automatic action take place for loss of MFWP.

Ee"3?: .ua "L'sM

, A"^,A" ". "?!c!""

i I I l l l l l l l l I l l l I I lil-6

a ,

SCENARIO NO.1993 DETAILED SCENARIO TIME LINE INITIATING MESSAGE NUMBER TIME EVENT

SUMMARY

T = 09:15 4 Reactor Trips on low RCS pressure.

- Pressurizing level increases due to vapor space break.

ANTICIPATED RESULTS Control Room Ooerator Enter E-O 2"E .ma

- *#4 A"""1. " ' * * "

e I l

.... ..l .. .. u ... .... .... ,... u,. u,, .... i.o l I I a=. .:. -

.g - -

-.= -

111- 7 1

SCENARIO NO,1993 DETAILED SCENARIO TIME LINE INITIATING MESSAGE NUMBER TIME EVENT

SUMMARY

T = 09:20 5

- RCS pressure continues to decrease resulting in Safety injection.

- #21 St Pump failed to start - Si on signal.

ANTICIPATED RESULTS Control Room Ooerator

- Re-enter E-O step 1 Senior Watch Supervisor

- Send NPO to investigate.

C #21 SI Pump T = 09:35 6 - PRT Disc Ruptures 4"4 " s,ues

'TL'2% >L'L"".' , ";* '"

l l l

\ I l  !

l l l l . I I

.g = ._

111- 8

SCENARIO NO.1993 DETAILED SCENARIO TIME LINE INITIATING MESSAGE NUMBER TIME EVENT

SUMMARY

T = 09:40 ANTICIPATED RESULTS Senior Watch Supervisor

- Declares Alert due to RCS leakage >100 gpm which constitutes a RCS breach.

Control Room Operator Directs Sound Site Emergency Assembly Alarm.

- Fills out " Rad. Emergency Data Form Part 1".

- Direct communicator to make appropriate notification in accordance with IP-1002.

T = 10:30 8 - Loss of offsite power occurs.-

- #21 and #22 EDG pick up load on Busses SA,2A and 3A.

- #23 EDG Breaker fails to close due to Bus 6A.

- No high head injection pumps.

- RCS pressure to high for low head injection.

- Core uncovering continues.

EM -

"L* "l% A*"""u

- "?!c!'"

l I I I l l l 111- 9 l s

^~

s >

SCENARIO NO.1993 DETAILED SCENARIO TIME LINE INITIATING MESSAGE NUMBER TIME EVENT

SUMMARY

T = 10:55 9 - After Si and Phase A reset Valve No.1228 is opened.

- Valve No.1190 opens - Attempt to close Valve failed.

ANTICIPATED RESULTS EmeLqency Director (ED)

- Declares SAE because two Barrier Breach.

- Fills out " Rad. Emergency Data Form Part 1"

- Have offsite authorities notified.

- Evacuate onsite nonessential personnel.

Central Control Room T = 11:05 D - Send NPO to investigate why Valve No.1190 failed to close.

4 BRIA3

'%'J0; A,TF,"o ";! !'"

I l I l l l l l l l l l 111- 1 0

SCENARIO NO.1993 DETAILED SCENARIO TIME _ LINE INITIATING MESSAGE NUMBER TIME EVENT

SUMMARY

T = 12:30 10

- Small Break LOCA results in voids in Rx vessel.

- RVLIS level continues to decrease.

- R-25 and 26 increasing in V.C.

E - Samples taken from RCS indicates >28 uci/cc.

_ ANTICIPATED RESULTS Em_ersency DirectorJE_D) 11

- Declares a GE a/c fuel clad - Breach third Barrier failure.

l l

l l

1 1

l svama i l

  • a',"Jr A"m'#fm * * *!c!'"

l ..., l l

.... .. . .. n 1.>. .... us. 22.. 2. 2.a l l l l  !

  1. 4% 5 "'

om JE;*o E"E""'3."

111- 1 1  !

l

SCENARIO NO.1993 DETAILED SCENARIO TIME LINE INITIATING MESSAGE NUMBER TIME EVENT

SUMMARY

T = 13:30 F - Power restored to Bus 6A upon restoration of #23 EDG.

T = 13:45 G - Number 22 SI Pump repair turnover to CCR.

T = 13:55 H - l & C installs jumper which closes Valve PCV-1190.

- Terminates release

- Plant proceeding to cold shutdown.

T = 14:00 12 - Two Day Time Warp.

- Rx in cold shutdown.

- All equipment functioning normal.

4"^"

m oua

%'= A "4 " ,

.... ..l .. ... .m ..I ., ,,,, , ,i , , u,. n, .... , .1, I .. .- - -

111- 1 2 l

C '

CONSOLIDATED EDISON COMPANY OF NEW YORK INDIAN POINT UNIT NO. 2 DRILL SCENARIO NO.1993 IV. MESSAGE TO: ALL DRILL PARTICIPANTS LOCATION: ALL LOCATIONS TIME: When the players report to the facility MESSAGE: DRILL GROUND RULES All participants are required to observe the following Ground Rules for the entire duration of the exercise, if you have any questions, ask your Facility Controller for clarification at this time.

1. Ensure that all communications indicate that this is only a drill. Make a positive statement that this is a drill-related message at the beginning and 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-drill related operations.
3. Take immediate action (s) to restore safe operation, if an unsafe condition exists. Ignore drill situation if actual safety becornes a concern.
4. Use only the information provided in accordance with the ground rules or derived from approved procedures. Do not imorovise information.
a. Controllers will provide appropriate information at the location where that information would normally be available (e.g., Reactor status at the Control Room, dose rate readings with field teams, meteorological information at Control Room or EOF).
b. Only selected parameters and readings will be provided. The selected information will be sufficient to make decisions in accordance with Con Edison plans and procedures. -

IV-1 -

o;

  • SCENARIO NO. 1' 993
c. The intent of the scenario is to test inplementation of the emergency plans and procedures by Con Edison and the offsite authorities. In certain instances the logic involved in selecting the' details stretches the imagination. This has been done to accommodate the onsite and offsite objectives of the drill. Do not become overly concerned when this occurs,
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 drill in order to keep the drill progressing in accordance with the scenario. Observer / Controllers will also observe all aspects of the drill to prepare an in house evaluation of plans, procedures and training.
5. Be sure that the Con Edison Observer / Controller is aware of your actions (actual or simulated).
6. Make all procedurally required notifications unless directed not to do so by the Controller.
7. If samples inside or outside the site are deemed necessary, their callection will be performed and their analysis conducted unless simuistions is directed by a Controller. Observer / Controllers will accompany the survey teams, onsite and offsite.
8. This drill is conducted to evaluate our plans and procedures. The drillis also a training vehicle for members of the Con edison 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 Observer / Controller at the conclusion of the drill.

9. If, during any part of the drill, 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.
10. The Radiation Work Permit number for the emergency drillis 10001. This number will be used by all part<cipants and observer / controllers entering the radiation area.

IV-2

a co - - . ,

r SCENARIO NO.1993 SIMULATION -

CONTROL ROOM _{CR)

.1. Kiuse 4

TECHNICAL SUPPORT CENTER (TSC)

~

None OPERATIONAL SUPPORT CENTER (OSC) j '

1. Anti-C and respirators for teams
2. Sampling and Counting, including the PASS .
3. Entry of repair teams into contaminated areas or areas 1
4. Requiring a site specific RWP l

EMERGENCY OPERATIONS FACILITY (EOF)

1. Kiuse [
2. Disarming of Halon System
3. Switching ventilation to internal mode
4. Evacuation _ and, movement of all non-essential personnel  :
5. Estimates of population dose after recovery t
6. Buchanan Sub Station Service Center not participating _
7. With the exception of the Security Guard for CCR, EOF and onsite team, all other .;

. security requests will be simulated. i

8. The Main Gate and the Command Guard house will be secured for one h'our after  :

the assembly alarm is sounded. - At another times it will be simulated.

ASTORIA ECC

1. . Only one offsite team needs to be dispatched from Astoria. After the team is dispatched, the rest of the personnel may be released for normal duty.

CORPORATE RESPONSE CENTER (CRC)

1. CRC personnel are only required to contact appropriate directors, managers and .

chief engineers DDcp after activating the facility stating, "This is a notification drill being oerformed in con _iunction with an Indian Point Site Drill. Thank you."

CENTRAL INFORMATION GROUP (Clq) '

1. The initiation of the Automated Telephone Emergency Notification Service (IP 1002 Section 5.4.1.c).

IV-3 P

+.-m - - -, ,-.,,,w a .. - --- ,-,, 4 m, y m , w r ,, --- y

~

SCENARIO NO.1993 TO: SENIOR WATCH SUPERVISOR LOCATION: CENTRAL CONTROL ROOM TIME: T = 07:30 MESSAGE: NO.1 This is a Drill Con Edison Indian Point Unit No. 2 has been operating at full power for 177 days.

AOl-28.0.7 completed through Step 3.2.3.

A severe thunderstorm watch was declared at 06:30.

Plant parameters are stable and norma!.

All Gas Turbines are running per procedure.

VC pressure relief in progress.

No. 22 SIS Pump was taken out for service at 06:00 for seal replacement. The Pump is expects back at approximately 15:00.

No. 22 ABFP is in for repairs since 16:00 yesterday and is expected back for service at approximately 16:00 today.

This is a Drill i

IV-4 ,

1

SCENARIO NO.1993

_C_ONTROLLER FIELD REPORT A TO: NUCLEAR PLANT OPERATOR LOCATION: ROOF OF THE TURBINE HALL TIME: T = 08:00 ,

MESSAGE:

This is a Drill it is expected that the SRO has dispatched an NPO to the roof of the turbine hall building to perform a tornado watch (per AOl-28.0.7).

The NPO will observe a tornado touching down within one mile of the plant at Charles Point. It is expected that the NPO will relay this information to the CCR.

This is a Drill i

l 1

IV-5

SCENARIO NO.1993 '

TO: CENTRAL CONTROL ROOM LOCATION: CONTROL OPERATOR TIME: T = 08:30 MESSAGE: NO.2 JJ11s is a Drill The Control Operator, upon attempting to secure from a pressure relief, receives alarms and indications as follows:

+ Indication light SL Panel PCV-1191 and PCV-1192 indicate open.

e Indication light SL Panel PCV-1190 indicates closed.

111111s a Drill IV-6

6- O SCENARIO NO,1993

_C_ONTROLLER FIELD REPORT B TO: NPO REPAIR TEAM LOCATION: PCV-1191 AND 1192 TIME: T = 08:45 MESSAGE:

This is a Drill it is expected that the Control Room Operator will dispatch an NPO to close the valves from the Fan Room. If this occurs, inform the NPO that the valves will not close.

it is expected that t'he SWS will request that the Maintenance Section send a team to the CCR where the SWS will direct them to make a detailed investigation.

Give the following information when trouble shooting starts and it is requested.

VALVE INITIAL INVESTIGATION DETAILED INVESTIGATION PCV-1191 Problem is not electrical Valve stem is broken - jamming valve PCV-1192 Problem is not electrical Problem is a broken spring and a butterfly shaft is jammed.

This is a Drill IV-7

SCENARIO NO.1993 TO: CONTROL ROOM OPERATOR LOCATION: CONTROL ROOM TIME: T = 08:57 MESSAGE: NO. 3 This is a Drill Loss of No. 21 Main Boiler Feed Pump occurs.

Reactor Coolant System pressure increases to activate PORV's.

As pressure drops PORV's close, but Pressurizer pressure does not stop decreasing.

PRT level increases.

Pressurizer Safety Discharge Outlet header temperature indicates increasing.

Acoustic monitor indicates that the Safety Valves are open.

This is a Drill IV-8 e

~

SCEfMRIO NO.1993 TO: CONTROL ROOM OPERATOR LOCATION: CONTROL ROOM TIME: T = 09:15 MESSAGE: NO. 4 This is a Drill Reactor Trip on Low Pressurizer Pressure, Turbine Trip.

All equipment functions are normal.

This is a Drill i

IV-9 I 1

-o SCENARIO NO.1993 TO: CONTROL ROOM OPERATOR LOCATION: CONTROL ROOM TIME: T = 09:20 MESSAGE NO. 5 This is a Drill Safety injection, Low Pressurizer Pressure.

No. 21 Si Pump fails to start.

This is a Drill i

1%10

$ +

SCENARIO NO.1993 CONTROLLER FIELD REPORT C TO: CONTROL ROOM OPERATOR LOCATION: CONTROL ROOM TIME: T = 09:3G MESSAGE:

This is a Drill it is expected that the SWS will send an NPO to see why Safety injection Pump No.

21 failed to start as an initial investigation. After being informed by the NPO of the status of the pump, it is expected that a repair team will be sent from the OSC to make a detailed investigation.

Give the following information when trouble shooting starts and it is requested.

Pump Initial investigation Detailed Investigation 21 SIP Problem is not electrical Problem is a wiped bearings. Estimated repair time is 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

This is a Drill l

IV-11 l i

~

> s SCENARIO NO.1993 TO: CONTROL ROOM OPERATOR LOCATION: CONTROL ROOM TIME: T = 09:35 MESSAGE: NO. 6 This a Drill i

Increasing pressure in the PRT.

PRT Disc Ruptures.

increasing level in the Containment pump.

Pressure decreases in the PRT.

l This is a Drill 1

1 IV-12

A o SCENARIO NO.1993 TO: CONTROL ROOM CONTROLLER LOCATION: CONTROL ROOM TIME: T = 09:40 MESSAGE: NO. 7 This is a Drill SWS should declare an Alert because of RCS Barrier Breach.

This is a Drill

.i IV 13 **

x s l

SCENARIO NO.1993 TO: CONTROL ROOM OPERATOR LOCATION: CONTROL ROOM TIME: T = 10:30 MESSAGE: NO. 8 This is a Drill As a result of the Tornado a disturbance in the offsite electrical power system causes a loss of all offsite power supplies into the plant.

EDG's have already started, however, only EDG No. 21 and No. 22 load to the bus.

No. 23 EDG Breaker fails to close due to fault on Bus 6A.

> No high head Safety injection Pumps available.

This is a Drill IV-14

-4 .

SCENARIO NO.1993 TO: CONTROL ROOM CONTROLLER LOCATION: CONTROL ROOM TIME: T = 10:55 MESSAGE: NO. 9 This is a Drill

> After Control Room Operator resets Si and Phase A, valve 1228 is opened as per E-1.

> Valve 1190 inadvertently opens, attempts to close failed, valve will not close.

This a Drill IV-15

SCENARIO NO.1993 CONTROLLER FIELD REPORT D TO: CONTROL ROOM OPERATOR LOCATION: CONTROL ROOM TIME: T = 11:05 MESSAGE:

This is a Drill Attempts to close Valve No.1190 unsuccessful.

This is a Drill l

I 1

l l

IV-16

s.
  • SCENARIO NO.1993 CONTROLLER FIELD REPORT E TO: CHEMIST LOCATION: CHEMISTRY FIELD TIME: T = 12:30 MESSAGE:

This is a Drill RCS System Sample

> 28 uci/cc This is a Drill i ,

l IV-17 '

i

i e SCENARIO NO.1993 TO: CONTROL ROOM OPERATOR LOCATION: CONTROL ROOM TIME: T = 12:30 MESSAGE: NO.10 This is a Drill

> Small break LOCA results in voids in the Reactor Vessel head.

> RVLIS reading declining.

> Sample taken from RCS indicates >28 uci/cc.

This is a Drill l

I IV-18 -

s i SCENARIO NO.1993 TO: CONTROLLER LOCATION: CONTROL ROOM / EOF TIME: T = 12:45 MESSAGE: NO.11 This is a Drill Emergency Director should declare a General Ernergency as a result of the third barrier breach (fuel clad).

This is a Drill IV-19

. e SCENARIO NO.1993 CONTROLLER FIELD REPORT F TO: CONTROL ROOM OPERATOR LOCATION: CONTROL ROOM TIME: T = 13:30 MESSAGE:

This is a Drill

> Maintenance completes repairs on EDG No. 23.

> EDG No. 23 energizes Bus 6A.

This is a Drill IV-20

. i SCENARIO NO.1993 CONTROLLER FIELD REPORT G TO: CONTROL ROOM OPERATOR LOCATION: CONTROL ROOM TIME: T = 13:45 MESSAGE:

This is a Drill

> SIS Pump No. 22 repairs completed.

> SIS Pump No. 22 placed in service.

This is a Drill IV-21

SCENARIO NO.1993 CONTROLLER FIELD REPORT H TO: CONTROL ROOM OPERATOR LOCATION: CONTROL ROOM TIME: T = 13:55 MESSAGE:

This is a Drill

> I & C installs jumper to close Valve No.1190.

> Maintenance repairs Valve No.1191 and valve closes.

> Plant proceeding to cold shutdown.

This is a Drill IV-22 -

c ,

SCENARIO NO.1993 TO: CONTROL ROOM OPERATOR LOCATION: CONTROL ROOM TIME: T = 14:00 MESSAGE: NO.12 This is a Drill Two Day Tme Warp.

Reactor in cold shutdown.

All equipment normal.

This is a Drill

)

IV-23 -

1

CONSOLIDATED EDISON COMPANY OF NEW YORK INDIAN POINT UNIT NO. 2 DRILL SCENARIO NO.1993 V. OBSERVER / CONTROLLER INSTRUCTIONS A. Exercise Control Oraanization 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 actNely 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 questions. The assignment sheets at the end of this section contain the listing of all exercise players, Observers and Controllers, as well as their locations.

B. Exercise Control Instructions 1.

All Controllers shall be pre-positioned at least one half hour prior to the first message time.

2. Prior to exercise commencement, all Controller communications will be tested to ensure 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. Message shall be delivered by the Controller at the appropriate times, to the designated individual (s). In the case of emergency declarations, if the response of exercise participants necessitates the use of a contingency message, the situation should be discussed with the Chief Controller prior to issuance of the message.

V-1

j SCENARIO NO.1993 i Controllers will use the following techniques to control the exercise in accordance with the scenario,

a. Messages & Field Reoorts - Messages providing information are given to the participant at the specific time. The Controller may clarify the message by answering questions to ensure that no extraneous meaning is lead into the message. Field reports are for the Controller's use and are not given to the participant. When the field report contains direction to the Controller to provide information it is done verbally. The Controller will not tell participants what action they are expected to take.
b. Continaency Messaaes - Contingency messages will be used only if participants fail to take the major actions expected from the control messages by the time designated. Controllers will give the contingency message to the designated participant and explain in as much detail as necessary what actions the participant is expected to perform. Contingency messages are used 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 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 period to obtain requested data from the appropriate tables in Section 8.
d. Control Guidance - Controllers will provide verbal guidance to participants to keep the exercise oriented to the pre-arranged scope and scenario. Controllers will direct participants to simulate certain actions 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. Participants must request information that is not automatically provided from participants at other locations. Controllers will steer participants away from types of information that are outside the exercise scope to avoid bogging the exercise down in a quest for information that Controllers do not possess and have no intention or providing.

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

V-2

SCENARIO NO.1993

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 development 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 padicipants regarding scenario development or resolution of problem areas encountered. The exercise participants are expected to obtain information through their own organization and exercise their own judgements 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 consists 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 insists that certain pads 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 and of this section to take detailed notes regarding the progress of tha exercise and the responses of the exercise participants at their respective assigned locations. 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 / Controller's comments should consider the evaluation elements set forth in Section C,

" Exercise Evaluation Criteria." All notes taken should be retained for the purpose of reconstructing the exercise chronology and preparing a written critique to 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 given at that time.

NOTE: In the event of a real emergency during the exercise, the exercise may be immediately terminated by the Chief Controller, if deemed appropriate.

V-3

SCENARIO NO.1993 C. 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:

+

Notification, alerting and mobilization of emergency response personnel.

+

Adequate communications capabilities among onsite personnel and offsite monitoring team.

+

Timely activation of emergency facilities and teams.

+

Clear and appropriate direction and control of all exercise activities.

+

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

+

Overall adequacy of the scenario to test the various emergency preparedness plans and procedures.

+

Benefit of the exercise to its participants.

The following guidelines provide basic evaluation criteria which must be addressed by the Observer / Controller in order to effectively critique the exercise. Evaluation criteria are grouped according to exercise activity location and individual (or team) functions.

NOTE: Specific exercise performance must be compared directly with company emergency procedures. Therefore, indivkfuals assigned as Observer / Controllers shall be cognizant of the respective procedures and all actions that shall be carried out by the participants they 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 recommendations to improve performance and emergency preparedness. Critique comments will be requested from all participants at the conclusion of the exercise.

V-4

SCENARIO NO.1993

1. Control Room Prior to initiating the exercise, the Chief Controller will confer with the Senior Watch Supervisor (SWS) in order to identify any ongoing operational or maintenance activities that should not be interrupted.

Those personnel engaged in these activities 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 terminated and station announcements will specify "THIS IS NOT A DRILL" and 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:

+ Use of map and overlays.

+ Placement of calls to NRC, NYS and Counties.

+

Notification, alerting and mobilization of emergency personnel.

+

Operations handling of accident conditions if appropriate.

+

Instructions given to Search and Rescue teams, and Repair and Corrective Action teams, and Radiation Protection and Chemistry Technicians by the Senior Watch Supervisor (SWS).

+

Does the SWS handle the emergency by directing his people or trying to do the work himself,

+

ls the time frame of actions by the SWS reasonable enough.

+ Deportment of all personnel in the Control Room.

The following procedures could be used in the eva!uation:

IP-1001 Mobilization of Onsite Emergency Organization IP-1002 Emergency Notification and Communication 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 V-5

I ..

SCENARIO NO.1993 IP-1013 Recomrnendation of Protective Actions for offsite Population IP 1016 Obtaining Meteorological Data IP-1020 Airborne Radiciodine Determination IP-1021 Manual Update and Readout of Proteus Plant Parameter Data IP-1024 Emergency Classification IP-1037 Obtaining Offsite Reuter-Stokes Monitor Data IP-1038 Emergency Personnel Exposure IP-1043 Operation of the NYS Radiological Emergency Communication System (RECS)

IP-1047 Obtaining Offsite Exposure Rates from MIDAS Via Control Room Terminal.

Plus immediate Action Procedures for SWS, CRO, WATCH HP, POM

2. Technical Sucoort Center The Observer / Controller should obsewer the fol!owing:

+ Timely activation

+

A minimum of four qualified persons manning the center.

+ Field sumey performed.

+ Field survey performed.

+ Noble gas monitor set up.

+ "Frisker" set up.

+ Work performed in professional manner.

+

Phones are plugged in and direct lines to Control Room, OSC, and EOF are checked out.

The following procedures are to be used in the evaluation:

IP-1020 Airborne Radiciodine Determination IP-1021 Manual Update and Readout of Proteus Plant Parameter Data IP-1035 Technical Support Center IP-1041 Use of the Triton to Monitor Radiogas V-6

f SCENARIO NO.1993

3. Central Information Grouo (CIG)

The Observer / Controller should observer the following:

+

Timely initiation of a call to the paging service company.

+

Adequate communicat!ons, including how problems with the radio and telephones are handled. Message handling and communication logging procedures.

+

Verification call to Indian Point Unit No. 2 Control Room for authenticity of emergency.

+ Preparation of records of personnel who has called in.

The following procedure is to be used in the evaluation:

IP-1002 Emergency Notification and Communication

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

+

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

+ 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.

1

+

ls there documentation of accountability and is it l understandable to others.

l The following procedure is to be used in the evaluation IP-1027 Site Personnel Accountability and Evacuation i

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

+

ls there documentation of accountability and is it understandable to others?

+

Do the personnel awaiting assignment remain orderly?

V-7

SCENARIO NO.1993

+ Were radiation surveys performed and recorded?

+ Receipt of request to form teams.

+ Handling the assignment of team members.

The following procedures are to be used in the evaluation.

IP-1020 Airborne Radiciodine Determination IP-1023 Operational Support Center IP-1027 Site Personnel Accountability and Evacuation IP-1041 Use of the Triton to Monitor Radiogas.

6. Emerciency Operations Facility This is the Command Post for the interface with offsite authorities and it should seem so to the Observer / Controller. Look for the following:

+ The Emergency Director is in command of the EOF.

+

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.

+

Any extra personnel, spectators and those awaiting orders are quietly standing out of the way.

