ML17289B189

Exercise 93 Supply Sys Annual Exercise Evaluated by Nrc.

ML17289B189
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Site:	Columbia
Issue date:	02/24/1993
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WASHINGTON FUBLIC FOWER 4S SUPPLY SYSTEM STRICTLY PRIVATE .

LOCKED STORAGE REQUIRED THE ATTACHED DOCUMENT MUST NOT BE LEFT UNA'ITENDED OR WHERE ANY UNAUTHORIZED PERSON MAY HAVE ACCESS TO IT.

WHEN NOT IN USE, O'UST BE STORED IN h LOCKED REPOSITORY.

WHILE IN YOUR POSSESSION IT IS YOUR RESPONSIBILITY TO PRO TECT IT AND AS CONTENTS FROM ANY UNAUTHORIZED PERSON.

AFTER PROCESSING, WHEN THE ATI'ACHED DOCUMENT IS READY TO BE FILED IN A LOCKED REPOSITORY, THIS COVER SHEET MAY BE DETACHED AND DESTROYED.

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EXERCISE '.93 UGLIER EXERCISE DIRECTOR:

RON EXERCISE COORDINATORS:

PAT BAGAN - Scenario TERRY CHRISLER - Health Physics Data SCENARIO AUTHORS:

Pat Bagan - Scenario Script, Sintational Data, Initial Conditions & Messages Terry Chrisler - Health Physics Data, Meteorology, Radiological & Contamination Data OJ Brooks 5 Ed Neasham - Scenario Development & Review

EXERCISE 93 TABLE OF CONTENTS L GE2692L INFORMATION Schedule Meteorological Data Initial Conditions/Scenario Script/Timeline Summary Objectives/Limitations Evaluator/Controller Listing Evaluator/Controller Instructions Player/Observer Instructions Acronyms II. ORGANIZATIONSPECIFICS

~ Plant-Simulator(CR), OSC, TSC

'essage/Data Sheets

~ EOF-MUDAC, HPC, SSDC, TDC, OACC Message/Data Sheets

~ JIC Message/Data Sheets Control Cell Evaluation Criteria Worksheets Control Cell Operations and Messages III. EVALUATIONSECTION Timeline Worksheets/Evaluation Criteria Worksheets Evaluator Logs 5QXR' Center specific drill packages include all information listed in the General Information section and the message/data sheets, timeline worksheet, evaluation criteria worksheets and evaluator logs applicable to that center.

~ EXERCISE '93 SCHEDULE ~ February 1993 February 22

',"PRES/DENT.,S 'QA'7"i"",';::,"'."::,'.';,",.:F,',:::-:.:'"',"-". ':"":,"::".'.:-:;:.,':.'!'.,'.-';~i:,'::.,: 1l:30 Player Orientation Mtg&SB Conf. Room

00 Player Orientation Mtg PSF Auditorium

"'-'k!i'.-.".:<:4.:;=,':::-;:.'>'"-.:j';:.='.

!TOES DAY."',.':

February 16 February 23 08:30 Cntlr/Eval Scenario Mtg-PSF Rm 120  :,:,:-".:;.':.:.":,~gqCQNDUCT~EXERCISEj'93".,'"i: ""::<"!".-:: ',5;"j 03:00 Op's/HP Player Orientation Mtg-Simulator 10:00 Phyer/Evaluator Critique-Emergency Center February 17 DNESDAY: February 24 07:30 Cntir/Eval Critique Meeting-PSF Rm 141 12:00 Key Cntlr/Eval 8 EP Mtg-PSF Rm 141

".'-THURS DAYP February 18 February 25 08:00 Corporate Critique Presentation 14:00 NRC Exit

=:::,-::.;"'.FRlDAYÃ:"'i:

February 19 February 26 08:30 Final Ctlr/Eval Pre-Exercise Mtg-PSF Rm 141 February March S M T W T F S S M T W T F S 1 2 3 4 5 6 2 3 4 5 6 7 8 9 10 11 12 13 7 8 9 10 11 12 13 14 15 16 17 18 19 20 14 15 16 17 18 19 20 21 22 23 24 25 26 27 21 22 23 24 25 26 27 28 28 29 30 31 EXERCISE '93 2/23/93 2/4/1993

4 WASNlNGTOl4 SUPPLY SYSTEM CONTROLLER INFORMATION GENERAL DATA SHEET PubLlc 'POWER DRILL NO. Exercise 93 PAGE sHEETNo. E1.a REsPGNsIBLEcoNTRDLLERILocATIoNJ "Control Room {Simulator), MUDAC 5. TSC" REAL TIME oF: 03:00 TO: 12I00 DRILL TIME oF: 00:00 To: 09:00 ASSO CIATED WITHMESSA GES INFORMATION APPLIES TO Meteorologica/Data-

&cather Forecast A. Forecast 0000-1200 Walla Walla Valley forecast valid until 12:00 noon PST, Tuesday February 23, 1993, from the National Weather Service in Pendelton, OR lor Seattle, Washington) as of 00:00 a.m. PST February 23, 1993 Temperatures this morning are expected to be in the mid 30 degree range with warming into the mid 40's by late morning. Light to moderate west through southwest winds and gusty mechanical turbulence beginning mid morning and remaining throughout the remainder of the day.

It will be partly to mostly cloudy today. Winds will be light early morning becoming moderately gusty by mid morning.

B, Controller information, NOTE: For CONTROLLERS- If Battelle is called for the weather, use the backup data from Sheet Eld.

C

0 WhStttNGTON POSLtC POWER SUPPLY SYSTEM CONTROLLER 1NFORMATION GEMWAL DATA SHEET DR/LL NO. Exercise 93 PAGE SHEET NO. E1.b REsPoNslBLE coNTRoLLER ILocATIoNI Control Room (Simulator), MUDAC 5, TSC REAL TlhtE OF: 03:00 TO: 12/00 DRILL TlhfE OF: 00:DO TO. 09IOD ASSOC/A TED WITH MESSAGES INFOR/ifA TION APPLIES TO iWeteorolo gical Data-StabiTity Cbssilication Table A. Stability Class vs. 5 T/LLz signal Stability Pasquill Temperature Change

~abulia u* /sate,eries With Hci ht s aC/l Extremely Unstable A itsT/d,x 2 Moderately unstable B -1 9' 5 T/6 x 2 70 Slightly unstable C -1.7 2 6 T/6 x 2 Neutral d TIER 2 Slightly stable E 43'2 LIT/kx 2 18 Moderately stable F ET/ 6* 2 4.O.

Extremely stable G 40~2 ETIAM x 2 B. Stability Class vs. Sigma 8 Theta Signal Stability PasquiQ = Tcmperaturo Chango

~CI ~Cl With Hei ht cs aCI Extremely Unstablo A sigma 8 2 Moderately unstable B 223' sigma 8 2 Slightly unstable C 173'? sigma 8 2 17.5'2.S'.S'Se Neutral 128~ 2 sigma 8 2 Slightly stable E 79~ 2 sigma 8 Modcratcly stable F 3.8 2 sigma 8 2 2.1' Extremely stable G 21 ~ 2 sigma 8

ti WASNiNGTON PUSLlC POWER supprv svsTEM CONTROLLER INFORMATION GENERAL DATA SHEET Exercise 93 PAGE 1 of 2 SHEET NO. E1.c REsPoNslBLEcoNTRGLLER ILocATIoNI Control Room (Simulator), MUDAC 5 TSC REAL TIME oF: 0ZI00 To: 12I00 DRILL TIME OF: 00:00 To: 09:00 ASSOCIATED WITHAfESSAGES INFORMATIONAPPLIES TO Meteorological Data-Primary and Backup Primary Met Tower Readings Direction Delta T Wind Wind iT/iz Sigma 8 Temp.

Speed

~MH From Pas quill Degrees

~41~0m Theta

~Dry Degrees

' ~if Stability i

0000-0300 1 226-224 F 2.0 2.0 7.2 Moderately Stable 0400-0600 1 226-224 F 2.0 2.0 7.2 Moderate~table 0600-0700 2 226-224 F 2.0 2.0 7.2 Moderately Stable 0700-0800 2 228-222 E 0.5 4.0 7.2 Slightly Stable 0800-0900 2 229-222 E 0.5 5.0 7.8 Slightly Stable 0900-1000 3 231-219 E 0.0 6.0 8.9 Slightly Stable 1000-1100 6 216-234 B -1.8 18.0 10.0 Moderately Unstable

'l100-1200 6 216-234 -1.8 18.0 11.1 Moderatley Unstable 1200-1300 6 215-235 B -1.8 20.0 12.2 Moderately Unstable 1300-1400 8 215-236 B -1.9 21.0 12.8 Moderately Unstable 1400-1500 8 215-235 B -1.9 20.0 14.4 Moderately Unstable 1500-1600 6 217-233 C -1 07 16.0 15.5 Slightly Unstable

'1600-1700 6 218-232 C -1.6 14.0 15.5 Slightly Unstable

A WhSLLLMGTOM PLlLLLLC POWER SUPPLY SYSTEM CONTROLLER INFORMATION GENERAL DA TA SHEET DRILL NO. Exercise 93 PAGE 2 of 2 SHEET NO. E1.d REsPDNsIBLEcoNTRDLLER ILocATIoNI Control Room (Simulator}, MUDAC & TSC REAL TINE OF: 03IOO TO: T2IOO DRILL TlhfE OF: 00:00 TO: 09:00 ASSOCIA TED WITHNIESSA GES INF0RMATIDNAPPLIEs To Meteorologicel Dete-Prirnery end Backup Backup Met Tower Readings Direction Delta T Wind Wind iT/iz Sigma 8 Temp.

Speed From Pas quill Degrees Theta Degrees Stability iMM~D L C lalpm oOO1~ ~D!qrri~ ~lifi 0000-0300 1 226-224 F 2.0 2.0 7.2 Moderately Stable 0400-0600 1 226-224 F 2.0 2.0 7.2 Moderately Stable 0600-0700 2 226-224 F 2.0 2.0 7.2 Moderately Stable 0700-0800 2 228-222 E 0.5 4.0 7.2 Slightly Stable 0800-0900 2 229-222 E 0.5 5.0 7.8 Slightly Stable 0900-1000 3 231-219 E 0.0 6.0 8.9 Slightly Stabl 1000-1 100 6 216-234 B -1.8 18.0 10.0 Moderately Uns le 1100-1200 6 216-234 B -1.8 18.0 11.1 IVloderatley Unstable 1200-1300 6 215-235 B -1.8 20.0 12.2 Moderately Unstable 1300-1400 8 215-236 B -1.9 21.0 12.8 Moderately Unstable 1400-1500 8 215-235 B -1.9 20.0 14A lVloderately Unstable 1 500-1 600 6 217-233 C -1.7 16.0 15.5 Slightly Unstable 1 600-1 700 6 218-232 C -1.6 14.0 15.5 Slightly Unstable

DETAXLED SC1WMtXO E2KRCISE 93 NITIAL CONDITIONS The date is February 23, 1993 seven months after the R-7 outage.

The plant is running at 1004 power. Operations is currently preforming RCIC Quarterly. surveillance (7.4.7.,3.3.b). Service Water pump B is running and RHR pump B is in suppression pool cooling to support the surveillance. All other conditions are normal.

The temperature is in the low to mid 30's warming to the low 40's later in the day. Winds are light and from the west.

~SC .'lNM~IO At 0340 a .1g earthquake is experienced and the "Minimum Seismic Earthquake" annunciator alarms. A number of shock lights i

The motion of the quake dislodges bus-work in SM-8 causing a short to ground which severely damages the switch-gear. This means there is a loss of Division 2 AC power.

The earthquake will also cause a rupture disk on the exhaust line of the running RCIC turbine to fail. This will pressurize a pressure switch giving the RCIC system an isolation signal. The RCIC turbine trips but the containment isolation valves fail to close. Inboard isolation valve (RCIC-V-63) due to a loss of power, and outboard isolation valve (RCIC-V-8), in mid position, due to a bent stem. This prompts the operating crew to announce an ALERT due to "Reactor Coolant Pressure Boundary Lines Fail To Isolate When Design Logic Met".

The loss of SM-8 puts the plant in a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> LCO (3.8.2.1.b) for loss of Division 2 battery charger. This and the earthquake damage may cause the Shift Manager to shut the plant down.

Soon after the earthquake the BPA will call the control room and request that WNP-2 stay on line as long as possible. WNP-2 is the only power source for the region because of downed power lines and other grid disturbances. The BPA requests we stay at maximum power until additional sources of power are returned to the grid.

A default message to the Shift Manager and oncoming PED will ensure the plant stays at 1004 power until the next event.

At ~630 a .075g after shock will occur. This will cause a loss of 230kv Startup Power to TR-S and a spurious trip of the Main Generator output breakers. This will cause a Turbine)Generator trip and resulting reactor SCRAM.

The reactor will be shutdown but several rods will not be completely inserted. This is technically an ATWS (Anticipated Transient Without SCRAM) and will drive the operating crew into the ATWS EOP's.

This after shock will cause a RCIC steam line break downstream of RCIC-V-8 (near the TIP room). Steam will flow from the break to the Reactor Building and out the running train of Standby Gas Treatment.

Since there are no adequate "Outside The Shroud" injection systems available for makeup to the reactor a cooldown will not, be performed and pressure will be maintained (800 - 1000 psig).

This means steam at high pressure will continue to flow into the Reactor Building.

Because of the loss in power there will be a loss of Primary Containment cooling which will cause Containment temperature and pressure to rise. When pressure rises to 1.68 psig an auto start signal is sent to the HPCS Diesel. The diesel will start and then trip on overspeed due to a failed speed signal to the governor.

At 0700 level in the reactor slowly drops until two Area Radiation Monitors (ARM) exceed their "Maximum Safe Operating Values" at which time the reactor will be "Emergency Depressurized" by opening seven Safety Relief Valves (SRV's). The rapid loss of steam through the SRV's will cause the reactor water level to decrease quickly.

At ~05 as level in the reactor drops and cannot be maintained above -192 inches the remaining "Inside The ShroudIILow Quality Systems" will be lined up for injection into the reactor.

A G GENC will be declared due to "Loss Of Two Barriers And Potential Loss Of Third".

When RHR pump A (LPCI A) is lined up to the reactor it' injection valve (RHR-V-42A) will not open due to the disk being jammed into the seat.

When LPCS pump is lined up for injection to the reactor the pump breaker will trip open if the due tois a started will fail to close. This will be pump

~o the pump breaker minor breaker problem.

The level in the reactor will continue to drop uncovering the core causing fuel temperature to rise.

At 0725 the breaker problem with LPCS pump will be fixed and the

,pump started. The large amount of cold water injected by the LPCS system on to the hot fuel will cause thermal stress resulting in cladding damage.

The LPCS pump will return reactor level to above Top Of Active Fuel.

The release through the RCIC steam line break vill rapidly diminish as pressure in the reactor is lost.

At about 0900 a shift change will occur vith the oncoming emergency team.

At about 1000 terminate Exercise 93.

C SUA TY CONTRO Casualty control. after the initial earthquake will consist of:

Assessing the damage to SM-8 (will not be returned to service for remainder of exercise)

Attempting to close RCIC-V-S (will not close for remainder of exercise)

Possibly finding an alternate power supply to RCIC-V-63 (if re-energized breaker vill trip due to internal fault in valve motor)

In addition tours of the plant will be conducted to determine if there is any other earthquake damage.

Casualty control after the second earthquake will consist of:

Isolating the close) steam leak (RCIC-V-S and RCIC-V-63 vill not Repairing HPCS Service Rater pump in order to return HPCS diesel and pump to service Open RHR-V-42A (valve will not be able to open until LPCS pump has returned reactor water level to above -161 inches)

Repairing LPCS pump breaker (will allow breaker operation after core uncovered appropriate amount of time for fuel temperature to increase)

Lining up Firewater to Condensate Crosstie for possible injection to reactor vessel

TJIMH IZME 8UMMAR KG~&CISE 93 TIME ACTXVI'XT 0330 Start Exercise 93, 100% Power, RCIC Surveillance In Progress.

0340 Minimum Seismic Earthquake (.1 g).

SM-8 Overcurrent Trip (Bus Damage).

RCIC Isolation Signal with RCIC-V-63 and RCIC-V-8 Failing Open.

0345 ~~

Met.

Reactor Coolant Pressure Boundary Fail To Isolate When Design Logic BPA Dittmer Calls And Requests WNP-2 Stay On Line As Long As Possible Due To Loss Of Several Dams In The Region And Power Distribution Lines Down Due To An Earthquake.

0630 Minimum Seismic Earthquake (.075 g).

Loss 230 kv to TR-S.

RCIC Steam Line Breaks Just Down Stream Of RCIC-V-8 Causing Unisolatable Leak To Reactor Building.

Main Generator Trip / Reactor Scram.

Several Rods Fail To Completely Insert. ATWS (Anticipated Transient With Out SCRAM).

HPCS Diesel Trips Rendering HPCS-P-1 Inoperable 0700 Emergency Depressurize When Two ARM's Exceed Maximum Safe Operating Values 4 0705 Reactor Water Level Less Than -192 Inches.

R N Loss Of Two Barriers, Potential Loss Of Third.

LPCS-P-1 Breaker Trips (Or Won't Close).

Start RHR-P-2A, Injection Valve RHR-V-42A Won't Open.

0725 LPCS-P-1 Back In Service, Injecting To Reactor Vessel.

Thermal Shock To Fuel, Fuel Damage Occurs (Gap Release).

0730 Reactor Water Level Above Top Of Active Fuel.

Shift Change.

Terminate Exercise 93.

0 OBJECTIVES 4 LEVQTATIONS EXERCISE '93 A. SCOPE H

The primary purpose of this Exercise, scheduled for February 22/23, 1993 is to demonstrate effective management of the emergency and plant reentry operations with efficient coordination and communications between the activated Supply System emergency centers; Control Room (simulator), Operations Support Center (OSC),

. Technical Support Center (TSC), the Emergency Operations Facility (EOF) and the Joint Information Center (JIC). The exercise willbe characterized by required response to an emergency situation that will involve classification, notification, center activation, team deployment, accident prognosis and mitigation.

Two other major puqeses of this Exercise are to conduct an "off-hours" exercise as required to be demonstrated once every six years by NuReg-0654, and to conduct a shift change of designated positions in the Supply System Emergency Response Organization.

Timely and proper response by the players willcontribute to mitigation of the simulated accident consequences. Participation by EOF k JIC liaison personnel, as well as offsite agencies to include Benton/Franklin Counties, Washington State Division of Emergency Management (DEM) and Department of Health (DOH), the Oregon State Department of Energy and US-DOE will occur.

B. OBJECTIVX8 AND LBCITATIONS

'The Objectives and Limitations are divided into two major sections. The first section describes the General Objectives and Limitations which are applicabe to the Supply System and the various offsite agencies. The second section, titled

'Facility Specific Objectives'eflects NRC standardized objectives which are applicabe to specific emergency response facilities at WNP-2.

OB3ECTIVES dt I EVJEI'ATIONS EXERCISE '93 GX2692AL OBJECTIVf<D SUPPLY SYSTEM General Objectives and Limitations

1) 'o demonstrate the ability of the Emergency Response Organization to respond to an "off-hours" emergency situation and to conduct a shift change of the Supply System emergency response personnel (this is a NuReg 0654 six-year objective).

2) To provide Supply System personnel with the opportunity to participate interactively with the State and County Offsite Response Organizations as well as with US-DOE RL Hanford Site operations.

3) To provide Supply System personnel with the opportunity to practice Casualty Control methodology for the prompt mitigation of the consequences of a postulated accident and/or radiological release.

4) To demonstrate the use by Supply System personnel of plant parameter type Emergency Action Levels (EAL's).

Limitations

1) The Primary Access Point and Alternate Access Point willremain functional for routine plant operations; Actual security is not to be jeopardized.

2) SCBA's may be worn by bearded personnel. SCBA's need only be utilized throughout the first deployment of each emergency worker if proficiency is demonstrated. In the interest of safety, SCBA's may be removed from anyone stressed by its use.

3) Operations and certain Security personnel playing in the Exercise will be individuals specifically predesignated as participants.

4) The Control Room will be exempted from Exercise play; the CR Simulator will serve in its stead. Not all CR functions are simuhted in the CR Simulator. The main exceptions are listed, but not limited to the following:

No Secondary Alarm Station No functional ENS to the NRC Access is not limited Select Balanmf-Plant equipment is not simulated Certain divisional equipment is simulated for one, but not both divisions

5) No Protected Area or Exclusion Area Evacuation wiH be demonstrated during this Exercise (Exclusion Area sirens will not be activated).

OBJECm'ES dh LIMXTATIONS EXERCISE '93 No relocation of major emergency center or use of alternate emergency center will be demonstrated during this Exercise.

First and second shift players will be pre-designated.

8) Shift change will not be demonstrated by the Simulator staf'f.

9) Shift change within the emergency centers will be limited to the following emergency positions for that center:

QKC PED OSC Director RPM Accountability Coord.

TSC Director Lead HP Admin. Manager Electrical Craft Lead Plant/NRC Liaison Mechanical Craft Lead Ops. Manager I & C Craft Lead Core Thermal Eng.

Mechanical Eng.

Electrical Eng. 55DC Computer Eng. Recovery Manager Security Manager Site Support Manager REM EOF PIO Field Team Dispatcher Env. Field Teams Dose Projection HP TDC Director MUDAC Coordinator Fuels Assessment Eng.

Field Team Coord. Plant Systems Assessment Eng.

HPC Coordinator Electrical/I&C Eng.

ZK EQFXC JIC Director EOFCC Coordinator WASHINGTON STATE General Objectives and Limitations No general objectives or limitations have been identified for Washington State.

OB3ECTXVES dt I IMIITATIONS EXERCISE '93 OREGON STATE General Objectives and Limitations Test new and established methods for exchange of information between

')

Oregon and other emergency response organizations as appropriate.

Test methods for exchange of information among Oregon emergency responders as appropriate.

BENTONIFaaNKUN COUNTY General Objectives and Limitations No general objectives have been identified for Benton/Fruiklin Counties.

.US-DOE QU ) General Objectives and Limitations

1) Provide RL support to the WNP-2 Emergency Operations Facility and the MUDAC.

2) Provide RL/contractor support to the Supply System Joint Information Center.

Limitations

1) RL/RL Contractor involvement in this exercise will be limited to those resources identified in the RL Exercise Scope statement (nor a part of tMs document).

2) Hanford Site safety or security shall not be degraded for the sake of this exercise.

Allsafety and security requirements and pmxxiures shall be complied with during the exercise. This shall include proper entry and exit out of radiologically controlled areas.

3) The Patrol Operations Center (POC) business number, 373-3800, shall be used in lieu of 811. When using this number in lieu of 811, the caQer must identify the communication as an exercise message.

The objectivee for Oregon State contained within this document are for training end scenario development purpoeee on!V,

OBJECTIVES 4 I IMETATIONS EXERCISE '93 FACILITYSPECIFIC 083ECTIVF8

1. Demonstrate the ability for the Shift Manager and the control room operators to recogriize abnormal events, determine plant conditions and bring the plant into a safe shutdown mode.

2. Demonstrate the ability of the control room operators to correctly implement the immediate actions of the Emergency Plan Implementing Procedures.