+

The Health Physics or support personnel are performing duties in a timely and efficient manner and reporting results to either the Emergency Director or ORAD.

+

instrumentation deployed in the EOF is placed in a non-interfering position.

+

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

+

Radioactive release rates, whole body and thyroid exposures to the offsite population are calculated quickly after the receipt of data from the Control Room or the offsite monitoring teams (s).

va

a -

SCENARIO NO.1993

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

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

+

Data forrns filled out and turned in to the ORAD / Health Physicist.

+ Timely deployment of teams.

+

A central point for receipt of radiological monitoring data is designated and adequate communications with field teams demonstrated.

+

Denvastrate ability to assess plant conditions, reclassify the inc;.sent (if appropriate), develop timely protective action recommendations, and communicate to offsite authorities in an accurate and timely manner.

  • Demonstrate ability to control radiological monitoring field teams for " plume-tracking," and ingestion pathway monitoring.

+

Demonstrate ability to develop recommendations for recovery and re-entry activities.

+

Demonstrate ability to provide radiation exposure control for emergency workers.

The following procedures are to be used in the evaluation:

IP-1002 Emergency Notification and Communication IP-1003 Planned Discharge of Containment Atmosphere During Accident Conditions IP-1004 Post Accident Offsite Environmental Surveys, Sampling and Counting IP-1005 Use of MS-2/ SPA-3 to Determine Thyroid Burdens IP-1006 Site Perimeter Surveys IP-1007 Determine of the Magnitude of Release and Exposure Rate IP-1013 Recommendations of Protective Actions for Offsite Population IP-1016 Obtaining Meteorological Data IP-1020 Airborne Radiciodine Determination V-9

e -

SCENARIO NO.1993 IP-1021 Manual Update and Readout of Proteus Plant Parameter Data IP-1024 Emergency Classification IP-1029 Emergency Closecut/ 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 Noble Gas IP-1043 Operation of the NYS Radiological Emergency Communications System (RECS)

IP-1048 Deescalation of Emergency and initiation of Recovery Plus immediate Action Procedures for Ed, TA, ORAD, DAHP, STHP, MIDAS, COMM, EOF CLERICAL

7. Security Buildino(slor 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 Radiation Protection Technician gives other directions because of radiological conditions. The Observer /

Controller will pay special attention to the above along with the following:

+

Timely activation or establishment of control points.

+

No one is wearing Anti-C clothing when leaving the site.

+

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

The following procedures are to be used in the evaluation:

IP-1017 issuance and Use of Radiological Equipment Stored in the Command Guard House

8. Onsite Monitorino Teams Onsite monitoring teams will normally be assigned field survey work onsite, outside of the Protected Area fence, and the Service Center building complex.

V-10  !

O O SCENARIO NO.1993 Check on the following items:

+

Received Kl dose (simulated) from ORAD if required.

_ NOTE: Do not actually take the Ki Dose.

  • They have a dosimeter and TLD badge.

+

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

+

Radio check performed before leaving the EOF parking lot.

+

Field readings taken along the route to the designated area.

Simulated field data will only be available at designated monitoring points.

+ Work performed in a professional manner.

+ 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 IP-1014 Radiological Check of Equipment Before it Leaves the Site IP-1028 Onsite (out of plant) Field Surveys

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

+

Received Kl dose (simulated) from ORAD if required.

NOTE: Do not actually take the Kl dose.

+

Operational check performed on survey instruments, sample counter and sample pump before leaving the EOF parking lot.

l

+ Equipment check-off performed.

+

Assignment of badges and dosimeters before leaving the EOF i ;

parking lot.

j i

V-11 4

SCENARIO NO.1993

+

Charcoal cartridge respirator made available before leaving EOF parking lot.

Survey instrument made ready to take field readings.

Radio check-out by communication to EOF before leaving.

Beta and gamma field surveys performed on the way to sample point.

+

Sampling and field surveys performed at sample location.

+

Instrument calibration performed and samples counted.

  • 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 Monitoring Teams - Immediate Response IP-1020 Airborne Radiciodine Determination IP-1034 Mobilization and Operational Procedure for Offsite Monitoring Teams - Supplemental Response IP-1039 Offsite Contamination Checks

10. Health Physics Technician (HPT)

The Observer / Controller should observe the following:

+

HPT follows his instructions indicated in immediate action procedures.

+

HPT pedorms survey as indicated using appropriate instrumentation.

The following procedures are to be used in the evaluation:

IP-1010 Search and Rescue Teams IP-1011 Repair ahti Corrective Action IP-1020 Airborne Radiciodine Determination IP-1042 In-Plant Radiological Surveys and Sampling V-12

1

6. O SCENARIO NO.1993 1

Plus immediate Action Procedure WATCH H.P.

11. Chemistry Technician The Observer / Controller should observe the following:
  • Chemistry Technician follows Chemistry Procedures as appropriate.

+

Samples are actually collected and counted, as indicated by the scenario.

+

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 to Atmosphere IPC-E-004 Post Accident Sampling and Analysis of Main Steam Releases to Atmosphere-

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

+ Response and repair time.

+ Proper equipment brought to perform the work.

  • Maintenance Repair Team members follow Health Physics Technician's instructions.
  • Radiological precautions taken.

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 V-13

EMERGENCY EXERCISE / DRILL OBSERVER / CONTROLLER LOG SHEET Name:

Date:

Location: __

TIME OBSERVATION / COMMENT V-14

e

  • CON EDISON TS-S-7.701 INDIAN POINT STATION Rev.8 TECHNICAL SERVICES ATTACHMENT 7.2 Page 1 OF 3 EMERGENCY DRILL PARTICIPANT ASSIGNMENT SHEET Controllers-Observers Drill Date 9/22/93 LOCATION POSITION NAME CCR Chief Controller inzirillo, F.

Controller Limoges,Ferrick Controller - SWS Dose Assessment Controller Communicators Bollin, E.

Controller - Watch HP Technician Gately, D.

Controller - Watch Chem Technician Peters, J.

Controller - Medical Controller - Fire Brigade Controller - NPO Stroppel, M.

Controller - Data Displayer Hood,H.

TSC Controller Hayes, C.

Info flow & Observer - utilization Sutton, R.

Observer - Communicator Redding, R.

OSC Controller - Coordinators TSC 53' Julian, J.

Controller OSC Team (Maint) Puppa,J.

Controller - OSC Team (Maint) Montalvo, E.

Controller - OSC Team (I&C) Naku,K.

Controller - OSC Team (Rad Pro) Cubeta, G.

Controller - OSC Team (Chem) Kohnken,J.

Controller - 72' Elevation Pisiak, B.

EOF Controller Ferraro, A.

Observer - Communicators Whitney, M.

Observer - Dose Assessment Smith, D.

CON EDISON TS-S-7.701 INDIAN POINT STATION Rev.8 TECHNICAL SERVICES ATTACHMENT 7.2 Page 2 OF 3 EMERGENCY DRILL PARTICIPANT ASSIGNMENT SHEET Controllers-Observers Drill Date 9/22/93 LOCATION POSITION NAME EOF Controller - Emergency Director McAvoy, J.

Controller - Offsite Team Sadlon, S.

Controller - Offsite Team Miller, D.

Controller - Onsite Team Martucci, R.

ASSEMBLY Observer - Area A-B Grassie, W.

Observer - Simulator Miller, M.

Observer - Constr. Off. Complex Condon,C.

Observer - M.O. Building ----

Observer - 72' TS/ Admin Cummings, B.

Observer - Unit No.1 Admin Bldg. Giaccone, F.

Observer - Service Center -----

Observer - Security Admin Bldg. Capalbo, R.

SECURITY Controller - Controller Guard House Elsroth, T.

Observer - River Front Gate -

Observer - Main Gate Observer - ---

ENC Controller Assigned by Walden Observer "

Observer "

Observer "

CIG Controller Ross, M.

CRC Controller Wystepek

CON EDISON TS-S-7.701 INDIAN POINT STATION Rev.8 TECHNICAL SERVICES ATTACHMENT 7.1 Page 3 OF 3 EMERGENCY DRILL PARTICIPANT ASSIGNMENT SHEET Controllers-O_bservers Drill Date 9/22/93 LOCATION POSITION NAME ASTORIA-ECC Controller Peters, R.

Controller - Offsite Team Megluevich RC Controller AEOF Controller Ferraro, A.

CON EDISON TS-S-7.701 INDIAN POINT STATION Rev.8 TECHNICAL SERVICES ATTACHMENT 7.1 Page 1 OF 4 EMERGENCY DRILL PARTICIPANT ASSIGNMENT SHEET Drill Date_.9/22/93 JOB FUNCTION NAME Emergency Director (ED) Miele, M.

Offsite Radiological Assessment Director Gaynor, D.

Dose Assessment Health Physics Teague,T.

Survey Team Health Physics Magee, M.

Technical Advisor Griffith MIDAS Operators Hewitt, R.

EOF Information Uaison Spall, M.

Technical Advisor to Public Information Primrose Liaison to NYS EOC EOF Communicator No.1 & 2 Falciano, Maier Offsite Team Ressihuber, B.

Muller, Mettery, English, Onsite Team Baier, J., Agrest Astoria ECC Coordinator Colenaro Astoria Backup Team (s) Lynch, Damsky Meteorologist Cohen EOF Clerical Daly, Accomando, Birong, D.

SAS/ Proteus Operator Genadry, A.

Plant Operations Manager Hugo,G.

TSC Manager Curry, J.

1 & C Coordinator Olson, B.

Radiation Protection Coordinator Shannon, M.

Maintenance Coordinator Meyer, W.

o .

I CON EDISON TS-S-7.701 l INDIAN POINT STATION Rev.8 TECHNICAL SERVICES )'

1 ATTACHMENT 7.1 Page 2 OF 4 EMERGENCY DRILL PARTICIPANT ASSIGNMENT SHEET Drill Date 9/22/93 JOB FUNCTION NAME Test & Performance Engineer Barlok, J.

Systems Analysis Coordinator Bar, A.

TSC Communicator Barlin, I.

Data Courier McKeon TSC Communicator at CCR Primrose, H.

Data Processor at CCR _

Brooks, T.

Core Physics Engineer Wong Document Controller Armstrong Data Logger /SAS-Proteus Operator Matalanis TSC Clerical Saylor, McKeon OSC Manager Noto, M.

Accountab:iity Officer McHugh OSC Communicator Evans, G.

Chemistry Popices, Accomando, Scott Maintenance Doyle, Tamburri, Bunch, Downing Nichols, Jerrick, Perez, Larson EOF Clerical Capalbo, R.,Edip,S.,McGuire,K.

Instrument & Control Karasinski, Edling, Keyes, Mak, Dupilka, Usewski Quality Assurance Boardman, Trombeta Radiation Protection Ga!!eghar, Buda, Burris, Cubeta, Mages, Danielle Material Control Storekeeper Mete Accident Victim METACON/First Aid Team

6

  • CON EDISON TS-S-7.701 INDIAN POINT STATION Rev.8 TECHNICAL SERVICES ATTACHMENT 7.1 Page 3 OF 4 EMERGENCY DRILL PARTICIPANT ASSIGNMENT SHEET Drill Date 9/22/93 JOB FUNCTION NAME Medical Representative Senior Watch Supervisor Jawor, J.

Support Facility Supervisor Spangenberger Senior Reactor Operator Gorman, A.

Reactor Operator O' Dell Nuclear Plant Operators (7) Pasquale, M., Jones, R., Schlagel, Studley, Campbell, Suneson, Hagarty Watch Engineer Santini Control Room Communicator Spagnola Security Supervisors Cullen, G.

Watch Rad Pro Tech Colville, R.

Watch Chem Tech Higgins, P.

Administration & Logistics Manager Smith, L Engineering & Construction Support Manager Remshaw Central Information Group Watch Recovery Manager -----

Schedule & Planning Coordinator Project Management Specialist Emergency News Center Director Walden, D.

Asst. Emergency News Center Director Assigned by Walden Corporate Spokesperson Evans, J. M.

Information Coordinator Assigned by Walden Information Gatherer

e .

CON EDISON TS-S-7.701 '

lilDIAN POINT STATION Rev.8 TECHNICAL SERVICES ATTACHMENT 7.1 Page 4 OF 4 EMERGENCY DRILL PARTICIPANT ASSIGNMENT SHEET Drill Date 9/22/93 JOB FUNCTION NAME Writer Assigned by Walden Government Liaison "

Media Liaison "

Technical Expert Reese Health Physics Expert Parry Documenter Assigned by Walden Status Board Person "

Rumor Control Staff "

inquiry Response Staff "

Audio / Visual Coordinator "

Registration Coordinator "

Telecopier Operator -

Photocopier Operator "

Typist "

Messenger a

rn 14e? I 07'. 93 TORNR00 BL o iC PR LBMFP TRIP SI DI: _.

PRRRhtitR TIME 07:30 07:45 08:00 08:15 08:30 08:45 09:00 09:15 09:20 09:35 09:45 R; actor Shutdown (Y/N) N N N H N N N Y HIS Power.-range (%) 100 100 100 100 Y Y Y 100 100 75 0 NIS Interim Range 0 0 0--

C35 (Reps) 3.7E-04 3.7E-04 3.7E-04 3.7E-04 NIS Interim Range 3.7E-04 3.7E-04 2.8E-04 5.2E-10_5.2E-10 1.2E-11 1.2E-11 C36 (Reps) 3.,9E-04 3.9E-04 3.9E-04 3.9E-04 NIS Source Range 3.9E-04 3.9E-04 2.9E-04 5.3E-10 .5.3E-10 1.6E-11 1.6E-11 C31 (Amps) 0 0 0 0 0 0 NIS Source Range 0 0 0 7000 7000

  1. 32 (Rmps) 0 0 0 0 0 0 0 RCS Incor T/C 0 0 9500 9500 (C:nter)(DegF) 599 599 599 599 599 RCS Incor T/C 599 586 558 558 599 599 (Highest)(DegF) 603 '- 603 603 605 ,. 605 RCS Pressure (PSIG) 605 596 562 562 603 603 2254 2254 2254 2254 2254 2254 2245 RCS Rvg. Temp.(DegF) 559 1872 1700 1510 1510 559 559 559 559 559 556 545 RCS Cold Leg Temp. (OegF) 533 541 574 574 533 533 533 533 533 537 545 SRT Meter Margin (OegF) 41 41 535 545 545 41 41 41 41 51 64 RCP in Service (Y/N) Y Y 64 0 0 Y Y Y Y Y Y Y Pressurizer Level (%) 40 40 40 40 40 40 40 N N R2cetor Vessel Level (%) 51 71 100 100 116 116 116 116 116 116 116 5/G HR Levels #21 (%) 55 115 115 95 e0 55 55 55 55 55 55 52 s22 53 53 52 62 62 53 53 53 53 53 51 51
  1. 23 53 53 53 63 63 53 53 53 53 52 52
  1. 24 55 55 55 59 59 55 55 55 55 53 53 5/G Press .a21 (PSIG) 664 664 664 664 664 61 61 a22 664 699 1005 1005 1005 1005 658 658 658 658 658 658 692 a23 1002 1002 1002. 1002 663 663 663 $63 663 663 695
  1. 24 1004 1004 1004 1004 666 666 666 666 666 666 704 VC Pressure (PSIG) -0.3 998 998 998 998

-0.4 -0.2 -0.2 -0.3 -0.3 -0.3 -0.3 UC Temperature (OegF) 95 95 95 95

-0.3 1.2 1.2 95 95 95 93 93 VC Sump Level (ft.) 40.2 40.2 40.2 40.2 40.2 99 99 VC Hydrogen (%) 40.2 40.2 40.2 40.2 40.2 41.2 0 0 0 0 0 0 0 0 Rux FW Flow SG21 (GPM) 28.1 0 0 0 28.1 28.1 28.1 28.1 28.1 28.1 200 200 SG22 0 0 100 100 0 0 0 0 0 201 201 SG23 0 0 0 112 112 0 0 0 0 198 198 SG24 0 0 0 98 98 0 0 0 0 203 203 RMST Level (ft.) 37.6 37.6 37.6 37.6 37.6 37.6 37.6 102 102 Cond Stor Tk Level (ft.) 37.5 37.5 37.0 36.5 28.5 28.5 28.5 28.5 28.5 28.5 28.5 28.5 28.4 28.4 28.4 NUE 1190 SHUT 2 ULV OPN

.,,.._w. .,w m a u -

Lud:2_eww FRIL ~

e-M". i 07/ 33 'OEFSITE OPEN  :

oE WIN 004 PRRAMETER TIME 10:00 10:15 10:30 ~' 10:45 10:55 11:15 11:30 11: 45 12:bb 12:15 12:30 Reactor Shutdown (Y/N) Y Y Y Y Y Y Y Y Y NIS Power range (%) 0 0- 0 0 0 0 0 Y Y NIS Interim Range 0 0 0 0

  1. 35 (Amps) .. 1.2E-11 1.2E-11 1.2E-11 1.2E-11 1.2E-11 1.1E-11 NIS Interim Range 1.1E-11 1.1E-11 1.1E-11 1.1E-11 1.1E-11 u36 (Rmps) 1.6E-11 1.6E-11 1.6E-11 1.5E-11 1.5E-11 1.5E-11 NIS Source Range 1.5E-11 1.5E-11 '1.5E-11 1.5E-11 1.4E-11
  1. 31 (Rmps) 6700 6400 6100 5800 5500 5200 NIS Source Range 4900 4600 4300 4000 3700
  1. 32 (Rmps) 9050 8600 8150 7700 7250 6800 RCS Incor T/C 6350 5900 5450 5000 4550 (Center)(DegF) 603 639 637 660 690 722 714 RCS Incor T/C 754 759 797 793 (Highest)(DegF) 625 645 655 665 ,. 695 725 745 RCS Pressure (PSIG) 760 780 795 820 1500 1530 1560 1500 1500 1500 1500 RCS Rvg. Temp.(DegF) 1500 1550 1405 1300 587 595 600 605 621 643 655 665 RCS Cold Leg Temp. (OegF) 548 676 689 708 545 545 545 547 561 564 570 573 SRT Meter Margin (OegF) 0 0 0 584 597 0 0 0 0 0 0 0 RCP in Service (Y/N) N N N N tt N H 0

Pressurizer Level (%) N M N N 100 100 100 100 100 100 100 100 Reactor Vessel Level (%) 100 100 100 77 76 75 73 68 63 58 53 5/G WR Levels #21 (%) 45 30 23 62 62 62 62 62 60 59 58

  1. 22 63 55 54 54 63 63 63 63 63 60 53 55 a23 59 59 53 52 59 58 58 58 57 57 57
  1. 24 61 61 57 57 61 61 61 61 60 59 5/G Press n21 (PSIG) 1005 59 59 59 1005 1005 1005 985 964 944 915 n22 908 904 884 1002 1002 1002 1002 950 932 912 912 m23 1004 903 887 883 1004 1004 1004 1002 999 978 969 n24 964 963 964 1005 1005 1005 1005 998 979 978 VC Pressure (PSIG) 962 936 932 932 1.8 2.1 2.3 2.4 1.9 1.1 0.9 VC Temperature (OegF) 0.5 0.5 0.6 0.2 101 102 102 102 102 103 104 VC Sump Level (ft.) 104 104 104 105 43.4 45.9 45.9 45.9 45.9 45.9 45.9 45.9 45.9 45.9 VC Hgdrogen (%) O O O O O O O 45.9 Rux FW Flow SG21 (GPM) 100 100 O 0.73% 0.78% 1.41%

100 100 203 203 203 203 203 SG22 112 112 203 203 112 112 204 204 204 204 204 SG23 98 98 0 204 204 0 0 0 0 0 0 0 SG24 102 102 0 0 0 0 0 0 0 0 0 RWST Level (ft.) 36.2 35.9 35.6 35.3 0 35.0 34.7 34.4 34.1 33.8 33.5 Cond Stor Tk Level (ft.) 28.4 28.3 28.3 28.3 33.2 28.3 28.3 29.2 28.2 28.2 28.2 28.2 RELERSE BRSED ON STRRTS SRMPLE

i

~

5 Y0 2 3 0 5 2  %

80880N052391 0O001 1

1 1

3 1 9 0300 1 1 1 66656 0

2 02. 00000033 8

58 8 E E 40 0 0 0 32 1 1 P

RS 0 Y0 2 3 0  %

RR 4 4 00000N052391 0O001 WU O

0 1

1 3 1 9 1 31 1 11 1

66656 0

2 02.00000033 8

58 8 E E .

EH 0 0 0 40 32 M

I 8 - 1 1 T4 ~

l  :
' . . : : :: l l  :::: l l  : : :: l 5 Y0 0 0 7  %

1 1 5031 0N057779421 71

_. 1 1

1 0

3 5

9 9

8 9575 8476 0644558873 1

77991 99.6000340080 01 5 22 08

_ 4 E E 1 1 45 1 3 32 C. .

1 1 0 Y0 0 0 7  %

1 1 30440N08877931 0

1 1

0 6

0 4

9 8

0074 9476 0544558073070.0 1

78991 99.000434001 1 5 22 1 8

. 0 4 E E 1 1 1 45 1

3 32 O.

1 1 0T 5 Y0 1 0 0 7  %

1 05370N01 9U 1

1 S H

5 3

1 E

E 1

0 9

1 5

8 1

9 8

1 9476 773 1

05445581 1

97793096739.300 63 7899015 0

6340040 22 1 8 1 0 4 44 32 1 1 EP 5 Y0 0 0 7  %

1 1 301 R1 O5 T2 4

3 1

E 1

E 0

2 2

0 3

8 8

1 9576 073 00N0498793786389.000 0444550363 1

889901 5 0

4340071 22 18 S2 1 2 1 44 ?2 4

O. .

1 1 ER 0 Y0 0 0 7  %

1 1 50040N07087951 RE OW TO 3

3 E

1 1

E 0

5 5

7 0

9 1072 9376 0354552663855.0 1

889901 5 89.500 9340001 22 28 2 2 1 43 SP 1 1 4 32 E . .