3. Demonstrate the ability of the control room operators to classify the emergency using the Emergency Action Levels (EALs) and determine the necessary onsite and offsite protective actions.

4, For a Site Area or General Emergency, demonstrate the ability of the control room to evacuate nonessential personnel and initiate protective actions for all personnel remaining on site.

~i'g'o Protected Area or Exclusion Area evacuation during this Exercise.

will be demonstrated

5. Demonstrate the ability of the control room to promptly notify onsite personnel of emergency events, conditions or actions.

6. Demonstrate the ability of the control room to promptly notify offsite officials of emergency events, conditions or actions.

7. Demonstrate the ability to make Secondary Alarm Station (SAS) and NRC notifications in a timely manner.

8. Demonstrate the timely and systematic transfer of the Plant Emergency Director (PED) duties.

For Alerts, Site Area and General Emergencies, dern'onstrate that the TSC can be activated and prepared to perform required functions within about 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after declaration of the emergency.

2. Demonstrate the ability of the TSC to assess plant conditions and determine the proper emergency classification.

OSJECTTVES 4 LIIKKATIONS EXERCISE '93

3. Demonstrate the ability of the TSC to assess and direct actions to mitigate the consequences of an emergency.

4. Demonstrate the ability of the TSC to determine the necessary protective actions for onsite and offsite personnel.

5. Demonstrate the ability of the TSC to promptly notify onsite personnel of emergency events, classifications and actions.

6. Demonstrate the ability to conduct and maintain personnel accountability.

7. Demonstrate the ability of the TSC Director to communicate with onsite and offsite emergency response personnel when making decisions and implement corrective actions in an effective and timely manner.

8. Demonstrate the ability of the TSC to communicate technical information to the Control Room, OSC, EOF and NRC.

~i'gtjgg' control cell will be used to simulate the NRC in the event the NRC Operations Center declines to participate after the initial notification.

9. Demonstrate the capability of the Duty Plant Emergency Director to make timely and effective decisions and demonstrate command and control of the TSC and onsite response effort.

10. Demonstrate the timely and systematic transfer of Recovery Manager duties.

1. For Alerts, Site Area and General Emergencies, demonstrate that the OSC can be activated and prepared to perform required functions within about 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after declaration of the emergency.

2. Demonstrate the ability to maintain appropriate radiological controls in the Protected Area, throughout the course of the event.

,

• Demonstrate the ability of the OSC to effectively communicate with the EOF, TSC and repair teams, adequately brief, track and debrief teams dispatched from the OSC.

4. Demonstrate the ability to respond to and analyze simulated elevated airborne and direct radiation measurements in the Protected Area environment.

6

OBJECTIVES 4 LIlKlTATIONS EXERCISE '93

5. Demonstrate the ability to provide respiratory protection and contamination control in the Protected Area.

~mi ag Use of SCBAs will be limited to one-time fuii use and bottle changeout by each emergency worker needing to wear one.

6. Demonstrate the ability to monitor OSC habitability.

Lim~iggn. Relocation of the OSC will not be demonstrated.

7. Demonstrate the ability to main~ accountability for all on-site personnel for the duration of the emergency event.

8. Demonstrate the ability of the OSC Director to command and coordinate OSC activities with the CR and TSC.

9. Demonstrate the ability to communicate technical information to the TSC and CR.

10. Demonstrate the ability to implement emergency exposure guidelines for onsite emergency workers.

EIUS N F I. For Alerts, Site Area and General Emergencies, demonstrate that the Emergency Operations Facility (EOF) can be activated and prepared to perform required functions within about I hour aAer declaration of the emergency.

2. Demonstrate the ability of the EOF to deploy environmental sampling teams to appropriate locations, promptly and correctly project direction and maximum dose within the plume EPZ and the distance to which EPA PAGs are projected to be exceeded and perform dose assessment ifa release is in progress.

3. Upon activation, demonstrate the ability of the EOF to make offsite protective action recommendations and transmit these to offsite agencies.

4. Demonstrate the ability of the EOF to set up and maintain a communications channel to offsite authorities, including NRC and keep them informed of emergency conditions.

~i~~g' control cell will be used to simulate the NRC in the event the NRC Operations Center declines to participate after the initial notification.

5. Demonstrate the ability to periodically assess the habitability of the EOF.

6., Demonstrate the abiTity to brief offsite representatives at the EOF and keep them informed of emergency conditions.

r

OBJECTIVES & LIIMlTATIONS EXERCISE '93

~ ~

Demonstrate the ability of the EOF to. communicate effectively with corporate

~

7.

headquarters and other emergency response personnel and centers and to obtain outside resources in a timely.manner, when requested.

8. Demonstrate the abili*ty to dispatch offsite monitoring teams in a timely manner and the teams to implement their functions in a timely manner.

9. Demonstrate proficiency of offsite monitoring teams to use protective measures ..

equipment, locate sampling and monitoring locations, coQect, bag and label samples and other duties as required to effectively perform their function.

10. Demonstrate the ability of the Recovery Manager to make timely and effective decisions and demonstrate command and control of the EOF functions and overall response effort.

1. Demonstrate the ability of the Joint Information Center gIC) to properly coordinate news releases with the NRC and other offsite agencies and disseminate information to the media/press in an accurate and timely manner.

LimiQjjgg' control cell will be used to simulate the NRC in the event the NRC Operations Center declines to participate after the initial notification.

2. Demonstrate the ability of the JIC to maintain adequate communications for use by the news media.

EVALVATOR/ CONTROLLER LIST EXERCISE 93 I. PLANT CONTROL ROOM (Simulator)

Lead Controller/Evaluator Paul Taylor Simulator Controller/Evaluator OS Brooks Lead Scenario Controller Pat Bagan GDS/CIS Controller Dean Kovacs Simulator Programmer Fred Guyer Real Control Room Controller On-Shift CRS OPERATIONS SUPPORT CENTI&-

Lead Controller/Evaluator Bruce Olson Reentry Team Controller/Evaluators Mechanical Jim Cooper Electrical Brian Evans Instrument & Control Ken Kirley Lead HP Controller/Evaluator Gary Phillips Health Physics Max Valdez Health Physics Carl Hemphill Health Physics Don Ehlert Health Physics Mike Tuel PET Controller/Evaluator 'Skip'owlex

Evaluator/Controller est Chemistry Controller/Evaluator TECHNICAL SUPPORT CENTER Lead Controller/Evaluator Mark Reis Evaluator Terry Meade C1~22HRAL ALARMSTATION Lead Controller/Evaluator Andy Conner

2. EMERGENCY OPMZATIONS FACILITY I

SUPPLY SYSTEM DECISION CFKHHt Lead Controller/Evaluator Dave Kobus SECURITY DECISION CENT&K / EOF COMMUNICATIONSCENTb&

Lead Controller/Evaluator Sue Morris OFFSITE AGENCY COORD1NATION CENT1~&

Lead Controller/Evaluator Doug Coleman TECHNICALDATA CEDER Lead Controller/Evaluator Dennis Armstrong HEALTH PHYSICS CF&IXR Lead Controller/Evaluator Ron Wardlow METEOROLOGY & VN1FIED DOSE ASSESSMENT CENT1~&

Lead Controller/Evaluator Terry Chrisler Dose Projection Evaluator Jesse James Field Team Coordinator Controller/Evaluator Bzyce Twitty

Evaluator/Controller Lfst WPPSS Field Team Controller/Evaluators:

Team Number One Charlie McDonald Team Number Two Terry Northstrom Team Number Three Steve Rejniak Aerial Monitoring Controller/Evaluator Not Staffed

3. HKLDQUAR119tS JOINT INFORMATIONCI22ITDt Lead Evaluator Richard Romanelli Controller/Evaluator Sandra Day CRISIS MANAGEMENTCENTER Lead Controller/Evaluator Not Staffed CONTROL CELL Lead Controller Nancy Garza Telephone Query/Role Player Controllers:

Public Information Media Information Suzanne Livingston State/County Agencies TBD

CONTROLLER CO CATIONS LISTING EXERCISE 93 CENTER/POSITION PERSON PHONE Actual Control Room Controller On-Duty CRS 377-2348 OSC - Lead Controller B Olson 377-2730 TSC - Lead Controller MP Reis 377-2310 CAS - Lead Controller AJ Conner 377-2089 Simulator - Lead Controller PM Taylor 377-8567 Lead Scenario Controller PT Bagan 377-8567 SSDC - Controller DR Kobus 377-8181 EOFCC - Controller S Morris 377-8228 OACC - Controller DW Coleman 377-8071 TDC - Controller DA Armstrong 377-8092 MUDAC - Lead Controller FD Quinn 377-8191 HP Center - Controller RL Wardlow (750 PSF Page) gxXerci e Exercise Director RL Utter 377-8330 Q~mm nd (or pager) 780-0505 Control Coordinator PT Bagan 377-8567 JIC - Lead Controller RL Romanelli 372-5860 Control Cell - Lead Controller N Garza 372-5346 CELLULARPHONES FIELD TEAM CONTROLLER PHONE NUMBERS (NOD VEHICLELICENSE NUMBER):

'I PHONE LICENSE¹ NOTE:

948-0485 C58462 C01VTROLLERS CALL MUDAC 377-8191 948-0484 C58614 948-0483 C58468 CELLULARS ARE FOR THE USE OF CONTROLLERS ONLY notes & exceptions...

~ In an emergency or failure of radios during the Exercise, the cellulars may be used by the players.

~ Cost is expensive, limit use accordingly.

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~ Controllers need to have hands-on training (10 minutes)

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GEmmQ EVALUATOR/COMPTROLLER INSTRUCTIONS EXERCISE 93 A. Exercise Preparation: Under the supervision of the Exercise director, the foHowing will nornmEfp be accomplished prior to the exercise:

Completion of the scenario package.

2. Arrangements for +quired facilities, including for the larger drills and the exercise; use of the simulator.

3. Validation run of the scenario on the simulator, and the loading of scenario data on the graphics display system emulator.

4. Scheduling of pre- and post~ meetings with evaluators/controllers and players, and evaluator/controller traiiung for those not certified.

5. Procurement of props, realistic staging of casualty areas and briefings of any role players. However, neither actual plant operations, security or personnel safety are to be jeopardized.

6. Administrative and logistical arrangements, e.g., pager carrier duty roster revisions, controller and simulator communications set up, coffee and doughnuts contract, etc.

B. Exercise Meetings for Evalnators and Controllers: There will normally be two meetings:

A exercise package issue and overview meeting will be conducted for aQ evaluators/controllers; such things as objectives, limitations, schedules, evaluator/controller assignments, scenario introduction, the organization of scenario forms, messages, anticipated responses, general data sheets, critical points, and special evaluator/controller instructions will be covered.

Evaluator/controller team (center) breakout sessions will be conducted for all evaluators/controllers covering such things as specific messages, data input, event evaluation assignments, team communications, documentation and other coordination matters.

Exercise Scenario Compromise-AH controllers and evaluators wiH be required to sign an "Emergency Preparedness Exercise Security Agreement" prior to the Exercise stating that they have specialized knowledge about the Exercise scenario and that they will not knowingly divulge this information to any unauthorized persons. Following the Exercise, they will again sign the same agreement stating that they did not divulge any specialized information during the course of the Exercise.

C. Exercise Players Briefings:

A briefing on the exercise activities will be conducted for preassigned players, covering generalities of the exercise package. An excerpt from the exercise package can be issued as a handout. Topics should include: introduction, schedule, player positions to be activated, instructions for players, any recent procedural changes and any special coordination matters. A synopsis of current Plant Conditions may be disseminated at this time.

2. Informal table top drills may also be conducted prior to an exercise to revie~ center/team operations, procedures, etc. However, specifics on the particular scenario are not to be compromised.

D. Exercise Evaluation and Control:

Scenario Inputs:

Scenario messages and data will be provided to the players by center controllers or a controHer in the control cell in as realistic a manner as possible. For example, a controller may caH the Shift Manager and role-play as the BPA dispatcher with a scenario message; a controHer may provide simulated radiation readings to a reentry team HP technician from a scenario package data sheet if commensurate with the type and scale setting of the instrument being used. ControHers do not provide conclusions, they furnish simulated sensory inputs, e.g., if the portrayed emergency condition actually existed, what would be seen, heard, smeHed, etc.

- " 'ontroHers are specifically cautioned against 'letting to the Players what might/might-not be successful during Exercises and, to a lesser extent, during Drills. ControHers/Evaluators are not to inform the players of such items except as specifically permitted by the scenario or min~

by permission from the Exercise Director or Lead Scenario Controller.

~

Additionally, Controllers are cautioned not to permit player 'pre-staging'nless specifically permitted by the scenario. Should players show up at emergency centers or other areas in which Drill/Exercise play is to be conducted before it is appropriate for them to arrive, the Controller in charge is to request them to leave the area.

2. Scenario Devia6ons:

a. Controllers seeing a need to modify the scenario should inform their team lead controller, who will contact the exercise director.

Only the exercise director has the authority to start, stop or deviate the scenario. Scenario deviations, especially on the larger driQs and the exercises are to be infrequent and only implemented after thorough coordination, to include any lead federal evaluators and lead offsite agency controllers. The exercise director is also responsible for arbitrating any jurisdictional or interagency disagreements which may occur during the exercise.

Performance Evaluation:

ao Player task performance must be closely monitored by evaluators, as well as controllers as long as it does not interfere with their controller functions. Action taken should be compared with anticipated responses and procedural guidance.

Evaluator logs are to be used to record observations.

Center/team documentation should also be checked to verify the chronology of events and for correctness.

b. Interference by evaluators/controllers with player actions should be minimized, with questioning restricted to slack times and the immediate critique session right after the exercise, with the following major exceptions:

During the 1992 Exercise, the NRC observed that a Controller had informed TSC players that they would not be able to stop the release prior to 9:15 a.m. This was communicated between emergency centers, thus prompting players as to when this item would rewnter Exercise play. Emergency Preparedness has committed to caution Controller/Evaluators not to inform players of this (and Hkel items, except as appropriate.

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o Safety - Evaluators/controQers will immediately intervene to prevent or mitigate any unsafe condition or act.

o Major scenario deviation - If the players depart from the anticipated responses to the extent successful run of the scenario, and the meeting of driQ or exercise objectives, is jeopardized.

o During drills only, for brief, on-the-spot informal training to address incorrect task performance. 1Ms is NOT penniued during grnded exenises.

C. The reasons for incorrect task performances must be captured for proper preparation of the driQ critique. This normally requires thorough questioning of the individual(s) involved.

Critiques Immediate In-Center Critique Sessions:

Conducted in the center by the Emergency Planner or Lead controller immediately after the exercise, this informal session wiQ be used to provide the players with feedback, ensure Center Director/Manager is aware of his/her responsibility to return center/team equipment to readiness state, resolve issues, complete any informal training and ascertau> any systematic reasons behind unfavorable observations. For some findings it may be necessary to conduct a category 3 Root Cause Analysis (RCA) pursuant to PPM 1.3.48. The key is to deterniine the "why" of each unfavorable observation involving personnel error that indicates a problem with the system, e.g., improper procedural step, poor personnel selection for the position, ambiguous training, etc. The Emergency Planners or Lead Controllers are to coQect aQ logs, After-Action Reports, and administrative paper work for delivery at the formal critique session.

2. Formal Critique Work Session:

NormaQy conducted the day after the exercise, this session involves two p11ases:

Specific center team breakout sessions for aQ evaluators/

controllers will be held during this day. During these sessions observations are discussed, researched with players and drafted

up on the critique work sheets as either favorable and unfavorable observations. Time-line inputs and answers to specific evaluation questions will be assembled during this time.

Necessary RCA's with the players ifpresent will be completed

-at this time, to assure a reason for each unfavorable finding is ascertained using the RCA Qow sheets. Final team/center documentation and CARs will be prepared for submission by the Emergeircy Planner or Lead Controlle'r. Eey players may also be called to participate in these sessions.

b. In the afternoon a center lead controller session is held, team inputs are discussed and submitted, appropriate observations are consolidated, assignments are made for any required follow-on actions and issues are identified and categorized for the written formal critique. Again, key players may be requested to be present.

written Critique:

The exercise director will,disseminate a written critique usually within 30 days of the exercise. The critique will normally consist of:

Part I - Chronology: A time line of the major scenario and player response activities.

Part H - Assessment of Drill Objectives: An identification of any of the objectives that were not met and the reasons.

r Part III- Favorable Observations: Any noted display of special initiative or judgement meeting one of the two following definitions:

o Exceptional Performance - A display of initiative or judgement that exceeds procedural requirements to mitigate emergency conditions.

o Noteworthy Performance - A display of procedural initiative or judgement that is performed with a high degree of efficiency to mitigate an emergency condition.

Part IV: Corrective Action Records: Unfavorable findings divided by severity as defined below, as well as by those already closed out (normally involving isolated personnel errors) and those still requiring

action {normally involving needed equipment, procedure, software, trauung, etc., fixes).

In categorizing the severity of exercise findings, the potential significance of the concern under investigation should not be minimized by the possibly limited scope of the scenario. The concern should be extrapolated out to determine the potential total impact under a worse case real event situation:

Major Deficiencies: Observed inadequacies that could cause a finding that emergency preparedness is not adequate to provide reasonable assurance that appropriate protective measures can be taken to protect the health and safety of the public, and/or that of emergency workers.

b. Mnor Deficiencies: Findings which have emergency response impact but do not adversely impact the health and safety of the general public or of emergency workers.

c. Items of Clarification: Findings which do not have an adverse impact on health and safety, but would enhance an organization's level of emergency preparedness.

Part V - Informational Observations: Major points that w orant consideration but do not meet the criteria for unfavorable findings, e.g., efforts directed by a center staff did not appear to be in the most efficient sequence. These do not require resolution or tracking. For critiques of exercises and the larger drills, the critique may simply make reference to a separate report disseminating informational observations to interested parties.

Part VI -

Participants:

A listing of aH recorded participants who are to receive credit for the activity.

Paxt VII- Minority Opinion - In the unlikely event some evaluators/

controllers take exception to the content of the report, their minority opinion will be stated here.

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SPEChV EVALUATOR/CONIROLLER INSTRUCTIONS EXERCISE 93 A. CONTROL Player Response: Players at all of the different emergency centers are to interact with one another as if the simulated situations actually exist.

However, communications that would be initiated to individuals and agencies not actually playing in the Exercise, e.g., BPA, Hanford Patrol, National Weather Service, etc., are to be made to controllers in the control cell who will role play the parts.

2. Coordination: Emergency Planners or lead controllers in each of the emergency centers will be linked by telephones set aside for that purpose. This will be used for exercise control coordination, such as to resolve p- blems or make needed scenario deviations. A controller commur. -ns listing is attached.

3. Player Participation: For additional players the current players want to use who would not normally be at the plant under the given exercise conditions, inject a one-hour response delay time before the additional player(s) are allowed to be used.

B. RECORD KEEPING Logs: Evaluator log forms are at the "Evaluator Logs" tab. Also, you may write observations on the message forms, anticipated response forms or data sheets.

2. Times: Accurate times are important. Call the Simulator at X-8942 to set your watch to the official exercise time. Do this after hearing the PA announcement that the Exercise has started to ensure you will recieve an answer on the phone.

3.

Participants:

Player and Controller/Evaluator listings for your center should be documented for "credit" purposes. Special attendance records should be signed by each player during the drill. These records are to be turned in at the formal critique work sessions.

r~voIu~r.E osSERV~moN WORKSHEEr Exercise 93 A. Favorable Finding:

UI&AVO&LBIE OBSERVATION WORKSHEET XXKKCISE93 A. Relevant Objectives (List from Objectives section of the Scenario Package):

B. Findings (who, what, when, where, consequences, violation) ALL MUST BE COMPLETED WHO?:

WHAT?:

VIOLATION REFERENCE? fifdifferent orin addition to section A, above)

WHEN?:

WHERE?:

CONSEQUENCES?:

PERSONNEL CONTACTED TO VERlFY ACCURACY OF FINDlNG? (List who):

(Writ on the back of this formif you need more spaceJ C. Cause(s) from the Basic Root Cause Determination (in Section III C of the scenario package):

WHY?:

D. Feedback (complete for ~r~nZl performance issues identifiedin the Basic Root Cause Determinatfon):

Involved personnel briefed on findings? Yes; No.

Root Cause analysis attached? Yes; No.

DIGLL & EXERCISE ROOT CAUSE ANALYSIS Y SHEET Initial Information Collection Pertinent Data - Identify sources of data e.g. - center logs, team logs, procedure excerpts, personal statements, etc. Attach the data to this summary sheet.

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DRILL/EXERCISE UINFAVO&&IE OBSERVATION ROOT CAUSE ANALYSIS GUIDE A. General The cause of incorrect personnel task performance(s) will be included for each unfavorable observation. Ifsimple questioning of the player(s) involved fails to identify, the cause(s), then a Category 3 type root cause analysis (RCA) willbe conducted by and evaluator/controller in accordance with this guide and attached to the unfavorable observation.

B. Process

l. Initiate the Root Cause Analysis Summary Sheet (Enclosure I) by filling in the blanks for your name and the unfavorable observation number ~

2. Gather the information necessary to complete the Initial Information Collection and Pertinent Data Blocks on the enclosure. Question involved personnel and complete personal statements on Personal Statement Forms (Enclosure 2).

3. Using the information gathered, determine root cause(s) of the problem by application of the basic root cause determination method on the supplied copy of the Root Cause Tree. Do nor hesitate to collect additional infonnasion if necessary to validare your findings.

For the problem being analyzed, determine if the primary cause ~

is equipment,-personnel, or procedures (Secrion A of the tree).

b. For each area in Section A of the tree identified as a primary cause, determine which subcategory (Secrion B of the tree) led to the primary cause. To do this, a list of questions (Section C of the tree) has been developed.

Use your own numbering system... Just start with number 1, number 2, etc.

Although the root cause(s) may be determined to be realated to only one of these primary categories, all three should be considered initially to ensure complete coverage. Without complete consideration of the three categories, AILroot causes may not be identmed.

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C. For any question in Section C of the tree which is answered "Yes", it is a root cause. Any root cause shall be circled for easy identification.

Limiting root cause(s) to those identified in the tree will aid in the trending of similar problems.

List at the bottom of the Root Cause Analysis Summary Sheet {Enclosure 1) the names of personnel, besides yourself, who assisted in performing the RCA. List the completion date of the RCA.

5. Attach the completed Root Cause Analysis Summary Sheet (Enclosure I),

accompanying Personal Statement Forms tEnclosure 2), and copies of any other relevant documentation, e.g., centerlteam logs, etc., to the unfavorable observation critique worksheet.

Enclosures:

1. Root Cause Analysis Summary Sheet

2. Personal Statement Form

PLAYER/OBSERVER INSTRUCTIONS EXERCISE 93 A. Player's Rules

1. General Instructions for all players:

a. 'layer designation: Players should be selected with several criteria in mind.

1) All emergency response personnel should be available to attend a players meeting.

2) Players need to be pre-designated for this exercise so the auto-dialer database can be set up to call in the first shift personnel and the designated second shift personnel can be contacted regarding shift change time.

3) Only the correct number of players will be allowed to play per the Emergency Response Organization Assignment List. Credit will only be given for those personnel who play specific positions.