R 1 1 5 Y0 1 1 0 0 7  %

1 3

E 1

1 E

0 8

2 0

2 3

6 8 50930N02097979756.0 9552 8176 1 0354554663 1

889901 5 89.400 6340031 22 28 1 1 4 43 32 1 1 0 Y0 0 0 7  %

1 1 5081 0N01 1 0 1 1 0 5 4 6031 035555776307953556.0795340061 3

1 E

E

- 1 3

6 3

8 8176 1

1 8899015 430.2 2 00 28 32 1 4 1 1 5 Y0 0 0  %

1 1 9 00500N061 07953531 4

1 1

0 4

0 1

2 8

4521 8276 0255557763 1

0899015 69.3003340091 0

22 28 2 E E 3 4 1 42 1 1 32

. 4.,

1 1

)

u F ) ) )

g)  % G )

t ) .

x eF ( I M t N Og ) ) S ) P n / ) ( e) %l % P f

n Y) ) F F G (

t ( % ON( e( ( g) (

Gg .( / v ) e u3 E ( e e I ep

. l _

a9' M n g g e e Yl e12341 234GOt 1234 e _

) SDmn(

P( ei eL22222222I I wen) n) g) g) v # s# an# n#S

( f 2222) v T ogasasnsns ) F( .T geel P e

( ) GGGG .e _

d n R pR p a p a pC F C g p rcLes ( rl(

%S5SStL _

t a a mRmR m / g/ e e m g ai f _

.7 urmRmR R RTeTDreef vrse i sl ue ( k .

v0 h i( i( e( e( G ( uTL reev et vnw T R Srr r c c r( r) s re=Ve s raeeo u r L gl l _

u E ee5e6r1 er u 3 ur2o) 3 c rots .deSi _

T rwt3t3 c s e gl t L s se oF vo

..1 E oonmnao# osnenervoenuoR rr e sppr et M tPI I S S r emmdW LS

, . R c ItIhPRCMistW n g P reuyF R ASS S I sc PTSH Td s.C V. R eII S I S I SeSiSSSTPeaG CCCHCCCRCre/ G x Sn _

'; P RHH H N N R(R( RRRSRPR5 S

/ CCCCu Mo _

UVVVR RC _

'S 6 SCENARIO No. 1993 PLANT STATUS LOG PARAMETER T I ME___ PARAMETER TIME 07:30 07:30 Of fsite Power Avallebte 138KV 0 Service Water Pm ps #21 0~

13.8KV  ;

S (Circle Essential Hdr) #22 S 6900 Volt BUS NO. 1 0 #23 0 BUS NO. 2 0 #24 5 BUS NO. 3 0 *

  1. 25 0 BUS NO. 4 0 #26 0 BUS NO. 5 0 Circ Water Pm ps #21 0-BUS NO. 6 0 #22 0 480 Volt BUS SA 0 #23 0 BUS 2A 0 #24 0 BUS 3A 0 #25 0 BUS 6A 0 #26 0 Emergency D/Gs #21 S Condensate Pmps #21 0
  1. 22 S
  1. 22 0
  1. 23. S
  1. 23 0 Gas Turbines GT 1 0 Corp. Cool Heat Exch #21 0 GT-2 0 #22 S GT 3 0 RHR Heat Exchanger #21 S SIS Pm ps #21 S
  1. 22 S
  1. 22 0/S Fan cooler Units #21 0 j
  1. 23 S
  1. 22 0 RHR Pm ps #21 S
  1. 23 0
  1. 22 S
  1. 24 0 Charging Pm ps #21 0 #25 0
  1. 22 5
  1. 23 S Rx Coolant Pm ps #21 0 VC Isol. Phase A (f/N) N
  1. 22 0 VC Isol. Phase B (Y/N) N
  1. 23 0 VC isol. Vent (Y/N) N
  1. 24 0 Cocponent Cooling Pm ps #21 S Exceptions PCV-1190,1191,1192 OPEN
  1. 22 0 i
  1. 23 0 Nigh Head' SIS Flow #21 (CPM) 0 -

Aux Conponent Cooling Pmps #21 S

  1. 22 (CPM) 0
  1. 22 $
  1. 23 (CPM) 0 Aux Feed Water Pwps #21 S
  1. 24 (CPM) 0
  1. 22 0/S Low Head SIS Flow #21 (CPM) 0
  1. 23 S
  1. 22 (CPM) 0' Containment spray Pm ps #21 S
  1. 23 (CPM) 0
  1. 22 5
  1. 24 (GPM) 0 Recirculation Pm ps #21 S Accmulator Leve! #21 (%) 67
  1. 22 S
  1. 22 (%) 66 Hyttrrgen Reconbiner #21 5
  1. 23 (%) 67
  1. 22 S
  1. 24 (%) 68 Legend 0 s Operating O/S = Out of Service used to denote defective equipnent S = $tandby
  • Change on status from previous Log l

l VI - 4 i

3 a l

i SCENARIO WO. 1993 PLANT STATUS M l

PARAMETER TIME PARAMETER TIME 07:45 07:45 Of f site Power Available 138KY 0 Service Wr.ter Pm ps '

  1. 21 0 13.BKV S (Circle Essential Hdr) #22' S 6900 Volt BUS NO. 1 0
  1. 23 0 BUS Wo. 2 0
  1. 24 $

BUS NO. 3 0

  1. 25 0 BUS NO. 4 0
  1. 26 0 BUS NO. 5 0 Circ Water Pmps #21 0 BUS NO. 6 0
  1. 22 0 480 Volt BUS SA 0
  1. 23 0 BUS 2A 0 #24 0 BUS 3A 0 #25 0

BUS 6A 0 #26 0 Emergency D/cs #21 S Condensate Ptstos #21 0

  1. 22 5
  1. 22 0
  1. 23 S
  1. 23 0 Gas Turbines GT 1 0 Comp. Cool Heat Exch #21 0 GT-2 0
  1. 22 S GT-3 0 RHR Heat Exchanger #21 S

$1S Pmps #21 S

  1. 22 S
  1. 22 0/S Fan Cooler Units #21 0
  1. 23 S
  1. 22 0 RHR Pw ps #21 S
  1. 23 0
  1. 22 S
  1. 24 0 Charging Pm ps #21 0 #25 0
  1. 22 S
  1. 23 S Rx Coolant Pw ps #21 0 VC 1 sol. Phase A Conplete (Y/N) N
  1. 22 0 VC Isol. Phase B Cocplete (Y/N) N
  1. 23 0 VC isol. Vent Cocplete (Y/N) N
  1. 24 0 Component Cooling Pm ps #21 S Exceptions PCV 1190,1191,1192 OPEN
  1. 22 0
  1. 23 0 High Head SIS Flow #21 (GPM) 0 Aux Corrpanent Cooling Pmps #21 S
  1. 22 (GPM) 0
  1. 22 S
  1. 23 (GPM) 0 Aux Feed Water Pwps #21 S
  1. 24 (GPM) 0
  1. 22 O/S Low Head SIS Flow #21 (GPM) 0
  1. 23 S
  1. 22 (GPM) O Containment Spray Pm ps #21 S
  1. 23 (GPM) 0
  1. 22 S
  1. 24 (GPM) 0 Recirculation Pm ps #21 S Acetrnulator Level #21 (%) 67
  1. 22 S
  1. 22 (%) 66 Hydrogen Recentiner #21 S
  1. 23 (%) 67
  1. 22 S
  1. 24 (%) 68 Legend 0 = Operating O/S = out of Service used to denote defective equipment S e S t arvby
  • = Change on status from previous log VI - 5

_ ^

.j r g.

SCENARIO NO, 1993 PLANT STATUS tog PARAMETER YlME PARAMETER TIME 08:00 08:00 offsite Po wer Available 138KV O Service Water Ptinps #21' 0 13.8KV S (Circle Essential Hdr) #22 S 6900 Volt DUS No. 1 0 #23 0 BUS NO. 2 0 #24 S BUS NO. 3 0 #25 0

  • BUS NO. 4 0 #26 0 BUS NO. 5 0 Circ Water Ptros #21 0 BUS NO. 6 0 #22 0 480 Volt BUS SA 0 #23 0 BUS 2A 0 #24 0 BUS 3A 0 #25 0 BUS 6A 0 #26 0 Emergency D/Gs #21 S Corx1ensate Ptros #21 0
  1. 22 S
  1. 22 0
  1. 23 S
  1. 23 0 '

Gas Turbines GT-1 0 Comp. Cool Heat Exch #21 0 GT-2 0 #22 S GT-3 0 RHR Heat Exchanger #21 S SIS Ptros #21 S

  1. 22 S
  1. 22 O/S Fan Cooler Units #21 0
  1. 23 5 #22 0 RHR Ptsps #21 5 #23 0
  1. 22 S
  1. 24 0 Charging Ptrps #21 0 #25 0
  1. 22 5
  1. 23 S Rx Coolant Ptrps #21 0 VC ! sol. Phase A Cortplete (Y/N) N
  1. 22 0 VC Isol. Phase B Complete (Y/N) N
  1. 23 0 VC isol. Vent Cortplete (Y/N) N
  1. 24 0 Corrponent Cooling Ptsps #21 S Exceptions PCV-1190,1191.1192 OPEN
  1. 22 0
  1. 23 0 High Head SIS Flow #21 (CPM) 0 Aux Component Cooling Ptmps #21 S
  1. 22 (GPM) 0
  1. 22 5 0

'#23 (CPM)

Aux Feed Water Ptrps #21 S

  1. 24 (CPM) 0
  1. 22 0/S Low Head SIS Flow 0
  1. 21 (CPM)
  1. 23 S
  1. 22 (CPM) O Contairment spray Ptrps #21 5
  1. 23 (CPM) 0
  1. 22 S
  1. 24 (CPM) 0 Recirculation Ptros #21 S Acetrulator Level #21 (%) 67
  1. 22 5
  1. 22 (%) 66 Hydrogen Reconbiner #21 S
  1. 23 (%) 67
  1. 22 5
  1. 24 (%) 68 Legend 0 = Operating O/S = Out of Service used to denote defective equipnent S = S t ancby
  • = Change on status frorn previous log VI - 6

b e SCENARIO NO. 1993 PLANT STATUS LOG PARAMETER TIME PARAMETER TIME 08:15 08:15 offsite Power Avellable 138KV 0 Service Water Pumps #21 0 13.8KV S (Circle Essential Ndr) #22 S 6900 Volt BUS NO. 1 0

  1. 23 0 SUS NO. 2 0
  1. 24 S BUS NO. 3 0
  1. 25 0 BUS NO. 4 0
  1. 26 0 BUS NO. 5 0 cire Water Pumps #21 0 BUS NO. 6 0
  1. 22 0 480 Volt BUS SA 0 #23 0 BUS 2A 0
  1. 24 0 BUS 3A 0
  1. 25 0 BUS 6A 0
  1. 26 0 Emergency D/Cs #21 S Condensate Pwps #21 0
  1. 22 S
  1. 22 0
  1. 23 S
  1. 23 0 Gas Turbines GT-1 0 Copp. Cool Heat Exch #21 0 GT-2 0 #22 S GT-3 0 RHR Heat Exchanger #21 S SIS Pm ps #21 S
  1. 22 S
  1. 22 O/S Fan Cooler Units #21 0
  1. 23 S
  1. 22 0 RHR PtsTin #21 S
  1. 23 0
  1. 22 S
  1. 24 0 Charging Pwps #21 0
  1. 25 0
  1. 22 S
  1. 23 S Rx Coolant Pwps #21 0 VC isol. Phase A Complete (Y/N) N
  1. 22 0 VC isol. Phase B Conclete (Y/N) N
  1. 23 0 VC isol. Vent Conplete (Y/N) N
  1. 24 0 Conponent Cooling Pwps #21 S Exceptions PCV-1190,1191,1192 OPEN
  1. 22 0
  1. 23 0 High Head SIS Flow #21 (CPM) 0 Aux Corponent Cooling PLrps #21 S
  1. 22 (CPM) 0
  1. 22 S
  1. 23 (CPM) 0 Aux Feed Water PLrps #21 S
  1. 24 (CPM) 0
  1. 22 O/S Low Head SIS Flow #21 (GPM) 0
  1. 23 S
  1. 22 (CPM) O Containment Spray Pwps #21 S
  1. 23 (GPM) 0
  1. 22 S
  1. 24 (CPM) 0 Recirculation Punps #21 S Acetsnulator Level #21 (%) 67
  1. 22 5 Hydrogen Recorrbiner #22 (%) 66
  1. 21 S
  1. 23 (%) 67
  1. 22 S
  1. 24 (%) 68 Legend 0 e Operatlng O/S = Out of Service used to denote defective equipnent S = Standby
  • =

Change en status frora previous log VI - 7

1 e a ECENARIO NO 1993 PLANT STATUS LOG PARAMETER TIME PARAMETER TIME 08:30 08:30 Offsite Power Available 138KV O Service Water Pumps #21 0 13.8CV S (Circle Essential Hdr) #22 S 6900 Volt BUS NO. 1 0 #23 0 BUS NO. 2 0 #24 S BUS NO. 3 0 #25 0 BUS NO. 4 0 #26 0 SUS NO. 5 0 Circ Water Ptsups #21 0 BUS NO. 6 0 #22 0 480 Volt BUS 5A 0 #23 0 BUS 2A 0 #24 0 BUS 3A 0 #25 0 BUS 6A 0 #26 0 Emergency D/Gs #21 S Condensate Pumps #21 0

  1. 22 S
  1. 22 0
  1. 23 S
  1. 23 0 Gas Turbines GT-1 0 Cocp. Cool Heat Exch #21 0 GT-2 0 #22 S GT-3 0 RHR Heat Exchanger #21 S SIS Pumps #21 S
  1. 22 0
  1. 22 0/S Fan Cooler Units #21 0
  1. 23 S
  1. 22 0 RHR Pumps #21 S
  1. 23 0
  1. 22 S
  1. 24 0 Charging Pumps #21 0 #25 0
  1. 22 S
  1. 23 S Rx Coolant Punps #21 0 VC isol. Phase A (Y/N) N
  1. 22 0 VC isol. Phase B (Y/N) N
  1. 23 0 VC 1s01. Vent (Y/N) N
  1. 24 0 Component Cooling Purps #21 S Exceptions PCV-1191,1192 OPEN
  1. 22 0 PCV 1190 CLOSED
  1. 23 0 High Head SIS Flow #21 (CPM) 0 Aux Conponent Cooling Punps #21 S
  1. 22 (GPM) 0
  1. 22 S
  1. 23 (GPM) 0 Aux Feed Vater Pumps #21 S
  1. 24 (CPM) 0
  1. 22 0/5 Low Head SIS Flow #21 (GPM) 0
  1. 23 S
  1. 22 (GPM) O Containment Spray Pumps #21 5
  1. 23 (CPM) 0
  1. 22 S
  1. 24 (GPM) 0 Recirculation Purps #21 S Accumulator Level #21 (%) 67
  1. 22 S
  1. 22 (%) 66 Hydrogen Recombiner #21 S
  1. 23 (%) 67
  1. 22 S
  1. 24 (%) 68 Legend 0 = Operating 0/S = Out of service used to denote defective equipment S = Standby
  • = Change on status from previous log VI - 8

,a a ICENARIO No. 1993 PLANT sfATus LOG PARAMETER TIME PARAMETER TIME 08:45 08:45 Of fsite Power Available 138KV 0 Service Water Puips #21 0 13.8KV S (Circle Essential Hdr) #22 S 6900 Volt BUS No. 1 0 #23 0 BUS No. 2 0 #24 S SUS No. 3 0 #25 0 BUS NO. 4 0 #26 0 BUS NO. 5 0 cire Water Punps #21 0 BUS NO. 6 0 #22 0 480 Volt BUS SA 0

  1. 23 0 BUS 2A 0 #24 0 BUS 3A 0 #25 0 BUS 6A 0 #26 0 Emergency O/Gs #21 0 Condensate Purps #21 0
  1. 22 0 #22 0
  1. 23 0 #23 0 Gas Turbines GT 1 S Ceep. Cool Heat Exch #21 0 GT-2 S
  1. 22 S CT-3 S RHR Heat Exchanger #21 S Sls Puros #21 S
  1. 22 S
  1. 22 0/S Fan Cooler Units #21 0
  1. 23 S
  1. 22 0 RHR Puvs #21 S
  1. 23 0
  1. 22 S
  1. 24 0 Charging Puys #21 0 #25 0
  1. 22 S
  1. 23 S Rx Coolant Purps #21 0 VC isol. Phase A (Y/N) N
  1. 22 0 VC Isol. Phase B (Y/N) N
  1. 23 0 VC isol. Vent (Y/N) N
  1. 24 0 Corrponent Cooling Puys #21 S Exceptions PCV-1191,1192 OPEN
  1. 22 0 PCV-1190 CLOSED
  1. 23 0 High Head $15 Flow #21 (GPM) 0 Aux Corrponent Cooling Puvs #21 S
  1. 22 (GPM) 0
  1. 22 S
  1. 23 (CPH) 0 Aux Feed Water Pums #21 S
  1. 24 (GPM) 0
  1. 22 0/S Low Head SIS Flow #21 (GPM) 0
  1. 23 S
  1. 22 (CPM) O Contalrunent sprey Purps #21 S
  1. 23 (CPM) 0
  1. 22 S
  1. 24 (GPM) 0 Rec 1rculation Ptsps #21 S Accunutator Levet #21 (%) 67
  1. 22 S
  1. 22 (%) 66 Hydrogen Reconbiner #21 5
  1. 23 (%) 67
  1. 22 S
  1. 24 (%) 68 Legend 0 = Operating O/S = Out of Service used to denote defective equipment S = $tandby
  • = Change on status from previous log VI - 9

e o SCENARIO NO, 1993 PLANT STATUS tog PARANETER TIME PARAMETER TIME 09:00 09:00 Offsite Power Available 138KV O Service Water Pwps #21 0 13.8KV S (Circle Essential Hdr) #22 5 6900 Volt BUS No. 1 0 #23 0 BUS NO. 2 0 #24 S BUS NO. 3 0 #25 0 BUS NO. 4 0 #26 0 BUS NO. 5 U Cire Water Pwps #21 0 BUS NO. 6 0 #22 0 480 volt RUS SA 0 #23 0 BUS 2A 0 #24 0 BUS 3A 0 #25 0 BUS 6A 0 #26 0 Emergency D/Gs #21 S Condensate Pwps #21 0

  1. 22 S
  1. 22 0
  1. 23 S
  1. 23 0 Gas Turbines GT-1 0 Corp. Cool Heat Exch #21 0 GT 2 0 #22 S GT-3 0 RHR Heat Exchanger #21 S SIS Pwps #21 S
  1. 22 S
  1. 22 0/S ran Cooler Units #21 0
  1. 23 S
  1. 22 0 RHR Pw ps #21 S
  1. 3 0
  1. 22 S
  1. 24 0 Charging Pwps #21 0 #25 0
  1. 22 'S
  1. 23 S Rx Coolant Pw ps #21 0 VC lsel. Phase A (Y/N) N
  1. 22 0 VC isol. Phase B (Y/N) N
  1. 23 0 VC ! sol. Vent (Y/N) N
  1. 24 0 Corponent Cooling Pwps #21 S Exceptions PCV-1191, 1192 OPEN
  1. 22 0 PCV-1190 CLOSED
  1. 23 0 High Head S!$ Flow #21 (GPM) 0 Aux Corponent Cooling Pwps #21 5
  1. 22 (CPM) 0
  1. 22 S 0
  1. 23 (CPM) l Aux Feed Water Pwps #21 0* #24 (CPM) 0 622 0/S Low Head SIS Flow #21 (GPM) 0
  1. 23 0* #22 (GPM) o Containment spray Pw ps #21 S
  1. 23 (CPM) 0
  1. 22 S 0
  1. 24 (CPM)

Recirculation Pwps #21 S Accumulator Level 67

  1. 21 (%) l
  1. 22 S 66
  1. 22 (%) l Hydrogen Recontiner #21 S
  1. 23 (%) 67 l
  1. 22 5 l
  1. 24 (%) 68 Legend 0 = Operating O/S = Out of Service used to denote defective equipment S = Standby i
  • = Change on status f run previous log VI - 10 i

l I

4 s SCENARIO NO. 1993 PLANT STATUS LOG PARAMETER TIME PARAMETER TIME 09:15 09:15 Of fsite Power Available 138KV O Service Water Ptrps #21 0 13.8KV S (Circle Essentlet Hdr) #22 S 6900 Volt BUS NO. 1 0 #23 0 BUS No. 2 0 #24 S BUS NO. 3 0

  1. 25 0 BUS NO. 4 0 #26 0 BUS WO. 5 0 circ Water Ptsrps #21 0 BUS ho. 6 0 #22 0 480 Volt SUS SA 0 #23 0 BUS 2A 0 #24 0 BUS 3A 0 #25 0 BUS 6A 0 #26 0 Emergency D/Gs #21 S Condensate Ptrps #21 0
  1. 22 S
  1. 22 0
  1. 23 S
  1. 23 S*

Gas Turbines CT 1 0 Copp. Cool Heat Exch #21 0 GT-2 0 #22 S GT-3 0 RHR Heat Exchanger #21 S SIS Ptsps #21 S

  1. 22 S
  1. 22 0/S Fan Cooler Units #21 0
  1. 23 S
  1. 22 0 RHR Ptrps #21 S
  1. 23 0
  1. 22 S
  1. 24 0 Charging Ptros #21 0 #25 0
  1. 22 S
  1. 23 S Rx Coolant Ptrps #21 0 VC isol. Phase A (Y/N) N
  1. 22 0 VC isol. Phase 8 (Y/N) N
  1. 23 0 VC Isol. Vent (Y/N) N
  1. 24 0 Corponent Cooling Ptrps #21 S Exceptions PCV-1191,1192 OPEN
  1. 22 O PCV 1190 CLOSED
  1. 23 0 Migh Head $1S Flow #21 (CPM) O Aux Conponent Cooling Ptsps #21 S
  1. 22 (GPM) 0
  1. 22 S
  1. 23 (CPM) 0 Atut Feed Water Ptsps #21 0
  1. 24 (GPM) 0
  1. 22 O/S Low Head SIS Flow #21 (CPM) 0
  1. 23 0
  1. 22 (GPM) O Contairrent Spray Ptsps #21 S
  1. 23 (GPM) 0
  1. 22 S
  1. 24 (CPM) 0 Recirculation Pttps #21 S Acetsnulator Level #21 (%) 67
  1. 22 S
  1. 22 (%) 66 Hydrogen Reconbiner #21 S
  1. 23 (%) 67
  1. 22 S
  1. 24 (%) 68 Legend 0 = Operating O/S = out of Service used to denote defective equipment S = Standby l
  • =

Change on status from previous log l

I VI - 11 1 l

1

a s SCENARIO No. 1993 PLANT STATUS tog PARAMETER TlHE PARAMETER TIME 09:20 09:20 Cffsite Power Available 13BKV O Service Water Pw ps #21 0 13.BKV 5 6900 Volt (Circle Essential Hdr) #22 0*

BUS NO. 1 0

  1. 23 0 BUS NO. 2 0
  1. 24 S BUS NO. 3 0
  1. 25 S*

BUS NO. 4 0

  1. 26 $*

BUS No. 5 0 Circ Water Pwps #21 0 BUS NO. 6 0

  1. 22 0 480 Volt BUS SA 0
  1. 23 o BUS 2A 0
  1. 24 0 BUS 3A 0
  1. 25 0 BUS 6A 0
  1. 26 0 Emergency D/Gs #21 0* Corriensate Pmps #21 0
  1. 22 0*
  1. 22 0
  1. 23 0*
  1. 23 $*

Gas Turbines GT-1 0 Conp. Cool Heat Exch #21 0 GT 2 0

  1. 22 S CT-3 0 RHR Heat Exchanger #21 0 SIS Pm ps #21 0/S*
  1. 22 0
  1. 22 0/S Fan Cooler Units #21 0
  1. 23 0*

K22 0 RHR Pw ps #21 0*

  1. 23 0
  1. 22 0*
  1. 24 0 Charging Pwps #21 S
  1. 25 0
  1. 22 S
  1. 23 S Rx Coolant Pwps #21 0 VC isol. Phase A (Y/N) Y
  1. 22 0 VC isol. Phase 8 (Y/N) N
  1. 23 0 VC ! sol. Vent (Y/N) N
  1. 24 0 Conponent Cooling Punps #21 0* Exceptions PCV-1191, 1192 OPEN
  1. 22 0 PCV-1190 CLOSED
  1. 23 0 High Head SIS Flow
  1. 21 (GPM) o Aux Component Cooling Pwps #21 0*
  1. 22 (CPM) 0
  1. 22 0*
  1. 23 (GPM) 0 Aux Feed Water Pw ps #21 0
  1. 24 (CrM) 0
  1. 22 0/S Low Head SIS Flow #21 (CPM) 0
  1. 23 0
  1. 22 (GPM) O Contairrnent Spray Pmps #21 S
  1. 23 (GPM) 0
  1. 22 S
  1. 24 (GPM) 0 Recirculation Pirnps #21 S Accunulator Level #21 (%) 67
  1. 22 S Hydrogen Reconbiner #22 (%) 66
  1. 21 S
  1. 23 (X) 67
  1. 22 S
  1. 24 (%) 68 Legend 0 = Operating O/S = out of Service used to denote defective eqJipnent S = Standby
  • =

Change on status from previous log VI 12

a 6 SCENARIO NO, 1993 PLANT STATUS LOG PARAMETER TIME PARAMETER TIME 09:30 09:39 Of fsite Power Available 138KV O Service Water Pumps #21 0 13.8KV S (circle Essential Hde) #22 0*

6900 Volt BUS NO. 1 0 #23 0 BUS No. 2 0 #24 S BUS NO. 3 0 #25 S*

BUS NO. 4 0 #26 S*

BUS No. 5 0 Circ Water Pumps #21 O BUS NO. 6 0 #22 0 480 Volt BUS 5A 0 #23 0 BUS 2A 0 #24 0 BUS 3A 0 #25 0 BUS 6A 0 #26 0 Energency D/Gs #21 0* Condensate Ptsps #21 0

  1. 22 o' #22 0
  1. 23 0* #23 S*

Cas Turbines 61 1 0 Comp. Cool Heat Exch #21 0' GT-2 0 #22 S GT-3 0 RHR Heat Exchanger #21 0 SIS Purps #21 0/S #22 0

  1. 22 0, s Fan Cooler Units #21 0
  1. 23 0 #22 0 RHR Punps #21 0 #23 0
  1. 22 0 #24 0 Charging Pumps #21 0* #25 0
  1. 22 S
  1. 23 5 Rx Coolant Pumps #21 0 VC isol. Phase A (Y/N) Y
  1. 22 0 VC Isol. Phase B (Y/N) N
  1. 23 0 VC 1 sol. Vent (Y/N) N
  1. 24 0 Component Cooling Purps #21 0 Exceptions PCV 1191, 1192 DPEN
  1. 22 0 PCV-1190 CLOSED
  1. 23 0 High Head SIS Flow #21 (CPM) 0 Aux Component Cooling Pumps #21 0 #22 (GPM) 0
  1. 22 0 0
  1. 23 (GPM)

Aux Feed Water Purps #21 0 #24 (GPM) 0

  1. 22 0/S Low Head SIS Flow #21 (GPM) 0
  1. 23 0 #22 (CPM) 0 Containment Spray Punps #21 5
  1. 23 (CPM) 0
  1. 22 5 0
  1. 24 (CPM)

Recirculation Pumps #21 5 Accumulator Level #21 (Z) 67

  1. 22 S
  1. 22 (%) 66 Hydrogen Reconbiner #21 5
  1. 23 (%) 67
  1. 22 S
  1. 24 (%) 68 Legend 0 = Operating O/S = out of Service used to denote defective equipment S = Standby
  • = Change on stetus from prevlous log VI - 13

s e SCENARIO NO. 1993 PLANT STATUS LOG P APANE f t'R TIME PARAMETER TIMF 09:35 09:35 Otisite Power Available 138KV O Service Water Pumps #21 0 13.8KV S (circle Essential Hdr) #22 0*

6900 Volt BUS No. 1 0 #23 0 BUS NO. 2 0 #24 S BUS NO. 3 0 #25 S*

BUS No. 4 0

  1. 26 S*

BUS NO. 5 0 Cire Water Pumps #21 0 BUS NO. 6 0 #22 0 480 Volt BUS SA 0

  1. 23 0 BUS 2A 0
  1. 24 0 BUS 3A 0 #25 0 BUS. 6A 0 #26 0 Emergency D/Gs #21 0 Condensate Pumps #21 0
  1. 22 0 #22 0
  1. 23 0 #23 S*

Gas Turbines GT-1 0 Comp. Cool Heat Exch #21 0 GT-2 0 #22 S CT 3 0 RHR Heat Exchanger #21 0

$15 Purps #21 0/5

' #22 0

  1. 22 0/S Fan Cooler Units #21 0
  1. 23 0 #22 0 RHR Pumps #21 0 #23 0
  1. 22 0 #24 0 Charging Pm ps #21 0 #25 0
  1. 22 $
  1. 23 S Rx Coolant Pumps #21 S VC isol. Phase A (Y/N) Y
  1. 22 S* VC ! sol. Phase B (Y/N) N
  1. 23 S* VC isol. Vent (Y/N) N
  1. 24 S*

Conponent Cooling Popps #21 0* Exceptions PCV 1191, 1192 OPEN

  1. 22 0 PCV-1190 CLOSED
  1. 23 0 High Head SIS Flow #21 (CPM) o Aux Component Cooling Pumps #21 0
  1. 22 (GPM) 0
  1. 22 0
  1. 23 (GPM) 0 Aux Feed Water Pupps #21 0
  1. 24 (GPM) 0
  1. 22 O/S Low Head SIS Flow #21 (GPM) 0
  1. 23 0
  1. 22 (GPM) O Containnent Spray Pumps #21 S
  1. 23 (GPM) 0
  1. 22 S
  1. 24 (GPM) 0 Recirculation PLnps #21 S Accumulator Level #21 (%) 67
  1. 22 3
  1. 22 (%) 66 Hydrogen Recombiner #21 S
  1. 23 (%) 67
  1. 22 S
  1. 24 (%) 68 Legend 0 = Operating D/S = Out of Service used to denote defective equirrnent S = Standby
  • = Change on status frcun previous log VI - 14

e e SCENARIO NO. 1993 EiANT SiniUS log PARAMETER TIME PARAMETER TIME 09:45 09:45 offsite Power Available 13BKV O Service Water Pumps #21 0 13.8KV S (Circle Essential Hdr) #22 0*

6900 Volt BUS NO. 1 0 #23 0 BUS WO. 2 0 #24 S BUS NO. 3 0 #25 $*

BUS NO. 4 0 #26 S*

BUS NO. 5 0 Circ Water Pumps #21 0 BUS NO. 6 0 #22 0 480 Volt BUS SA 0 #23 0 BUS 2A 0 #24 0 BUS 3A 0 #23 0 BUS 6A 0 #25 0 Emergency D/Gs #21 0 Condensate Pumps #21 0

  1. 22 0 #22 0
  1. 23 0 #23 S*

Gas Turbines CT-1 0 Ca T). Cool Heat Exch #21 0 GT 2 0 #22 S GT 3 0 RHR Heat Fxchanger #21 0 SIS Pumps #21 0/S #22 0

  1. 22 0/S fan Cooler Units #21 0
  1. 23 0 #22 0 RHR Purps #21 0 #23 0
  1. 22 0 #24 0 Charging Pumps #21 0* #25 0
  1. 22 S
  1. 23 S Rx Coolant Pulps #21 5 VC isol. Phase A (Y/N) Y
  1. 22 S VC isol. Phase B (Y/N) N
  1. 23 S VC ! sol. Vent (Y/N) ,

1

  1. 24 S Component Cooling Purps #21 0 Exceptions PCV 1191, 1192 OPEN
  1. 22 0 PCV 1190 CLOSED
  1. 23 0 High Head SIS tlow #21 (CPM) o Aux Component Cooling Ptrvs #21 0
  1. 22 (CPM) 0
  1. 22 0 #23 (GPM) o Aux Feed Water Punps #21 0 #24 (CPM) 0
  1. 22 O/S Low Head SIS Flow #21 (CPM) 0
  1. 23 0 #22 (crM) O Containment Spray Purps #21 S
  1. 23 (CPM) 0
  1. 22 S
  1. 24 (CPM) 0 Rectrculation PLrps #21 S Accunulator Level #21 (%) 67
  1. 22 S
  1. 22 (%) 66 Hydrogen Recombiner #21 S
  1. 23 (%) 47
  1. 22 S
  1. 24 (%) 65 Legend 0 = Operating O/S = Out of Service used to denote defective equipment S = Standby
  • = Change on status from previous log VI - 15

e o SCENARIO No. 1993 PLANT STATUS tog PARAMETER TIME PARAMETER ftMC 10:00 10:00 Offsite Power Available 138KV 0 Service Water Pwps #21 0 13.8KY S (Circle Essential Ndr) #22 0*

6900 Volt BUS No. 1 0 #23 0 BUS NO. 2 0 #24 5 BUS NO. 3 0 #25 S*

BUS NO. 4 0 #26 S*

BUS NO. 5 0 circ Water Punps #21 0 BUS NO. 6 0 #22 0 480 Volt BUS SA 0 #23 0 BUS 2A O #24 0 BUS 3A 0 #25 0 BUS 6A 0 #26 0 Emergency D/Gs #21 0* Condensate Pwps #21 0

  1. 22 0* #22 0
  1. 23 0* #23 S*

Gas Turbines GT-1 0 Comp. Cool Heat Exch #21 0 GT-2 0 #22 S GT-3 0 RhR Heat Exchanger #21 0

$15 Pwps #21 0/S #22 5

  1. 22 0/S Fan Cooter Units #21 0
  1. 23 0 #22 0 RHR Pw ps #21 0 #23 0
  1. 22 0 #24 0 Charging Pwps #21 0* #25 0
  1. 22 5
  1. 23 S Rx Coolant Pwps #21 O VC ! sol. Phase A (Y/N) Y
  1. 22 0 VC isol. Phase B (Y/N) N
  1. 23 0 VC Isol. Vent (Y/N) N
  1. 24 0 Component Cooling Pw ps #21 0* Exceptions PCV 1191, 1192 OPEN
  1. 22 0 PCV 1190 CLOSED
  1. 23 0 High Head S!$ Flow #21 (GPM) 0 Aux Corrponent Cooling Pwps #21 0* '
  1. 22 (GPM) 0
  1. 22 0* #23 (GPM) 0 Aun Feed Water Ptsps #21 0 #24 (GPM) 0
  1. 22 0/S Low Head SIS Flow #21 (GPM) 0
  1. 23 0 #22 (GPM) O Containment Spray Punos #21 S
  1. 23 (GPM) 0
  1. 22 S
  1. 24 (GPM) 0 Recirculation Pwps #21 S Acewulator Level #21 (%) 67
  1. 22 S
  1. 22 (%) 66 Hydrogen Reconbiner #21 S
  1. 23 (%) 67
  1. 22 S
  1. 24 (%) 68 Legend 0 = Operating O/S = out of Service used to denote defective eqJipnent S = Standby
  • = Change on status from previous Log VI - 16

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

's a b

SCENARIO No. 1993 PLANT STATUS LOG PARAMETER  !

Y1ME PARAMETER f!ME 10:15 10))

1 of fsite Power Available 138W 0 service Water Pw ps #21 0 '

13.8W S (Circle Essential Hdr) #22 0*

6900 Volt BUS No. 1 0

  1. 23 0 BUS NO. 2 0 #24 S BUS Wo. 3 0
  1. 25 S*

BUS NO. 4 0

  1. 26 $*

BUS Wo. 5 0 circ Water Pwps #21 0 BUS NO. 6 0 #22 0 480 Volt BUS 5A 0

  1. 23 0 BUS 2A 0 #24 0

BUS 3A 0 #25 0 BUS 6A 0

  1. 26 0 Emergency D/Gs #21 0 condensate Pwps #21 0
  1. 22 0
  1. 22 0
  1. 23 0 #23 S*

Gas Turbines GT-1 0 Conp. Cool Heat Exch #21 0 GT-2 0 #22 S +

Gi+3 0 RHR Heat Exchanger #21 0

$15 Pw ps #21 0/S #22 0

  1. 22 0/S Fan Cooler Units #21 0
  1. 23 0 #22 0 RHR Pw ps #21 0
  1. 23 0
  1. 22 0 #24 0 Charging Pw ps #21 0* #25 0
  1. 22 S
  1. 23 S I Rx Coolant Pw ps #21 S VC isol. Phase A (Y/N) Y
  1. 22 S VC isol. Phase B (Y/N) N.
  1. 23 - S VC Isol. Vent (Y/N) N
  1. 24 S Component Cooling Pwps #21 0 Exceptions PCV-1191, 1192 OPEN
  1. 22 0 PCV-1190 CLOSED I
  1. 23 0 High Head SIS Flow #21 (GPM) o Aux Conponent Cooling Pwps #21 0
  1. 22 (CPM) 0
  1. 22 0
  1. 23 (CPM) 0 Aux Feed Vater Pwps #21 0
  1. 24 (CPM) 0
  1. 22 0/S Low Head SIS Flow #21 (CPM) 0
  1. 23 0
  1. 22 (CPM) O Contalrment Spray Pwps #21 S
  1. 23 (CPM) 0
  1. 22 S
  1. 24 (CPM) 0 Recirculation Punps #21 5 Aecunulator Level #21 (%) 67
  1. 22 S
  1. 22 (%) 66 Hydrogen Recontiner #21 S
  1. 23 (%) 67
  1. 22 S
  1. 24 (%) 68 Legend 0 = Opefsting O/S = Out of Service used to denote defective equipment S = Standby ,
  • = Change itstus from previous log vt - 17

SCENARIO No. 1993 PLANT STATUS LOG PARAMETER TIME PARAMETER TIME 10:30 10:30 Of fsite Power Available 13BCV O/S* Service Water Pumps #21 0 13.8KV S 6900 Volt (Circle Essential Hdr) #22 0 BUS No. 1 $*

  1. 23 S*

BUS No. 2 S*

  1. 24 S BUS No. 3 S*
  1. 25 S BUS NO. 4 $*
  1. 26 S BUS No. 5 S* Circ Water Pumps #21 S*

BUS NO. 6 S*

  1. 22 S*

480 Volt BUS 2A 0

  1. 23 S*

BUS 3A 0

  1. 24 S*

BUS SA 0

  1. 25 S*

BUS 6A O/S Emergency D/Cs #26 S*

  1. 21 0 Condensate Pumps #21 S*
  1. 22 0
  1. 22 S*
  1. 23 0
  1. 23 S*

Gas Turbines GT-1 0 Comp. Cool Heat Exch #21 0 GT-2 0

  1. 22 5 GT-3 0 RHR Heat Exchanger #21 0 Sls Pumps #21 0/S
  1. 22 0
  1. 22 0/S Fan Cooler Units #21 0
  1. 23 S*
  1. 22 0 RNR Pugxi #21 0
  1. 23 0
  1. 22 S*
  1. 24 0 Charging Purps #21 0
  1. 25 $*
  1. 22 5
  1. 23 S*

Rx Coolant Purps #21 S VC isol. Phase A (Y/N) Y

  1. 22 5 VC isol. Phase B (Y/N) N
  1. 23 5 VC isol. Vent (Y/N) N
  1. 24 S Component Cooling Pumps #21 0 Exceptions PCV 1191, 1192 OPEN
  1. 22 0 PCV-1190 CLOSED
  1. 23 S* High Head $15 Flow
  1. 21 (GPM) 0 Aux Component Cooling Pumps #21 0
  1. 22 (GPM) 0
  1. 22 S*

Aux Fred Water Pumps #23 (GPM) 0

  1. 21 0
  1. 24 (CPM) 0
  1. 22 0/S Low Head SIS Flow #21 (CPM) 0
  1. 23 S*

Containment Spray Pumps #Z2 (GPM) o

  1. 21 5
  1. 23 (GPM) 0
  1. 22 S
  1. 24 (CPM) 0 Recirculation Pumps #21 S Accumulator Level #21 (%) 67
  1. 22 S Hydrogen Recombiner #22 (%) 66
  1. 21 5
  1. 23 (%) 67
  1. 22 S
  1. 24 (%) 68 Legend 0 = Operating O/S = Out of Service used to denote defective equipnent S = Standby
  • =

Change on status from previous log o

VI - 18

SCENARfD NO, 1993 PLANT STATUS LOG PARAMETER f!ME PARAMETER TIME 10:45 10:45 Offsite Power Available 138KV O/S Service Water Purnps #21 0 13.8KV S (Circle Essential Hdr) #22 0 6900 Volt BUS NO. 1 S

  1. 23 S BUS No. 2 S
  1. 24 S BUS NO. 3 $
  1. 25 S BUS NO. 4 S
  1. 26 S DUS NO. 5 S Cire Water Purps #21 S BUS NO. 6 S
  1. 22 S 480 Volt BUS 2A 0 #23 S BUS 3A 0 #24 S BUS SA 0 #25 S BUS 6A 0/S #26 S Emergency D/Gs #21 0 Condensate Pumps #21 S
  1. 22 0 #22 S
  1. B o #B S Gas Turbines GT-1 0 Comp. Cool Heat Exch #21 0 GT-2 0 #22 S GT-3 0 RHR Heat Exchanger #21 0 S!S Punps #21 0/S #22 0
  1. 22 0/5 Fan Cooler Units #21 0
  1. 23 S* #22 0 RHR Purps #21 0 #23 0
  1. 22 S* #24 0 Chorging Pumps #21 0 #25 S
  1. 22 S
  1. 23 S*

Rx Cootant Punt >s #21 S VC 1 sol. Phase A (Y/N) Y

  1. 22 S VC isot. Phase B (Y/h) N
  1. 23 S VC isol. Vent (Y/N) N
  1. 24 S Conponent Cooling Punts #21 0 Exceptions PCV-1191, 1192 QPEN
  1. 22 0 PCV-1190 CLOSED
  1. 23 S* High Head SIS Flow #21 (GPM) 0 Aux conponent tooling Pumps #21 0
  1. 22 (CPM) 0
  1. 22 S
  1. 23 (CPM) o Aux Feed Water Pumps #21 0
  1. 24 (CPM) 0
  1. 22 0/S Low Head SIS Flow #21 (GPM) 0
  1. 23 S
  1. 22 (CPM) O Containment Spray Pumps #21 S
  1. 23 (GPM) 0
  1. 22 S
  1. 24 (CPM) 0 Recirculation Punos #21 S Accuwulator Level #21 (%) 67
  1. 22 S
  1. 22 (%) 66 Hydrogen Recombiner #21 5
  1. 23 (%) 67
  1. 22 S
  1. 24 (%) 68 L egerad 0 = Operating O/S = Out of Service used to denote defective equipment S = Standby
  • =

Change on status f rom previots tog VI - 19

O

  • SCENARIO NO. 1993 PLANT STATUS LOG PARAMETER TIME PARAMETER TIME 10:55 10:55 Offsite Power Avaltable 1380V O/S Service Water Pteps #21 0 13.8KV S (Circle Essential Hdr) #22 0 6900 Volt BUS NO. 1 5
  1. 23 S BUS NO. 2 S
  1. 24 5 BUS No. 3 S
  1. 25 S BUS Wo. 4 S
  1. 26 5 BUS NO. 5 $ Circ Water Pumps #21 S BUS NO. 6 S
  1. 22 S 480 Vo1t BUS 2A 0 #23 $

BUS 3A 0 #24 S BUS 5A 0 #25 5 BUS 6A O/S #26 S Emergency D/Gs #21 0 Condensate Pumps #21 S

  1. 22 0 #22 S
  1. U 0 #3 S Cas Turbines GT-1 0 Cocp. Cool Heat Exch #21 0 GT-2 0 #22 S GT-3 0 RHR Heat Exchanger #21 0 SIS Punps #21 O/S #22 0
  1. 22 0/S Fan Cooler Units #21 0
  1. 23 S
  1. 22 0 RHR Purps #21 0 #23 0
  1. 22 S
  1. 24 0 Charging Purps #21 0 #25 S
  1. 22 S
  1. 23 S*

Rx Coolant Putps #21 S VC isot. Phase A (Y/N) Y

  1. 22 S VC isot. Phase B (Y/N) N
  1. 23 5 VC ! sol. Vent (Y/N) N
  1. 24 S Component Coot ing Purps #21 0 Exceptions PCV-1190, 1191, 1192 OPEN
  1. 22 0
  1. 23 $ High Head SIS Flow #21 (GPM) 0 Aux Conponent Cooling Ptrps #21 0 #22 (GPM) 0
  1. 22 S
  1. 23 (GPM) o Attx f eed Water Purps #21 0 #24 (GPM) 0
  1. 22 0/5 Low Head SIS Flow #21 (GPM) 0
  1. 23 S
  1. 22 (GPM) O Containment Spray Purps #21 S
  1. 23 (GPM) 0
  1. 22 S
  1. 24 (GPM) 0 Recirculation Punps #21 S Accumulator Level #21 (%) 67
  1. 22 S
  1. 22 (%) 66 Nydrogen Recombiner #21 S
  1. 23 (%) 67
  1. 22 S
  1. 24 (%) 68 Legend 0 = Operating O/S = Out of Service used to denote defective equipnent S = Standby
  • Change on status from previous tog VI - 20

o e SCENARIO NO. 1993 PLANT STATUS [OQ PARAMETER TIME PARAMETER TIME 11:00 11:00 Offsite Power Avsflable 138KV O/S Service Water Punps #21 0 13.BKV S (Circle Essential Hdr) #22 0 6900 Volt BUS NO. 1 S

  1. 23 S BUS NO. 2 5
  1. 24 S BUS NO. 3 5
  1. 25 S BUS No. 4 S
  1. 26 S BUS No. 5 S Circ Water Planps #21 S BUS NO. 6 S
  1. 22 S 480 volt BUS 2A 0 #23 S SUS 3A 0 #24 S BUS SA 0 #25 S BUS 6A O/S #26 S Emergency D/cs #21 0 Condensate Pm ps #21 0
  1. 22 0 #22 0
  1. 23 0 #23 0 Cas Turbines GT-1 0 Coup. Cool Heat Exch #21 0 CT-2 0 #22 S GT-3 0 RHR Heat Exchanger #21 0 S!S Purps #21 0/S #22 0
  1. 22 0/S Fan Cooler Units #21 0
  1. 23 $
  1. 22 0 RHR Pm ps #21 0 #23 0
  1. 22 S
  1. 24 0 Charging Pm ps #21 0 #25 S
  1. 22 S
  1. 23 5 Rx Cootent Pm ps #21 S VC isol. Phase A (Y/N) T
  1. 22 S VC ! sol. Phase B (Y/N) N
  1. 23 S VC 1 sol. Vent (Y/N) N
  1. 24 S Component Cooling Pm ps #21 0 Exceptions PCV-1190, 1191, 1192 OPEN
  1. 22 0
  1. 23 $ High Head S!S Flow #21 (CPM) 0 Aux Cment Cooling Pmps #21 0 0
  1. 22 (CPM)
  1. 22 S
  1. 23 (CPM) 0 Aux Feed Water Pm ps #21 0
  1. 24 (CPN) 0
  1. 22 0/S Los Head Sls flow #21 (GPM) O
  1. 23 S
  1. 22 (GPM) O Contalment Spray Punps #21 S
  1. 23 (CPM) 0
  1. 22 S
  1. 24 (GPM) O Recirculation Punps #21 S Accumulator Level #21 (%) 67
  1. 22 S
  1. 22 (%) 66 Hydrogen Recombiner #21 S
  1. 23 (%) 67
  1. 22 S
  1. 24 (%) 68 Legerd 0 e Operating O/S = Out of Service used to denote defective equipment S = Standby
  • = Change on status from previous log vi - 21

e e SCENARIO No. 1993 PLANT STATUS 10G

[AFAMETER TIME PARAMETER TIME 11:15 11:15 Offsite Power Availatte 138KV O/S Service Water Pumps #21 0 13.BKV S (Circle Essential Hdr) #22 0 6900 Volt BUS No. 1 S '

  1. 23 S BUS NO. 2 S
  1. 24 S BUS NO. 3 5
  1. 25 S BUS Wo. 4 5
  1. 26 S BUS NO. 5 S Cire Water Puups #21 S BUS Wo. 6 S
  1. 22 S 480 Volt BUS 2A 0 #23 s BUS 3A 0 #24 S BUS SA 0 #25 S BUS 6A O/S #26 S fmergency D/Gs #21 0 Condensate Pumps #21 S
  1. 22 0 #22 S
  1. 23 0 #23 =

Gas Turbines GT-1 0 Comp. Cool Heat Exch #21 0 GT-2 0 #22 S GT-3 0 RHR Heat Exchanger #21 0 SIS Pters #21 0/S #22 0

  1. 22 O/S Fan Cooler Units #21 0
  1. 23 S
  1. 22 0 RHR Punps #21 0 #23 0
  1. 22 5 #24 0 Charging Porrps #21 0 #25 S
  1. 22 S
  1. 23 S Rx Coolant Pucps #21 S VC iso!. Phase A (Y/N) Y
  1. 22 S VC isol. Phase B (Y/N) N
  1. 23 S VC 150l. Vent (Y/N) W
  1. 24 S Component Cooling Purps #21 0 Exceptions PCV-1190, 1191, 1192 OPEN
  1. 22 0
  1. 23 S High Head SIS Flow
  1. 21 (GPM) 0 ux Corponent Cooling Pumps #2) 0 #22 (GPM) 0
  1. 22 5
  1. 23 (GPM) 0 Aux Feed Water Pumps #21 0
  1. 24 (GPM) 0
  1. 22 0/S Low Head SIS Flow #21 (CPH) 0
  1. 23 S
  1. 22 (GPM) O Containment Spray Pumps #21 S
  1. 23 (GPM) 0
  1. 22 S
  1. 24 (GPM) 0 Recirculation Pumps #21 S Accumulator Level #21 (%) 67
  1. 22 5
  1. 22 (%) 66 Hydrogen Recombiner #21 S
  1. 23 (1) 67
  1. 22 S
  1. 24 (%) 68 Legend 0 = Operating O/S = Out of Service used to denote defective equipment S = Standby
  • = Change on status from previous log VI - 22 \

l D 9 SpfNARIO NO. 1993 ftANT STATUS toq PARAMETER TIME PARAMETER TIME 11:30 11:30 Of fsite Power Available 138KV O/S Service Water Fumps #21 0 13.8KV S (Circle Essential Hdr) #22 0 6900 Volt BUS No. 1 S