4) All emergency response personnel should rotate as drill/exercise participants so that an individual has served in his/her position(s) or as a Controller/Evaluator at least once every two years.

b. Exercise

1) Exercise pager carriers, carry the pager for your position.

2) When you arrive at your center and are designated to remain and be a player, sign in on the exercise attendance record. Put on the player badge and arm band.

C. Interactions with evaluators and controllers:

1) Answer any questions and ask questions ifyou are not clear on controller inputs.

2) React as if their scenario inputs are real.

3) Refer any disagreements up management channels.

4) Controllers may interrupt the play for essential reasons.

d. Safety FoQow procedures and safety rules. Use safeguards and safety equipment provided. Make safety a primary responsibility.

2) Realize safety takes precedence over all other requirements.

3) In case of accident or injury, know and follow existing procedures. Realize controllers may intervene to stop the play to terminate an unsafe act.

e. Realism

1) Complete all required caGs to non-participating outside agencies by calling the exercise control cell, where a controller will simulate the party whom you need to reach. Telephone numbers and instructions unique to the exercise are provided as part of this section. Use the Emergency Phone Directory for other emergency personnel and center numbers.

2) Play out all actions as much as possible in accordance with your emergency plan and procedures as if it were a real emergency.

3) Realize a need to respond to an actual emergency will take priority over the exercise play.

Exercise administrative items:

Start and conclude PA announcements, radio transmissions and phone conversations with the statement "This is an Exercise".

A shift change will be demonstrated.

3) At the conclusion of the Exercise, remain in place for a i

debriefing and Facilitative Post-Exercise critique by the Emergency Planner assigned to the center or the Lead ControQer-this includes first and second shift personnel. Fill out and submit After Action Reports with specific comments on the exercise.

4) Snacks will be provided for both shifts.

The NRC has new rules regarding the critique process. These rules were printed in the February 18, 1992 Federal Register. The rules are now in effect.

2. Additional instructions for JIC and EOF players:

a. Mutual aid response may NOT be demonstrated.

3. Additional instructions for Plant and EOF Players.

a Realism:

1) Play out the scenario as if it were real!!

2) Minimal simu1ation will be allowed. Realistic detailed responses will be required, especially by Plant reentry teams.

Describe verbally to your assigned Controller/Evaluator any action taken that must be simulated.

3) Real time exercise data will be available on the computer monitors in the EOF and the TSC. The data can be viewed on the display ternunals and printed out on local printers.

4) Critical data (eg - Plant Parameters) for the exercise that is not on the display terminals will be available from the controllers in the centers.

S) Physical manipulations of plant operational equipment and systems shall be simulated, but must be described verbally to the controller.

6) PA system usage both in-plant and the EOF shall be restricted to exercise activities, control room functions, normal operations activities or actual emergency activities, Pi.e., minimize personnel paging).

7) At exercise termination:

o All centers/kits shall be returned to full pre-exercise emergency preparedness status.

o SCBA bottles that were used shall be replaced with full bottles. The SCBA's shall be inspected, cleaned and placed back in their emergency locations prior to securing from work for the day.

c. Radiation levels:

1) Act as ifradiation levels are actually present.

2) Ifrequired by the simulated conditions and procedures, each radiation worker will need to don and continue using anti-c's throughout each of his/her deployments. There is one exception:

Field monitoring teams will not wear protective equipment ogthe Hanford Reservation.

3) For the exercise, respirators are to be donned, ifand when required by simulated conditions and procedures; The foHowing conditions apply:

o Each Player, if & when required, is to demonstrate

- Donning an SCBA

- Exhausting (breathing out) one complete bottle

- Changing to a fresh bottle o APer having demonstrated the three items above, the Player willnot be required to wear an SCBA in subsequent deployments, however-

- Players communicating by either radio or telephone shall simulate communications difhculties (ie - put on a face mask to mme htslher voice)

- When dispatching Players, ample delay is to be built in to simulate donninglun-donning activines (ie - putting on

& taking ogthe SCBA)

- The same Players shall not be repeatedly used on the various dispatched teams in order to avoid demonstration of SCBA use by other Players.

o SCBA's may be used by bearded personnel (ie - There is if no need to shave you are required to wear an SCBA in the Drill)

4) Protective clothing from normal plant supply should be used to reduce replacement in emergency kits.

5) Silver zeolite cartridges should not be used to sample for radioiodine. Use Charcoal cartridges.

4

6) To maintain separation from normal samples, if any samples are provided to the counting room at the plant or EOF, they should be marked "Exercise Sample" as appropriate. These samples and analytical results will be collected by the controller at the end of the exercise. Samples will not be "spiked."

Additional instructions for Plant Players:

a0 Player designation:

I) Accountability, although performed, will not be an objective of this exercise.

2) The simulator will be used for the exercise to portray the Control Room. Control Room players will be predesignated.

They, unlike other players, will be notified of the Exercise start date and time. They are to report to the Simulator prior to the start of the Exercise.

b. Exercise administrative items:

I) Exercise activities shall be conducted such as to minimize the affect on normal plant operating activities. The normal plant access points will remain functional during this exercise.

2) All routine security procedures remain in effect.

C. Security I) Some security officers will be dedicated to exercise participation.

2) Ifrequired, mockup dosimetry at the PAP and AAP will be transported (evacuated) in lieu of real dosimetry.

B. Observer's Information Identification: Potential observers must contact the exercise coordinator no later than the week prior to the exercise for clearance to observe the exercise.

Those willing to accept an evaluator's role will then have access to the area(s) to be evaluated. Designated evaluators will be committed to the schedule of controller/evaluator orientations and work sessions.

2. Observers'ules: Observers are expected to observe the following rules of emergency exercise observer etiquette:

Remain in designated observer areas within each emergency center.

Do not ask questions of the players.

Do not distract the players, evaluators or controllers by loud talhng, etc.

Adhere to any posted no smoking signs or similar prohibitions.

3. Exercise coordinators who may be contacted for evaluator duties, observer clearance or other particulars on the emergency exercise:

Plant & EOF Centers RL Utter 377-8330 Plant 8c EOF Centers TE Chrisler 377-8300 Plant 8c EOF Centers PT Bagan 377-8643 Joint Information Center JD Houchins 372-5116

SPECIAL PLAYERS TELEPHONE USE INSTRUCTIONS XXRRCISE 93 During the Exercise, the Supply System emergency centers will be fully activated.

State and County Emergency Operations Centers (EOCs) will be participating as Control Cells. Exercise communications and coordination should take place between the players in the Supply System centers and the applicable controllers at the EOCs.

n m 3 n n um EMD Decision Maker 206-923-4956 582-5487 DOH Decision Maker 206-923-4950 582-2813 Ag Decision Maker 206-923-4958 DOH Support 206-923-4960 FNF Planners 206-9234954 206-459-4133 If realistic play of the exercise requires you to contact someone at another agency not participating in the drill, e.g., General Electric, Coast Guard, National Weather Service, Kadlec Hospital staff, etc., use the appropriate number listed below.

Controllers will then role-play as representatives of the respective agency, and may have scenario information essential to your needs. When calling one of the listed numbers, specify the agency you wish to reach, e.g., "Zunis is the REM calling for the

¹tional Weather Service.

Players from: Call: For.

Supply System Centers 372-5440 Any other agency 372-5686 Any other agency B/F Counties EOC 372-5201 Any other agency WA State EOC 372-5247 Any other agency

2. The PSF Simulator will be used to portray the Control Room, use the following corresponding numbers to contact the staff there:

Control Room Actual Control Simulator Position Room Number Number to Call Shift Manager 2278 8978 Contxol Room Supv. 2348 8948 Shift Tech. Advsr. 2083 8103 Reactor Operators 2242 8942 Tag Desk 2658 8958 Outside Line 377-2691 377-8991 Fax Line 209 217 Dial-Up 309 317

3. Do Not Use the Emergency Notification System (EKS) phone in any emergency center. In order to simulate making NRC communication, call the Control CeH at 377-8095.

4. Do Not Vse the Health Physics Network (HPN) telephone system. This applies to the TSC and many of the Centers in the EOF. CaH the Control CeH at 377-8643.

5. Drill Emergency calls that would in reality be made on 2222 to the control room and EOF Communications Center should be made on 8832 (Simulator).

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DKFINl'1"lONS/ACROINVLVfS EXEC.CISE 93 AFFF Aqueous Film Forming Foam AG Agriculture, Department of Washington State AAP Alternate Access Point ARC American Red Cross, ARM Area Radiation Monitor ATWS Anticipated Transient Without Scram B Backup BOP Balance of Plant BPA Bonneville Power Administration CAC Containment Atmosphere Control CAS Central Alarm Station CCTV Closed Circuit Television CEP Containment Exhaust, Purge Ci Curie CN Containment Nitrogen gnerting System)

CR Control Room CRD Control Rod Drive CSP Containment Supply, Purge CVB Containment Vacuum Breaker DBA Design Basis Accident DEN Department of Emergency Management DG Diesel Generator DGB Diesel Generator Building DOE Department of Energy DOT Department of Transportation, Washington State DSHS Department of Social and Health Services, Washington State DW Drywell EBS Emergency Broadcast System ECCS Emergency Core Cooling System EDPS Emergency Dose Projection System EFPD Effective Full Power Days EFSEC Energy Facility Site Evaluation Council, Washington State EO Equipment Operator EOC Emergency Operations Center EOF Emergency Operations Facility EOFCC Emergency Operations Facility Communications Center EPIO Emergency Public Information Officer EPIP Emergency Plan Implementing Procedure EPZ Emergency Planning Zone ERP Elevated Release Point NNRoeAFhmosje~

EWAC Emergency Worker/Assistance Center FAX Facsimile FEMA Federal Emergency Management Agency FN Fan FRTS Fire Remote Transfer Switch GPM Gallons Per Minute Hg Hydrogen HCC Headquarters Communication Center HP Health Physics HPCS High Pressure Core Spray HVAC Heating, Ventilation, and Air Conditioning ISAAC Instrumentation and Control JIC Joint Information Center KI Potassium Iodide Thyroid Blocking Agent KV Kilovolt LLEA Local Law Enforcement Agency LOCA Loss of Cooling Accident LOOP Loss of Offsite Power L/0 Lockout (Circuit Breaker)

LPCI Low Pressure Coolant Injection LPCS Low Pressure Core Spray NREM Millirem MPF Multipurpose Facility MS Main Steam gine)

MSIV Main Steam Line Isolation Valve MSS/RV Main Steam Safety/Relief Valve MUDAC Meteorology and Unified Dose Assessment Center NRC Nuclear Regulatory Commission Np Nitrogen NS4 Nuclear Steam Supply Shutoff System Og Oxygen OACC Offsite Agency Coordination Center OCB Oil Circuit Breaker OOS Out of Service OSC Operations Support Center PAD Protective Action Decision PAG Protective Action Guide PAP Primary Access Point PAR Protective Action Recommendation PASS Post-Accident Sampling System PED Plant Emergency Director PEO Patrol (Hanford) Emergency Operations PI Pressure Indicator PIO Public Information Officer

PS Pressure Switch PSIG Pounds Per Square Inch PUD Public Utility District Quad Quadrant, evacuation RACES Radio Amateur Civil Emergency Service RB Reactor Building RCIC Reactor Core Isolation Cooling RCPB Reactor Coolant Pressure Boundary REA Reactor Exhaust Air REM Radiological Emergency Manager RFP Reactor Feed Pump RHR 'L Residual Heat Removal Richland Operations; Department of Energy RM Recovery Manager ROA Reactor Outside Air RPM Radiation Protection Manager RPS Reactor Protection System RPV RX Pressure Vessel RRA Reactor Recirculating Air RW Rad Waste Building RX Reactor S Startup SAS Secondary Alarm Station SC Suppression Chamber SDC Security Decision Center SDV Scram Discharge Volume SECON Security Condition SFP Spent Fuel Pit SGTS Standby Gas Treatment SLC Standby Liquid Control SM Shift Manager SP Suppression Pool SSDC Supply System Decision Center SSW Standby Service Water TDC Technical Data Center TGB Turbine Generator Building TK Tank TR Transformer TSC Technical Support Center USCG United States Coast Guard V Valve VDC Volts Direct Current WC Window Closed, Gamma, Radiation Detection Instrument WEIC Washington Emergency Information Center

WNP-2 Washington Nuclear Project Number 2 WO Window Open, Beta and Gamma, Radiation Detection Instrument WSP Washington State Patrol WW Wetwell

CONTROLLER XHFORMATION SCENARIO MESSAGES INDEX MESSAGE NO MESSAGE ABOUT START EXERCISE 93 BPA REQUEST WNP-2 STAY ON LINE DEFAULT MESSAGE FOR SM AND PED ABOUT WNP-2 STAYING ON LINE DEFAULT MESSAGE FOR ALERT BPA REPORTS ON LOSS OF 230 KV DEFAULT MESSAGE FOR GENERAL EMERGENCY DEFAULT MESSAGE FOR OPS MANAGER AND PED ABOUT LPCS PUMP BREAKER DEFAULT MESSAGE ABOUT SHIFT CHANGE TERMINATE EXERCISE 93

I 4 WASHlNGTON SUPPLY SYSTEM CONTROLLER INFORMATION tljbLlC tOWbb SCENARIO MESSAGES DRUB NO. PAGE EXERCISE 93 1OF1 MESSAGE NO. REAL TIME OF: DRILL TlME OF:

1 0330 0000 CONTROLLER LOCATlON CONTROL ROOM (SIMULATOR) 8L EOFCC CONTROLLER NAME ORGANIZATION MESSAGE FOR: ALI. PERSONNEL MESSAGE FROM: CONTROL ROOM (SIMULATOR) & LEAD EOFCC CONTROLLERS MESSAGE:

Please make the following announcements on the Plant and PSF PA's.

THIS IS AN EXERCISE... THIS IS AN EXERCISE.

KKRCISE 93 IS NOW IN PROGRESS. PERSONNEL NOT IDERIIFIED AS PARTICIPANTS IN THE EXERCISE SHOULD CONTINUE %9TH THEIR NORMAL V(ORE SCHEDULE.

h THIS IS AN EXERCISE... THIS IS AN EXERCISE.

REFERENCE GENERAt. DATA SHEETS:

"~" "' "'" >>h 4 'h" h '>>" P h%'MtP>hh 8 w' >h REPEAT THIS PA ANNOUNCEMENT APPROXMATELY EVERY HOUR.

4 WASIILNOTON tVbLIC tOWbb SUPPLY SYSTEM COXIROLLEK1NFORMATION SCENARIO MESSAGES DRILL NO. PAGE EXERCISE 93 1 of MESSAGE NO. REAL TIME OF: DRILL TIME OF:

0345 CONTROLER LOCATION CONTROL CELL (BPA)

CONTROLER NAME ORGANIZATION MESSAGE FOR: CONTROL ROOM SHIFT MANAGER MESSAGE FROM: BPA (CONTROL CELL)

MESSAGE:

" THIS IS AN E3CERCISE... THIS IS AN E3KRCISE" This is Dittmer in Vancouver, we request WNP-2 stay on line as long as possible. You are one of the few power sources left on line in the region following the earthquake. We would like you at maximum power until additional sources of power are returned to service.

"THIS IS AN EXERCISE... THIS IS AN EXERCISE" REFERENCE GENERAL DATA SHEETS:

Ifit appears the Shift Manager is going to shut down the plant, the controller in the Simu1ator will give the default message (message sheet 3).

4 WASRlNGTON PIISLlC POWhh SUPPLY SYSTEM CONTROLLl&INFORMATION SCENARIO MESSAGES DRILL NO. PAGE EXERCISE 93 't of:I MESSAGE NO. REAL TIME OF: DRILLTIME OF:

0346 CONTROLLER LOCATION CONTROL ROOM (SIMULATOR) - TSC CONTROLLER NAME OR QANI7ATION MESSAGE FOR: SHIFT MANAGER - PLANT EMERGENCY DIRECTOR MESSAGE FROM: CONTROL ROOM (SIMULATOR) AND TSC CONTROLLERS MESSAGE:

"THIS IS A DEFAULT MESSAGE" For the purposes of the Exercise the plant is to remain on line as requested by the BPA even if it is decided shutting it down would be more conservative.

"THIS IS A DEFAULT MESSAGE" REFERENCE GENERAL DATA SHEETS:

This message is to be read to the Shift Manager and/or PED ifit is decided to shut down the plant after the first earthquake. The plant must remain on line until the second earthquake which will automatically

. shutdown the plant.

a < 4 ~ 'L ~ ~ << ~

4 WASIllIIGTON tVBLlC tOWBB SUPPLY SYSTEM CONTROLLER INFORMATION SCENAIUO MESSAGES DRILL NO. PAGE EXERCISE 93 1 of 1 MESSAQE NO. REAL TIME OF: DRILL TIME OF:

0355 CONTROLLER LOCATION CONTROL ROOM (SIMULATOR)

CONTROLLER NAME ORGANIZATION MESSAGE FOR: SHIFT MANAGER MEssAGE FR0M: CONTROL ROOM (SMULATOR) CONTROLL'ER MESSAGE:

"THIS IS A DEFAULT MESSAGE" For the purposes of the Exercise the plant is to declare an AL~EX based on "Reactor Coolant Pressure Boundary lines fail to isolate when design logic met".

"THIS IS A DEFAULT MESSAGE" REFERENCE GENERAl. DATA SHEETS:

This message is to be read to the Shift Manager if it appears the Operating crew is not going to declare ~

an ALERT based on failure of RCIC steam isolation valves failing to close with an isolation signal present..

4 WASRlNGTON PlIbLlC POWSR SUPPLY'SYSTEM CONTROLLER INFORMATION SCENARIO MESSAGES DRILL NO. PAGE EXERCISE 93 1of1 MESSAGE NQ. REAL TIME OF: DRILL TIME OF:

0640 CONTROlLER LOCATION CONTROL CELL (BPA)

ORGANIZATION MESSAGE FOR: SHIFT MANAGER - PLANT EMERGENCY DIRECTOR MESSAGE FROM: BPA (CONTROL CELL)

MESSAGE:

"THIS IS AN'EXERCISE... THIS IS AN EXERCISE" The 230 KV lines from the ASHE substation to WNP-2 are down due to the earthquake. The prognosis is 12 - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before crews will be available to repair and another 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for lines to be re-energized.

"THIS IS AN EXERCISE... THIS IS AN EXERCISE" REFERENCE GENERAL DATA SHEETS:

The second earthquake will occur at 0630 at which time 230 KV will be lost . The Shift Manager or PED may contact BPA before BPA contacts them. This message is valid anytime after 0630.

WASRlNOTON PIIbL1C tOWbb

'S SUPPLY SYSTEM CONTROLLl<&INFORMATION SCENARIO MESSAGES DRILL NO. PAGE EXERCISE 93 1 of 1 ME88AQE NO. REAL TIME OF DRILL TIME OF:

6 0720 CONTROLLER LOCATION CONTROL ROOM (SllVIULATOR)- TSC CONTROLLER NAME OR QANIZATION MEssAGE FoR: SHIFT MANAGER - PLANT EMERGENCY DIRECTOR MEssAGE FRCM: CONTROL ROOM (SIMULATOR) AND TSC CONTROLLERS IVIESSAGE:

"THIS IS A DEFAULT MESSAGE" For the purposes of the Exercise the plant is to declare a E based on "Loss of two barriers and potential loss of the third".

"THIS IS A DEFAULT MESSAGE" REFERENCE GENERAL DATA SHEETS:

6>+'xXX~ x >+@~Akgb ><(<p~<~ x+j) i yzgMgc:"v 'p)R CONrROQM ONLYPr~ S+g<~aA~'.'4g~ws'"+V~&7v ~vs%'qi"~4~c'jul "@@VS'+~g6agg'""'"gP

~

This message is to be read to the Shift Manager and PED ifit appears the PED is not going to declare a GEt tERAL EMERGENCY with a RCIC steam line break into the reactor building and inadequate core coolin g .

4 WASHlNGTON l'IIbLIC POWbl SUPPLY SYSTEM CONIROLLXR INFORMATION SCENARIO MESSAGES DRILL NO. PAGE EXERCISE 93 1of1 MESSAGE NO. REAL TIME OF: DRILL TIME OF:

7 0706 CONTROLLER LOCATION TSC CONTROLLER NAME ORGANIZATION MESSAGE FOR: OPERATIONS MANAGER - PLANT EMERGENCY DIRECTOR MESSAGE FROM: LEAD TSC CONTROLLER MESSAGE:

"THIS IS A DEFAULT MESSAGE" For the purposes of the Exercise, regardless of any additional trouble shooting to be done, tell the OSC to reset the 86 lockout relay on LPCS pump breaker when the Control Room is ready.

"THIS IS A DEFAULT MESSAGE" This message is to be read to the Operations Manager and Plant Emergency Director as soon as the initial report from the OSC about the LPCS pump breaker comes in.

4 WASlllNGTON tlIBL1C tOWBB SUPPLY'YSTEM CONTROLLER REFORMATION SCENARIO MESSAGES ORILL NO. PAGE EXERCISE 93 1OF1 MESSAGE NO. REAL TIME OF: DRILL TIME OF:

1000 0000 CONTROLLER LOCATION CONTROL ROOM (SIMULATOR) 5 EOFCC CONTROLLER NAME ORQANIZATION MESSAGE FOR: ALLPERSONNEL MESSAGE FROM: CONTROL ROOM (SBGJLATOR) k LEAD EOFCC CONTROLLERS MESSAGE:

Please make the following announcements on the Plant and PSF PA's.

THIS IS AN EXERCISE... THIS IS AN E3CERCISE.

EXERCISE 93 IS NOW TERMDVATED. PERSONNEL IDENIIFIEDAS PARTICIPANTS IN THE DRILL SHOULD RETURN TO THEIR EMERGENCY CEDER TO CONDUCT POST EXERCISE CRI'HQUE.

THIS IS AN EXERCISE... THIS IS AN EXERCISE.

REFERENCE GENERAL DATA SHEETS:

tv"'Qp4~gp~~c~c'jc~~ggo &%ÃH+yIlg:+vp> v'xx oxpg<CONTROggg gE ONLY<4y+ox>+c@c'jggg gÃg'j/Algxx@srgggc xx >+g5y>ooo.cocc o oI

THIS PAGE IS PURPOSEL Y BLANK

CONTROLLER INFOR&QRTION GENERAL DATA SHEET INDEX SHEET NO INFORMATION APPLIES TO LOSS OF SM-8 RCIC-V-8 FAIL TO CLOSE RCIC-V-63 FAIL TO CLOSE RCIC EXHAUST RUPTURE DISK RCIC STEAM LINE BREAK HPCS DIESEL FAILURE RHR-V-42A FAIL TO OPEN LPCS PUMP BREAKER

WASHlNQTOI4 tUbLIC tOWhh

'IN SUPPLY'YSTEM CONTROLXkR INFORMATION GE%WAL DATA SHEET DRILL NO. PAGE EXERCISE 93 1of1 SHEET NO RESPONSIBLE CONTROLLER (LOCATION/

CR (S1MULATOR ) / SM-8 REAL TIME OF: TO: DRILL T1ME OF: TO:

0340 ASSOCIATED WITH MESSAGES INFORMATION APPLIES TO LOSS OF SM-8 At 0340 breaker 8-3 will trip and lockout, de-energizing SM-8. The Control Room will receive a fire alarm ("RW BLDG 467'LECT SWGR AREA 2").