  1. 23 S BUS No. 2 S
  1. 24 S BUS WO. 3 S
  1. 25 S BUS WO. 4 S
  1. 26 S BUS NO. 5 S Cire Water Pumps #21 S BUS No. 6 S
  1. 22 S 480 volt BUS 2A 0 #23 5 BUS 3A 0 #24 S BUS 5A 0 #25 S BUS 6A O/S #26 5 Emergency D/Gs #21 0 Condensate Pumps #21 S
  1. 22 0 #22 S
  1. 23 0 #23 S Gas Turbines GT-1 0 Corp. Cool Heat Exch #21 0 GT-2 0 #22 S CT-3 0 RHR Heat Exchanger #21 0 SIS Pumps #21 0/S #22 0
  1. 22 0/S Fan Cooler Units #21 0
  1. 23 S
  1. 22 0 RHR Ptsnps #21 0 #23 0
  1. 22 S
  1. ?4 0 Charging Ptrps #21 0 #25 S
  1. 22 S
  1. 23 S Rx Coolant Pumps #21 S VC isol. Phase A (Y/N) Y
  1. 22 S VC ! sol. Phase B (Y/N) N
  1. 23 S VC ! sol, Vent (Y/N) N
  1. 24 S Canponent Cooling Pumps #21 0 Exceptions PCV-1190, 1191, 1192 CPEN
  1. 22 0
  1. 23 S High Head SIS Flow #21 (CPM) 0 Aux Corponent Cooling Ptstps #21 0
  1. 22 (GPM) 0
  1. 22 S
  1. 23 (GPM) o Aux Feed Water Ptros #21 0
  1. 24 (GPM) 0
  1. 22 0/S Low Head SIS Flow #21 (GPM) 0
  1. 23 5
  1. 22 (GPM) O Contairrnent Spray Ptros #21 S
  1. 23 (GPM) 0
  1. 22 S
  1. 24 (GPM) 0 Recirculation Ptsps #21 S Acetsnulator Level #21 (%) 67
  1. 22 S
  1. 22 (%) 66 Hydrogen Recor.t2{rwr #21 S
  1. 23 (%) 67
  1. 22 S
  1. 24 (%) 68 Legerd 0 = Operating O/S = Out of Service used to denote defective equipment S = S t ardby
  • = Change on status fr.a previous log I

VI - 11 l

e o SCENARIO No. 1993 PLANT STATUS M PARAMETER TIME PARAMETER TIME 11:45 11:45 Of fsite Power Available 138KV O/S Service Water Ptsps '

  1. 21 0 13.8KV S (Circle Essential Hdr) #22 0 6900 Volt BUS NO. 1 S
  1. 23 S BUS No. 2 S
  1. 24 S BUS Wo. 3 S
  1. 25 S BUS NO, 4 5
  1. 26 S BUS NO. 5 S Circ Water Ptsps #21 S BUS No. 6 S
  1. 22 S 480 Volt BUS 2A 0 #23 S BUS 3A 0 #24 5 BUS SA 0 #25 S BUS 6A O/S #26 S Emergency D/Gs #21 0 Condensate Pumps #21 S
  1. 22 0 #22 S
  1. 23 0 #23 S Gas Turbines GT 1 0 Comp. Cool Heat Exch #21 0 GT-2 0 #22 S GT-3 0 RHR Heat Exchanger #21 0 SIS Pw pa #21 0/S #22 0
  1. 22 0/S Fan Cooler Units #21 0
  1. 23 5 #22 0 RHR Ptsps #21 0 #23 0
  1. 22 S
  1. 24 0 Charging Pwps #21 0 #25 S
  1. 22 S
  1. 23 S Rx Coolant Ptsps #21 $ VC isol. Phase A (Y/N) Y
  1. 22 S VC 1 sol. Phase B (Y/N) N
  1. 23 S vc Isol. Vent (Y/N) N
  1. 24 S Cocponent Cooling Ptops #21 0 Exceptions PCV-1190, 1191, 1192 OPEN
  1. 22 0
  1. 23 S High t:end SIS Flow #21 (GPM) 0 Aux Component Cooling Ptros #21 0
  1. 22 (GPM) 0
  1. 22 S
  1. 23 (CPM) o Aux Feed Water Pw ps #21 0 #24 (GPM) 0 j
  1. 22 0/S Low Head SIS Flow
  1. 21 (GPH) 0 '
  1. 23 3
  1. 22 (CPM) 0 Contairvnent Sprey Ptrps #21 5 )
  1. 23 (CPM) 0 l
  1. 22 S 0
  1. 24 (GPM) j Recirculation Ptsps #21 S Acewulator Level #21 (%) 67 I
  1. 22 S
  1. 22 (%) 66 Hydrogen Recwbiner #21 S
  1. 23 (%) 67
  1. 22 S
  1. 24 (%) 68 Legend 0 = Operating O/S = Out of service used to denote def ective equiptent S = Standby
  • = Change on status from previous log l

I VI - 24 4 1

l

- l

e e SCENARIO kO. 1993 PL ANT STATUS MLQ PARANE7ER TIME PARAMETER TIME 12:00 12:00 Offsite Power Available 138KV O/S Service Water Pu ms #21 0 13.8U S (circle Essential Hdr) #22 0 6900 Volt BUS Wo. 1 S

  1. 23 S BUS NO. 2 5
  1. 24 5 BUS NO. 3 E
  1. 25 S BUS NO. 4 S
  1. 26 5 BUS Wo. 5 S Circ Water Punps #21 S BUS NO. 6 S
  1. 22 3 480 volt BUS 2A 0
  1. 23 S BUS 3A 0 #24 S BUS SA 0
  1. 25 S BUS 6A O/S
  1. 26 S Emergency D/cs #21 0 Condensate Pums #21 $
  1. 22 0
  1. 22 S
  1. 23 C
  1. 23 S Gas Turbines GT-1 0 Conp. Coot Heat Exch #21 0 GT-2 0
  1. 22 S GT-3 0 RHR Heat Exchanger #21 0 515 Peps #21 0/S #22 0
  1. 22 0/S Fan Cooler Units #21 0
  1. 23 S
  1. 22 0 RHN Pums #21 0
  1. 23 0
  1. 22 5 I #24 0 Charging Pums #21 0
  1. 25 S
  1. 22 5
  1. 23 5 Rx Coolant Pums #21 S VC isol Phase A (Y/N) Y
  1. 22 S VC isol. Phase B (Y/N) N ,

, #23 S VC ! sol. Vent l (Y/N) N j

! #24 S Conponent Cooling Pums #21 0 Exceptions PCV-1190, 1191, 1192 OPEN

  1. 22 0
  1. 23 $ High Head SIS Flow #21 (GPM) 0 Aux Conponent Cooling Purs #21 0 '
  1. 22 (GPM) 0
  1. 22 3
  1. 23 (CPM) 0 Aux Feed Water Puys #21 0
  1. 24 (GPM) 0
  1. 22 O/S Low Head SIS Flow #21 (GPM) 0
  1. 23 S
  1. 22 (GPM) O Contalrrent Spray Pums #21 S
  1. 23 (GPM) 0
  1. 22 S
  1. 24 (CPM) 0 Recirculation Pumps #21 S Accuolator Level #21 (%) 67
  1. 22 S
  1. 22 (%) 66 Hydrogen Reconbiner #21 S
  1. 23 (%) 67
  1. 22 S
  1. 24 (%) 68 Legend 0 = Operating O/S = Out of Service used to denote defective equiprent S = Standby
  • = -

Change on status from previous log VI 25

e

  • SCENARIO NO. 1993 PL ANT STATUS LOG FARAMETER TIME PARAMETER TIME 12:15 12:15 Offsite Power Available 138KV O/S service Water Purps #21 0 13.8KV S (Circle Essential Hdr) #22 0 6900 Volt BUS No. 1 S
  1. 23 S BUS NO. 2 S
  1. 24 5 BUS NO. 3 S
  1. 25 S BUS NO. 4 5
  1. 26 S BUS NO. 5 S Cire Water Purnps #21 S BUS NO. 6 S
  1. 22 S 480 Volt BUS 2A 0 #23 $

BUS 3A 0 #24 5 BUS SA 0 #25 S BUS 6A O/S #26 S Emergency D/Gs #21 0 Condensate Pumps #21 S

  1. 22 0 #22 S
  1. 23 0 #23 S Gas Turbines GT-1 0 Comp. Cool Heat Exch #21 0 GT-2 0 #22 S GT-3 0 RHR Heat Exchanger f21 0 SIS Ptny s #21 0/S #22 0
  1. 22 O/S Fan Cooler Units #21 0
  1. 23 $
  1. 22 0 RHR Purps #21 0 #23 0
  1. 22 S
  1. 24 0 Charging Purps #21 0 #25 S
  1. 22 S
  1. 23 S Rx Coolant Pumps #21 S VC iscl. Phase A (Y/N) Y
  1. 22 S VC isol. Phase B (Y/N) N 823 S VC isol. Vent (T/N) N
  1. 24 S Component Cooling Pumps #21 0 Exceptions PCV-1190, 1191, 1192 OPEN
  1. 22 0
  1. 23 S High Head SIS Flow #21 (GPM) 0 1u4 Conponent Cooling Ptmps #21 0
  1. 22 (GPM) 0
  1. 22 S
  1. 23 (CPM) 0 Aux Feed Water Purps #21 0
  1. 24 (GPM) 0
  1. 22 0/S Low Head SIS Flow #21 (GPM) 0
  1. 23 S
  1. 22 (GPM) O Containment Spray Pumps #21 S
  1. 23 (GPM) 0
  1. 22 S
  1. 24 (GPM) 0 Recirculation Purps #21 S Accumulator Level #21 (%) 67
  1. 22 S
  1. 22 (%) 66 Hydrogen Recombiner #21 S
  1. 23 (%) 67
  1. 22 S
  1. 24 (%) 68 Legend 0 = Operating O/S = Out of Service used to denote defective equipnent S = Standby

= = Change on status from previous log VI 26 i

e e StiNARIO NO. 1993 PLANT STATUS LCC PARAMETER TIME PARAMETla TIME 12:30 12:30 Offsite Power Available 138KV O/ t Service Water Pumps #21 0 13.8KV S (Circle Essential hdr) #22 0 6900 Volt BUS NO. 1 S

  1. 23 5 BUS NO. 2 S
  1. 24 S Ads No. 3 S
  1. 25 S BUS NO. 4 S
  1. 26 S BUS No. 5 S Cire Water Pumrr. #21 S BUS No. 6 S
  1. 22 S 480 Volt BUS 2A 0 #23 S SUS 3A 0 #24 S BUS SA 0 #25 S BUS 6A O/S #26 S Emergency D/Gs #21 0 Condensate Pumps #21 S
  1. 22 0 #22 S
  1. 23 0 #23 5 Cas Turbines GT-1 0 Comp. Cool Heat Exe5 #21 0 GT-2 0 #22 S GT 3 0 RHR Heat Exchanger #21 0 SIS Purps #21 0/S #22 0
  1. 22 0/S Fan Cooler Units #21 0
  1. 23 S
  1. 22 0 RhR Porps #21 0 #23 0
  1. 22 S
  1. 24 0 Charging Pugn #21 0 #25 5
  1. 22 S
  1. 23 S Rx Coolant Punps #21 S VC ! sol. Phase A (Y/N) Y
  1. 22 S VC isoi. Phase B (Y/N) W
  1. 23 S VC Isol Vent (Y/N) W
  1. 24 S Component Cooling Purps #21 0 Exceptions PCV 1190, 1191, 1192 OPEN
  1. 22 0
  1. 23 $ High Head SIS Flow #21 (GPM) 0 Aux Corponent Cooling Pumps #21 0
  1. 22 (CPM) 0
  1. 22 5
  1. 23 (CPM) o Aux Feed Water Purps #21 0
  1. 24 (GPM) 0
  1. 22 0/5 Low Head SIS Flow #21 (CPM) 0
  1. 23 S
  1. 22 (CPM) O Containment Spray Pumps #21 5
  1. 23 (GPM) 0
  1. 22 5
  1. 24 (CPM) O Rectreulation Ptros #21 S Accumulator Level #21 (%) 67
  1. 22 5
  1. 22 (%) 66 Hydrogen Recanbiner #21 S
  1. 23 (%) 67
  1. 22 S
  1. 24 (%) 68 Legend 0 = Operating O/S = Out of Service used to denote defective equipment S = Standby
  • Change on status from previous log VI 27

e 8 SCENARIO NO. 1993 PLANT STATUS LOG PATAMETER 11ME PARAMETER TIME 12;M 12:45 Of fsite Power Available 13BKV O/S service Water Pwps #21 0 13.8KV 5 6900 volt (circle Essential Hdr) #22 0 BUS NO. 1 S

  1. 23 $

BUS ko. 2 S

  1. 24 5 BUS Wo. 3 S
  1. 25 S BUS NO. 4 S
  1. 26 S BUS No. 5 S Cire Water Pwps #21 S BUS NO. 6 S
  1. 22 S 480 Volt BUS 2A 0
  1. 23 S BUS 3A 0
  1. 24 S BUS SA 0
  1. 25 S BUS 6A O/S #26 S Emergency D/Gs #21 0 Condensate Punps #21 S
  1. 22 0
  1. 22 S
  1. 23 0
  1. 23 S Gas Turbines GT-1 0 Comp. Cool Heat Exch #21 0 GT-2 0
  1. 22 S GT-3 0 RHR Heat Exchanger SIS Pwps #21 0
  1. 21 0/S #22 0
  1. 22 O/S Fan Cooler Units #21 0
  1. 23 5 RHR Pwps #22 0
  1. 21 0
  1. 23 0
  1. 22 S
  1. 24 0 Charging PLrps #21 0
  1. 25 S
  1. 22 S
  1. 23 S Rx Coolant Pw ps #21 S VC lsol. Phase A (Y/N) Y
  1. 22 S VC ! sol. Phase B (Y/N) W
  1. 23 5 VC isol. Vent (Y/N) W
  1. 24 5 Cocponent Cooling Pw ps #21 0 Exceptions PCV 1190, 1191, 1192 OPEN
  1. 22 0
  1. 23 $ High Head $!S Flow #21 (GPM) o Aux Copponent Cooling Pwps #21 0
  1. 22 (GPM) 0
  1. 22 S Aux Feed Water Punps #23 (CPM) 0
  1. 21 0
  1. 24 (GPM) 0
  1. 22 0/S Low Head SIS Flow #21 (CPM) 0
  1. 23 5
  1. 22 (CPM) o containment spray Pwps #21 5
  1. 23 (CPM) 0
  1. 22 5
  1. 24 (CPM) 0 Recirculation Pw ps #21 S Acew ulator Level #21 (%) 67 j
  1. 22 5 Hydrogen Recontiner #22 (%) 66
  1. 21 $
  1. 23 (%) 67
  1. 22 S I
  1. 24 (%) 68 ~!

l Legend 0 = Operating O/S = Out of Service used to denote defective equipment S = Standby

  • =

Change on status from previous log 5

i VI - 28

e #.

SCENARfD Wo. 1993

[ QNT STAlps LOG PARAMETER TIME PARAMETER TlWE 13:00 13:00 Of fsite Power Available 138KV O/S Service Unter Pttps #21 0 13.8KV 3 (Circle Essentist Hdr) #22 0 6000 volt BUS No. 1 S

  1. 23 S BUS NO. 2 S
  1. 24 S BUS NO. 3 S
  1. 25 S BUS NO. 4 S
  1. 26 S BUS NO. 5 S Cire Water Punps #21 S BUS No. 6 S
  1. 22 S 480 Volt BUS 2A 0 #23 S BUS 3A 0 #24 S BUS SA 0 #25 S BUS 6A 0/5 #26 S Emergency D/Cs #?1 0 Condensate Pums #21 S
  1. 22 0 #22 S
  1. 23 0 #23 S Gas Turbines GT-1 0 Corro. Cool Heat Exch #21 0 GT-2 0 #22 S GT 3 0 RHR Heat Exchanger #21 0 SIS Pums #21 O/S #22 0
  1. 22 0/S Fan Cooler Units #21 0
  1. 23 S
  1. 22 0 RHR Punps *21 0 #23 0
  1. 22 5
  1. 24 0 Charging Pums #21 0 #25 5
  1. 22 S
  1. 23 S Rx Coolant Pums #21 S VC Isol. Phase A (Y/N) Y
  1. 22 S VC 1so1. Phase B (T/N) W
  1. 23 5 VC ! sol. Vent (Y/N) N
  1. 24 S Cortponent Cooling Fums #21 0 Exceptions PCV-1190, 1191, 1192 OPEN
  1. 22 0
  1. 23 S High Head SIS Flow #21 (GPM) 0 Aux Copponent Cooling Ptsps #21 0
  1. 22 (GPM) 0
  1. 22 S
  1. 23 (GPM) 0 Aux Feed Water Ptbut #21 0
  1. 24 (GPM) 0
  1. 22 O/S Low Head SIS Flow #21 (GPM) 0
  1. 23 $
  1. 22 (GPM) O Containment Spray Wrys #21 S
  1. 23 (GPM) 0
  1. 22 5
  1. 24 (GPM) 0 Recirculation Pu ps #21 S Accunulator Levet #21 (%) 67
  1. 22 S
  1. 22 (%) 66 Hydrogen Reconbiner #21 S
  1. 23 (%) 67
  1. 22 S
  1. 24 (%) 68 Legend 0 = Operating O/S = out of service used to denote defective equipnent S = Stan Wy
  • Change on status from previous log VI - 29

e e E NARIO Wo. 1993 S

PLAWT STATUS jog PARAMETER TIME PARANETER TIME 13:11 13:11 Of f alte Power Available 138KV O/S Service Water Pw ps #21 0 13.8KV 5 (Circle Essential Edr) #22 0 67PO Volt BUS No. 1 S

  1. 23 S BUS No. 2 5
  1. 24 S JUS NO. 3 5
  1. 25 S BUS No. 4 S
  1. 26 S BUS NO. 5 S Cire Water Pw ps #21 S BUS No. 6 S
  1. 22 S 480 Volt BUS 2A 0 #23 S BUS 3A 0 #24 S BUS 5A 0 #25 S BUS 6A O/S #26 S Emergency D/Gs #21 0 Condensate Pw ps #21 S
  1. 22 0 #22 S
  1. 23 0 #23 S Cas Turbines GT-1 0 Comp. Cool Heat Exch #21 0 GT-Z 0 #22 S GT-3 0 RHR Heat Exchanger #21 0 SIS Pw ps #21 0/S #22 0
  1. 22 0/S Tan Cooler Units #21 0
  1. 23 $ #22 0 RHR Pw ps #21 0 #23 0
  1. 22 S
  1. 24 o Charging Pw ps #21 0 #25 S
  1. ?2 5
  1. 23 5 Rx Coolant Pw pr #21 S VC Isol. Phase A (Y/N) Y
  1. 22 S VC ! sol. Phase B (Y/N) N
  1. 23 5 VC Isol. Vent (Y/N) N
  1. 24 S Corponent Cooling Pwps #21 0 Exceptions PCV 1190, 1191, 1192 OPEN
  1. 22 0
  1. 23 $ High Head $15 Flow 0
  1. 21 (GPM)

Aux Component Cooling Pw ps #21 0 #22 (GPM) 0

  1. 22 S
  1. 23 (GPM) 0 Aux Feed Water Pwps #21 0 #24 (CPM) 0
  1. 22 O/S Low Head SIS Flow #21 (GPM) 0
  1. 23 S
  1. 22 (GPM) o contaltunent Spray Pwps #21 S
  1. 23 (GPM) 0
  1. 22 S 0
  1. 24 (GPM)

Recirculation Pwps #21 S Accmulator Level #21 (%) 67

  1. 22 S
  1. 22 (%) 66 Hydrogen Reconciner #21 S
  1. 23 (%) 67
  1. 22 S
  1. 24 (%) 68 Legend 0 = Operating O/S = Out of Service used to denote defective equipnent S = Standby
  • = Change on status from previous log VI - 30 j l

l l

l a #

jLCENA#!O NO. 1993 Pp NT STATUS tgi PARAMETER

_f!ME PfARAMETER flME 13:30 13:30 Offsite Power Available 138KV O/S Service Water Pw ps #21 0 13.8KV S (circle Essential Hdr) #22 0 6900 Volt BUS NO. 1 S

  1. 23 0*

BUS NO. 2 S

  1. 24 S BUS No. 3 S
  1. 25 S BUS NO. 4 S
  1. 26 S BUS NO. 5 S Cire Water Pwps #21 S BUS NO. 6 S
  1. 22 S 480 Volt BUS 2A 0 #23 S BUS 3A 0 #24 S BUS 5A 0 #25 S BUS 6A 0* #26 S Emergency D/Gs #21 0 condensate Pwps #21 S
  1. 22 0 #22 S
  1. 23 0 #23 S Gas Turbines GT-1 0 Ccurp. Cool Heat Each #21 0 GT-2 0 #22 5 GT-3 0 RHR Heat Exchanger #21 0 SIS Pwps #21 0/S #22 0
  1. 22 0/S Fan Cooler Units #21 0
  1. 23 0* #22 0 RHR Pwps #21 0 #23 0
  1. 22 o' #24 0 Charging Punps #21 0 #25 0*
  1. 22 S
  1. 23 S Rx Coolant Pw ps #21 $ VC isol. Phase A (Y/N) Y
  1. 22 S VC ! sol. Phase B (Y/N) N
  1. 23 S VC isol. Vent (Y/N) N
  1. 24 S Cnmponent Cooling Pwps #21 0 Exceptions PCV-1190, 1191, 1192 OPEN
  1. 22 0
  1. 23 0* High Head S!S Flow #21 (GPM) 0 Aux Corrponent Cooling Pwps #21 0 #22 (GPM) 120
  1. 22 0 0
  1. 23 (GPM)

Aux Feed Water Pwns #21 0 #24 (GPM) 140

  1. 22 0/5 Low Head SIS Flow #21 (GPM) 0
  1. 23 S* #22 (GPM) O Contaltnent Spray Pwps #21 $ 0
  1. 23 (GPM)
  1. 22 S #24 (GPH) 0 Recirculation Pwps #21 S Accmulator Level #21 (%) 67
  1. 22 S
  1. 22 (%) 66 Hydrogen Recontiner #21 S
  1. 23 (%) 67
  1. 22 S
  1. 24 (%) 68 Legend 0 = operating O/S = Out of Service used to denote defective equipment S = Stardby
  • = Change on status from prewfous log VI - 31

a a SCENARIO NO. 1993 PLANT STATUS tog FARAMETER TIME _ PARAMETER TIMF 13:45 13:45 Of felte Power Available 13BKV O/S Service Water Puys #21 0 13.8KV S 6900 Volt (Circle Essential Hdr) #22 0 BUS No. 1 S

  1. 23 0 BUS NO. 2 S
  1. 24 S BUS NO. 3 5
  1. 25 S BUS Wo. 4 S
  1. 26 $

BUS NO. 5 S Circ Water Pums #21 $

BUS NO. 6 S

  1. 22 480 Volt BUS 2A 0 S
  1. 23 S BUS 3A 0
  1. 24 S BUS 5A 0
  1. 25 S BUS 6A 0
  1. 26 S Energency D/Gs #21 0 Condensate Pumps #21 5
  1. 22 0
  1. 22 S
  1. 23 0
  1. 23 S Gas Turbines GT-1 0 Comp. Cool Heat Exch #21 0 GT-2 0
  1. 22 S GT-3 0 RHR Heat Exchanger #21 0 SIS Ptaps #21 S/O
  1. 22 0
  1. 22 0 fan Cooler Units #21 0
  1. 23 0
  1. 22 0 RHR Puts #21 0
  1. 23 0
  1. 22 0
  1. 24 0 Charging Pups #21 0
  1. 25 0
  1. 22 5
  1. 23 S Rx Coolant Pums #21 S VC isol. Phase A (Y/N) Y
  1. 22 5 VC lsol. Phase B (Y/N) N
  1. 23 $ VC 1501. Vent (Y/N) N
  1. 24 $

Conponent Cooling Puvs #21 0 Exceptions PCV-1190, 1191, 1192 OPEN

  1. 22 0
  1. 23 0 High Head SIS Flow #21 (GPM) o Aux Corponent Cooling Purps #21 0
  1. 22 (GPM) 60
  1. 22 0
  1. 23 (GPM) 80 Aux Feed Water Purps #21 0
  1. 24 (GPM) 0
  1. 22 O/S Low Head SIS Flow #21 (GPM) 0
  1. 23 S
  1. 22 (GPM) o Containment Spray Ptsps #21 S
  1. 23 (GPM) 0
  1. 22 S
  1. 24 (GPM) 0 Recirculation Pups #21 S Accunulator Level #21 (%) 67
  1. 22 S Mydrogen Reconibiner #22 (%) 66
  1. 21 S
  1. 23 (%) 67
  1. 22 5
  1. 24 (%) 68 Legend 0 = Operating O/S = Out of Service used to denote defective equipment S = S t antby ,
  • = Change on status from previous log l VI - 32

I o -t I

SCENARfD No. 1993  !

PLANT STATUS LOG PARAMETER UML PARAMETEt

_ UE ,

13:55 13;j} l Of f site Powr Available 138KV O/S I Service Water Ptros #21 0 13.8KV S (circle Essential Hdr) #22 0 6900 Volt BUS No. 1 S l

  1. 23 0 OUS Wo. 2 S
  1. 24 $ '

Bt.l$ No. 3 S

  1. 25 S  ;

BUS NO. 4 5

  1. 26 S BUS Wo. 5 S Cire uater Purps #21 S BUS No. 6 S )
  1. 22 S 480 Volt BUS 2A 0
  1. 23 S BUS 3A 0
  1. 24 S BUS 5A 0 '
  1. 25 $-

BUS 6A 0

  1. 26 S Emergency D/Gs #21 0 Condensate Purps #21 S
  1. 22 0
  1. 22 S
  1. 23 0 #23 S Cas Turbines GT-1 0 Comp. Cool Heat Exch #21 0 GT-2 0
  1. 22 S GT-3 0 RHR Heat Exchanger #21 0 SIS Ptsps #21 0
  1. 22 0
  1. 22 0/S Fan Cooler Units '
  1. 21 0
  1. 23 0
  1. 22 0 RHR Purps #21 0
  1. 23 0
  1. 22 0
  1. 24 0 Charging Ptsps #21 0 #25 0
  1. 22 S
  1. 23 S Rx Coolant Purps #21 $ VC lsol. Phase A (Y/N) Y
  1. 22 S VC lsol. Phase B (Y/N) N
  1. 23 S VC isol. Vent (Y/N) W
  1. 24 $

Corrponent Cooling Ptrps #21 0 Exceptions PCV 1191, 1192 OPEN

  1. 22 0 PCV 1190 CLOSED
  1. 23 0 High Head SIS flow #21 (GPM) 0 Aux Component Cooling Purps #21 0
  1. 22 (CPN) 60
  1. 22 0
  1. 23 (GPM) 0 Aux Feed Water Pteps #21 0
  1. 24 (CPM) 80
  1. 22 0/S Low Head Sl$ Flow #21 (GPM) 0
  1. 23 S
  1. 22 (GPM) O Containment Spray Purps #21 $
  1. 23 (CPM) 0

.#22 5

  1. 24 (CPM) 0 Rectreulation Pttps & S Acetanulator Level #21 (%) 67 S

Hydrogen Recorrbiner #22 (%) 66 sc1 S

  1. 23 (%) 67 -
  1. 22 S
  1. 24 (%) 68 Legend 0 = Operating O/S = Out of Service used to denote defective equipment S = $tandby
  • = Change on status frorn previous tog VI - 33

e e f(1NAR10 No. 1992 P QNT STA?US LOG ERAMETER _ TIME PARAMETER TIME 14:00 14:00**

Offaite Power Available 138KV 0* Service Water Pwps #21 0 13.BKV 5 (circle Essential Hdr) #22 S*

6900 Volt BUS No. 1 0*

  1. 23 0 i BUS No. 2 0* #24 S BUS NO. 3 0* #25 0*

BUS NO. 4 0* #26 0*

BUS NO. 5 0* Circ Water Pwps #21 5 BUS NO. 6 0*

  1. 22 5 480 Volt BUS 2A 0
  1. 23 S BUS 3A 0
  1. 24 S BUS SA 0
  1. 25 5 BUS 6A 0
  1. 26 i Emergency D/Gs #21 S Conderisate Pttps #21 s

$22 S

  1. 22 S
  1. 23 S
  1. 23 S Cas Turbines GT-1 S Conp. Cool Heat Exch #21 0 GT-2 S
  1. 22 S GT-3 S RHR Heat Exchanger #21 0 SIS Pwps #21 S
  1. 22 S*
  1. 22 S Fan Cooler Units #21 0
  1. 23 S
  1. 22 0 RHR Pw ps #21 0 #23 0
  1. 22 S* #24 0 Charging Pw ps #21 5
  1. 25 0 s22 S
  1. 23 S Rx Coolant Pwps #21 S VC isol. Phase A (Y/N) N
  1. 22 S VC ! sol. Phase B (Y/N) N
  1. 23 S VC isol. Vent (Y/N) N
  1. 24 S Component Cooling Pwps #21 S* Exceptions PCV-1190, 1191, 1192 CLOSED
  1. 22 0
  1. 23 0 High Head SIS Flow #21 (CPM)- 0 Aux Ccmponent Cooling Pmps #21 S*
  1. 22 (GPM) 0
  1. 22 S*
  1. 23 (GPM) 0 Aux Feed Water Pwps #21 S*
  1. 24 (CPM) 0
  1. 22 S* Low Head SIS Flow #21 (GPM) 500
  1. 23 S*
  1. 22 (CPM) 460 Contairvnent Spray Pwps #21 S
  1. 23 (CPM) 480
  1. 22 S
  1. 24 (GPM) 510 Recirculation Pm ps #21 S Acew olater Level #21 (%) 67
  1. 22 5
  1. 22 (%) 66 Hydrogen Recombiner #21 S
  1. 23 (%) 67
  1. 22 S
  1. 24 (%) 68 Legend 0 = operating Q/S = Out of StrYict U$td to denott dtitCilyt equipment S = Standby
  • = Change on status from previous log VI - 34 i

MO NO. 1993 RADIOLOGICAL /METEROLOGXCRL LOG PARAMETER TIME 07:30 07:45 08:00 08:15 08:30 ~

08:45 09:00~

R-5987 MCC 98' mR/hr 1 1 1 1 1 1 1 i R-1 CCR mR/hr O.1 0.1 0.1 0.1 0.1 0.1 0.1 R-2 VC 80' mR/hr 1 1 1 1 1 1 1 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 5 5 R-8 Drum Sta. mR/hr 0.5 0.5 0.5 0.5 0.5 0.5 0.5 R-41 VC Part.uci/cc 4.0E-09 4.0E-09 4.0E-09 4.0E-09 4.0E-09 4.0E-09 4.0E-09 R-42 VC Gas uCi/cc 1.0E-03 1.0E-03 1.0E-03 1.0E-03 1.0E-03 1.0E-03 1.0E-03 R-43 Vent Part uCi/CC 4.0E-12 4.0E-12 4.0E-12 4.0E-12 4.0E-12 4.0E-12 4.0E-12 R-44 Vent Gas uCi/cc 1.0E-08 1.0E-08 1.0E-08 1.0E-08 1.0E-08 1.0E-08 1.0E-08 R-44 Vent I131 uCi/cc 1.0E-11 1.0E-11 1.0E-11 1.0E-11 1.0E-11 1.0E-11 1.0E-11 R-45 Air Ejector uCi/cc 1.0E-07 1.0E-07 1.0E-07 1.0E-07 1.0E-07 1.0E-07 1.0E-07 R-46 F.C. Water uCi/cc 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 R-47 Comp. Cool uCi/cc 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 R-48 Liquid Waste uCi/cc 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 R-49 S/G B.D. uCi/cc 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 R-53 F.C. Water uCi/cc 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 R-25 VC Hi-Rge R/hr <1 <1 <1 <1 <1 <1 <1 R-26 VC Hi-Rge R/hr <1 <1 <1 <1 <1 <1 <1 R-27 Vent Monitor uCi/cc 0 0 0 0 0 0 0 R-27 Vent Flow Rate CFM 4.5E+04 4.5E+04 4.5E+04 4.5E+04 4.5E+04 4.5E+04 4.5E+04 R-27 Vent Dis Rate uCi/sec 0 0 0 0 0 0 0 R-28 Main Stm Rad Mon CPM 10 10 10 10 10 10 10 R-29 Main Stm Rad Mon CPM 10 10 10 10 10 10 10 R-30 Main Stm Rad Mon CPM 10 10 10 10 10 10 10 R-31 Main Stm Rad Mon CPM 10 10 10 10 10 10 10 Vent Flow Rate CFM - - - - - - -

Main Steam Exh Lbs/Hr - - - - -

Air Ejector CFM (measured value) - - - - - - -

METEOROLOGICAL Wind Speed (meters /sec) 6.8 6.8 6.8 6.8 6.8 6.8 6.8 Wind Direction ~(degreees) 270 270 270 270 270 270 270 Pasquill Stability Catacorv D D D D

  • D D D I

i VII - 1 6-30-93 l

NO. 1,s3 RADIOLOGICAL / METEROLOGICAL LOG PARAMETER TIME 09:15 09:30 09:40 09:45 10:00 10:15 10:30 '

R-5987 MCC 98' mR/hr 1 1 1 1 1 2 3 R-1 CCR mR/hr 0.1 0.1 0.1 1 1 1 1 R-2 VC 80' mR/hr 1 1 5 7 10 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 0.5 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 12 15 18 22 25 R-8 Drum Sta. mR/hr 0.5 0.5 0.5 0.5 0.5 0.5 0.5 R-41 VC Part uCi/cc 4.0E-09 4.0E-09 4.0E-09 4.0E-09 4.0E-09 4.0E-09 4.0E-09 R-42 VC Gas uCi/cc 1.0E-03 1.0E-03 1.0E-03 1.0E-03 1.0E-03 1.0E-03 1.0E-03 R-43 Vent Part uCi/CC 4.0E-12 4.0E-12 4.0E-12 4.0E-12 4.OE-12 4.0E-12 4.0E-12 R-44 Vent Gas uCi/cc 1.0E-08 1.0E-08 1.0E-08 1.0E-08 1.0E-08 1.0E-08 1.0E-08 R-44 Vent I131 uCi/cc 1.0E-11 1.0E-11 1.0E-11 1.0E-11 1.0E-11 1.0E-11 1.0E-11 R-45 Air Ejector uCi/cc 1.0E-07 1.0E-07 1.0E-07 1.0E-07 1.0E-07 1.0E-07 R-46 F.C. Water uCi/cc 1.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 R-47 Comp. Cool uCi/cc 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 R-48 Liquid Waste uCi/cc 2.0E-07 2.OE-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 R-49 S/G B.D. uCi/cc 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 R-53 F.C. Water uCi/cc 2.0E-07 2.0E-07 2.0E.07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 R-25 VC Hi-Rge R/hr <1 <1 <1 <1 <1 <1 R-26 VC Hi-Rge R/hr <1

<1 <1 <1 <1 <1 <1 <1 R-27 Vent Monitor uCi/cc 0 0 0 0 0 0 0 R-27 Vent Flow Rate CFM 4.5E+04 4.5E*04 4.5E+04 4.5E+04 4.5E+04 4.5E+04 4.5E+04 R-27 Vent Dis Rate uCi/sec 0 0 0 0 0 0 0 R-28 Main Stm Rad Mon CPM 10 10 10 10 10 10 10 R-29 Main Stm Rad Mon CPM 10 10 10 10 10 10 10 R-30 Main Stm Rad Mon CPM 10 10 10 10 10 10 10 R-31 Main Stm Rad Mon CPM 10 10 10 10 10 10 10 Vent Flow Rate CFM - - - - - - -

Main Steam Exh Lbs/Hr - - - - - - -

Air Ejector CFM (measured value) - - - - - - -

METEOROLOGICAL Wind Speed (meters /sec) 6.8 6.8 6.8 6.8 6.8 6.8 6.0 Wind Direction (degreees) 270 270 270 270 270 270 270 Pasquill Stability Catacorv D D D D D D D VII - 2 6-30-93

SCENRRIO NO. 1993 RADYOLOGI C /GETEROLOGICAL LOG PARAMETER TIME 10:45 10:55 11:00 11:15 11:30 11:45 12:00 R-5987 MCC 98' mR/hr 1 1 1 1 1 R-1 CCR mR/hr 1 1 1 1 1 1 1 R-2 VC 80' mR/hr 17 1 1 21 25 25 27 27 R-4 Chrg. Pump mR/hr 1 1 30 1 1 1 1 R-5 F.S.B. mR/hr 0.2 0.2 0.2 0.2 0.2 0.2 1

R-6 Sample Rm. mR/hr 2 2 2 2 0.2

' 2 2 2 R-7 VC Seal Table mR/hr 28 32 36 38 40 42 45 R-8 Drum Sta._mR/hr 0.5 0.5 0.5 0.5 0.5 0.5 R-41 VC Part uCi/cc 4.0E-09 0.5 4.0E-09 4.0E-09 4.0E-09 4.0E-09 4.0E-09 R-42 VC Gas uCi/cc 1.0E-03 1.0E-03 4.0E-09 1.0E-03 1.0E-03 1.0E-03 1.0E-03 1.0E-03 R-43 Vent Part uCi/CC 4.0E-12 4.0E-12 4.0E-12 4.0E-12 4.0E-12 4.0E-12 R-44 Vent Gas uCi/cc 1.0E-08 1.0E-08 4.0E-12 1.0E-08 1.0E-08 1.0E-08 1.0E-08 1.0E-08 R-44 Vent I131 uCi/cc 1.0E-11 1.0E-11 1.0E-11 1.0E-11 1.0E-11 1.0E-11 1.0E-11 R-45 Air Ejector uCi/cc 1.0E-07 1.0E-07 1.0E-07 1.0E-07 R-46 F.C. Water uCi/cc 1.0E-07 1.0E-07 1.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 R-47 Comp. Cool uCi/cc 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 R-48 Liquid Waste uCi/cc 2.0E-07 2.OE-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 R-49 S/G B.D. uCi/cc 2.0E-07 2.0E-07 2.OE-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 R-53 F.C. Water uCi/cc 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 R-25 VC Hi-Rge R/hr <1 <1 <1 <1 R-26 VC Hi-Rge R/hr <1 <1 <1

<1 <1 <1 <1 <1 '

<1 <1 R-27 Vent Monitor uCi/cc 0 0 0 0 0 0 0 R-27 Vent Flow Rate CFM 4.5E+04 4.5E+04 4.5E+04 4.5E+04 4.5E+04 4.5E+04 4.5E+04 R-27 Vent Dis Rate uCi/sec 0 0 0 0 0 0 0 R-28 Main Stm Rad Mon CPM 10 10 10 10 10 R-29 Main Stm Rad Men CPM 10 10 10 10 10 10 10 R-30 Main Stm Rad Mon CPM 10 10 10 10 10 10 10 R-31 Main Stm Rad Mon CPM 10 10 10 10 10 10 10 10 Vent Flow Rate CFM - - - -

10 Main Steam Exh Lbs/Hr Air Ejector CFM -

(measured value) - - - - - - -

METEOROLOGICAL Wind Speed (meters /sec) 6.8 6.8 6.8 6.8 6.8 Wind Direction (degreees) 6.8 6.9 270 270 270 270 270 Pasquill 270 270 Stability Catacorv D D D D D D D VII - 3 6-30-93 I

SCENARIO NO. 13s3 RADIOLOGICAL / METEROLOGICAL LOG PARAMETER TIME 12:15 12:25 12:30 12:45 13:00 13:15 13:30 -

R-5987 MCC 98' mR/hr. 1 1 1 1 1 1 1 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 35 10000 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 3 2 2 2 2 2 R-7 VC Seal Table mR/hr 48 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-41 VC Part uCi/cc 1.OE-05 OFFSCALE OFFSCALE OFFSCALE OFFSCALE OFFSCALE OFFSCALE R-42 VC Gas uCi/cc 1.0E-05 OFFSCALE OFFSCALE FFSCALE OFFSCALE OFFSCALE OFFSCALE

R-43 Vent Part uCi/CC 4.0E-12 4.0E-12 4.0E+12 4.0E+12 4.0E+12 4.0E+12 4.0E+12 R-44 Vent Gas uCi/cc 1.0E-08 1.0E-08 1.0E-08 1.0E-08 1.0E-08 1.0E-08 1.0E-08 R-44 Vent I131 uCi/cc 1.0E-11 1.0E-11 1.0E-11 1.0E-11 1.0E-08 1.0E-08 1.0E-08 R-45 Air Ejector uCi/cc 1.0E-07 1.0E-07 1.0E-07 1.0E-07 1.0E-07 1.0E-07 1.0E-07 R-46 F.C. Water uCi/cc 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 R-47 Comp. Cool uCi/cc 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 R-48 Liquid Waste uCi/cc 2.0E-07 2.0E-07 2.0E-07 2.OE-07 2.0E-07 2.0E-07 2.0E-07 R-49 S/G B.D. uCi/cc 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 R-53 F.C. Water uCi/cc 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 R-25 VC Hi-Rge R/hr <1 1.5X101 6.0X101 2.6X102 4.0X103 4.5X103 4.5X103 R-26 VC Hi-Rge R/hr <1 1.9X101 7.3X101 2.9X102 4.2X103 5.2X103 5.2X103 R-27 Vent Monitor uCi/cc <1 1.8X10-2 7.1X10-2 3X10-1 4.7 5.7 6.2 R-27 Vent Flow Rate CFM 4.5E+04 4.5X104 4.5X104 4.X104 4.5E+04 4.5E+04 4.5E+04 R-27 Vent Dis Rate uCi/sec 0 3.8X105 1.5X106 6.5X106 1.0X108 1.3X108 1.3X108 R-28 Main Stm Rad Mon CPM 10 10 10 10 10 10 10 R-29 Main Stm Rad Mon CPM 10 10 10 10 10 10 10 R-30 Main Stm Rad Mon CPM 10 10 10 10 10 10 10 R-31 Main Stm Rad Mon CPM 10 10 10 10 10 10 10 Vent Flow Rate CFM - - - - - - -

Main Steam Exh Lbs/Hr - - - - - - -

Air Ejector CFM (measured value) - - - - - - -

METEOROLOGICAL Wind Speed (meters /sec) 6.8 6.8 6.8 6.8 6.8 6.8 6.8 Wind Direction (degreces) 270 270 270 270 270 270 270 Pasquill Stability Catacory D D D D D D D VII - 4 6-30-93 L____ _ ._ . _ _ _ _ _ _ - _ _ _ _ .__ ___.___._m_ _ _ _ - _ - _ . . . - - _ - _ _ _ _ _ . . - - __ __ _ ____" _ __ __

RADIOLOGICAL / METEROLOGICAL LOG ENARIO NO. 1993 PARAMETER TIME 13:45 13:55 14:00**

R-5987 MCC 98' mR/hr 1 1 1 R-1_CCR mR/hr 0.1 0.1 0.1 R-2 VC BO' mR/hr OFFSCALE OFFSCALE 10000 R-4 Chrg. Pump mR/hr 1 1 1 R-5 F.S.B. mR/hr 0.2 0.2 0.2 R-6 Sample Rm. mR/hr 2 2 2 R-7 VC Seal Table mR/hr OFFSCALE OFFSCALE 10000 R-8 Drum Sta. mR/hr 0.5 0.5 0.5 R-41 VC Part uCi/cc 4.0E-09 4.0E-09 4.0E-09 R-42 VC Gas uCi/cc 1.0E-03 1.0E-03 1.0E-03 R-43 Vent Part uCi/CC 4.0E-12 4.0E-12 4.0E+12 R-44 Vent Gas uCi/cc 1.0E-08 1.0E-08 1.0E-08 R-44 Vent I131 uCi/cc 1.0E-11 1.0E-11 1.0E-11 R-45 Air Ejector uCi/cc 1.0E-07 1.0E-07 1.0E-07 R-46 F.C. Water uCi/cc 2.0E-07 2.0E-07 2.0E-07 R-47 Comp. Cool uCi/cc 2.0E-07 2.0E-07 2.0E-07 R-48 Liquid Waste uCi/cc 2.0E-07 2.0E-07 2.0E-07 R-49 S/G B.D. uCi/cc 2.0E-07 2.0E-07 2.0E-07 R-53 F.C. Water uCi/cc 2.0E-07 2.0E-07 2.0E-07 R-25 VC Hi-Rge R/hr 4.5X103 4.5X103 4.5X102 R-26 VC Hi-Rge R/hr 5.2X103 5.2X103 5.2X102 R-27 Vent Monitor uC1/cc 6.2 0 0 R-27 Vent Flow Rate CFM 4.5E+04 4.5X104 4.5X10 4 R-27 Vent Dis Rate uCi/sec 1.3X108 o o R-28 Main Stm Rad Mon CPM 10 -10 10 R-29 Main Stm. Rad Mon CPM ~

10 10 10 R-30 Main.Stm Rad Mon CPM 10 10 10 R-31 Main Stm Rad Mon CPM 10 10 10 Vent Flow Rate CFM - - -

Main Steam Exh Lbs/Hr - - -

Air Ejector CFM (measured value) - - -

METEOROLOGICAL Wind Speed (meters /sec) 6.8 6.8 6.8 Wind Direction (degreees) 270 270 270 Pasquill Stability Catacorv D D D

    • Two days later VII - 5 6-30-93 e

_ _ _ , _ , , , _ ,__.--L-- --:'-"------ " " ' " ' ~ ~ ~ ~ ~ ~ ^ ~ ~ ^

e a i

CONBOLIDATED EDISON COMPANY OF NEW YORK INDIAN POIMT UNIT NO. 2 DRILL SCENARIO NO. 1993 VIII RADIOLOGICA_L INFORMATION TAB A TABLE 1: Primary Coolant Activity Boron Concentrations TAB B TABLE 2: Containment Activity TAB C TABLE 3: Release Path Activity TAB D TABLE 4: Plant / Sample Radiation Levels TAB E TABLE 5: Facility Radiation Levels TAB F TABLE 6: Reuter-Stokes Readings TAB G TABLE 7: Plume Monitoring Data & Figures TAB H TABLE 8: Offsite TLD Readings TAB I TABLE 9: Post Accident Enviromental Samples TAB J TABLE 10: Post Accident Offsite Contami-tion Levels TAB K TABLE 11: Medical Emergency Data

  • - r ,

VIII

, Reactor Coolant 08:00 09:30 10:30 11:00 11:30 12:00 12:30 13:00 13:30 14:00 Nuculide uCi/cc uCi/cc uCi/cc uCi/cc uCi/cc uCi/cc uCi/cc uCi/cc I-131 2.0E-03 1.2E-02 2.lE-02 3.0E-01 uCi/cc uCi/cc 1.0E+00 3.9EWO 1.0E+01 2.5E+02 I-132 3.2E-02 8.5E-02 9.0E-02 2.0E-01 3.2E+02 12E+02 8.0E-01 2.4 E+00 7.2E+00 1.4E+02 I-133 1.9E-02 6.2E-02 8.0E-02 8.9E-01 2.0E+00 1.6E+02 1.6E+02 I-134 6.7E-02 7.0E+00 1.4E+01 3.0E+02 3.5E+02 1.5 E-01 3.5E-02 LOE-02 3.5E+02 I-135 3.4E-04 3.0E-01 <LLD < LLD <LLD < LLD <LLD 1.l E-01 1.2E-01 4.0E-01 9.0E-01 3.5E+00 Xe-133 8.3E-03 9.1 E+00 1.6E+02 1.6E402 1.6E+02 5.8E-02 1.2E-01 5.0E-01 1.7E+00 7.2E+00 Xe-133m < LLD 3.2E+01 2.8E+03 2.7E+03 2 'E+03

< LLD < LLD <LLD 3.0E-01 9.4E-01 Xe-135 2.5E-02 4.0E+00 1.9E402 1.8E+02 1.8E+02 6.7E-02 9.6E-02 2.5E-01 6.0E-01 1.8E+00 Xe-135m 5.2E-03 1.9E+01 4.9E+02 5.0E+02 5.0E+02 2.2E-02 5.0E-02 7.0E-02 1.0E-01 6.0E-01 Xe-138 2.7E-02 3.l E-02 4.9E+00 1.SE+02 1.7E+02 1.7E+02 2.4E-02 < LLD < LLD < LLD <LLD Kr-85 < LLD < LLD < LLD < LLD <LLD <LLD