An Operator will be dispatched to investigate the cause of the fire alarm and the loss of SM-8.

Local indications will be:

Smoke in SM-8 room but no sign of an active fire.

Overcurrent relays on breaker 8-3 will have picked up (E-RLY-51/8/3).

Lockout relay on breaker 8-3 will have picked up and will not reset (E-RLY-86/8/3).

Further investigation will reveal that two to the phases of buswork in SM-8 are severely damaged possibly by some foreign object falling across them during the earthquake.

WASHlNGTON tlIbL1C tOWbh SUPPLY SYSTEM CONTROLLER INFORMATION GXZGRAL DATA SHEET DRLL NO. PAGE EXERCISE 93 1of1 SHEET NO. RESPONSIBLE CONTROLLER II.OCATIOPII 2 RCIC-V-8 REAL TIME OF: TO DRILL TIME OF: TO:

0340 ASSOCIATED WITH MESSAGES INFORMATION APPLIES TO RCIC-V-8 FAILING TO COMPLETELY CLOSE At 0340 the earthquake will cause an isolation signal in the RCIC system. RCIC-V-8 will get a close signal but will fail to go completely closed.

Control Room (Simulator) indication wilt be a valid isolation signal, RCIC-V-8 position indication showing both red and green tights illuminated (mid position) and GDS showing RCIC-V-8 still open.

Local indication (simulated) will be RCIC-V-8 in mid position with a visibly bent stem. All attempts to manually close RCIC-V-8 will fail due to the stem binding. In addition the valve will not re-open either.

Since the upstream isolation valve (RCIC-V-63) inside of containment will not close the valve cannot be disassembled for repair.

RCIC-V-8 must stay open for the duration of the Exercise. t

4 WASHlNGTON SUPPLY SYSTEM CONTROLS& INFORMATION l'lIbLIC POWBB GENITAL DATA SHEET DRILL NO. PAGE EXERCISE 93 1of1 SHEET NO. RESPONSISLE CONTROLLER g,OCA TIOIVI RCIC-V-63 REAL TIME OF: TO: DRILL TIME OF:

0340 ASSOCIATED WITH MESSAGES INFORMATION APPLIES TO RCIC-V-63 FAILING OPEN DUE TO LOSS OF POWER At 0340 an earthquake will cause a loss of SM-8 which causes power to be lost to IVIC-8BA which is the power supply to RCIC-V-63. This valve will fail as is on a loss of power which will be open.

This valve will be needed for isolation and an attempt may be made to connect an alternate power supply to the supply breaker for RCIC-Y-63 on MC-8BA. If this is attempted the crew will be allowed to simulate hooking up the power supply and when the attempt to close the valve is made in the Control Room (Simulator) the breaker will trip on overload and not be able to reset.

This valve will not be able to close until entry can be made into containment and the valve closed manually.

WhBMIHGTON bllbLIC POWBIL SUPPLY SYSTEM CONTROLLXR INFORMATION GENERAL DATA SHEET DRILL NO. PAQE EXERCISE 93 1 Qf 1 SHEET NO. RESPONSISLE CONTROLLER (LOCA TIONJ RCIC EXHAUST RUPTURE DISK REAL TIME OF: TO: DRILL TIME OF: TO:

0340 ASSOCIATED WiTH MESSAGES INFORMATION APPLIES TO FAILURE OF RCIC EXHAUST RUPTURE DISK At 0340 an earthquake occurs which causes the failure of RCIC Exhaust Rupture Disk RCIC-RD-1.

The RCIC system is being run for its quarterly surveillance and the failure of the rupture disk initiates an isolation signal.

Control Room (Simulator) indications are:

Annunciator F601.A4 3-8 "RCIC TURBINE EXH DIAPHRAGM PRESS HIGH" Annunciator P601.A11 4-1 "RCIC TURBINE EXH DIAPHRAGM PRESS HIGH" Locally if maintenance crew wants to inspect rupture disk (simulate) they will find that the disk has a hole in the diaphragm.

4 WASRlNGTOII PlIBLIC POWER SUPPLY SYSTEM CONTROLLER INFORMATION GENERAL DATA SHEET DRILL NO. PAGE EXERCISE 93 1of1 SHEET NO. RESPONSIBLE CONTROLLER (LOCA TIONJ 5 RCIC STEAM LINE BREAK NEAR RCIC-V-8 REAL TIME OF: TO: DRILL TIME OF: TO:

0630 ASSOCIATED WITH MESSAGES INFORMATION APPLIES TO RCIC STEAM LINE BREAK At 0630 a'second earthquake occurs which causes the RCIC steam line down stream of RCIC-V-8 to begin leaking (see attached drawing). This leak will propagate to a complete 4 inch line rupture within two minutes.

Control Room (Simulator) indications are:

Annunciator P601.A12 6-2 "LEAK DET RWCU/RCIC PIPE AREA TEMP HIGH" Annunciator P601.A2 1-1 "LEAK DET RCIC PIPE ROUTING AREA TEMP Hl-Hl" Annunciator P601.A3 1-8 "LEAK DET RCIC PIPE ROUTING AREA TEMP Hl-Hl" Increasing Area Radiation Monitor readings on:

ARM-RIS-7 TIP ROOM ARM-RIS-4 CRD AREA EAST ARM-RIS-8 SGT FILTER AREA Annunciator P602.A5 3-1 "REACTOR BLDG RAD HIGH" lf with a maintenance crew after 0630 in the area of the RCIC steam line break, inform crew of earthquake motion the sound of escaping steam and steam cloud forming above TIP room. The maintenance crew should evacuate the area and inform Control Room (Simulator), TSC or OSC.

4 WASII1NOTON PIISI IC POWbb SUPPLY'SYSTEM CONTROLI3~2L INFORMATION GENERAL DATA SHEET PAGE EXERCISE 93 1of1 SHEET NO. RESPONSISLE CONTROLLER (LOCA TION/

HPCS DIESEL FAILURE REAL TIME OF: TO: DRILL TIME OF: TO:

AFTER 0630 ASS OCIATEO WITH MESSAGES INFORMATION APPUES TO HPCS DIESEL FAILURE After 0630 the HPCS diesel which is running due to an auto start signal trips on overspeed.

Control Room (Simulator) indications are:

Annunciator P601.A1 3-1 "DIESEL ENGINE OVERSPEED" Annunciator P601.A1 3-3 "DIESEL ENGINE TRIP" Local DG-3 control panel indications are:

Annunciator DG-3 1-2 "UNIT LOCKOUT" Annunciator DG-3 5-2 "OVERSPEED TRIP" The cause of the overspeed condition will be a damaged connection between the magnetic speed pickup and the governor system. The loss of speed signal will cause the governor to speed up the diesel causing the overspeed trip.

The maintenance crew'and /or operator will reset the overspeed trip but on the subsequent start the diesel will overspeed again.

Until the damaged connection is repaired the diesel will not run.

4 WASH1NGTON PURLIC POWRR SUPPLY SYSTEM CONIROLLEK INFORMATION GENZRAL DATA SHEET DRILL NO. PAGE EXERCISE 93 1of1 SHEET NO. RESPONSIBLE CONTROLLER /LOCA TION/

7 RHR-V-42A REAL TIME OF: TO: DRILL TIME OF: TO:

0705 ASSOCIATED WITH MESSAGES INFORMATION APPLIES TO RHR-V-42A FAlLING TO OPEN At approximately 0705 the operating crew in the Control Room (Simulator) will attempt to open RHR-V-42A to inject water to the Reactor Vessel. The valve will fail to open from the control switch on P601 due to the valve disk jammed into the seat. Radiation levels in the area of RHR-V-42A will be to high to send an operator to open the valve manually.

If an Operator and/or Maintenance Crew is sent to the valve to open it manually, the valve wilt not open.

SUPPLY SYSTEM CONTROLLER INFORMATION GENERAL DATA SHEET DRILL NO. PAGE EXERC1SE 93 1of1 SHEET NO. RESPONSIBLE CONTROLLER II.OCA TIOIVI 8 LPCS PUMP BREAKER (SM-7)

REAL TIME OF: TO: DRILL TIME OF: TO:

0705 INFORMATIONAPPUES TO TRIP OF LPCS PUMP BREAKER Depending on the operating crews decision the LPCS pump may be running with its injection valve closed or the pump may be off when it is time to use the LPCS system for injection to the Reactor Vessel.

If the pump is running and the injection valve is opened the pump will trip.

lf the pump is off and the pump is started it wilt subsequently trip.

Control Room (Simulator) indicators are:

Annunciator P601.A3 3-2 "LPCS PUMP P-1 OVERLOAD" Annunciator P601.A3 4-2 "LPCS PUMP P-1 TRIP" Local indications on the LPCS pump breaker at SM-7 are:

LPCS-RLY-51X/P1 tripped LPCS-RLY-86/P1 tripped The cause of the pump trip is a spurious overcurrent relay trip. When a maintenance crew and/or operator is sent to SM-7 to investigate there will be no apparent cause of the overcurrent condition. Ensure the maintenance crew and/or operator report findings to the OSC.

When the OSC reports to the TSC its findings a DEFAULT MESSAGE will have the TSC tell the OSC to reset the 86 lockout relay when the Control Room (Simulator) is ready.

When the 86 lockout is reset the LPCS pump breaker will close and the pump will run.

'A SUPPLYINFORMATION WASlllNGTON POSLLC POWER CONTROLLER SYSTEM GENERAL DATA SHEET DRILL No. EIIercise 93 PAGE SHEET No. REsPONsisLEcoNTROLLERILocATIONI Control Room (Simulator), MUDAC 5 TSC REAL TIME OF: 03:00 To: 12IOO DRILL TIME OF: 00:00 To: 09:00 ASSOCIATED WITH MESSAGES INFORMATIONAPPLIES, To TABLE OF CONTENTS TAB HEA DIN P1 REACTOR WATER ACTIVITYCONCENTRATION P2 DRYWELL GAS ACTIVITYCONCENTRATION P3 WETWELL GAS ACTIVITYCONCENTRATION P4 WETWELL WATER ACTIVITYCONCENTRATION PS RX BLDG 5 REFUEL FLOOR ACT. CONC.

P6 RX BLDG ELEVATED RELEASE POINT CONC.

P7 RADWASTE BLDG/RADWASTE BLDG EXHAUST PB TURBINE BLDG/TURBINE BLDG EXHAUST PS RADIATION MONITORING SYSTEM DATA P10 IN-PLANT SURVEY AND SAMPLING DATA P11 ONSITE SURVEY AND SAMPLING DATA P12 AIRBORNE ACTIVITY(PLANT VICINITY)

P13 CRITICAI. PLANT PARAMETER

SUMMARY

P14 PUMP AND FAN STATUS

SUMMARY

E1 METEOROLOGICAL DATA

SUMMARY

E2 OFFSITE SURVEY AND SAMPLING DATA E3 ENVIRONMENTALSAMPLING DATA PE1 EMERGENCY RESPONSE FACILITY DATA

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE Pl. a REACTOR WATER ACTIVITY CONCENTRATION (T = 00:00) ( 03:00)

Provide current Chem data 30 minutes after sample recgxest Nuclide Concentration Kr-85m 1.76E-03 uCi/cc Kr-87 3.06E-03 uCi/cc Kr-88 4.85E-03 uCi/cc Xe-131m 7.67E-05 uCi/cc Xe-133 1.30E-02 uCi/cc Xe-133m 4.59E-04 uCi/cc Xe-135 2.66E-03 uCi/cc Xe-138 5.41E-03 uCi/cc I-131 4.35E-03 uCi/cc I-132 5.61E-03 uCi/cc I-133 8.62E-03 uCi/cc I-134 7.68E-03 uCi/cc I-135 7.44E-03 uCi/cc Cs-134 9.61E-04 uCi/cc Cs-136 3.84E-04 uCi/cc Cs-137 6.03E-04 uCi/cc TOTAL WATER SAMPLE 6.71E-02 uCi/cc Normal Sample (15. ml) Dose Rate PASS Sample (10. ml) Dose Rate at at 1

1 ft.:

ft.: <

0.1 mR/hr 0.1 mR/hr PASS Sample (0.1 ml) Dose Rate at 1 ft.: < 0.1 mR/hr For 2" lead shield divide dose rate by: 3.0E+1 For 4" lead shield divide dose rate by: 6.2E+2

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P1. c REACTOR WATER ACTIVITY CONCENTRATION (T = 03:30) ( 06:30)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 1. 76E-03 uCi/cc Kr-87 3 05E-03 uCi/cc Kr-88 4 84E-03 uCi/cc Xe-131m 7 '7E-05 uci/cc Xe-133 1<<32E-02 uCi/cc Xe-133m 4.58E-04 uCi/cc Xe-135 3.47E-03 uCi/cc Xe-138 5 '1E-03 uCi/cc I-131 4.35E-03 uCi/cc I-132 5.55E-03 uCi/cc I-133 8.61E-03 uCi/cc I-134 7 '7E-03 uCi/cc I-135 7 '4E-03 uci/cc Rb-88 1.89E-03 uCi/cc Cs-134 9.61E-04 uCi/cc Cs-136 3.84E-04 uC1/cc Cs-137 6 03E-04 uCi/cc TOTAL WATER SAMPLE 6.98E-02 uCi/cc Normal Sample (15. ml) Dose Rate at 1 PASS Sample (10. ml) Dose Rate at 1 ft.:

ft.: < 0.1 mR/hr

< 0.1 mR/hr PASS Sample (0.1 ml) Dose Rate at 1 ft.: < 0.1 mR/hr For 2" lead shield divide dose rate by: 2.9E+1 For 4" lead shield divide dose rate by: 6.1E+2

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P1. d REACTOR WATER ACTIVITY CONCENTRATION (T = 04:00) ( 07:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentr'ation Kr>>85m 2.26E-03 uCi/cc Kr-87 3.30E-03 uCi/cc Kr-88 5.98E-03 uCi/cc Xe-131m 1.06E-04 uCi/cc Xe-133 1.81E-02 uCi/cc Xe-133m 6.29E-04 uCi/cc Xe-135 4.82E-03 uCi/cc Xe-138 1.98E-03 uCi/cc I-131 6 '8E-03 uCi/cc I-132 6.79E-03 uCi/cc I-133 1.19E-02 uCi/cc I-134 7.53E-03 uCi/cc I-135 9.94E-03 uCi/cc Rb-88 1.24E-03 uCi/cc Cs-134 1.35E-03 uCi/cc Cs-136 5.37E-04 uCi/cc Cs-137 8.45E-04 uCi/cc TOTAL WATER SAMPLE 8.36E-02 uCi/cc Normal Sample (15. ml) Dose'Rate at, 1 PASS Sample (10. ml) Dose Rate at 1 ft.:

ft.: <

0.1 mR/hr 0.1 mR/hr PASS Sample (0.1 ml) Dose Rate at 1 ft.: < 0.1 mR/hr For 2" lead shield divide dose rate by: 3.1E+1 For 4" lead shield divide dose rate by: 6.5E+2

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P1. e REACTOR WATER ACTIVITY CONCENTRATION (T = 04:30) ( 07:30)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 2.42E+00 uCi/cc Kr-87 3.62E+00 uCi/cc Kr-88 6.46E+00 uCi/cc Xe-133 1.94E+01 uCi/cc Xe-133m 6.68E-01 uCi/cc Xe-135 6.30E+00 uCi/cc Xe-138 2.52E+00 uCi/cc Br-83 8 '4E-01 uCi/cc Br-84 6.69E-01 uCi/cc I-131 1.02E+01 uCi/cc I-132 1.19E+01 uCi/cc I-133 1.99E+01 uCi/cc I-134 1 '2E+01 uCi/cc I-135 1.67E+01 uCi/cc Rb-88 5.24E+00 uCi/cc Cs-134 3.02E+00 uCi/cc Cs-136 1.05E+00 uCi/cc Cs-137 2 '5E+00 uCi/cc TOTAL WATER SAMPLE 1.27E+02 uCi/cc Normal Sample (15. ml) Dose Rate at at 1 ft.:

ft.: 11. mR/hr 7.3 mR/hr PASS Sample (10. ml) Dose Rate 1 PASS Sample (0.1 ml) Dose Rate at 1 ft.: < 0.1 mR/hr For 2" lead shield divide dose rate by: 3.2E+1 For 4" lead shield divide dose rate by: 6.9E+2

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P1. f REACTOR WATER ACTIVITY CONCENTRATION (T = 05-00) ( 08:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 1.72E+00 uCi/cc Kr-87 2 '3E+00 uci/cc Kr-88 4.53E+00 uCi/cc Xe-133 1.41E+01 uCi/cc Xe-133m 4.85E-01 uCi/cc Xe-135 4.61E+00 uCi/cc Xe-138 1.18E+00 uCi/cc Br-83 6 02E-01 uCi/cc Br-84 4 OOE-01 uci/cc'Ci/cc I-131 7.38E+00 I-132 8.29E+00 uCi/cc I-133 1 44E+01 uCi/cc I-134 8.54E+00 uCi/cc I-135 1 20E+01 uCi/cc Rb-88 2 '9E+00 uCi/cc Cs-134 2.20E+00 uCi/cc Cs-136 7.65E-01 uCi/cc Cs-137 1 49E+00 uCi/cc TOTAL WATER SAMPLE 8 '3E+01 uCi/cc Normal Sample (15. ml) Dose Rate PASS Sample (10. ml) Dose Rate at at 1

1 ft.:

ft.: 7.5 mR/hr 5.0 mR/hr PASS Sample (0.1 ml) Dose Rate at 1 ft.: < 0.1 mR/hr For 2" lead shield divide dose rate by: 3.2E+1 For 4" lead shield divide dose rate by: 7.1E+2

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 0

TABLE P1. g REACTOR WATER ACTIVITY CONCENTRATION (T = 05 30) ( 08:30)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 1.68E+00 uCi/cc Kr-87 2.24E+00 uCi/cc Kr-88 4.37E+00 uCi/cc Xe-133 1.41E+01 uCi/cc Xe-133m 4.84E-01 uCi/cc Xe-135 4.64E+00 uCi/cc Xe-138 7 '1E-01 uCi/cc Br-83 5.77E-01 uCi/cc Br-84 3.29E-01 uCi/cc I-131 7.38E+00 uCi/cc I-132 7.93E+00 uCi/cc I-133 1.43E+01 uCi/cc I-134 7.59E+00 uCi/cc I-135 1.18E+01 uCi/cc Rb-88 2.07E+00 uCi/cc Cs-134 2.20E+00 uCi/cc Cs-136 7.65E-01 uCi/cc Cs-137 1.49E+00 uCi/cc TOTAL WATER SAMPLE 8.51E+01 uCi/cc Normal Sample (15. ml) Dose Rate PASS Sample (10. ml) Dose Rate at at 1

1 ft.:

ft.: 7.2 mR/hr 4.8 mR/hr PASS Sample (0.1 ml) Dose Rate at 1 ft.: < 0.1 mR/hr For 2" lead shield divide dose rate by: 3.3E+1 For 4" lead shield divide dose rate by: 7.3E+2

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P1. h REACTOR WATER ACTIVITY CONCENTE&TION (T ~ 06:00) ( 09:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 1.64E+00 uCi/cc Kr-87 2.06E+00 uCi/cc Kr-88 4.21E+00 uCi/cc Xe-133 1.41E+01 uCi/cc Xe-133m 4.83E-01 uCi/cc Xe-135 4.67E+00 uCi/cc Xe-138 4 '0E-01 uCi/cc Br-83 5.52E-01 uCi/cc Br-84 2.70E-01 uCi/cc I-131 7.38E+00 uCi/cc I-132 7.58E+00 uCi/cc I-133 1.42E+01 uCi/cc I-134 6.74E+00 uCi/cc I-135 1.16E+01 uCi/cc Rb-88 1.56E+00 uCi/cc Cs-134 SAMPLERS 2.20E+00 uCi/cc Cs-136 7.65E-01 uCi/cc Cs-137 1 '9E+00 uCi/cc Mo-99 8 '8E-02 uCi/cc TOTAL WATER 8.24E+01 uCi/cc Normal Sample (15. ml) Dose Rate at 1 PASS Sample (10. ml) Dose Rate at 1 ft.:

ft.: 6.9 mR/hr 4.6 mR/hr PASS Sample (0.1 ml) Dose Rate at 1 ft.: < 0.1 mR/hr For 2" lead shield divide dose rate by: 3.3E+1 For 4" lead shield divide dose rate by: 7.4E+2

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P1 i REACTOR WATER ACTIVITY CONCENTRATION (T = 06:30) ( 09:30)

Provide current Chem data 30 minutes after sample recpxest Nuclide Concentration Kr-85m 1.60E+00 uCi/cc Kr-87 1.90E+00 uCi/cc Kr-88 4.06E+00 uCi/cc Xe-131m 8.14E-02 uCi/cc Xe-133 1.41E+01 uCi/cc Xe-133m 4.82E-01 uCi/cc Xe-135 4.69E+00 uCi/cc Xe-138 3.15E-01 uCi/cc Br-83 5.29E-01 uCi/cc Br-84 2 '2E-01 uCi/cc I-131 7.37E+00 uCi/cc I-132 7.24E+00 uCi/cc I-133 1.42E+01 uCi/cc I-134 5.98E+00 uCi/cc I-135 1.14E+01 uCi/cc Rb-88 1.19E+00 uCi/cc Cs-134 2.20E+00 uCi/cc Cs-136 7.65E-01 uCi/cc Cs-137 1.49E+00 uCi/cc Mo-99 8.47E-02 uCi/cc TOTAL WATER SAMPLE 8.01E+01 uCi/cc Normal Sample (15. ml) Dose Rate at 1 PASS Sample (10. ml) Dose Rate at 1 ft.:

ft.: 6.6 mR/hr 4.4 mR/hr PASS Sample (0.3. ml) Dose Rate at 1 ft.: < 0.1 mR/hr For 2" lead shield divide dose rate by: 3.3E+1 For 4" lead shield divide dose rate by: 7.6E+2

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P1.