< LLD < LLD < LLD < LLD < LLD Kr-85m 2.0E-03 8.0E-03 1.lE-02 3.7 E-02

< LLD < LLD 2.0E-01 1.lE+00 3.1 E+00 <LLD Kr-87 3.2E-03 1.0E-02 8.0E-03 <LLD < LLD

<LLD <LLD Kr-88 < LLD <LLD <LLD < LLD < L.L D 3.3E-03 1.2E-02 9.3E-03 2.0E-02 1.2E-01 Rb-88 8.0E-01 5. l E+00 <LLD < LLD < LLD 1.0E-02 7.0E-02 5.2E-02 1.5E-02 1.0E-01 Rb-89 7.5 E-01 4.6E+ 00 < LLD <LLD <LLD 8.0E-03 5.0E-02 < LLD < LLD < LLD < LLD Te-132 < LLD < LLD < LLD < LLD < LLD

< LLD < LLD <LLD < LLD < LLD Cs-134 < LLD 9.0E-01 1.5E+01 7.5E+01 7.5 E+01 2.lE-03 5.0E-03 1.4E-02 5.lE-02 2.lE-01 Cs-137 < LLD 4.5E+00 4.5E+02 1.2E+03 1.2E+03 2.2E-03 6.0E-03 1.6E-02 5.6E-02 2.4 E-01 Ce-144 < LLD 4.7E+00 5. l E+02 1.5E+03

< LLD < LLD < LLD < LLD < LLD 1.5E+03 La-140 < LLD 1.2E+00 1.0E+02 5.3E+02 5.3E+02

< LLD < LLD < LLD < LLD < LLD < LLD Ba-140 < LLD < LLD 1.2E+01 8.7E+01 8.7E+01

< LLD < LLD < LLD < LLD 1.0E+00 La-142 < LLD < LLD 7.5E+01 5.0E+02 5.0E+02

< LLD < LLD < LLD < LLD < LLD Ba-142 < LLD < LLD 1.0E+01 7.2E+01 7.2E+01

< LLD < LLD < LLD < LLD 7.0E-01 6.2E+01 4.7E+02 4.7E+02 Total 2.lE-01 7.5E-01 7.3E-01 2.6E+00 8.2E+00 3.0E+01 1.3E+02 5.7E+03 8.9E+03 8.9E+03 EBAR 1.7 1.4 1.4 1.32 1.3 1.23 1.21 1.21 1.21 1.21

% Tech S[iec 0.60 1.75 1.70 5.79 17.83 62.30 254.10 11583.73 18004.80 18004.80 VIII-A-1

g.  ;

V C COOLING '

08:00 09:30 10:30 11:00 11:30 12:00 12:30 13:00 13:30 14:00 Nuculide uCi/cc uCi/cc uCi/cc uCi/cc I-131 uCi/cc uCi/cc uCi/cc uCi/cc 2.0E-09 2.lE-09 5.0E-07 1.0E-08 8.0E-08 uCi/cc uCi/cc I-132 < LLD 1.lE-07 5.0E-06 1.0E-03 1.8E-03

< LLD < LLD 2.0E-03 I-133 1.0E-09 1.3E-09 4.0E-07 2.0E-04 2.IE-04 1.9E-04 4.5 E-07 1.5E-08 1.0E-07 2.0E-07 I-134 < LLD < LLD 8.0E-06 2.1 E-03 2.2E-03 2.5E-03

< LLD I-135 <LLD < LLD < LLD 3.0E-07 2.0E-06 1.5E-06 9.0E-07 TOTA'L 3.0E-09 3.4E-09 9.5E-07 2.5E-08 1.8E-07 3. l E-07 1.4E-05 3.3E-03 4.2E-03 4.7E-03 Xe-133 6.0E-04 6.0E-04 1.4E-02 2.3 E-02 8.8E-02 9.4 E-02 5.2E+00 2.8 E+01 Xe-133m < LLD < LLD < LLD < LLD 3.2E+01 3.2E+01

< LLD 9.4E-04 9.0E-02 1.9E+00 Xe-135 3.0E-04 3.0E-04 2.2E-04 8.0E-04 2.8 E+00 2.8E400 9.8E-03 1.5E-02 3.0E400 2.5E+01 Xe-135m 1.0E-04 1.0E-04 1.8E-04 6.5 E-04 2.3 E+01 2.8E+01 6.5E-03 9.6E-03 2.0E+00 1.9E+01 Xe-138 < LLD < LLD < LLD < LLD < LLD 2.6E+01 2.6E+01 Kr-85 < LLD < LLD < LLD < LLD < LLD

< LLD <LLD < LLD < LLD < LLD < LLD Kr-85m < LLD < LLD < LLD < LLD < LLD < LLD 2.3E-05 4.3E-05 1.2E-03 9.2E-03 7.5E-01 Kr-87 < LLD < LLD 1.l E+01 1.3E+01 1.3E+01

<LLD < LLD < LLD < LLD <LLD < LLD Kr-88 <LLD < LLD 9.3E-05 2.3E-04 < LLD < LLD 7.3 E-03 1.0E-02 9.0E-01 9.0E+00 1.l E+01 1.lE+01 TOTAL 1.0E-03 1.0E-03 L5E-02 2.5E-02 1. l E-01 1.4E-01 1.2E+01 9.3E+01 1.IE+02 1.lE402 Rb-88 1.0E-10 1.0E-10 6.8E-08 2.0E-07 3.8E-07 4.0E-07 8.2E-06 < LLD Rb-89 < LLD < LLD < LLD < LLD < LLD < LLD

< LLD < LLD < LLD < LLD < LLD Te-132 < LLD < LLD < LLD < LLD < LLD < LLD

< LLD Cs-134 4.4E-10 < LLD 2.0E+00 2.2E+00 2.2E+00 4.4E-10 6.0E-10 1.3E-09 1.5E-09 2.1E-09 Cs-137 5.6E-10 4.2E-07 4.5E+01 5.1E+01 5.1E+01 5.6E-10 7.0E-10 1.5E-09 1.7E-09 2.4E-09 Ce-144 < LLD < LLD 4.8E-07 4.7E+01 5.4E+01 5.4E+01

< LLD < LLD < LLD < LLD < LLD La-140 < LLD < LLD < LLD 5.0E+00 5.3E+00 5.3E400

< LLD < LLD < LLD < LLD 8.0E+00 Ba-140 < LLD < LLD < LLD < LLD 9.2E+00 9.2E+00

< LLD < LLD < LLD 5.6E+00 La-142 < LLD < LLD < LLD < LLD 6.lE+00 6.lE+00

< LLD < LLD < LLD 7.0E+00 Ba-142 < LLD < LLD < LLD < LLD 8.0E+00 8.0E+00

< LLD < LLD < LLD 4.8E+00 5.2E+00 5.2E+00 Total 1.1E-09 1.1E-09 6.9E-08 2.0E-07 3.8E-07 4.0E-07 9. lE-06 1.2E+02 1.4E+02 1.4E402 VIII-B-1 ,

5

' 4' . g

PLANT VENT -

08:00 09:30 10:30 11:00 11:30 12:00 12:30 13:00 13:30 14:00 Nuculide uCi/cc uCi/cc aCi/cc uCi/cc uCi/cc uCi/cc uCi/cc uCi/cc I-131 < LLD < LLD (LLD 3.0E-11 3.lE-10 uCi/cc uCi/cc I-132 < LLD 2.2E-09 7.0E-08 1.0E-05 2.0E-05 L.LD

< LLD < LLD I-133 < LLD < LLD 3.5E-09 2.0E-06 2.0E-06 LLD

< LLD 3.8E-11 3.7E-10 2 5E-09 1.6E-08 I-134 < LLD < LLD < LLD 2.0E-05 2.0E-05 LLD I-135 < LLD < LLD < LLD LLD 1.5E-09 2.0E-08 2.0E-08 LLD TOTAL 0 0 0 6.8E-I l 6.8E-10 4.7E-09 9.l E-08 3.2E-05 4.2E-05 0.0E+00 Xe-133 < LLD < LLD < LLD 8.2E-04 1.1 E-03 Xe-133m 1.3E-03 2.5E-01 1.8E+00 3.0E+00

< LLD < LLD < LLD < LLD < LLD LLD 1.0E-06 4.0E-04 5.0E-01 Xe-135 < LLD < LLD < LLD 1.5E-06 3.0E-06 6.0E-01 LLD Xe-135m 4.0E-06 2.3 E-01 2. l E+00 3.2E+00

< LLD < LLD < LLD 1.2E-06 2.0E-06 LLD Xe-138 3.3E-06 2.0E-01 1.9E+00 2.4E +00 LLD

< LLD < LLD < LLD < LLD < LLD Kr-85 < LLD < LLD < LLD < LLD LLD

< LLD < LLD < LLD < LLD <LLD <LLD Kr-85m < LLD < LLD < LLD < LLD < LLD LLD

<LLD 9.0E-07 1.2E-05 1.3E-05 8.9E-02 5.8 E-01 Kr-87 < LLD < LLD < LLD < LLD 9.0E-01 LLD

< LLD < LLD < LLD < LLD < LLD Kr-88 < LLD < LLD < LLD 1.0E-06 1.3 E-05 LLD 1.0E-05 9.0E-02 7.0E-01 1.0E+00 LLD TOTAL 0.0E+00 0.0E+00 0.0E+00 8.2E-04 1.lE-03 1.3E-03 8.6E-01 7.6E+00 1.lE+01 0.0E+00 VIII-C-1 '

e .

SCENARIO NO.1993 PLANT / SAMPLE RADIATION LEVELS TABLE OF CONTENTS SUBJECT PAGE FAN BUILDING DATA Vill-D-2 FAN BUILDING PHYSICAL LAYOUT 3 PLANT VENT ALLEY DATA 4 PLANT VENT ALLEY PHYSICAL LAYOUT 5 PAB 80' DATA 6

PAB 80' PHYSICAL LAYOUT 7 PAB 98' DATA 8

PAB 98' PHYSICAL LAYOUT 9 SIS PUMPS DATA 10 RHR PUMPS PHYSICAL LAYOUT 11 SIS PUMPS PHYSICAL LAYOUT 12 SECURITY FENCE DATA 13 SECURITY FENCE / ASSEMBLY AREA LAYOUT 14 ASSEMBLY AREA FIELD DATA 15 BUILDING 43'& 18' DATA 16 ABFP BUILDING 43' PHYSICAL LAYOUT 17 ABFP BUILDING 18' PHYSICAL LAYOUT 18 P' PING PENETRATION AREA FIELD DATA 19 PIPING PENETRATION AREA LAYOUT 20 Vill-D1

SCENARIO NO.1993 LOCATION TIME RADIATION LEVELS FAN BLDG. - Point 1 < 12:29 AS READ mR/hr 12:29 to 12:59 0 mR/hr 13:00 to 13:55 900 mR/hr

> 14:00 50 mR/hr Point 2 < 12:29 AS READ mR/hr 12:29 to 12:59 100 mR/hr 13:00 to 13:55 1200 mR/hr

> 14:00 50 mR/hr Point 3 < 12:29 AS READ mR/hr 12:29 to 12:59 70 mR/hr 13:00 to 13:55 825 mR/hr

> 14:00 15 mR/hr Point 4 < 12:29 AS READ mR/hr 12:29 to 12:59 40 mR/hr 13:00 to 13:55 200 mR/hr

> 14:00 10 mR/hr Point 5 < 12:29 AS READ mR/hr 12:29 to 12:59 40 mR/hr 13:00 to 13:55 200 mR/hr

> 14:00 5 mR/hr NOTE 1: All open window (OW) mR/hr readings will be the same as the closed

, window (CW) mR/hr readings listed above. 1 NOTE 2:

All loose contamination and airborne concentrations are actual levels detected.

NOTE 3: Data to be supplied to Radiation Protection Technician at the locations after the survey is performed. t l

Vill-D2 1 ,

e i SCENARIO NO.1993 FAN HOUSE ELEVATION 80',72', 88' 90' ZONE 59A PIPINC PEttTH ATlON t) NIT !

CONT AINMENT y CHARCOAL FILTER 5 TO CONT.

ELEv. P'.FCE D' JCT g e- pef t.

I ol

@c '

M 5TW M PIPINC ZWE 59A **>0 #' PE NC 7R A TION TAN nom) 20tES 90A & 9 f A p CRATING [(y.dy -

OPEN 10 ELEv.97

/

~

J ELEv.87 _;;;3 ;i

~~

@ UP(llllllllllllll g ELEV.

CHARCOAL ELEv.ae& %r ADJACEtJT 2ONE ABOVE- t@ E BELOW - ZONE l A I 01 20eE STA wOsE sT'4tiONs rAN NOUSE TdRE ARE 3 ON TK 80' EL Or ELEV. 87

&#DA ANTS -++H o H.P. 79 & HOSE box 9 II II 'II DN (BETWEEN TmE #4&O II I' 'I BLDC. Ato THE PAD) lII iiti1 'd(LU-40 ELEV.Id & 7?

Fil tilli M --

TO Cot 4TAINMENT ROLL.UP DOOR f

ILU-41 SECLHili .-

N5x . .

j

. . _ . _ . . p,o ' 4 Vlli-D3 -Ellv my ' '

, i SCENARIO NO.1993 LOCATION TIME RADIATION LEVELS PLANT VENT - Point 1 < 12:29 AS READ mR/hr -

ALLEY 12:30 to 12:59 150 mR/hr 13:00 to 13:55 15000 BUILDING mR/hr

> 14:00 400 mR/hr Point 2 < 12:29 AS READ mR/hr 12:30 to 12:59 40 mR/hr 13:00 to 13:55 1300 mR/hr

> 14:00 50 mR/hr i

NOTE 1: All open window (OW) mR/hr readings will be the same as the closed window (CW) mR/hr readings listed above.

l NOTE 2:  !

All loose contamination and airborne concentrations are actual levels l detected.

NOTE 3: Data to be supplied to Radiation Protection Technician at the locations after the survey is performed.

Vill-04 i

s SCENARIO NO.1993 f ALLEY BY PLANT VENT i

r

~

1. PIPE's N UCLEc6 R E ACTOR
  • rl h r q

~

. g6 4 PIPES .

,s., .

\

4sgs- s.

s l i '( dfp NNT OPE d/

b

.L A DPL A -- D FAN bulDiNo

( FOP, T H 1'a AF, E A *>E E -

DARWIN (s No. 7 A,7b) e

" W e e e i

' ALLEY bY PLANT VEN"

l Vill-D5 q

. i SCENARIO NO.1993 LOCATION TIME RADIATION LEVELS 80' PAB -

- Point 1 < 12:29 AS READ mR/hr 12:30 to 12:59 15 mR/hr 13:00 to 13:55 30 mR/hr

> 14:00 2 mR/hr Point 2 < 12:29 AS READ mR/hr 12:30 to 12:59 8 mR/hr 13:00 to 13:55 15 mR/hr

> 14:00 2 mR/hr Point 3 < 12:29 AS READ mR/hr 12:30 to 12:59 8 mR/hr 13:00 to 13:55 10 mR/hr

> 14:00 2 mR/hr Point 4 < 12:29 AS READ mR/hr 12:30 to 12:59 6 mR/hr 12:30 to 13:55 15 mR/hr

> 14:00 2 mR/hr NOTE 1: All open window (OW) mR/hr readings will be the same as the closed window (CW) mR/hr readings listed above.

NOTE 2:

All loose contamination and airborne concentrations are actual levels detected.

NOTE 3: Data to be supplied to Radiation Protection Technician at the locations after the survey is performed.

Vill-D6

O SCENARIO NO.1993 PRIMARY AUXILIARY BUILDING ELEVATION 80' GN FAN HOUSE &

CONTAINMEt#

, b '

f I I Ptsy i

, - m m m CHA5F CR A Tir<. OVER l CCW PUMP 5 l o gk k CD CCW 09 Ga Og KAT I p il s m . _ .J 1 TArM 22 E5

$"E CH u. CRUM

^ 3 2 s E X CHAPCERS 8 Em EE I

- u e 5A m . ",y*t fE {g 32 g{ l

_ NATROCEN C TMK5 = F ~C CIff' l BORIC *M BORIC ACO

[puup--- i AC O i

y 1 i

E5 EVAPORATOR

] TArx 28 55

_ , t  ! k, l ((  ! 55 BUILDING

  • TER OR c' BARRIER I'CCY r - 1 ._e w_,j;

=

, tan.<

'L TRAr 5FER mEROe ALTERt4 ATE s' , SwlTCH

. $HUTDOW Pti

  1. i DN PH e sePJTFW tM. CO2

' 1 _

A 'a -

e i

G M i

is CLEAN CHANrl AREA

< . . . _ _. n FEt<ED' ACCE55 &

FRISK NG

.1 PRE 55tRIZED AIR RICEf WR5 s*

t CAS WAiTE CAS WASTE E XTE RIOR # ## U

,N IPl.lP2 STRIPPER COMPRESSORS COrOENSATE SHOP ROOM T AtK ROOM N , PA15ACCWAY P*A*B* AttEX I

PRIMARY AUXILIARY BUILDING

, ELEVATION BO' Vill-D7 i i 1'

l l

l SCENARIO NO.1993 LOCATION TIME RADIATION LEVELS 98' PAB -

Point 1 < 12:29 AS READ mR/hr l

12:30 to 12:59 8 mR/hr 13:00 to 13:55 45 mR/hr

> 14:00 8 mR/hr Point 2 < 12:29 AS READ mR/hr 12:30 to 12:59 8 mR/hr 13:00 to 13:55 45 mR/hr

> 14:00 8 mR/hr Point 3 < 12:29 AS READ mR/hr 12:30 to 12:59 7 mR/hr 13:00 to 13:55 40 mR/hr

> 14:00 7 mR/hr Point 4 < 12:30 AS READ mR/hr 12:30 to 12:59 8 mR/hr 13:00 to 13:55 55 mR/hr

> 14:00 7 mR/hr Point 5 < 12:29 AS READ mR/hr 12:30 to 12:59 6 mR/hr 13:00 to 13:55 35 mR/hr

> 14:00 4 mR/hr Point 6 < 12:30 AS READ mR/hr 12:30 to 12:59 6 mR/hr 13:00 to 13:55 35 mR/hr

> 14:00 2 mR/hr NOTE 1: All open window (OW) mR/hr readings will be the same as the closed window (CW) mR/hr readings listed above.

NOTE 2:

All loose contamination and airborne concentrations are actual levels detected.

NOTE 3: Data to be supplied to Radiation Protection Technician at the locations after the survey is performed.

Vill-D8

, . r E v ,

a, gQm 6, .

2 me g:_.E < DCXF~>

ag W bU{Q e 6

Mr*m<>y g $'6 Vs$>c 2 O* p*I M4E R _

C E 1 oT _ A 6

_ ) 7 FIL _ C N R C

_ D GA 8 1l I ,L E M -

IN- E T +-

HtC r

C I 1 .%

L W 1

x c

r S

I 3

(

E r O2 O3 l 6

2 fr C7 C7# A A# A C

C B CW - M A R

I CW 6

RA I 7

P O

B 0T 1 e 6 C N C-M b E S 3'

p T F A r.

R f

TE AC R

j N V

w KAH KA' oA wC H rT A

c t.

n H

CX CE WC CX CE V l l C

m1 A -

B N A 0 A R O T Nqw & 8 6 O r R 7 7 I E EaA t pT C C R T

X Ot C C E

[ P o r. M M 1

x MoG E OCUSR C

y aoC l l v -

e hD oui k yw8e t m do2 ~

n a -

A

! f 4 R E E (C T A T R.

W AtA y

E E LKH A C e

  • r< {<- T T A X r

e A C

E S E 0 ts bu

[(C] {

E T }.

e EEEEug$ g w-xy C E I A C

e E

T A

,W

  • C '

i

& E T

L A R a

< C Do t CtA A , A R T R C E E Co I

Rp _

T T A OA Q C i. BvE ._

2 _

OO

}C E S T5 A F* P R

PM E' J r C vC ,

$pgq )

oT rA OV OEL -

RE

J SCENARIO NO.1993 TABLE 4 PLANT RADIATION LEVELS LOCATION TIME HADIATION LEVELS SIS PUMPS - ROOM ALL TIMES O' mR/hr l

l l

NOTE 1: All open window (OW) mR/hr readings will be the same as the closed l window (CW) mR/hr readings listed above.

NOTE 2:

All loose contamination and airborne concentrations are actual levels l detected.

l NOTE 3: Data to be supplied to Radiation Protection Technician at th9 locations after l survey is performed.

Vill-D10 1

,-W SCENARIO NO.1993 RHR PUMPS PHYSICAL LAYOUT NOT REQUIRED FOR THIS SCENARIO Vill-011

2 e SCENARIO NO.1993 PRIMARY AUXILIARY BUILDING ELEVATION 59' 0

N PIPE CHASE

$1 PUMP 23 I

I b

LLU %)

1 I

I --

sArETY l CC e FH 51 PUMP 22 P4JE C ON g _

AHEA us I

El %c2 51 PUMP 21 i

l aCC l

rtRE 20tf ,

DCLrf AT:Ord g #

> ~

L, CATE8 I

O O O O O

O O

O o ooo l

l 1

PRIMARY AUXILIARY BUILDINC ELEVATION 59' ,

Vill-D12

SCENARIO NO. .A TABLE 4 SECURITY FENCE FIELD DATA -MR/HR LOCATION POINTS TIME A B C D E F G

< 12:25 0 0 0 0 0 0 0 12:25 0 1 4 1 0 0 0 12:30 0 3 18 3 0 0 0 12:45 0 20 78 30 0 0 0 13:00 4 600 1010 750 0 0 0 13:15 4 610 1315 800 0 0 0 13:30 4 610 1315 800 0 0 0 13:45 4 610 1315 800 0 0 0 14:00 0 0 0 0 0 0 0 Vill-D-13

-em =e-

-__- - - _ _ ' - - - - w o

,c ,

SCENARIO NO.1993

" i-- , ,- _

j' s

' e SECURITY FENCE - '

PARK ASSEMBLY AREA LAYOUT ENVIR.

,/ BLDG.

(srcuRITY vtxcr - ff e s ,

ASSEMBLY ABEA LAYOUT l

9

\ o S cio coewo[

N # m ,- \ . . .

==

N7 -

a{ o xN , ,

/, g ,. g

//

Cm. Ng'wr r

FUEL HDL G.

( ,

A n o

8'*x M

M. O. x ~I g T I j RAJ R f FSpk0

/

~

I A \

UNIT / [~

Q ^cr)$' W & F_

l 10 04 // \\ 'N I G \

UNIT /U/1T I s AUX UNIT 3

l. HBINE . / JJRBIN TURBlNE Y , HTR. BAY / S/R. BLDG. RTRSAY

\, DIS.CAN.

f \ __ ...I ,

lSCR MW.l l \ \ J_ _U. 1

, Vill-D14 l

SCENARIO NO.1993 LOCATION TIME RADIATION LEVELS SIMULATOR /VlSITOR < 12:59 AS READ CENTER mR/hr 13:30 to 13:55 7 mR/hr

> 14:00 AS READ mR/hr SECURITY / ADMIN ALL TIMES AS READ BUILDING mR/hr ASSEMBLY AREA A-B ALL TIMES AS READ mR/hr 15 FT TURBINE BLDG M.O. BUILDING < 12:59 AS READ mR/hr CONST OFFICE 13:30 to 13:55 100 COMPLEX mR/hr

< 14:00 2 mR/hr NOTE 1: All open window (OW) mR/hr readings will be the same as the closed window (CW) mR/hr readings listed above.

NOTE 2:

All loose contamination and airborne concentrations are actual levels detected.

NOTE 3: Data to be supplied to Radiation Protection Technician at the locations after the survey is performed.

Vill-D15 I

SCENARIO NO.1993 LOCATION

~

TIME RADIATION LEVELS 43' ABFP BLDG - Point 1 - < 12:29 AS READ mR/hr 12:30 to 12:59 2 mR/hr 13:00 to 13:55 7 mR/hr

< 14:00 3 mR/hr PIPE PENET Point 2 < 12:29 AS READ mR/hr 12:30 to 12:59 10 mR/hr 13:00 to 13:55 100 mR/hr

< 14:00 15 mR/hr 18' ABFP BLDG - Point 1 < 12:29 AS READ mR/hr 12:30 to 12:59 1 mR/hr 13:00 to 13:55 5 mR/hr

< 14:00 1 mR/hr Point 2 < 12:29 AS READ mR/hr 12:30 to 12:59 1 mR/hr 13:00 to 13:55 10 mR/hr

< 14:00 2 mR/hr NOTE 1: All open window (OW) mR/hr readings will be the same as the closed window (CW) mR/hr readings listed above.