REACTOR WATER ACTIVITY CONCENTRATION fT = 07:00) ( 10:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 1.56E+00 uCi/cc Kr-87 1.75E+00 uCi/cc Kr-88 3.91E+00 uCi/cc Xe-131m 8 13E-02 uCi/cc Xe>>133 1.41E+01 uCi/cc Xe-133m 4.81E-01 uCi/cc Xe-135 4.71E+00 uCi/cc Xe-138 2.03E-01 uCi/cc Br-83 '5.06E-01 uCi/cc Br-84 1.82E-01 uCi/cc I-131 7.37E+00 uCi/cc I-132 6.92E+00 uCi/cc I-133 1.41E+01 uCi/cc I-134 5.32E+00 uCi/cc I-135 1.12E+01 uCi/cc Rb-88 9 32E-01 uCi/cc Cs-134 2.20E+00 uCi/cc Cs-136 7.64E-01 uCi/cc Cs-137 1.49E+00 uCi/cc Mo-99 8.45E-02 uCi/cc TOTAL WATER SAMPLE 7.81E+01 uCi/cc Normal Sample (15. ml) Dose Rate at 1 PASS Sample (10. ml) Dose Rate at 1 ft.:

ft.: 6.4 mR/hr 4.3 mR/hr PASS Sample (0.1 ml) Dose Rate at 1 ft.: < 0.1 mR/hr For 2" lead shield divide dose rate by: 3.4E+1 For 4" lead shield divide dose rate by: 7.7E+2

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P1. k REACTOR WATER ACTIVITY CONCEN&VkTION (T = 07:30) ( 10:30)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 1.53E+00 uCi/cc Kr-87 1.62E+00 uCi/cc Kr-88 3.77E+00 uCi/cc Xe-131m 8.13E-02 uCi/cc Xe-133 1.41E+01 uCi/cc Xe-133m 4 '1E-01 uCi/cc Xe-135 4.73E+00 uCi/cc Xe-138 1.30E-01 uCi/cc Br-83 4.85E-01 uCi/cc Br-84 1.50E-01 uCi/cc I-131 7.36E+00 uCi/cc I-132 6.62E+00 uCi/cc I-133 1.40E+01 uCi/cc I-134 4.72E+00 uCi/cc I-135 1.11E+01 uCi/cc Rb-88 7.46E-01 uCi/cc Cs-134 2 20E+00 uCi/cc Cs-136 7.64E-01 uCi/cc Cs-137 1.49E+00 uCi/cc Mo-99 8.44E-02 uCi/cc TOTAL WATER SAMPLE 7.63E+01 uCi/cc Normal Sample (15. ml) Dose Rate PASS Sample (10. ml) Dose Rate at at 1

1 ft.:

ft.: 6.2 mR/hr 4.2 mR/hr PASS Sample (0.1 ml) Dose Rate at 1 ft.: < 0.1 mR/hr For 2" lead shield divide dose rate by: 3.4E+1 For 4" lead shield divide dose rate by: 7.8E+2

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P1 l REACTOR WATER ACTIVITY CONCENTRATION (T = 08:00) ( 11:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 1.49E+00 uCi/cc Kr-87 1.49E+00 uCi/cc Kr-88 3.64E+00 uCi/cc Xe-131m 8 '3E-02 uCi/cc Xe-133 1.41E+01 uCi/cc Xe-133m 4.80E-01 uCi/cc Xe-135 4.75E+00 uCi/cc Xe-138 8.39E-02 uCi/cc Br-83 4.65E-01 uCi/cc Br-84 1.23E-01 uCi/cc I-131 7.36E+00 uCi/cc I-132 6.33E+00 uCi/cc I-133 1.40E+01 uCi/cc I-134 4.19E+00 uCi/cc I-135 1.09E+01 uCi/cc Rb-88 6.11E-01 uCi/cc Cs-134 2.20E+00 uCi/cc Cs-136 7.64E-01 uCi/cc Cs-137 1 '9E+00 uCi/cc Mo-99 8 '3E-02 uCi/cc TOTAL WATER SAMPLE 7 48E+01 uCi/cc Normal Sample (15. ml) Dose Rate PASS Sample (10. ml) Dose Rate at at 1

1 ft.:

ft.: 6.1 mR/hr 4.0 mR/hr PASS Sample (0.1 ml) Dose Rate at 1 ft.: < 0.1 mR/hr For 2" lead shield divide dose rate by: 3.4E+1 For 4" lead shield divide dose rate by: 8.0E+2

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 t TABLE P2. a DRYWELL GAS ACTIVITY CONCENTRATION (T = 00:00) ( 03:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 1.47E-08 uCi/cc Kr-87 2.42E-08 uCi/cc Kr-88 3.90E-08 uCi/cc Xe-133 1.29E-07 uCi/cc Xe-135 1 58E-07 uCi/cc Xe-138 4.48E-08 uCi/cc TOTAL GAS SAMPLE 4.14E-07 uCi/cc I-131 8.79E-10 uCi/cc I-132 1.14E-09 uCi/cc I-133 1 92E-09 uCi/cc I-134 1 51E-09 uCi/cc I-135 1.76E-09 uCi/cc TOTAL CHARCOAL SAMPLE 7.22E-09 uCi/cc Cs-134 2 49E-10 uCi/cc Cs-136 9 '6E-11 uCi/cc Cs-137 1.61E-10 uCi/cc Np-239 8.34E-11 uci/cc TOTAL FILTER SAMPLE 6.19E-10 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P2. a DRYWELL GAS ACTXVITY CONCENTRATION (T = 00:00) ( 03:00)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate at at 1 ft.:

ft.:

< 0.1 0.1 mR/hr PASS Sample (14. ml) Dose Rate 1 < mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1

1 ft.:

ft.: <

0.1 0.1 mR/hr per mR/hr per cf cf For 2" lead shield divide dose rate by:2.8E+1 For 4" lead shield divide dose rate by:4.6E+2 Hydrogen Concentration: .04 Oxygen Concentration: 3.94 Cladding Failure: 0.4 Fuel Melt: 0.4

HNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P2. b DRYWELL GAS ACTIVITY CONCENTRATION (T = 04:00) ( 07:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 3.71E-07 uCi/cc Kr-87 3.26E-07 uCi/cc Kr-88 8.64E-07 uCi/cc Xe-133 3.74E-06 uCi/cc Xe-133m 1.28E-07 uCi/cc Xe-135 8.56E-07 uCi/cc TOTAL GAS SAMPLE 6.37E-06 uCi/cc I-13 1 5.53E-09 uCi/cc I-132 4.68E-09 uCi/cc I-133 1.05E-08 uCi/cc I-134 3.75E-09 uCi/cc I-135 8.13E-09 uCi/cc TOTAL CHARCOAL SAMPLE 3.26E-08 uCi/cc Rb-88 5.53E-08 uCi/cc TOTAL FILTER SAMPLE 5.97E-08 uCi/cc Normal Sample (15. ml) Dose Rate at, 1 PASS Sample (14. ml) Dose Rate at 1 ft.:

ft.:

< 0.1 0.1 mR/hr

< mR/hr PASS Sample (charcoal) Dose Rate at 1 PASS Sample (filter) Dose Rate at 1 ft.:

ft.: <

0.1 0.1 mR/hr per mR/hr per cf cf For 2" lead shield divide dose rate by:2.3E+1 For 4" lead shield divide dose rate by:3.7E+2 Hydrogen Concentration: .04 Oxygen Concentration: .04 Cladding Failure: 0.4 Fuel Melt: 0.4

WNP-2 Nuclear Generating Station Scenario . 93e Annual Exercise Unit 2 REV 0 TABLE P2. c DRYWELL GAS ACTIVITY CONCENTRATION (T = 05:00) ( 08:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 1 11E-03 uCi/cc Kr-87 1.57E-03 uCi/cc Kr-88 2.92E-03 uCi/cc Xe-133 9.06E-03 uCi/cc Xe-133m 3 13E-04 uCi/cc Xe-135 2 '8E-03 uCi/cc Xe-138 7 '7E-04 uCi/cc TOTAL GAS SAMPLE 1.87E-02 uCi/cc Br-83 1.69E-06 uCi/cc I-131 2.07E-05 uCi/cc I-132 2 33E-05 uCi/cc I-133 4.04E-05 uCi/cc I-134 2.40E-05 uCi/cc I-135 TOTAL CHARCOAL SAMPLE Rb-88 3 '6E-05 uCi/cc 1.45E-04 uCi/cc 1 15E<<04 uCi/cc 0

Cs-134 3 19E-05 uCi/cc Cs-136 1.11E-05 uCi/cc Cs-137 2 17E-05 uCi/cc TOTAL FILTER SAMPLE 1.80E-04 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P2. c DRYWELL GAS ACTIVITY CONCENTRATION (T = 05:00) ( 08:00)

(continued)

Provide current Chem

\

data 30 minutes after sample request Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1 ft.:

ft.:

< 0.1 0.1 mR/hr 1 < mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1 ft.:

ft.:

< 0.1 0.1 mR/hr per cf cf 1 < mR/hr per For 2" lead shield divide dose rate by:2.3E+1 For 4" lead shield divide dose rate by:3.7E+2 Hydrogen Concentration: .04 Oxygen Concentration: 3.84 Cladding Failure: 3.% Fuel Melt: 0.4

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P2. d DRYWELL GAS ACTIVITY CONCENTRATION (T = 06:00) ( 09:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 1 OOE-03 uCi/cc Kr-87 1.26E-03 uCi/cc Kr-88 2 '7E-03 uCi/cc Xe-133 8 '7E-03 uCi/cc Xe-133m 2.95E-04 uCi/cc Xe-135 2.67E-03 uCi/cc Xe-138 3 01E-04 uCi/cc TOTAL GAS SAMPLE 1 68E-02 uCi/cc Br-83 1.02E-07 uci/CC I-131 1.36E-06 uCi/cc I-132 1.39E-06 uCi/cc I-133 2.62E-06 uCi/cc I-134 1 24E-06 uCi/cc I-135 2 14E-06 uCi/cc TOTAL CHARCOAL SAMPLE 8.91E-06 uCi/cc Rb-88 9.54E-05 uCi/cc Cs-134 1.27E-05 uCi/cc Cs-137 8.59E-06 uCi/cc TOTAL FILTER SAMPLE 1.21E-04 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABIE P2. d DRYWELZ GAS ACTIVITY CONCENTRATION (T = 06: 00) ( 09: 00)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1 ft.:

ft.:

< 0.1 0.1 mR/hr 1 < mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1 ft.:

ft.:

< 0.1 0.1 mR/hr per cf cf 1 < mR/hr per For 2" lead shield divide dose rate by:2.3E+1 For 4" lead shield divide dose rate by:3.6E+2 Hydrogen Concentration: .04 Oxygen Concentration: 3.84 Cladding Failure: 3.4 Fuel Melt: 0.4

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P2. e DRYWELL GAS ACTIVITY CONCENTEVLTION (T = 07:00) ( 10:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 9.32E-04 uCi/cc Kr-87 1.05E-03 uCi/cc Kr-88 2.33E-03 uCi/cc Xe-133 8.35E-03 uCi/cc Xe-133m 2.87E-04 uCi/cc Xe-135 2.55E-03 uCi/cc TOTAL GAS SAMPLE 1.57E-02 uCi/cc Br-83 1.48E-08 uCi/cc I-131 2.16E-07 uCi/cc I-132 2.03E-07 uCi/cc I-133 4.13E-07 uCi/cc I-134 1.56E-07 uCi/cc I-135 3 29E-07 uCi/cc TOTAL CHARCOAL SAMPLE 1.34E-06 uCi/cc Rb-88 8.54E-05 uCi/cc Cs-134 5.29E-06 uCi/cc TOTAL FILTER SAMPLE 9 62E-05 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P2. e DRYWELL GAS ACTIVITY CONCENTRATION (T = 07:00) ( 10:00)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1 ft.:

ft.: < 0.1 0.1 mR/hr 1 < mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1 ft.:

ft.: < 0.1 0.1 mR/hr per cf cf 1 < mR/hr per For 2" lead shield divide dose rate by:2.3E+1 For 4" lead shield divide dose rate by:3.6E+2 Hydrogen Concentration: .04 Oxygen Concentration: 3.84 Cladding Failure: 3.4 Fuel Melt: 0.4

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P2 f DRYWELL GAS ACTIVITY CONCENTRATION (T ~ 08:00) ( 11:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentr'ation Kr-85m 8.80E<<04 uCi/cc Kr-87 8 77E-04 uCi/cc Kr-88 2 '4E-03 uCi/cc Xe-133 8.24E-03 uCi/cc Xe-133m 2.82E-04 uCi/cc Xe-135 2.46E-03 uCi/cc TOTAL GAS SAMPLE 1.50E-02 uCi/cc Br-83 8 '5E-09 uCi/cc I-131 1.40E-07 uCi/cc I-132 1.21E-07 uCi/cc I-133 2.66E-07 uCi/cc I-134 8.00E-08 uCi/cc I-135 2.08E-07 uCi/cc TOTAL CHARCOAL SAMPLE 8 '6E-07 uCi/cc Rb-88 7.82E-05 uCi/cc TOTAI FILTER SAMPLE 8.30E-05 uCi/cc Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1

1 ft.:

ft.: <

0.1 mR/hr 0.1 mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1

1 ft.:

ft.: <

0.1 mR/hr per cf O.l mR/hr per cf For 2" lead shield divide dose rate by:2.3E+1 For 4" lead shield divide dose rate by:3.7E+2 Hydrogen Concentration: .04 Oxygen Concentration: 3.84 Cladding'Failure: 3.4 Fuel Melt: 0.4

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P3.. a METHELL GAS ACTIVITY CONCENTRATION (T = 00:00) ( 03:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 1.44E-07 uCi/cc Kr-87 2 '2E-07 uCi/cc Kr-88 3.97E-07 uCi/cc Xe-133 1.07E-06 uCi/cc Xe-133m 3.74E-08 uCi/cc Xe-135 2 '5E-07 uCi/cc Xe<<138 4 64E-07 uCi/cc TOTAL GAS SAMPLE 2.58E-06 uCi/cc I-131 3 47E-09 uCi/cc I-132 4.51E-09 uCi/cc I-133 6 89E-09 uCi/cc I-134 6 '1E-09 uCi/cc I-135 5.96E-09 uCi/cc TOTAL CHARCOAL SAMPLE 2 70E-08 uCi/cc

~

7.68E-10 uCi/cc 3.07E-10 uCi/cc 4.81E-10 uCi/cc TOTAL FILTER SAMPLE 1.63E-09 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P3. a WETWELL GAS ACTIVITY CONCENTRATION (T = 00:00) ( 03:00)

(continued)

Provide current Chem data 30 minutes after sample recpxest Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1

1 ft.:

ft.: <

0.1 0.1 mR/hr mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1 ft.:

ft.: < 0.1 0.1 mR/hr per cf cf 1 < mR/hr per For 2" lead shield divide dose rate by:2.3E+1 For 4" lead shield divide dose rate by:3.7E+2 Hydrogen Concentration: .04 Oxygen Concentration: 3.24

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit. 2 REV 0 TABLE P3 b WETWELL GAS ACTIVITY CONCENTRATION (T ~ 04:00) ( 07:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentr'ation Kr-85m 3.03E-08 uCi/cc Kr-87 2.68E-08 uCi/cc Kr-88 7.09E-08 uCi/cc Xe-133 3.03E-07 uCi/cc Xe-133m 1.04E-08 uCi/cc Xe-135 6.31E-08 uCi/cc TOTAL GAS SAMPLE 5.11E-07 uCi/cc I-131 1.08E-09 uCi/cc I-132 8.06E-10 uCi/cc I-133 2.02E<<09 uCi/cc I-134 5.28E-10 uCi/cc I-135 1.52E-09 uCi/cc TOTAL CHARCOAL SAMPLE 5.95E-09 uCi/cc Rb-88 4.90E-09 uCi/cc TOTAL FILTER SAMPLE 5.39E-09 uCi/cc Normal Sample (15. ml) Dose Rate PASS Sample {14. ml) Dose Rate at at 1

1 ft.:

ft.: <

0.1 O.l mR/hr mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1

1 ft.:

ft.: <

0.1 0.1 mR/hr per mR/hr per cf cf For 2" lead shield divide dose rate by:2.3E+1 For 4" lead shield divide dose rate by:3.7E+2 Hydrogen Concentration: .0%

Oxygen Concentration: .1%

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P3. c METALL GAS ACTIVITY CONCENTRATION (T = 05:00) ( 08:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 1.58E+01 uCi/cc Kr<<87 2.24E+01 uCi/cc Kr-88 4.17E+01 uCi/cc Xe-133 1.29E+02 uCi/cc Xe-133m 4.46E+00 uCi/cc Xe-135 4.14E+01 uCi/cc Xe-138 1.09E+01 uCi/cc TOTAL GAS SAMPLE 2.68E+02 uCi/cc Br-83 2.06E-01 uCi/cc I-131 2.53E+00 uCi/cc I~132 2.84E+00 uCi/cc I-133 4.92E+00 uCi/cc I-134 2.92E+00 uCi/cc I-135 TOTAL CHARCOAL SAMPLE 4.09E+00 1.76E+01 uCi/cc uCi/cc 0 Rb-88 2 '3E+00 uCi/cc Cs-134 7.52E-01 uCi/cc Cs<<136 2 '2E-01 uCi/cc Cs-137 5.11E-01 uCi/cc TOTAL FILTER SAMPLE 3.56E+00 uCi/cc CONTINUED ON NEXT PAGE h

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P3 c WETl&LL GAS ACTIVITY CONCENTRATION (T = 05:00) ( 08:00)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1 ft.:

ft.: 26.

25.

mR/hr 1 mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1

1 ft.:

ft.: 3000.

580.

mR/hr per mR/hr per cf cf For 2" lead shield divide dose rate by:2.4E+1 For 4" lead shield divide dose rate by:4.0E+2 Hydrogen Concentration: 16.54 Oxygen Concentration: .74

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P3. d I HZTNELL GAS ACTIVITY CONCENTRATION (T = 06:00) ( 09:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 1.51E+01 uCi/cc Kr-87 1.90E+01 uCi/cc Kr-88 3 87E+01 uCi/cc Xe-133 1.29E+02 uCi/cc Xe-133m 4.44E+00 uCi/cc Xe-135 4.06E+01 uCi/cc Xe-138 4.50E+00 uCi/cc TOTAL GAS SAMPLE 2.53E+02 uCi/cc Br-83 1.42E-01 uCi/cc I-131 1.89E+00 uCi/cc I-132 1.94E+00 uCi/cc I-133 3.65E+00 uCi/cc I-134 1.73E+00 uCi/cc I-135 TOTAL CHARCOAL SAMPLE 2.97E+00 1.24E+01 uCi/cc uCi/cc 0 Rb-88 2.03E+00 uCi/cc Cs-134 5.63E-01 uCi/cc Cs-136 1.96E-01 uCi/cc Cs-137 3.83E-01 uCi/cc TOTAL FILTER SAMPLE 3.18E+00 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P3. d HETWELL GAS ACTIVITY CONCENTRATION (T = 06:00) ( 09:00)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate at 1 PASS Sample (14. ml) Dose Rate at, 1 ft.:

ft.: 24.

23.

mR/hr mR/hr PASS Sample (charcoal) Dose Rate at 1 PASS Sample"(filter) Dose Rate at 1 ft.:

ft.: 2100. mR/hr per cf cf 510. mR/hr per For 2" lead shield divide dose rate by:2.4E+1 For 4" lead shield divide dose rate by:4.0E+2 Hydrogen Concentration: 17.74 Oxygen Concentration: 2.24

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5. m RX BLDG & REFUEL FLOOR ACT. CONC (T = 06:00) ( 09:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 8.35E-03 uCi/cc Kr-87 1.05E-02 uCi/cc Kr-88 2 '5E-02 uCi/cc Xe-133 7.16E-02 uCi/cc Xe-133m 2.46E-03 uCi/cc Xe-135 2.27E-02 uCi/cc Xe-138 2.50E-03 uCi/cc TOTAL GAS SAMPLE 1.40E-01 uCi/cc Br-83 1.78E-04 uCi/cc I-131 2.37E-03 uCi/cc I-132 2.44E-03 uCi/cc I-133 4.58E-03 uCi/cc I-134 2 17E-03 uCi/cc I-135 3.73E-03 uCi/cc TOTAL CHARCOAL SAMPLE 1.56E-02 uCi/cc Rb-88 2 OOE-03 uCi/cc Cs<<134 1.95E-03 uCi/cc Cs-136 6.78E-04 uCi/cc Cs-137 1 32E-03 uCi/cc TOTAL FILTER SAMPLE 6.14E-03 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P3. e WETWELL GAS ACTIVITY CONCENTRATION (T = 07:00) { 10:00)

Provide current Chem data 30 minutes after samyle request Nuclide Concentration Kr-85m 1.44E+01 uCi/cc Kr-87 1.61E+01 uCi/cc Kr-88 3.59E+01 uCi/cc Xe-133 1.29E+02 uCi/cc Xe-133m 4.42E+00 uCi/cc Xe-135 3 '8E+01 uCi/cc TOTAL GAS SAMPLE 2.43E+02 uCi/cc Br-83 1.01E-01 uCi/cc I-131 1.47E+00 uCi/cc I-132 1.38E+00 uCi/cc I-133 2.82E+00 uCi/cc I-134 1.06E+00 uCi/cc I-135 2.25E+00 uCi/cc TOTAL CHARCOAL SAMPLE 9.13E+00 uCi/cc Rb-88 1.92E+00 uCi/cc Cs-134 4.40E-01 uCi/cc Cs-136 1.53E-01 uCi'/cc Cs-137 2.99E-01 uCi/cc TOTAL FILTER SAMPLE 2.81E+00 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P3. e WETWELL GAS ACTIVITY CONCENTRATION (T = 07:00) ( 10:00)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1

1 ft.:

ft.: 23.

22.

mR/hr mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1

1 ft.:

ft.: 1500.

440.

mR/hr per mR/hr per cf cf For 2" lead shield divide dose rate by:2.4E+1 For 4" lead shield divide dose rate by:3.9E+2 Hydrogen Concentration: 18.2%

Oxygen Concentration: 2.84

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P3. f WETWELL GAS ACTIVITY CONCENTEVLTION {T = 08:00) { 11:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentr'ation Kr-85m 1.37E+01 uCi/cc Kr-87 1.37E+01 uCi/cc Kr-88 3.34E+01 uCi/cc Xe-133 1.29E+02 uCi/cc Xe-133m 4.40E+00 uCi/cc Xe-135 3.91E+01 uCi/cc TOTAL GAS SAMPLE 2.35E+02 uCi/cc Br-83 7 '9E-02 uCi/cc I-131 1.20E+00 uCi/cc I-132 1 03E+00 uCi/cc I-133 2.28E+00 uCi/cc I-134 6.85E-01 uCi/cc I-135 1.78E+00 uCi/cc TOTAL CHARCOAL SAMPLE 7.08E+00 uCi/cc Rb-88 1.78E+00 uCi/cc Cs-134 3.59E-01 uCi/cc Cs-137 2.44E-01 uCi/cc TOTAL FILTER SAMPLE 2.51E+00 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P3. f WETWELL GAS ACTIVXTY CONCENTRATION (T = 08:00) ( 11:00)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1

1 ft.:

ft.: 21.

21.

mR/hr mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1 ft.:

ft.: 1200. mR/hr per cf cf 1 390. mR/hr per For 2" lead shield divide dose rate by:2.4E+1 For 4" lead shield divide dose rate by:3.9E+2 Hydrogen Concentration: 18.54 Oxygen Concentration: 3.14

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P4. a WETWELL WATER ACTIVITY CONCENTRAT1ON (T = 00:00) ( 03:00)

Provide current Chem data 30 minutes after sample recpxest Nuclide Concentration Kr-85m 4.02E-10 uCi/cc Kr-87 7.04E-10 uCi/cc Kr-88 1.11E-09 uCi/cc Xe-133 4.66E-09 uCi/cc Xe-133m 1.05E-10 uCi/cc Xe-135 1.66E-09 uCi/cc Xe-138 1.30E-09 uCi/cc I-131 8.70E-09 uCi/cc I-132 1.13E-08 uCi/cc I-133 1.72E-08 uCi/cc I-134 1.56E-08 uCi/cc I-135 1.49E-08 uCi/cc Cs-134 1.92E-09 uCi/cc Cs-136 7.67E-10 uCi/cc Cs-137 1 20E-09 uCi/cc TOTAL WATER SAMPLE 8.16E-08 uCi/cc Normal Sample (15. ml) Dose Rate at 1 PASS Sample (10. ml) Dose Rate at 1 ft.:

ft.:

< 0.1 mR/hr

< 0.1 mR/hr PASS Sample (0.1 ml) Dose Rate at 1 ft.: < 0.1 mR/hr For 2" lead shield divide dose rate by: 3.3E+1 For 4" lead shield divide dose rate by: 7.8E+2

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P4. c WETWELL WATER ACTIVITY CONCENTRATION {T = 03:30) ( 06:30)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 4.92E-09 uCi/cc Kr-87 4.80E-09 uCi/cc Kr-88 1.17E-08 uCi/cc Xe-133 4.98E-08 uCi/cc Xe-133m 1.63E-09 uCi/cc Xe-135 1.93E-08 uCi/cc Xe-138 1.56E-09 uCi/cc I-131 9.84E-08 uCi/cc I-132 8.05E-08 uCi/cc I-133 1.86E-07 uCi/cc I-134 6.16E-08 uCi/cc I-135 1.43E-07 uCi/cc Rb-88 1.57E-08 uCi/cc Cs-134 2.19E-08 uCi/cc Cs-136 8.71E>>09 uCi/cc Cs-137 1.37E-08 uCi/cc TOTAL WATER SAMPLE 7.24E-07 uCi/cc

~

Normal Sample (15. ml) Dose Rate at 1 PASS Sample {10. ml) Dose Rate at 1 ft.:

ft.: <

0.1 mR/hr 0.1 mR/hr Sample (0.1 ml) Dose Rate at, 1 ft.: < 0.1 mR/hr 'ASS For 2" lead shield divide dose rate by: 3.5E+1 For 4" lead shield divide dose rate by: 8.8E+2

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P4. d WETWELL WATER ACTIVITY CONCENTO!TION (T = 04:00) ( 07:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 4.28E-09 uCi/cc Kr-87 3 53E-09 uCi/cc Kr-88 9.84E-09 uCi/cc Xe-133 4.64E-08 uCi/cc Xe-133m 1.51E-09 uCi/cc Xe-135 1.90E-08 uCi/cc I-131 8.72E-08 uCi/cc I-132 6.24E-08 uCi/cc I-133 1.62E-07 uCi/cc I-134 3.83E-08 uCi/cc I-135 1 21E-07 uCi/cc Rb-88 9.23E-09 uCi/cc Cs-134 1.94E-08 uCi/cc Cs-136 7.73E-09 uCi/cc Cs-137 1.22E-08 uCi/cc TOTAL WATER SAMPLE 6.06E-07 uCi/cc Normal Sample (15. ml) Dose Rate at 1 PASS Sample (10. ml) Dose Rate at 1 ft.:

ft.:

< 0.1 mR/hr

< 0.1 mR/hr PASS Sample (0.1 ml) Dose Rate at 1 ft.: < 0.1, mR/hr For 2" lead shield divide dose rate by: 3.6E+1 For 4" lead shield divide dose rate by: 9.2E+2

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P4. e WETHELL WATER ACTIVITY CONCENTRATION (T ~ 04:30) ( 07:30)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-87 4.35E-02 uCi/cc Kr-88 7 76E-02 uCi/cc Xe-133 2 36E-01 uCi/cc Xe-135 1.04E-01 uCi/cc Br-83 4.07E-01 uCi/cc Br-84 3 15E-01 uCi/cc I-131 4.79E+00 uCi/cc I-132 5.62E+00 uCi/cc I-133 9.36E+00 uCi/cc I-134 6.23E+00 uCi/cc 1-135 7.88E+00 uCi/cc Rb-88 2.40E+00 uCi/cc Cs-134 1.42E+00 uCi/cc Cs-136 4.96E-01 uCi/cc Cs-137 9.67E-01 uCi/cc Mo-99 5.68E-02 uCi/cc Tc-99m 5.41E-02 uCi/cc TOTAL WATER SAMPLE 4.06E+01 uCi/cc Normal Sample (15. ml) Dose Rate at 1 PASS Sample (10. ml) Dose Rate at 1 ft.:

ft.: 3.4 mR/hr 2.3 mR/hr PASS Sample (0.1 ml) Dose Rate at 1 ft.: < 0.1 mR/hr For 2" lead shield 'divide dose rate by: 3.4E+1 For 4" lead shield divide dose rate by: 8.2E+2

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P4. f WETWELL WATER ACTIVITY CONCENTE&TION (T = 05 00) ( 08:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-87 4.69E-02 uCi/cc Kr-88 8.73E-02 uCi/cc Xe-133 2.81E-01 uCi/cc Xe-135 1.65E-01 uCi/cc Br-83 3.96E-01 uCi/cc Br-84 2.63E-01 uCi/cc I-131 4.86E+00 uCi/cc I-132 5.45E+00 uCi/cc I-133 9.46E+00 uCi/cc I-134 5.62E+00 uCi/cc I-135 7.87E+00 uCi/cc Rb-88 1.74E+00 uCi/cc Cs-134 1.45E+00 uCi/cc Cs-136 5.04E-01 uCi/cc Cs-137 9.82E-01 uCi/cc Mo-99 5.68E-02 uCi/cc Tc-99m 5.34E-02 uCi/cc TOTAL WATER SAMPLE 3.94E+01 uCi/cc Normal Sample (15. ml) Dose Rate PASS Sample (10. ml) Dose Rate at at 1

1 ft.:

ft.: 3.3 mR/hr 2.2 mR/hr PASS Sample (0.1 ml) Dose Rate at 1 ft.: < 0.1 mR/hr For 2" lead shield divide dose rate by: 3.4E+1 For 4" lead shield divide dose rate by: 8.5E+2

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P4. g WETWELL WATER ACTXVITY CONCENTRATION (T ~ 05:30) ( 08:30)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-87 4.90E-02 uCi/cc Kr-88 9.55E-02 uCi/cc Xe-133 3 23E-01 uCi/cc Xe-135 2 22E-01 uCi/cc Br-83 3.84E-01 uCi/cc Br-84 2 '9E-01 uCi/cc I-131 4.91E+00 uCi/cc I-132 5.28E+00 uCi/cc I-133 9.53E+00 uCi/cc I-134 5.05E+00 uCi/cc I-135 7.85E+00 uCi/cc Rb-88 1.28E+00 uCi/cc Cs-134 1.46E+00 uCi/cc Cs-136 5.10E-01 uCi/cc Cs-137 9.94E-01 uCi/cc Mo-99 5.67E-02 uCi/cc Tc-99m 5.26E-02 uCi/cc Ru-103 3 91E-02 uCi/cc TOTAL WATER SAMPLE 3.84E+01 uCi/cc Normal Sample (15. ml) Dose Rate PASS Sample (10. ml) Dose Rate at at 1

1 ft.:

ft.: 3.2 mR/hr 2.1 mR/hr PASS Sample (0.1 ml) Dose Rate at 1 ft.: < 0.1 mR/hr For 2" lead shield divide dose rate by: 3.5E+1 For 4" lead shield divide dose rate by: 8.7E+2

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P4. h WETWELL WATER ACTIVITY CONCENTRATION (T ~ 06:00) ( 09:00)

Provide current Chem data 30 minutes after sample request Nuclide 'oncentr'ation Kr-85m 3.99E-02 uCi/cc Kr-87 5.03E-02 uCi/cc Kr-88 1.03E-01 uCi/cc Xe-133 3.64E-01 uCi/cc Xe-135 2.75E-01 uCi/cc Br-83 3.72E-01 uCi/cc Br-84 1.82E-01 uCi/cc I-131 4.96E+00 uCi/cc I-132 5.09E+00 uCi/cc I-133 9.58E+00 uCi/cc I-134 4.53E+00 uCi/cc I-135 7.80E+00 uCi/cc

'b-88 9.63E-01 uCi/cc Cs-134 1.48E+00 uCi/cc Cs-136 5.15E-01 uCi/cc Cs-137 1.00E+00 uCi/cc Mo-99 5.67E-02 uCi/cc Tc-99m 5.18E-02 uCi/cc Ru-103 3.92E-02 uCi/cc TOTAL WATER SAMPLE 3.75E+01 uCi/cc Normal Sample (15. ml) Dose Rate PASS Sample (10. ml) Dose Rate at at 1

1 ft.:

ft.: 3.1 mR/hr 2.0 mR/hr PASS Sample (0.1 ml) Dose Rate at 1 ft.: < 0.1 mR/hr For 2" lead shield divide dose rate by: 3.5E+1 For 4" lead shield divide dose rate by: 8.9E+2

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P4. i WETWELL WATER ACTIVITY CONCENTRATION (T = 06:30) ( 09:30)

Provide current Chem data 30 minutes after sample request Nuclide Concentiation Kr-85m 4.28E-02 uCi/cc Kr-87 5.08E-02 uCi/cc Kr-88 1.08E-01 uCi/cc Xe-133 4.03E-01 uCi/cc Xe-135 3.25E-01 uci/cc Br-83 3 '9E-01 uCi/cc Br-84 1.51E-01 uCi/cc I-131 5.00E+00 uCi/cc I-132 4.91E+00 uCi/cc I-133 9.60E+00 uCi/cc I-134 4.06E+00 uCi/cc I-135 7.74E+00 uCi/cc Rb-88 7.36E-01 uCi/cc Cs-134 1.49E+00 uCi/cc Cs-136 5.19E-01 uCi/cc Cs-137 Mo-99 Tc-99m Ru-103 1.01E+00 5.67E-02 5.10E-02 3.92E-02 uCi/cc uCi/cc uCi/cc uCi/cc 4

TOTAL WATER SAMPLE 3.67E+01 uCi/cc Normal Sample (15. ml) Dose Rate PASS Sample (10. ml) Dose Rate at at 1

1 ft.:

ft.: 3.0 mR/hr 2.0 mR/hr PASS Sample (0.1 ml),Dose Rate at 1 ft.: < 0.1 mR/hr For 2",lead shield divide dose rate by: 3.6E+1 For 4" lead shield divide dose rate by: 9.1E+2

WNP>>2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P4. j WETHELL WATER ACTZVZTY CONCENTRATZON (T = 07:00) ( 10:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentiation Kr-85m 4.53E-02 uCi/cc Kr-87 5.08E-02 uCi/cc Kr-88 1 13E-01 uCi/cc Xe-133 4.39E-01 uCi/cc Xe-135 3.71E-01 uCi/cc Br-83 3.46E-01 uCi/cc Br-84 1.24E-01 uCi/cc Z-131 5.03E+00 uCi/cc Z-132 4.72E+00 uCi/cc Z-133 9.62E+00 uCi/cc Z-134 3.63E+00 uCi/cc Z-135 7.67E+00 uCi/cc Rb-88 5.75E-01 uCi/cc Cs-134 1.50E+00 uCi/cc Cs-136 5.22E-01 uCi/cc Cs-137 1.02E+00 uCi/cc Mo-99 5.66E-02 uCi/cc Tc-99m 5.03E-02 uCi/cc Ru-103 3.92E-02 uCi/cc TOTAL WATER SAMPLE 3 59E+01 uCi/cc Normal Sample (15. ml) Dose Rate PASS Sample (10. ml) Dose Rate at at 1 ft.:

ft.: 2.9 mR/hr 1.9 mR/hr 1

PASS Sample (0.1 ml) Dose Rate at 1 ft.: < 0.1 mR/hr For 2" lead shield divide dose rate by: 3.6E+1 For 4" lead shield divide dose rate by: 9.3E+2

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P4 k WETWELL WATER ACTIVITY CONCENTRATION (T = 07-30) ( 10:30)

Provide current Chem data 30 minutes afte TABLE P4 k WETWELL WATER ACTIVITY CONCENTRATION (T = 07:30) ( 10:30)

Provide current Chem data 30 minutes after sample request Nuclide Concentration

&&WWA&W Kr-85m 4 76E-02 uCi/cc Kr-87 5.03E-02 uCi/cc Kr-88 1.18E-01 uci/cc Xe-133 4.75E-01 uCi/cc Xe-135 4.14E-01 uCi/cc Br-83 3 '3E-01 uCi/cc Br-84 1.03E-01 uCi/cc I-131 5 05E+00 uCi/cc I-132 4 '4E+00 uCi/cc I-133 9 '2E+00 uci/cc I-134 3.24E+00 uCi/cc I-135 7.59E+00 uCi/cc Rb-88 4 '1E-01 uCi/cc Cs-134 1.51E+00 uCi/cc Cs-136 5.24E-01 uCi/cc Cs-137 1.02E+00 uCi/cc Mo-99 5.65E-02 uCi/cc Tc-99m 4.95E-02 uCi/cc Ru-103 3 '2E-02 uCi/cc TOTAL WATER SAMPLE 3 '3E+01 uCi/cc Normal Sample (15. ml) Dose Rate PASS Sample (10. ml) Dose Rate at at 1

1 ft.:

ft.: 2.8 mR/hr 1.9 mR/hr PASS Sample (0.1 ml) Dose Rate at 1 ft.: < 0.1 mR/hr For 2" lead shield divide dose rate hy: 3.7E+1 For 4" lead shield divide dose rate by: 9.5E+2

HNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P4 l HETWELL HATER ACTIVITY CONCENTRATION (T = 08:00) ( 11:00)

Provide current Chem data 30 minutes after sample recpxest Nuclide Concentration Kr-85m 4.96E-02 uCi/cc Kr-87 4.95E-02 uCi/cc Kr-88 1.21E-01 uCi/cc Xe-133 5.08E-01 uCi/cc Xe-135 4.55E-01 uCi/cc Br-83 3.20E-01 uCi/cc Br-84 8.48E-02 uCi/cc I-13 1 5.07E+00 uCi/cc I-132 4.36E+00 uCi/cc I-133 9.61E+00 uCi/cc I-134 2.89E+00 uCi/cc I-135 7.50E+00 uCi/cc Rb-88 3.79E-01 uCi/cc Cs-134 1.51E+00 uCi/cc Cs-136 5.26E-01 uCi/cc Cs-137 1.03E+00 uCi/cc Mo-99 5.65E-02 uCi/cc Tc-99m 4.87E-02 uCi/cc Ru-103 3 '2E-02 uCi/cc TOTAL HATER SAMPLE 3.46E+01 uCi/cc Normal Sample (15. ml) Dose Rate PASS Sample (10. ml) Dose Rate at at 1

1 ft.:

ft.:: 2.8 mR/hr 1.8 mR/hr PASS Sample (0.1 ml) Dose Rate at 1 ft < 0.1 mR/hr For 2" lead shield divide dose rate by: 3.7E+1 For 4" lead shield divide dose rate by: 9.7E+2

e WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 t TABLE P5. a RX BLDG & REFUEL FLOOR ACT. CONC. (T = 00:00) ( 03:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 1 95E-10 uCi/cc Kr-87 3 39E-10 uCi/cc Kr-88 5 36E-10 uCi/cc Xe-133 1.46E-09 uCi/cc Xe-133m 5.06E-11 uCi/cc Xe-135 5.10E-10 uCi/cc Xe-138 6 09E-10 uCi/cc TOTAL GAS SAMPLE '3.71E-09 uCi/cc I-131 4 59E-11 uCi/cc I-132 5 '7E-11 uCi/cc I-133 1 10E-10 uCi/cc I-134 7.65E-11 uci/cc I-135 1 05E-10 uCi/cc TOTAL CHARCOAL SAMPLE 3.97E-10 uCi/cc Cs-134 1 OOE-11 uCi/cc Cs-136 3.99E-12 uCi/cc Cs-137 6 51E-12 uCi/cc Np-239 2 '3E-12 uCi/cc TOTAL FILTER SAMPLE 2.33E-11 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5. a RX BLDG & REFUEL FLOOR ACT. CONC. (T ~ 00:00) ( 03:00)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate at 1 0.1 mR/hr PASS Sample (14. ml) Dose Rate PASS Sample (charcoal) Dose Rate at at 1

1 ft.: 0.1 0.1 mR/hr mR/hr per cf PASS Sample (filter) Dose Rate at 1 0.1 mR/hr per cf For 2" lead shield divide dose rate by:2.SE+1 For 4" lead shield divide dose rate by:4.3E+2 Hydrogen Concentration: .0%

Oxygen Concentration: 21.04 Airborne Beta Dose Rate: < 0.1 mRad/hr Airborne Thyroid Dose Rate: 0.2 mRem/hr Net Air Sample Contact Rate: 2.4 cpm/cf sample Floor Contamination: ( 0.1 cpm/100cm2 Wall and Equipment Contamination: < 0.1 cpm/100cm2 Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Personnel Contamination Rate: ( 0.1 cpm/100cm2 per minute Stay Time: 2 MPC hr (no mask):1.6E@2 Hours Stay 'Time: 2 MPC hr (in mask):S.OE+3 Hours Stay Time: 2 MPC hr (in Air Sup. mask):3.2E+5 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5. b RX BLDG & REFUEL FLOOR ACT. CONC. (T = 03:00) ( 06:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentr'ation Kr-85m 1.40E-09 uCi/cc Kr-87 1.65E>>09 uCi/cc Kr-88 3.51E-09 uCi/cc Xe-133 1.24E-08 uCi/cc Xe-133m 4.29E-10 uCi/cc Xe-135 2.77E-09 uCi/cc Xe-138 8.02E-10 uCi/cc TOTAL GAS SAMPLE 2.31E-08 uCi/cc I-131 1.68E-10 uCi/cc I-132 1.73E-10 uCi/cc I-133 3.26E-10 uCi/cc I-134 1.77E-10 uCi/cc I-135 2.66E-10 uCi/cc TOTAL CHARCOAL SAMPLE 1.11E-09 uCi/cc Rb-88 2.42E-10 uCi/cc Cs-134 5.87E-11 uCi/cc Cs-136 2.34E-11 uCi/cc Cs-137 3.68E-11 uCi/cc TOTAL FILTER SAMPLE 3.61E-10 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenar io 93e Annual Exercise Unit 2 REV 0 TABLE P5. b RX BLDG & REFUEL FLOOR ACT. CONC. (T = 03:00) ( 06:00) 0 (continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1

1 ft.:

ft.: 0.1 0.1 mR/hr mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1 ft.:

ft.: 0.1 0.1 mR/hr per cf cf 1 mR/hr per For 2" lead shield divide dose rate by:2.4E+1 For 4" lead shield divide dose rate by:3.9E+2 Hydrogen Concentration: .04 Oxygen Concentration: 21.04 Airborne Beta Dose Rate: < 0.1 mRad/+

Airborne Thyroid Dose Rate: 0.5 mRem/hr Net Air Sample Contact Rate: 8.3 cpm/cf sample Floor Contamination: 0.4 cpm/100cm2 Mall and Equipment Contamination: < 0.1 cpm/100cm2 Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Personnel Contamination Rate: < O.l cpm/100cm2 per minute Stay Time: 2 MPC hr (no mask):4.6E+1 Hours Stay Time: 2 MPC hr (in mask):2.3E+3 Hours Stay Time: 2 MPC hr (in Air Sup. mask):9.3E+4 Hours

MNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 t TABLE P5. c RX BLDG & REFUEL FLOOR ACT. CONC. '(T = 03:30) ( 06:30)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 1.61E-09 uCi/cc Kr-87 1.79E-09 uCi/cc Kr-88 3.96E-09 uCi/cc Xe-133 1.47E-08 uCi/cc

'e-133m 5.08E-10 uCi/cc Xe-135 3.30E-09 uCi/cc Xe-138 8.01E-10 uCi/cc TOTAL GAS SAMPLE 2.68E-08 uCi/cc I-13 1 1.78E-10 uCi/cc I-132 1.78E-10 uCi/cc I-133 3.44E<<10 uCi/cc I-134 1.79E-10 uCi/cc I-135 2 '8E-10 uCi/cc TOTAL CHARCOAL SAMPLE 1.16E-09 uCi/cc Rb-88 2.83E-10 uCi/cc Cs-134 6 49E-11 uCi/cc Cs-136 2.58E-11 uCi/cc Cs-137 4.07E-11 uCi/cc TOTAL FILTER SAMPLE 4 '5E-10 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5. c RX BLDG & REFUEL FLOOR ACT. CONC. (T = 03:30) ( 06:30)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate at 1 ft.:

ft.:

< 0.1 mR/hr PASS Sample (14. ml) Dose Rate at 1 < 0.1 mR/hr PASS Sample (charcoal) Dose Rate at 1 ft.:

ft.:

< 0.1 mR/hr per cf cf PASS Sample (filter) Dose Rate at 1 < 0.1 mR/hr per For 2" lead shield divide dose rate by:2.4E+1 For 4" lead shield divide dose rate by:3.9E+2 Hydrogen Concentration: .04 Oxygen Concentration: 21.04 Airborne Beta Dose Rate: < O.l mRad/hr Airborne Thyroid Dose Rate: 0.5 mRem/hr Net Air Sample Contact Rate: 8.9 cpm/cf sample Floor Contamination: 0.4 cpm/100cm2 Wall and Equipment Contamination: < 0.1 cpm/100cm2 Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Stay Time: 2 MPC hr (no mask):4.3E+1 Hours Stay Time: 2 MPC hr (in mask):2.2E+3 Hours Stay Time: 2 MPC hr (in Air Sup. mask):8.7E+4 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5. d RX BLDG & REFUEL FLOOR ACT. CONC. (T = 03:45) ( 06:45)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 8 '7E-07 uCi/cc Kr-87 1.30E-06 uCi/cc Kr-88 2 21E-06 uCi/cc Xe-133 6.34E-06 uCi/cc Xe-133m 2 '0E-07 uCi/cc Xe-135 1.66E-06 uCi/cc Xe-138 1.34E-06 uCi/cc TOTAL GAS SAMPLE 1-39E-05 uCi/cc I-131 1.77E-07 uCi/cc I-132 2.11E-07 uci/cc I-133 3 49E-07 uCi/cc I-134 2 '1E-07 uCi/cc I-135 2.96E-07 uCi/cc

'OTAL CHARCOAL SAMPLE 1.29E-06 uCi/cc Rb-88 1.14E-07 uCi/cc Cs-134 4 31E-08 uCi/cc Cs-136 1.72E-08 uCi/cc Cs-137 2 71E-08 uCi/cc TOTAL FILTER SAMPLE 2 02E-07 uCi/cc CONTINUED ON NEXT PAGE

WNP-.2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5. d RX BLDG & REFUEL FLOOR ACT CONC (T = 03:45) ( 06:45)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate at at 1 ft.:

ft.:

< 0.1 0.1 mR/hr mR/hr PASS Sample (14. ml) Dose Rate 1 <

PASS Sample (charcoal) Dose Rate at 1 ft.:

ft.:

< 0.1 mR/hr per cf cf PASS Sample (filter) Dose Rate at 1 < 0.1 mR/hr per For 2" lead shield divide dose rate by:2.4E+1 For 4" lead shield divide dose rate by:4.1E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.94 Airborne Beta Dose Rate: 4.4 mRad/hr Airborne Thyroid Dose Rate: 540. mRem/hr Air Sample Contact Rate: 2.8 mR/hr / cf sample Floor Contamination: 46. cpm/100cm2 Wall and Equipment Contamination: 4.6 cpm/100cm2