NOTE 2:

All loose contamination and airborne concentrations are actual levels detected.

NOTE 3: Data to be supplied to Radiation Protection Technician at the locations after the survey is performed.

Vill-D16

a .

SCENARIO NO.1993 MAIN STEAM VALVE ARE ELEVATIONS 43', 53' ZONES 65A,61A t A ILNLON CRATING AT ELEV. 43*

20if 41A

__( g--. EXTERIOR I

Cy

,4;y y JRBUL PIPE BRIDCE CONCRE TE 9 55'""

IL OC FLOO6 DN =

ELEV.47 __

y m CATWALK = opgN 111 Ft Fv 43'

~

CATw ALK ELEY. 53' bCO2 gy.gs

, ELE Y. 6 9J{tu-2) [LU.20 2C*f 65A I UHf T 2 CONTAINunn TR AN5FOR 4R STEAuk LINES YARO 4

I T ZOPE 74A -

ELECTniCAL  !

\ eut 77t A rsON AREA MAIN STEAM VALVE AREA ELEVATIONS 43',53' ZOBES 65A,6l A Vill-D17 1

I i

s ,

SCENARIO NO.1933 AUXILIARY BOILER FEEDWATER PUMP HOUSE ELEVATION 18' 0

N 20PE 17A mt [r a taTra m Exitason

$It En '~

id

=

(LV-19 L (LU-IF O I 1 b-ArwWw n i 1 dcY

_ baMRIE9

~

ADJACENT 70*E5 ZOPC 23 A00VI. 20t4~ dOA & il A BELOW. CA ADC N

(LU.175 ar=M v C,',"C.) anc. m.

usi ! CCPdf A**(NT 4 W Sta flo*6 ON t&CH ELKY.

-o ..,n g.3sgt;g;., ,

  • L'!w' Tor'ITA eci m%n I

,, I(tu-is q= Jl.

t L/

"~:' =

l Vill-D18

...e, .

'i l

SCENARIO NO.1993 ..

1 l

P!PE PENETRATION 51' .

F yc

,' ~

_y-

<_ t*~

ptt $ KEllEF g O

@ 0 PcJ-1991 f12>'

-es ='

c..

b O I 0 -

9 b

a=,

a5 o M *-*

  • f"' "
l .

<=======

l m

5/C t '.oM ' '

l -1

\~

, .< 1 Vill-D20

SCENARIO NO.1993 TABLE 5 FACILITY RADIATION LEVELS 3

1 METER HElGHT READING 10FT AIR SAMPLE i OCATION TIME OW CW BKGD IODINE PART mR/hr mR/hr CPM CPM CPM Emergency ALL < 1.0 < 1.0 20 20 20 Operation Times Facility (EOF)

Operational All < 1.0 < 1.0 20 20 20 Support Times Center (OSC)

Technical All < 1.0 < 1.0 20 20 20 Support Times Center (TSC) antrol Room All < 1.0 < 1.0 20 20 20 sdR) Times Recovery All < 1.0 < 1.0 20 20 20 Center (RC) Times NOTE: Data to be supplied to Radiation Protection Technician after the survey is completed.

Vill-E

O-SCENARIO NO. J TABLE 6 -

REUTER-STOKES READINGS mR/HR UME 1 2 3 4 5 6 7 8

< 12:30 BKGD BKGD BKGD 12:30 BKGD 4.7 2.0 12:45 BKGD 19.1 8.4 13:00 .01 285.0 78.0 13:15 .03 348.0 97.0 13:30 .03 348.0 97.0 13:45 .03 348.0 <.1 14:00 <.01 10.0 <.1 Vill-F-1 '

M _ _ _ - --

r BCENARIO NO.-1993 '

TADLE 7 ELUME MONIIQRING DATA MID FIGURES P

NOT REQUIRED FOR THIS SCENARIO i

+

VIII - G

1993 SCENARIO CW OW THYROID CHARCOAL MR/hr , MR/hr mrem /hr CPM-TIME < 1225 WD 270 WS m/sec 6.8 1/WS 0.15 PASQUILL D SB Xu/Q 1.4X 10" <1 <1 <1 BKGD 1 mi Xu/O 5.1X10 5 <1 <1 <1 BKGD 2 mi Xu/O 1.9X 10'5 <1 <1 <1 BKGD 3 mi Xu/Q 1.0X10 5 <1 <1 <1 BKGD 4

, 4 mi Xu/O 6.8X10 <1 <1 <1 BKGD

..nl Xu/O 5.1X104 <1 <1 <1 BF.GD 6 mi Xu/O 3.8X10 ' <1 <1 <1 BKGD 4

7 mi Xu/O 3.2X10 <1 <1 <1 BKGD 4

8 mi Xu/O 2.7X10 <1 <1 <1 BKGD 9 mi Xu/O 2.3X104 <1 <1 <1 BKGD 4

10 mi Xu/Q 2.1X10 <1 <1 <1 BKGD N.G.Ci/sec Ci/sec 1/D HRS 3 NB Kl ~ 4.3X105 71Y K2 7X108 /

N

to

  • 1993 SCENARIO CW OW TIIYROID CIIARCOAL Mit/lir MR/hr mrem /hr CPM f TlME 1225 x

WD 270 WS m/sec 6.8 1/WS 0.15 N  %

PASQUILL D

'N _

SB Xu/O 1.4 X 10" 3 4 <1 DKGD 1 mi Xu/O 5.0X10~5 <1 <1 <1 BKGD 2 mi Xu/Q 19X105 <1 <1 <1 BKGD 3 mi Xu/O 1.0X10 5 <1 <1 <1 BKGD 4 4

_ mi Xu/O 6.8X10 <1 <1 <1 BKGD 4

.ii Xu/Q 5.1X10 <1 <1 <1 BKGD 4

6 mi Xu/O 3.8X10 <1 <1 <1 BKGD 4

7 mi Xu/Q 3.2X10 <1 <1 <1 BKGD 4

8 mi Xu/O 2.7X10 <1 <1 <1 BKGD 4

9 mi Xu/O 2.3X10 <1 <1 <1 DKGD 4

10 mi Xu/O 2.1X10 <1 <1 <1 BKGD N.G. Ci/sec 3.8X10'3 m

I Ci/sec 3.8X10-5 S/D llRS 31/4 WB K1 4.3 X 10' _

N_

IIIY K2 7.0X10" g

P

o ,

~ . . . . .

1993 SCENARIO CW OW THYROID CHARCOAL MR/hr MR/hr mrem /hr CPM T1ME 1230 WD 270

WS m/sec 6.8 1/WS 0.15 PASQUILL D 4

N SB Xu/O 1.4X10 14 18 2 6 1 mi Xu/Q 5.0X105 5 7 <1 BKGD 2 mi Xu/O 1.9X10-5 2 3 <1 BKGD  ;

3 mi Xu/O 1.0X10 5 <1 <1 <1 BKGD 4 mi Xu/O 6.8X104 <1 <1 <1 BKGD-

, mi Xu/Q 5,1X10 4 <1 <1 <1 BKGD 6

6 mi Xu/O 3.8X10 <1 <1 <1 BKGD 4

7 mi Xu/O 3.2X10 <1 <1 <1 BKGD 4

8 mi Xu/O 2.7X10 <1 <1 <1 BKGD 4

9 mi Xu/O 2.3X10 <1 <1 <1 BKGD 4

10'mi Xu/O 2.1X10 <1 <1 <1 BKGD N.G. Ci/sec 1.5 p'

I 4

/

Ci/sec 1.5X10 S/D HRS 31/4 WB K1 4.3X105 THY K2  ; 7.0X108 o .

j l

~ v 1993 SCENARIO CW OW THYROID CHARCOAL-MR/hr MR/hr mrem /hr CPM-TIME 1245 x

.WD 270' 'N WS m/sec 6.8 N w 1/WS 0.15 PASQUILL D SB Xu/O 1.4X 10" 60 78 10 30 5

1 mi Xu/Q 5.0X10 21 27 3 9 2 mi Xu/O 1.9X 10 5 8 10 1 3 3 mi Xu/O 1.0X10'5 4 6 <1 BKGD 4

4 mi Xu/O 6.8X10 3 5 <1 BKGD 4

mi Xu/Q 5.1X10 2 3 <1 BKGD 4

6 mi Xu/O 3.8X10 1 2 <1 BKGD 6

7 mi Xu/O 3.2X10 1 2 <1 BKGD 8 mi Xu/O 2.7X.10 <1 <1 <1 BKGD 9 mi Xu/O 2.3X10-6 <1 <1 <1 BKGD 4

' 10 mi Xu/Q 2.1X10 <1 <1 <1 UKGD N.G. Ci/sec 6.5

! Ci/sec 6.5X10"

/" .

3/D IIRS 31/2 _

NB K1 4.3X10' IIIY K2 7.0X10s p f I

o e

  • e

1993 SCENARIO CW OW THYROID CHARCOAL MR/hr MR/hr mrem /hr _ CPM TIME 1300 WD 270' WS m/sec 6.8 x

1/WS 0.15 PASQUILL D S13 Xu/O 1.4 X 10" 780 1010 154 490 1 mi Xu/O 5.0X10-5 280 365 55 175 2 mi Xu/O 1.9X10-5 106 140 21 70 3 mi Xu/O 1.0X10~5 55 70 11 35 4

4 mi Xu/O 6.8X10 38 50 7 23 4

.niXu/O 5.1X10 28 35 6 19 4

6 mi Xu/O 3.8X10 21 27 4 13 4

7 mi Xu/O 3.2X10 18 23 3 9 4

8 mi Xu/O 2.7X10 15 18 3 9 4

9 mi Xu/O 2.3X10 13 16 2 6 4

10 mi Xu/O 2.1X10 12 15 2 6 2

N.G.Ci/sec 1X10

~

I Ci/sec IX10-2 S/D IIRS 33/4 WB K1 3.7X10 5

FHY K2 7X108

1 l

1 1993 SCENARIO I

)

CW OW THYROID CHARCOAL MR/hr MR/hr mrem /hr llME _ CPM 1315 WD 270" WS m/sec 6.8 1/WS 0.15 PASQUILL D SU Xu/O 1.4X10" 1010 1315 196 580 1 mi Xu/O 5.0X104 360 470 70 220 4

2 mi Xu/O 1.9X10 135 175 27 82 4

3 mi Xu/Q 1.0X10 70 90 14 47 4

11Xu/O 6.8X10 50 65 10 30 4

5 mi Xu/Q 5.1X10 35 45 7 23 4

6 mi Xu/O 3.8X10 25 32 5 14 4

7 mi Xu/O 3.2X10 20 26 5 14 4

8 mi Xu/O 2.7X10 19 24 4 13 4

9 mi Xu/O 2.3X10 17 20 3 9 4

10 mi Xu/O 2.1X10 15 13 3 9 9.G.Ci/sec 1.3X10 2 N

~ \

Ci/sec 1.3X10 2 1/D HRS 4 VB K1 3.7X10' _

11Y K2 7X10" i

i

v c>

1993 SCENARIO CW OW TIIYROID CIIARCOAL MR/hr MR/hr mrem /hr CPM TIME 1330 WD 270 WS m/sec 6.8 1/WS 0.15

\

PASQUILL D N SB Xu/O 1.4X 10" 1010 1315 196 580 1 mi Xu/O 5.0X104 360 470 70 220 4

2 mi Xu/O 1.9X10 135 175 27 82 4

3 mi Xu/O 1.0X10 70 90 14 47 4

d mi Xu/O 6.8X10 50 65 10 30 4

.niXu/O 5.1X10 35 45 7 23 4

6 mi Xu/O 3.8X10 25 32 5 14 4

7 mi Xu/O 3.2X10 20 26 5 14 4

8 mi Xu/O 2.7X10 19 24 4 13 4

9 mi Xu/O 2.3X10 17 20 3 9 4

l0 mi Xu/O 2.1X10 _

15 13 3 9 2

tG. Ci/sec 1.3X10 Ci/sec 1.3X10 2 N \

/DIIRS 41/4 ._

N VB K1 3.7X10' MY K2 7X10 8 e

o e 1993 SCENARIO CW OW THYROID CHARCOAL MR/hr MR/hr mrem /hr CPM TlME 1345 WD 270 WS m/sec 6.8 1/WS 0.15 PASQUILL D d

SB Xu/O 1.4X10 1010 1315 196 580 1 mi Xu/Q 5.0X 10~5 360 470 70 220 2 mi Xu/Q l.9X10~5 135 175 27 82 3 mi Xu/O 1.0X10 5 70 90 14 47 4

d mi Xu/Q 6.8X10 50 65 10 30

_.niXu/O 5.1X104 35 45 7 23 4

6 mi Xu/Q 3.8X10 25 32 5 14 4

7 nd Xu/O 3.2X10 20 26 5 14 4

8 nd Xu/Q 2.7X10 19 24 4 13 9 mi Xu/Q 2.3X104 17 20 3 9 0 mi Xu/Q 2.1X10* 15 13 3 9 2

LG.Ci/sec 1.3X10 Ci/sec 1.3X10-2

/D HRS 41/2

/B K1 3.7X105 HY K2 7X108 9

4.

A

s 9 1993 SCENARIO CW OW TIIYROID CHARCOAL MR/hr MR/hr mrem /hr CPM TIME 1400 '

~~_... '-

WD 270

'N WS m/sec 6.8 1/WS 0.15 PASQUILL D SB Xu/O 1.4 X 10" <1 <1 <1 BGRD 1 mi Xu/Q 5.0X10~5 <1 <1 <1 BORD 2 mi Xu/Q l.9X10 5 135 175 27 82 5

3 mi Xu/O 1.0X10 70 90 14 47 4

4 mi Xu/Q 6.8X10 50 65 10 30

.niXu/O 5.1X104 35 45 7 23 4

6 mi Xu/O 3.8X10 25 32 5 14 4

7 mi Xu/O 3.2X10 20 26 5 14 4

8 mi Xu/O 2.7X10 19 24 4 13 4

9 mi Xu/O 2.3X10 17 20 3 9 4

.0 mi Xu/Q 2.1X10 15 13 3 9 f.G.Ci/sec 0 _

Ci/sec 0

/D HRS 43/4 VB K1 5 3.1X10 11Y K2 7X108

+ c>

1993 SCENARIO CW OW TIIYROID CIIARCOAL MR/hr _ MR/hr mrem /hr CPM -

TIME 1400 2 DAYS LATER WD 220 ,

WS m/sec 5.2 ,

1/WS 0.19 ,

PASQUILL C j ,[

SB Xu/O <1 <1 <1 BGRD 1 mi Xu/Q <1 <1 <1 BGRD-2 mi Xu/Q <1 <1 <1 BGRD 3 mi Xu/Q <1 <1 <1 BGRD d mi Xu/Q s.1 <1 <1 BGRD s mi Xu/O <1 <1 <1 BGRD 6 mi Xu/Q <1 <1 <1 BGRD 7 mi Xu/O <1 <1 <1 BGRD 8 mi Xu/Q <1 <1 <1 BGRD 9 mi Xu/O <1 <1 <1 BGRD 10 mi Xu/O <1 <1 <1 BGRD

.N.G.Ci/sec 0 / _

I Ci/sec 0 S/D HRS / ./ , , . -

WB K1 TI1Y K2 f

t

%. I '

K L

a-  %- - . -, . - .

' r ,

f'T i '

Continued Ort Map Ho.10

. d' $::

3 i4 is is o in w u.rmS 1,3 1

l$

. 4 l,

~f Q),

[F MyJy 1

Q+dyk 7O y.' ga ( _c ,,r 4 l' W s m

o

..- c= C.. e.h N

85'*"" - +<- , '

t. 0501 :_.k i

~ ,)

3 ,

ER

  • n -  %, 0; / # ,w no or k -

, c-j , ,

]t ^N p. - 9 g

(h 9- W~

oi K1 b  %, -~

{

~

y

/ '. 0,tg

{ @fp]Ik y;i[g' sg@;tM,"l x

g

-Q

~ ' " " *

. 1 *

\ 's .e

[} h' bc w

yq)flo y

f:gg)i ~\ %j Q, s

_l '

.4

- u_

\

[w 1

- ' :m, o

,7r -u o V"+ 4 ';I c a.,.;

n V: v>

l fJ 7

f CitOTON - a f ,

  • \- ,, y tilfiditTE N [{l' 1 ,

\ * ~ #

'l

? I  %,.,. A.~~ ~ ~ '

W.. f .;" ,

&~.l " i 4

'~

l i

ein ,.,. ne.c.

m$5-s'1'e\ppyoun &.,

J ., . $

j i

}

U f e.

res rm sernturarr '. .

Y

  • Q e,

/} I4 l 1$ 1s II l IO l 'U U ,,.,

" 36 Contirased On Map Ho.12 w--  %,.

DASHED LINES ON EITHER~ SIDE I ..,.,3

-1993 SENARIO A-- =

OF THE PLUME SIGNIFY -

,.7.! '

1/10 OF THE CENTERLINF VAIIII: -

likT .

' a..t.Aiz;.2{t& & p l\lkhf$)!h_b ((fk '

M Continued On Map No.17 s}E;fg 51 (

4- l 9 l 10 l 11

~ Continued On Map No.18 ' ', f f

.e H" Yf~ - ,,,,, .\ Q.l

~

K 12 l

-A ""

13 14 Urf i 4

[_e ' ,

"] --'4 7, M,nf-~ V p{ t e

~ (M Q&j.

,. Y

-3 g d sH k m *' { , p .

g

.: . 'j '

A h FML- $ g 4

.7 I

,? W 3/ 'c N jh os ,

_1 .

7h y

  • , ;f-- -g,4 y, y > - - -

4

,A ~,,,o e\ (..g. w- ,

j*W q 1~

..-flj

~ ' - - -

L d.

~_ :--

y5: L-..~.l . -~ , N

  • ~ ~ ' .,

~

i

_. j l '

i

( 100dattt ' '

f

~

_{']f pngp;hf(tgp(*l f"p- ['

k O.

  • [ C' g" p_ p - b E '* h' . - '

t [ wcu lf ,* \

  • 4TSipC '

L -y ~; '

.I i q >

\ O

}

hr0c: 3 ( A{ jj k ' ) r, m g

W'j F

\, h'Y ~~'~ "

p.

g g/./

,i ^T "^~= DN )y.

c,q# Yx

) { ~pa g j\ L_

\ N 4 1_3 ser rower yn, o j ""

f f.

4 x . m,W j{ .

{

h -

g "{ } ' H Mp/dh g

}

..., _ 5

.' .o 4

y3 , -

t. Nb.g.ygn

'!L

\ @-

\ ~ 4.

p. ..

.+

L in AME Mg ' .

.gf

~

/

"(r  !

i

\' '

9*

QQ Q '

\

k ,,

J i i:

y._ --

i k

Ek '

^'"

..g\ , }

N 1\'

t

+V, r w t

/ g ,,,,,

. # ,j

.I 9

., c 1 , l.

u.

0 o .;

1 5 l 10 I 11 1

17 l 13 1 14 s .

g ;;fl. p Contuiued On Map No,11

.,

  • 35 '

DASHED LINES ON EITHER SDE -

-1993 SENARIO- - -- 'y$f OF THE PLUME SIGNIFY tw

%.in6 1/10 OF THE CENTERLINE VALUE . ._. -

t  :

A: , s, _1

' s j l d '

  • \ 3 l y..... .oo v., .og no. u h

4 l 5 , h[

Q2ll,'u","' ~ '""

d \' El 6 1 7 I q NL W=%

y

' ,,f'- t t

} Q.

B e

~.

G, ,).. $k p h,jh"k_gj',gQef(N.'pr.....

9o '<' N i.g ^

$ E s 4e N,s.e( kk.3fs

_A w U, w A: .

g+..),... ...;.r4.h,o. , _ -.

e Lv,, v ,.w e.(Ni 4 ,,..,,.

,,3,q,cagg ,

9; ..

a c_ _ -

~

n Z'O t g' 3.3 pg .

~

MJ" /

r

.. . _ ,,.,. U; .

-inf

  • d') All f <

elf i '. /  :

"l,,'fld n][,nink.)yy $$hfh I "!hl.l  :

~

,- (,,s.Tir ' [ 2 p; .:-b (.

^L 'i' t

e. '

/

. l4f[) ?llllll@ll ,. f GiE. p.

y 'b}..e~%y)i["ijf8

)

n;

% ll9,  ;-

5

,,;9 :

3e

~4 p,

.y \ w.~ aa

-y**< c'ssr .. vuu wcw; -

l n;

-& s.'y / tr

c. :

e;r

% i.W,. ~'t'* ,u r

.u <

,,,. o Q \g)5,.qe>g> f G7 L.f p

~

s' e} 1 y.4 .%~)

~

11 O I A A \ /' -

~ ' " f. ~.' ,

i  :

N' inj . .

r h*!

P '

/

~

' ~ ~

,.. f '

^) ..

(($ ..,

Sh k, & h , b-}.k.

'bk. , t *

~

s%p

~!hhN.A 7 ,' * "f j

-o g t

.-y s .:.~ 3 ,

  1. ,f )Nta' W

/s. ,.

- . . , , ,y . .Fs,.xA . .-

_- d ,

3 , 4 u s s

I a

i

<B i J  ;?

co.,u,n.eni on unn tio.11 a <'

"e 5

  • Ei DASHED LINES ON EITHER SIDE ,,

,f

-1993 SENARIO 1- - ' i OF THE PLUME SIGNIFY 1/10 OF THE CENTERLINE VALUE . -l'!,IU

" M N.;

t  :'i?W-

- +

SCENARIO NO.1993 TABLE 8

_OFFSITE TLD READINGS MILE MILE

_ SECTOR HING MREM _ SECTOR _ RING MRFM 1 1 9 1 5 5 10 10 2 1 10 1 5 5 10 10 3 1 11 1 5 10

  • 10 10 4 1 12 1 5 5 10 10 5 1 1362.8 13 1 5 89.8 5 10 32.9 6 1 14 1 5 5 10 10 i

7 1 15 1 5 5 ,

10 10 l 8 1 16 1 5 5 10 10 NOTE: Data to be supp!!ed to Offsite Radiological Assessment Director.

1 e

Vill-H

_-p

& Y' SCENARIO NO.1993 TABLE 9 POST ACCIDENT SAMPLES NOT REQUIRED FOR THIS SCENARIO f

A Vill-1

t' SCENARIO NO.1993 TABLE 10 POST ACCIDENT OFFSITE CONTAMINATION LEVELS NOT REQUIRED FOR THIS SCENARIO 1

Vill-J

F 9MNO*

SCENARIO NO.1993 TABLE 11

_ MEDICAL EMERGENCY DATA i

l NOT REQUIRED FOR THIS SCENARIO l

Vill-K

'4 w CONSOLIDATED EDISON COMPANY OF NEW YORK Mw INDIAN POINT UNIT NO. 2 EXERCISE SCENARIO NO.1993 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

+ Astoria Emergency Control Center

+

Emergency News Center (Con Edison Personnel Only)

B. Participation Assembly and accountability will be required by all Con Edison personnel and contractor personnel at the site. After accountability has been completed, personnel not participating as players, controllers or observers ,

will be permitted to return to their normal work locations. New York Power Authority personnel and contractors are not required to participate.

C. Arm Band Use Re following arm band color coding will be used during the drill.

Green -

Controller Red -

Observer White -

Player 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 participating

will be directed by their Department Managers to refrain from entering the TSC and OSC areas. Non drill participants requiring entry to the Control i

Room will be directed to contac' the SWS assigned to the watch. Security '

restrictions on entry throu0h the Main Gate and Command Guard House will be lifted by the Security Controller one hour after the declaration of ALERT.

IX-1

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 Emergency Planning will hold a critique at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> on September 23, 1993 at the Simulator Auditorium. All controllers and observers shall attend.

k

(. "

IX-2

_ _

Retrieved from "https://kanterella.com/w/index.php?title=ML20062J228&oldid=3078921"