'Personnel Contamination Rate: 0.9 cpm/100cm2 per minute Personnel Contamination Rate: 0.9 cpm/100cm2 per minute Stay Time: 2 MPC hr (no mask):4.7E-2 Hours Stay Time: 2 MPC hr (in mask):2.3E+0 Hours Stay Time: 2 MPC hr (in Air Sup. mask):9.3E+1 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5. e RX BLDG & REFUEL FLOOR ACT. CONC. (T = 04:00) ( 07:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 9.20E-07 uCi/cc Kr-87 1.35E-06 uCi/cc Kr-88 2.44E-06 uCi/cc, Xe-133 7.36E-06 uCi/cc Xe-133m 2.55E-07 uCi/cc Xe-135 1.90E-06 uCi/cc Xe-138 8.58E-07 uCi/cc TOTAL GAS SAMPLE 1.52E-05 uCi/cc I-13 1 1.67E-07 uci/cc I-132 1.87E-07 uCi/cc I-133 3.27E-07 uCi/cc I-134 2.09E-07 uci/cc I-135 2 73E-07 uCi/cc TOTAL CHARCOAL SAMPLE 1.16E-06 uCi/cc Rb-88 1.23E-07 uCi/cc Cs-134 4.52E-08 uCi/cc Cs-136 1.80E-08 uCi/cc Cs-137 2.83E-08 uCi/cc TOTAL FILTER SAMPLE 2.15E-07 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5. e RX BLDG & REFUEL FLOOR ACT. CONC. (T = 04:00) ( 07:00)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1

1 ft.:

ft.: <

0.1 0.1 mR/hr mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1 ft.:

ft.: < 0.1 0.1 mR/hr per cf cf 1 < mR/hr per For 2" lead shield divide dose rate by:2.4E+1 For 4" lead shield divide dose rate by:4.0E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.84 Airborne Beta Dose Rate: 4.5 mRad/hr Airborne Thyroid Dose Rate: 510. mRem/hr Air Sample Contact Rate: 2.6 mR/hr / cf sample Floor Contamination: 98. cpm/100cm2 Wall and Equipment Contamination: 9.8 cpm/100cm2 Personnel Contamination Rate: 0.8 cpm/100cm2 per minute Personnel Contamination Rate: 0.8 cpm/100cm2 per minute Stay Time: 2 MPC hr (no mask):4.9E-2 Hours Stay Time: 2 MPC hr (in mask):2.5E+0 Hours Stay Time: 2 MPC hr (in Air Sup. mask):9.8E+1 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5. f RX BLDG 6 REFUEL FLOOR ACT CONC ,(T = 04: 15) ( 07:3.5)

Provide current Chem data 30 minutes after sample request Nuclide Concentr'ation Kr-85m 6.93E-03 uCi/cc Kr-87 1.08E-02 uCi/cc Kr-88 1 87E-02 uCi/cc Xe-133 5.48E-02 uCi/cc Xe-133m 1.89E-03 uCi/cc Xe-135 1.77E-02 uCi/cc Xe-138 9.35E-03 uCi/cc TOTAL GAS SAMPLE 1 21E-01 uCi/cc Br-83 1.12E-03 uCi/cc Br-84 9.53E-04 uCi/cc I-131 1 28E-02 uCi/cc I-132 1.55E-02 uCi/cc I-133 2.52E-02 uCi/cc I-134 1.80E-02 uCi/cc I-135 2.13E-02 uCi/cc TOTAL CHARCOAL SAMPLE 9.48E-02 uCi/cc Rb-88 8.33E-03 uCi/cc Cs-134 4.04E-03 uCi/cc Cs-136 1.41E-03 uCi/cc Cs-137 2 '4E-03 uCi/cc TOTAL FILTER SAMPLE 1.69E-02 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5. f RX BLDG & REFUEL FLOOR ACT CONC. (T = 04:15) ( 07:15)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate at 1 0.1 mR/hr PASS Sample (14. ml) Dose Rate PASS Sample (charcoal) Dose Rate at at 1

1 ft.:

ft.: < 0.1 mR/hr

15. mR/hr per cf PASS Sample (filter) Dose Rate at 1 ft.: 2.5 mR/hr per cf For 2" lead shield divide dose rate by:3.0E+1 For 4" lead shield divide dose rate by:6.0E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.74 Airborne Beta Dose Rate: 3.8E4 mRad/hr Airborne Thyroid Dose Rate: 3.9E7 mRem/hr Air Sample Contact Rate: 2.1E5 mR/hr / cf sample Floor Contamination: 630. mR/100cm2 Hall and Equipment Contamination: 63. mR/100cm2 Personnel Contamination Rate: 22. mR/100cm2 per minut Personnel Contamination Rate: 22. mR/100cm2 per minut Stay Time: 2 MPC hr (no mask):7.3E-7 Hours Stay Time: 2 MPC hr (in mask):3.7E-5 Hours Stay Time: 2 MPC hr (in Air Sup. mask):1.5E-3 Hours

MNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5. g RX BLDG Er REFUEL FLOOR ACT. CONC. (T = 04:30) ( 07:30)

Provide current Chem data 30 minutes after sample recpxest Nuclide Concent'ration Kr-85m 9.93E-03 uCi/cc Kr-87 1.49E-02 uCi/cc Kr-88 2.66E-02 uCi/cc Xe-133 7.96E-02 uCi/cc Xe-133m 2.75E-03 uCi/cc Xe-135 2.58E-02 uCi/cc Xe-138 1.04E-02 uCi/cc TOTAL GAS SAMPLE 1.71E-01 uCi/cc Br-83 1.21E-03 uCi/cc I-131 1.42E-02 uCi/cc I-132 1.66E-02 uCi/cc I-133 2 '7E-02 uCi/cc I-134 1.84E-02 uCi/cc I-135 ~ 2.33E-02 uCi/cc TOTAL CHARCOAL SAMPLE 1.02E-01 uCi/cc Rb-88 8.58E-03 uCi/cc Cs-134 4.96E-03 uCi/cc Cs-136 1.73E-03 uCi/cc Cs-137 3.37E-03 uCi/cc TOTAL FILTER SAMPLE 1.91E-02 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5. g RX BLDG & REFUEL FLOOR ACT. CONC (T = 04 30) ( 07:30)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate at at 1 ft.:

ft.:

< 0.1 mR/hr 0.1 mR/hr PASS Sample (14. ml) Dose Rate 1 <

PASS Sample (charcoal) Dose Rate at 1 ft.:

ft.: 16. mR/hr per cf PASS Sample (filter) Dose Rate at 1 2.9 mR/hr per cf For 2" lead shield divide dose rate by:2.9E+1 For 4" lead shield divide dose rate by:5.8E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.64 Airborne Beta Dose Rate: 5.2E4 mRad/hr Airborne Thyroid Dose Rate: 4.3E7 mRem/hr Air Sample Contact Rate: 2.3E5 mR/hr / cf sample Floor Contamination: 2200. mR/100cm2 Wall and Equipment Contamination: 220. mR/100cm2 Personnel Contamination Rate: 24. mR/100cm2 per minute Personnel Contamination Rate: 24. mR/100cm2 per minute Stay Time: 2 MPC hr (no mask):6.6E-7 Hours Stay Time: 2 MPC hr (in mask):3.3E-5 Hours Stay Time: 2 MPC hr (in Air Sup. mask):1.3E-3 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5. h RX BLDG & REFUEL FLOOR ACT. CONC. (T = 04:45) ( 07:45)

Provide curreht Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 9.67E-03 uCi/cc Kr-87 1.41E-02 uCi/cc Kr-88 2 '7E-02 uCi/cc Xe-133 7.84E-02 uCi/cc Xe-133m 2.70E-03 uCi/cc Xe-135 2.53E-02 uCi/cc Xe-138 8.21E-03 uCi/cc TOTAL GAS SAMPLE 1.65E-01 uCi/cc Br-83 8.74E-04 uCi/cc I-131 1 '5E-02 uCi/cc I-132 1.20E-02 uCi/cc I-133 2.05E-02 uCi/cc I-134 1.29E-02 uCi/cc I-135 1.71E-02 uCi/cc TOTAL CHARCOAL SAMPLE 7.45E-02 uCi/cc Rb-88 6.46E-03 uCi/cc Cs-134 4.24E-03 uCi/cc Cs-136 1.48E-03 uCi/cc Cs-137 2.88E-03 uCi/cc TOTAL FILTER SAMPLE 1.55E-02 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5 h RX BLDG & REFUEL FLOOR ACT CONC. (T ~ 04:45) ( 07:45)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1

1 ft.:

ft.: 0.1 mR/hr 0.1 mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1

1 ft.:

ft.: 12. mR/hr per 2.3 mR/hr per cf cf For 2" lead shield divide dose rate by:2.9E+1 For 4" lead shield divide dose rate by:5.5E+2 Hydrogen Concentration: .0%

Oxygen Concentration: 20.64 Airborne Beta Dose Rate: 4.9E4 mRad/hr Airborne Thyroid Dose Rate: 3.2E7 mRem/hr Air Sample Contact Rate: 1.7E5 mR/hr / cf sample Floor Contamination: 3600. mR/100cm2 Wall and Equipment Contamination: 360. mR/100cm2 Personnel Contamination Rate: 17. mR/100cm2 per minute Personnel Contamination Rate: 17. mR/100cm2 per minute Stay Time: 2 MPC hr (no mask):8.8E-7 Hours Stay Time: 2 MPC hr (in mask):4.4E-5 Hours Stay Time: 2 MPC hr (in Air Sup. mask):1.8E-3 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5. i RX BLDG & REFUEL FLOOR ACT. CONC. (T = 05:00) ( 08:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentr'ation Kr-85m 9.39E-03 uCi/cc Kr-87 1.33E-02 uCi/cc Kr-88 2.48E-02 uCi/cc Xe-133 7 '0E-02 uCi/cc Xe-133m 2.65E-03 uCi/cc Xe-135 2.48E-02 uCi/cc Xe-138 6.47E-03 uCi/cc TOTAL GAS SAMPLE 1.59E-01 uCi/cc Br-83 6.35E-04 uCi/cc I-131 7 '8E-03 uCi/cc I-132 8 73E-03 uCi/cc I-133 1 '2E-02 uCi/cc I-134 9 ~ OOE-03 uCi/cc I-135 1 '6E-02 uCi/cc TOTAL CHARCOAL SAMPLE 5.43E-02 uCi/cc Rb-88 4.93E-03 uCi/cc Cs-134 3.63E-03 uCi/cc Cs-136 1.26E-03 uCi/cc Cs-137 2 '6E-03 uCi/cc TOTAL FILTER SAMPLE 1.26E-02 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV .0 TABLE P5 RX BLDG 6 REFUEL FLOOR ACT. CONC (T = 05:00) ( 08:00)

(continued)

Provide current Chem data 30 minutes after sample recpxest Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1 ft.:

ft.:

< 0.1 0.1 mR/hr 1 < mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1

1 ft.:

ft.: 8.7 1.9 mR/hr per mR/hr per cf cf For 2" lead shield divide dose rate by:2.8E+1 For 4" lead shield divide dose rate by:5.3E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.64 Airborne Beta Dose Rate: 4.6E4 mRad/hr Airborne Thyroid Dose Rate: 2.4E7 mRem/hr Air Sample Contact Rate: 1.3E5 mR/hr / cf sample Floor Contamination: 4500. mR/100cm2 Wall and Ecgxipment Contamination: 450. mR/100cm2 Personnel Contamination Rate: 13. mR/100cm2 per minute~

Personnel Contamination Rate: 13. mR/100cm2 per minute~

Stay Time: 2 MPC hr (no mask):1.2E-6 Hours Stay Time: 2 MPC hr (in mask):5.9E-5 Hours Stay Time: 2 MPC hr (in Air Sup. mask):2.4E-3 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5. j RX BLDG & REFUEL FLOOR ACT. CONC. (T = 05:15) ( 08:15)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 9 12E-03 uCi/cc Kr-87 1 25E-02 uCi/cc Kr-88 2 39E-02 uCi/cc Xe-133 7 56E-02 uCi/cc Xe-133m 2.60E-03 uCi/cc Xe-135 2 '2E-02 uCi/cc Xe-138 5.10E-03 uCi/cc TOTAL GAS SAMPLE 1.54E-01 uCi/cc Br-83 4 '1E-04 uCi/cc I-131 5.77E-03 uCi/cc I-132 6.34E-03 uCi/cc I-133 1.12E-02 uCi/cc I-134 6.29E-03 uCi/cc I-135 9.29E-03 uCi/cc TOTAL CHARCOAL SAMPLE 3.97E-02 uCi/cc Rb-88 3 82E-03 uCi/cc Cs-134 3 '0E-03 uCi/cc Cs-136 1 08E-03 uCi/cc Cs-137 2 '1E-03 uCi/cc TOTAL FILTER SAMPLE 1.04E-02 uCi/cc CONTINUED ON NEXT PAGE

MNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5.

RX BLDG & REFUEL FLOOR ACT. CONC. (T = 05:15) ( 08:15)

. (continued)

Provide current, Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1

1 ft.:

ft.: <

'0.1 mR/hr 0.1 mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1

1 ft.:

ft.: 6.4 mR/hr per cf 1.6 mR/hr per cf For 2" lead shield divide dose rate by:2.8E+1 For 4" lead shield divide dose rate by:5.0E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.64 Airborne Beta Dose Rate: 4.4E4 mRad/hr Airborne Thyroid Dose Rate: 1.7E7 mRem/hr Air Sample Contact Rate: 9.4E4 mR/hr / cf sample Floor Contamination: 5200. mR/100cm2

'no Mall and Equipment Contamination: 520. mR/100cm2 Personnel Contamination Rate: 9.3 mR/100cm2 per minute Personnel Contamination Rate: 9.3 mR/100cm2 per minute Stay Time: 2 HPC hr mask):1.6E-6 Hours Stay Time: 2 MPC hr (in mask):7.8E-5 Hours Stay Time: 2 NPC hr (in Air Sup. mask):3.1E-3 Hours

HNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5 k RX BLDG & REFUEL FLOOR ACT. CONC. (T = 05-30) ( 08:30)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 8.86E-03 uCi/cc Kr-87 1.18E-02 uCi/cc Kr-88 2.31E-02 uCi/cc Xe-133 7.42E-02 uCi/cc Xe-133m 2.56E-03 uCi/cc Xe-135 2 '7E-02 uCi/cc Xe-138 4.02E-03 uCi/cc TOTAL GAS SAMPLE 1.49E-01 uCi/cc Br-83 3.35E-04 uCi/cc I-131 4 29E-.03 uCi/cc I-132 4.60E-03 uCi/cc I-133 8 '1E-03 uCi/cc I-134 4.40E-03 uCi/cc I-135 6.84E 03 uci/cc TOTAL CHARCOAL SAMPLE 2 '0E-02 uCi/cc Rb-88's-134 3.02E-03 uCi/cc 2.66E-03 uCi/cc Cs-136 9.25E-04 uCi/cc Cs-137 1.80E-03 uCi/cc TOTAL FILTER SAMPLE 8.66E-03 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenar io 93e Annual Exercise Unit 2 REV 0 TABLE P5. k RX BLDG & REFUEL FLOOR ACT. CONC (T = 05:30) ( 08:30)

.(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate at 1 0.1 mR/hr PASS Sample (14. ml)

PASS Sample (charcoal)

Dose Dose Rate Rate at at 1

1 ft.:

ft.: 0.1 4.7 mR/hr mR/hr per cf PASS Sample (filter) Dose Rate at 1 ft.: 1.3 mR/hr per cf For 2" lead shield divide dose rate by:2.7E+1 For 4" lead shield divide dose rate by:4.8E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20. 64 Airborne Beta Dose Rate: 4.2E4 mRad/hr Airborne Thyroid Dose Rate: 1.3E7 mRem/hr Air Sample Contact Rate: 7.1E4 mR/hr / cf sample Floor Contamination: 5600. mR/100cm2 Wall and Equipment Contamination: 560. mR/100cm2 Personnel Contamination Rate: 6.8 mR/100cm2 per minute Personnel Contamination Rate: 6.8 mR/100cm2 per minute Stay Time: 2 MPC hr .

(no mask):2.1E-6 Hours Stay Time: 2 MPC hr (in mask):1.0E-4 Hours Stay Time: 2 MPC hr {in Air Sup. mask):4.1E-3 Hours

MNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5 l RX BLDG & REFUEL FLOOR ACT. CONC. (T = 05:45) ( 08:45)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 8.60E-03 uCi/cc Kr-87 1.12E-02 uCi/cc Kr-88 2.22E-02 uCi/cc Xe-133 7.29E-02 uCi/cc Xe-133m 2.51E-03 uCi/cc Xe-135 2.32E-02 uCi/cc Xe-138 3.17E-03 uCi/cc TOTAL GAS SAMPLE 1.45E-01 uCi/cc Br-83 2.44E-04 uCi/cc I-131 3.19E-03 uCi/cc I-132 3.35E-03 uCi/cc I-133 6.17E-03 uCi/cc I-134 3.09E-03 uCi/cc I-135 5. 05E-03, uCi/cc TOTAL CHARCOAL SAMPLE 2 '2E-02 uCi/cc Rb-88 2.43E-03 uCi/cc Cs-134 2.27E-03 uCi/cc Cs-136 7.92E-04 uCi/cc Cs-137 1.54E-03 uCi/cc TOTAL FILTER SAMPLE 7.26E-03 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5. l RX BLDG & REFUEL FLOOR ACT. CONC. (T = 05:45) ( 08:45)

,(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1

1 ft.:

ft.: <

0.1 0.1 mR/hr mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1

1 ft.:

ft.: 3.4 1.1 mR/hr per mR/hr per cf cf For 2" lead shield divide dose rate by:2.6E+1 For 4" lead shield divide dose rate by:4.6E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.64 Airborne Beta Dose Rate: 4.0E4 mRad/hr Airborne Thyroid Dose Rate: 9.6E6 mRem/hr Air Sample Contact Rate: 5.4E4 mR/hr / cf sample Floor Contamination: 6000. mR/100cm2 Wall and Equipment Contamination: 600. mR/100cm2 Personnel Contamination Rate: 5.0 mR/100cm2 per minute Personnel Contamination Rate: 5.0 mR/100cm2 per minute Stay Time: 2 MPC hr (no mask):2.7E-6 Hours Stay Time: 2 MPC hr (in mask):1.4E-4 Hours Stay Time: 2 MPC hr (in Air Sup. mask):5.4E-3 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5. m RX BLDG & REFUEL FLOOR ACT. CONC. (T ~ 06-00) ( 09 00)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml)

PASS Sample (14. ml)

Dose Rate Rate at at 1 ft.:

ft.: < 0.1 0.1 mR/hr Dose 1 < mR/hr PASS Sample (charcoal)

PASS Sample (filter)

Dose Dose Rate Rate at at 1

1 ft.:

ft.: 2.5 0.9 mR/hr per mR/hr per cf cf For 2" lead shield divide dose rate by:2.6E+1 For 4" lead shield divide dose rate by:4.5E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.64 Airborne Beta Dose Rate: 3.8E4 mRad/hr Airborne Thyroid Dose Rate: 7.1E6 mRem/hr Air Sample Contact Rate: 4.1E4 mR/hr / cf sample Floor Contamination: 6200. mR/100cm2 Wall and Equipment Contamination: 620. mR/100cm2 Personnel Contamination Rate: 3.7 mR/100cm2 per minute Personnel Contamination Rate: 3.7 mR/100cm2 per minute Stay Time: 2 MPC hr (no mask):3.6E-6 Hours Stay Time: 2 MPC hr (in mask):1.8E-4 Hours Stay Time: 2 MPC hr (in Air Sup. mask):7.1E-3 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5. n RX BLDG & REFUEL FLOOR ACT. CONC (T = 06:15) ( 09:15)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 8 11E-03 uCi/cc Kr-87 9 92E-03 uci/cc Kr-88 2.07E-02 uCi/cc Xe-133 7 '3E-02 uCi/cc Xe-133m 2 42E-03 uCi/cc Xe-135 2 '2E-02 uCi/cc Xe-138 1 97E-03 uCi/cc TOTAL GAS SAMPLE 1.36E-01 uCi/cc Br-83 1.30E-04 uCi/cc I-131 1.77E-03 uCi/cc I-132 1.78E-03 uCi/cc I-133 3.41E-03 uCi/cc I-134 1.52E-03 uCi/cc I-135 2.76E-03 uCi/cc TOTAL CHARCOAL SAMPLE 1.14E-02 uCi/cc Rb-88 1.69E-03 uCi/cc Cs-134 1.67E-03 uCi/cc Cs-136 5.82E-04 uCi/cc Cs-137 1.14E-03 uCi/cc TOTAL FILTER SAMPLE 5.23E-03 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5. n RX BLDG & REFUEL FLOOR ACT. CONC (T = 06:15) ( 09:15)

(continued)

Provide current Chem data 30 minutes after sample request I

Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1 ft.:

ft.:

< 0.1 0.1 mR/hr 1 < mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1 ft.:

ft.: 1.9 0.8 mR/hr per cf cf 1 mR/hr per For 2" lead shield divide dose rate by:2.6E+1 For 4" lead shield divide dose rate by:4.3E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.64 Airborne Beta Dose Rate: 3.7E4 mRad/hr Airborne Thyroid Dose Rate: 5.3E6 mRem/hr Air Sample Contact Rate: 3.1E4 mR/hr / cf sample Floor Contamination: 6300. mR/100cm2 Wall and Equipment Contamination: 630. mR/100cm2 Personnel Contamination Rate: 2.8 mR/100cm2 per minute Personnel Contamination Rate: 2.8 mR/100cm2 per minute Stay Time: 2 MPC hr (no mask):4.6E-6 Hours Stay Time: 2 MPC hr (in mask):2.3E-4 Hours Stay Time: 2 MPC hr (in Air Sup. mask):9.2E-3 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5. o RX BLDG & REFUEL FLOOR ACT CONC. (T = 06:30) ( 09:30)

Provide current Chem data 30 minutes after sample recpxest Nuclide Concentration Kr-85m 7.88E-03 uCi/cc Kr-87 9.36E-03 uCi/cc Kr-88 2.00E-02 uCi/cc Xe-133 6 91E-02 uCi/cc Xe-133m 2.37E-03 uCi/cc Xe-135 2 17E-02 uCi/cc Xe-138 1.55E-03 uCi/cc TOTAL GAS SAMPLE 1 33E-01 uCi/cc Br-83 9 52E-05 uCi/cc I-131 1.33E-03 uCi/cc I-132 1.30E-03 uCi/cc I-133 2 55E-03 uCi/cc I-134 1.08E-03 uCi/cc I-135 2 '5E-03 uCi/cc TOTAL CHARCOAL SAMPLE 8.44E-03 uCi/cc Rb-88 1.45E-03 uCi/cc Cs-134 1.44E-03 uCi/cc Cs-136 4 '9E-04 uCi/cc Cs-137 9.74E-04 uCi/cc TOTAL FILTER SAMPLE 4.49E-03 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5. o RX BLDG & REFUEL FLOOR ACT. CONC. (T ~ 06:30) ( 09:30)

(continued)

Provide current. Chem data 30 minutes after sample reepxest Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1 ft.:

ft.: << 0.1 0.1 mR/hr 1 << mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1 ft.:

ft.: 1.4 0.7 mR/hr per cf cf 1 mR/hr per For 2" lead shield divide dose rate by:2.5E+1 For 4" lead shield divide dose rate by:4.2E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.64 Airborne Beta Dose Rate: 3.5E4 mRad/hr Airborne Thyroid Dose Rate: 4.0E6 mRem/hr Air Sample Contact Rate: 2.4E4 mR/hr / cf sample Floor Contamination: 6400. mR/100cm2 Mall and Equipment Contamination: 640. mR/100cm2 Personnel Contamination Rate: 2.1 mR/100cm2 per minute Personnel Contamination Rate: 2.1 mR/100cm2 per minute Stay Time: 2 MPC hr (no mask):5.9E-6 Hours Stay Time: 2 MPC hr (in mask):3.0E-4 Hours Stay Time: 2 MPC hr (in Air Sup. mask):1.2E-2 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0, TABLE P5. p RX BLDG 6 REFUEL FLOOR ACT. CONC. (T = 06:45) ( 09:45)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 7.65E-03 uCi/cc Kr-87 8 '3E-03 uCi/cc Kr-88 1.93E-02 uCi/cc Xe-133 6.79E-02 uCi/cc Xe-133m 2.33E-03 uCi/cc Xe-135 2.12E-02 uCi/cc TOTAL GAS SAMPLE 1.29E-01 uCi/cc Br-83 7.01E-05 uCi/cc I-131 9.98E-04 uCi/cc I-132 9.57E-04 uCi/cc I-133 1.91E-03 uCi/cc I-134 7.62E-04 uCi/cc I-135 1.53E-03 uCi/cc TOTAL CHARCOAL SAMPLE 6.26E-03 uCi/cc Rb-88 1.27E-03 uCi/cc Cs-134 1 '3E-03 uCi/cc Cs-136 4.29E-04 uCi/cc Cs-137 8.37E-04 uCi/cc TOTAL FILTER SAMPLE 3.88E-03 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5. p RX BLDG & REFUEL FLOOR ACT. CONC. (T = 06:45) ( 09:45)

(continued)

Provide current Chem data 30 minutes after sample request.

Normal Sample (15. ml) Dose Rate at at 1 ft.:

ft.: < 0.1 0.1 mR/hr PASS Sample (14. ml) Dose Rate 1 < mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1

1 ft.:

ft.: 1.0 0.6 mR/hr per mR/hr per cf cf For 2" lead shield divide dose rate by:2.5E+1 For 4" lead shield divide dose rate by:4.1E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.64 Airborne Beta Dose Rate: 3.4E4 mRad/hr Airborne Thyroid Dose Rate: 3.0E6 mRem/hr Air Sample Contact Rate: 1.9E4 mR/hr / cf sample Floor Contamination: 6400. mR/100cm2 Wall and Equipment Contamination: 640. mR/100cm2 Personnel Contamination Rate: 4700. cpm/100cm2 per minute Personnel Contamination Rate: 4700. cpm/100cm2 per minute Stay Time: 2 MPC hr (no mask):7.5E-6 Hours Stay Time: 2 MPC hr (in mask): 3. 7E-4 Hours Stay Time: 2 MPC hr (in Air Sup. mask):1.5E-2 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5. q RX BLDG & REFUEL FLOOR ACT. CONC. (T ~ 07:00) ( 10:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 7 '3E-03 uCi/cc Kr-87 8 33E-03 uCi/cc Kr-88 1.86E-02 uCi/cc Xe-133 6.67E-02 uCi/cc Xe-133m 2.29E-03 uCi/cc Xe-135 2 07E-02 uCi/cc TOTAL GAS SAMPLE 1.26E-01 uCi/cc Br-83 5.18E-05 uCi/cc I-131 7.54E-04 uCi/cc I-132 7 '8E-04 uCi/cc I-133 1.44E-03 uCi/cc I-134 5 '3E-04 uCi/cc I-135 1.15E-03 uCi/cc TOTAL CHARCOAL SAMPLE 4.67E-03 uCi/cc Rb-88 1.14E-03 uCi/cc Cs-134 1 '6E-03 uCi/cc Cs-136 3.69E-04 uCi/cc Cs-137 7.20E-04 uCi/cc TOTAL FILTER SAMPLE 3.38E-03 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5. q RX BLDG & REFUEL FLOOR ACT. CONC. (T = 07 00) ( 10:00)

(continued)

Provide current. Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1 ft.:

ft.:

< 0.1 0.1 mR/hr 1 < mR/hr PASS Sample (charcoal) Dose Rate at 1 ft.: 0.8 mR/hr per cf PASS Sample (filter) Dose Rate at 1 ft.: 0.5 mR/hr per cf For 2" lead shield divide dose rate by:2.5E+1 For 4" lead shield divide dose rate by:4.1E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.64 Airborne Beta Dose Rate: 3.3E4 mRad/hr Airborne Thyroid Dose Rate: 2.3E6 mRem/hr Air Sample Contact Rate: 1.5E4 mR/hr / cf sample Floor Contamination: 6400. mR/100cm2 Mall and Equipment Contamination: 640. mR/100cm2 Personnel Contamination Rate: 3600. cpm/100cm2 per minute Personnel Contamination Rate: 3600. cpm/100cm2 per minute Stay Time: 2 MPC hr (no mask):9.4E-6 Hours Stay Time: 2 MPC hr (in mask):4.7E-4 Hours Stay Time: 2 MPC hr (in Air Sup. mask):1.9E-2 Hours

WHP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5. r RX BLDG & REFUEL FLOOR ACT. CONC (T = 07:15) ( 10:15)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 7.22E-03 uCi/cc Kr-87 7.86E-03 uCi/cc Kr-88 1.79E-02 uCi/cc Xe-133 6.55E-02 uCi/cc Xe-133m 2.25E-03 uCi/cc Xe-135 2 02E-02 uCi/cc TOTAL GAS SAMPLE 1.22E-01 uCi/cc Br-83 3.87E-05 uCi/cc I-131 5.74E-04 uCi/cc I-132 5.27E-04 uCi/cc I-133 1.10E-03 uCi/cc I-134 3.90E-04 uCi/cc I-135 8.69E-04 uCi/cc TOTAL CHARCOAL SAMPLE 3 51E-03 uCi/cc Rb-88 1.03E-03 uCi/cc Cs-134 9.14E-04 uCi/cc Cs-136 3.18E-04 uCi/cc Cs-137 6.21E-04 uCi/cc TOTAL FILTER SAMPLE 2.96E-03 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5. r RX BLDG & REFUEL FLOOR ACT. CONC. (T ~ 07:15) ( 10:15)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml)

PASS Sample (14. ml)

Dose Dose Rate Rate at at 1

1 ft.:

ft.:

0.1 0.1 mR/hr mR/hr PASS Sample (charcoal)

PASS Sample (filter)

Dose Rate at at 1 ft.:

ft.: 0.6 0.5 mR/hr per cf cf Dose Rate 1 mR/hr per For 2" lead shield divide dose rate by:2.5E+1 For 4" lead shield divide dose rate by:4.0E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.64 Airborne Beta Dose Rate: 3.1E4 mRad/hr Airborne Thyroid Dose Rate: 1.7E6 mRem/hr Air Sample Contact Rate: 1.2E4 mR/hr / cf sample Floor Contamination: 6400. mR/100cm2 Wall and Equipment Contamination: 640. mR/100cm2 Personnel Contamination Rate: 2700. cpm/100cm2 per minute Personnel Contamination Rate: 2700. cpm/100cm2 per minute Stay Time: 2 MPC hr (no mask):1.2E-5 Hours Stay Time: 2 MPC hr '(in mask):5.8E-4 Hours Stay Time: 2 MPC hr (in Air Sup. mask):2..3E-2 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE PS. s RX BLDG & REFUEL FLOOR ACT CONC (T = 07:30) { 10:30)

Provide current, Chem data 30 minutes after sample request Nuclide Concentr'ation Kr-85m 7 '1E-03 uCi/cc Kr-87 7.41E-03 uCi/cc Kr-88 1.73E-02 uCi/cc Xe-133 6.43E-02 uCi/cc Xe<<133m 2.20E-03 uCi/cc Xe-135 1.98E-02 uCi/cc TOTAL GAS SAMPLE 1.19E-01 uCi/cc Br-83 2.91E-05 uCi/cc I-131 4.42E-04 uCi/cc I-132 3.96E-04 uCi/cc I-133 8.41E-04 uCi/cc I-134 2.83E-04 uCi/cc

'I-135 6.63E-04 uCi/cc TOTAL CHARCOAL SAMPLE 2.66E-03 uCi/cc Rb-88 9.47E-04 uCi/cc Cs-134 7.89E-04 uCi/cc

's-136 2.74E-04 uCi/cc Cs-137 5.36E-04 uCi/cc TOTAL FILTER SAMPLE 2.61E-03 uCi/cc CONTINUED ON NEXT PAGE

~ 'ABLE NNP-2 Nuclear Generating Station Annual Exercise RX BLDG &

P5. s REFUEL FLOOR ACT. CONC (continued)

Scenario (T = 07-30)

Unit

( 10:30) 93e 2 REV 0 Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate at. 1 PASS Sample (14. ml) Dose Rate at 1 ft.:

ft.:

< 0.1 0.1 mR/hr

< mR/hr PASS Sample (charcoal) Dose Rate at 1 PASS Sample (filter) Dose Rate at 1 ft.:

ft.: 0.4 0.4 mR/hr per cf cf mR/hr per For 2" lead shield divide dose rate by:2.4E+1 For 4" lead shield divide dose rate by:3.9E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.64 Airborne Beta Dose Rate: 3.0E4 mRad/hr Airborne Thyroid Dose Rate: 1.3E6 mRem/hr Air Sample Contact Rate: 9900. mR/hr / cf sample Floor Contamination: 6300. mR/100cm2 Mall and Equipment Contamination: 630. mR/100cm2 Personnel Contamination Rate: 2100. cpm/100cm2 per minute Personnel Contamination Rate: 2100. cpm/100cm2 per minute Stay Time: 2 MPC hr (no mask):1.4E-5 Hours Stay Time: 2 MPC hr (in mask):7.0E-4 Hours Stay Time: 2 MPC hr (in Air Sup. mask):2.8E-2 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE PS. t RX BLDG & REFUEL FLOOR ACT. CONC. (T = 08:00) ( 11:00)

Provide current Chem data 30 minutes after sample recpxest Nuclide Concentr'ation Kr-85m 6.62E-03 uCi/cc Kr-87 6.60E-03 uCi/cc Kr-88 1.61E-02 uCi/cc Xe-133 6.21E-02 uCi/cc Xe-133m 2.13E>>03 uCi/cc Xe-135 1.89E-02 uCi/cc TOTAL GAS SAMPLE 1.13E-01 uCi/cc Br-83 1.71E-05 uCi/cc I-131 2.71E-04 uCi/cc I-132 2.32E-04 uCi/cc I-133 5.13E-04 uCi/cc I-134 1.54E-04 uCi/cc I-135 4.00E-04 uCi/cc TOTAL CHARCOAL SAMPLE 1.59E-03 uCi/cc Rb-88 8.24E-04 uCi/cc Cs-134 5.91E-04 uCi/cc Cs-136 2.05E-04 uCi/cc Cs-137 4.01E-04 uCi/cc TOTAL FILTER SAMPLE 2.07E-03 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P5. t RX BLDG 5 REFUEL FLOOR ACT. CONC. (T = 08:00) ( 11:00)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1

1 ft.:

ft.: <

0.1 0.1 mR/hr mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1 ft.:

ft.: 0.3 0.3 mR/hr per cf cf 1 mR/hr per For 2" lead shield divide dose rate by:2.4E+1 For 4" lead shield divide dose rate by:3.9E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.64 Airborne Beta Dose Rate: 2.8E4 mRad/hr Airborne Thyroid Dose Rate: 8.1E5 mRem/hr Air Sample Contact Rate: 6900. mR/hr / cf sample Floor Contamination: 6200. mR/100cm2 Wall and Equipment Contamination: 620. mR/100cm2 Personnel Contamination Rate: 1300. cpm/100cm2 per minute Personnel Contamination Rate: 1300. cpm/100cm2 per minute Stay Time: 2 MPC hr (no mask):2.0E-5 Hours Stay Time: 2 MPC hr (in mask):9.9E-4 Hours Stay Time: 2 MPC hr (in Air Sup. mask):3.9E-2 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. a RX BLDG ELEVATED RELEASE POINT CONC. (T = 00:00) ( 03:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 2 46E-10 uCi/cc Kr-87 4 '3E-10 uCi/cc Kr'-88 6.80E-10 uCi/cc Xe-133 1 84E-09 uCi/cc Xe-133m 6 38E-11 uCi/cc Xe-135 5 '3E-10 uCi/cc Xe-138 8 23E-10 uCi/cc TOTAL GAS SAMPLE 4.69E-09 uCi/cc I-131 4.42E-11 uCi/cc I-132 5.80E-11 uCi/cc I-133 1.07E-10 uCi/cc I-134 7.45E-11 uCi/cc I-135 1 '4E-10 uCi/cc TOTAL CHARCOAL SAMPLE 3 '8E-10 uCi/cc Cs-134 9 '0E-12 uCi/cc Cs-136 3.79E-12 uCi/cc Cs-137 6 20E-12 uCi/cc Np-239 2 '3E-12 uCi/cc TOTAL FXLTER SAMPLE 2.24E-11 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. a RX BLDG ELEVATED RELEASE POINT CONC. (T = 00:00) ( 03:00)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1

1 ft.:

ft.: <

0.1 0.1 mR/hr mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1 ft.:

ft.: < 0.1 0.1 mR/hr per cf cf 1 < mR/hr per For 2" lead shield divide dose rate by:2.4E+1 For 4" lead shield divide dose rate by:4.1E+2 Hydrogen Concentration: .04 Oxygen Concentration: 21.04

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. b RX BLDG ELEVATED RELEASE POINT CONC (T = 03:00) ( 06:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 1.04E-OS uCi/cc Kr-87 1 '6E-08 uCi/cc Kr-88 2 '7E-08 uCi/cc Xe-133 9.40E-08 uCi/cc Xe-133m 3.26E-09 uCi/cc Xe-135 1.97E-OS uCi/cc Xe-138 5.05E-09 uCi/cc TOTAL GAS SAMPLE 1.70E-07 uCi/cc I-131 1. 35E-13 uCi/cc I-132 1.27E-13 uCi/cc I-133 2.60E-13 uCi/cc I-134 1.15E-13 uCi/cc I-135 2.07E-13 uCi/cc TOTAL CHARCOAL SAMPLE 8.43E-13 uCi/cc Rb-88 1 47E-11 uCi/cc TOTAL FILTER SAMPLE 1.49E-11 uCi/cc Normal Sample (15. ml) Dose Rate'at PASS Sample (14. ml) Dose Rate at 1 ft.:

ft.:

< 0.1 0.1 mR/hr 1 < mR/hr PASS Sample (charcoal) Dose Rate at PASS Sample (filter) Dose Rate at.

1 ft.:

ft.: < 0.1 0.1 mR/hr per cf cf 1 < mR/hr per For 2" lead shield divide dose rate by:2.3E+1 For 4" lead shield divide dose rate by:3.6E+2 Hydrogen Concentration: .04 Oxygen Concentration: 21.04

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. c RX BLDG ELEVATED RELEASE POINT CONC (T = 03:30) ( 06:30)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 1.18E-08 uCi/cc Kr-87 1 24E-08 uCi/cc Kr-88 2.87E-08 uCi/cc Xe-133 1 11E-07 uCi/cc Xe-133m 3.83E-09 uCi/cc Xe-135 2.33E-08 uCi/cc Xe-138 5.05E-09 uCi/cc TOTAL GAS SAMPLE 1 97E-07 uCi/cc I-131 1 54E-13 uCi/cc I-132 1 36E-13 uCi/cc I-133 2 '2E-13 uCi/cc I-134 1 17E-13 uCi/cc I-135 2.30E-13 uCi/cc TOTAL CHARCOAL SAMPLE 9 29E-13 uCi/cc Rb-88 1.67E-11 uCi/cc TOTAL FILTER SAMPLE 1.70E-11 uCi/cc Normal Sample (15. ml) Dose Rate.

PASS Sample (14. ml) Dose Rate at at 1 ft.:

ft.:

< 0.1 0.1 mR/hr 1 < mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1 ft.:

ft.: < 0.1 0.1 mR/hr per cf cf 1 < mR/hr per For 2" lead shield divide dose rate by:2.3E+1 For 4" lead shield divide dose rate by:3.6E+2 Hydrogen Concentration: .04 Oxygen Concentration: 21.04

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. d RX BLDG ELEVATED RELEASE POINT CONC. (T = 03:45) ( 06:45)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 7.25E-07 uCi/cc Kr-87 1.18E-06 uCi/cc Kr-88 1.97E-06 uCi/cc Xe-133 5.58E-06 uCi/cc Xe-133m 1.94E-07 uCi/cc Xe-135 1 '6E-06 uCi/cc Xe-138 1.36E-06 uCi/cc TOTAL GAS SAMPLE 1.25E-05 uCi/cc I-131 4.97E-11 uCi/cc I-132 6.01E-11 uCi/cc I-133 9.79E-11 uCi/cc I-134 7.61E-11 uCi/cc

.I-135 8,.34E-11 uCi/cc TOTAL CHARCOAL SAMPLE 3.67E-10 uCi/cc Rb-88 7 '4E-09 uCi/cc TOTAL FILTER SAMPLE 7.42E-09 uCi/cc Normal Sample (15. ml) Dose Rate at. 1 ft.:

ft.:

< 0.1 mR/hr PASS Sample (14. ml) Dose Rate at 1 < 0.1 mR/hr PASS Sample (charcoal) Dose Rate at 1 ft.:

ft.:

< 0.1 mR/hr per cf cf PASS Sample (filter) Dose Rate at 1 < 0.1 mR/hr per For 2" lead shield divide dose rate by:2.3E+1 For 4" lead shield divide dose rate by:3.6E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.94

MNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit, 2 REV 0 TABLE P6. e RX BLDG ELEVATED RELEASE POINT CONC. (T = 04:00) ( 07:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 8.85E-07 uCi/cc Kr-87 1 33E-06 uCi/cc Kr-88 2 36E-06 uCi/cc Xe-133 7 02E-06 uCi/cc Xe-133m 2 44E-07 uci/cc Xe-135 1 '2E-06 uCi/cc Xe-138 9.49E-07 uCi/cc TOTAL GAS SAMPLE 1.47E-05 uCi/cc I-131 5.11E-11 uCi/cc I-132 5.82E-11 uCi/cc I-133 1.00E-10 uCi/cc I-134 6. 67E-11 uCi/cc I-135 8.41E-11 uCi/cc TOTAL CHARCOAL SAMPLE 3 60E-10 uCi/cc

~

Rb-88 8.80E-09 uCi/cc TOTAL FILTER SAMPLE 8 '9E-09 uCi/cc Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1

1 ft.:

ft.: <

0.1 0.1 mR/hr mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1

1 ft.:

ft.: <

0.1 0.1 mR/hr per mR/hr per cf cf For 2" lead shield divide dose rate by:2.2E+1 For 4" lead shield divide dose rate by:3.6E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.84

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. f RX BLDG ELEVATED RELEASE POINT CONC. (T = 04:15) ( 07:15)

Provide current Chem data 30 minutes after sample request Nuclide 'oncentration Kr-85m 6.59E-03 uCi/cc Kr-87 1.03E-02 uCi/cc Kr-88 1 78E-02 uCi/cc Xe-133 5 21E-02 uCi/cc Xe-133m 1 80E-03 uci/cc Xe-135 1.69E-02 uCi/cc Xe-138 8 96E-03 uCi/cc TOTAL GAS SAMPLE 1.15E-01 uCi/cc Br-83 3 '9E-07 uCi/cc Br-84 2.81E-07 uCi/cc I-131 3 77E-06 uCi/cc I-132 4.55E-06 uCi/cc I-133 7.39E-06 uCi/cc I-134 5.28E-06 uCi/cc I-135 6.26E-06 uCi/cc TOTAL CHARCOAL SAMPLE 2.79E-05 uCi/cc Rb-88 1 14E-05 uCi/cc Cs-134 3.93E-06 uCi/cc Cs-136 1 37E-06 uCi/cc Cs-137 2 '7E-06 uCi/cc TOTAL FILTER SAMPLE 1.94E-05 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. f RX BLDG ELEVATED RELEASE POINT CONC. (T = 04:15) ( 07:15)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1

1 ft.:

ft.: 0.1 0.1 mR/hr mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1 ft.:

ft.: 0.1 0.1 mR/hr per cf cf 1 mR/hr per For 2" lead shield divide dose rate by:2.3E+1 For 4" lead shield divide dose rate by:3.7E+2

, Hydrogen Concentration: .04 Oxygen Concentration: 20.64

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. g RX BLDG ELEVATED RELEASE POINT CONC. (T = 04:30) ( 07:30)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 9 '2E-03'Ci/cc Kr-87 1.46E-02 uCi/cc Kr-88 2.60E-02 uCi/cc Xe-133 7.79E-02 uCi/cc Xe-133m 2 69E-03 uCi/cc Xe-135 2.52E-02 uCi/cc Xe-138 1.02E-02 uCi/cc TOTAL GAS SAMPLE 1.67E-01 uCi/cc Br-83 3 63E-07 uCi/cc I-131 4.26E-06 uCi/cc I-132 5.00E-06 uCi/cc I-133 8.33E-06 uCi/cc I-134 5.54E-06 uCi/cc I-135 7.01E-06 uCi/cc TOTAL CHARCOAL SAMPLE 3.08E-05 uCi/cc Rb-88 8.58E-06 uCi/cc Cs-134 4 '6E-06 uCi/cc Cs-136 1 73E-06 uCi/cc Cs-137 3.37E-06 uCi/cc TOTAL FILTER SAMPLE 1.87E-05 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e

'Annual Exercise Unit 2 REV 0 TABLE P6. g RX BLDG ELEVATED RELEASE POINT CONC (T = 04:30) ( 07:30)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate Rate at at 1 ft.:

ft.:

0.1 0.1 mR/hr mR/hr PASS Sample (14. ml) Dose 1 PASS Sample (charcoal) Dose Rate at 1 ft.:

ft.:

< 0.1 mR/hr per cf cf PASS Sample (filter) Dose Rate at 1 < 0.1 mR/hr per For 2" lead shield divide dose rate by:2.3E+1 For 4" lead shield divide dose rate by:3.7E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.64

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. h RX BLDG ELEVATED RELEASE POINT CONC. (T = 04:45) ( 07:45)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 9.49E-03 uCi/cc Kr-87 1.38E-02 uCi/cc Kr-88 2.52E-02 uCi/cc Xe-133 7.69E-02 uCi/cc Xe-133m 2.65E-03 uCi/cc Xe-135 2.48E-02 uCi/cc Xe-138 8.11E-03 uCi/cc TOTAL GAS SAMPLE 1 62E-01 uCi/cc Br-83 2.66E-07 uCi/cc I-131 3.20E-06 uCi/cc I-132 3.67E-06 uCi/cc I-133 6.24E-06 uCi/cc I-134 3.93E-06 uCi/cc I-135 5.22E-06 uCi/cc TOTAL CHARCOAL SAMPLE 2 '7E-05 uCi/cc Rb-88 1.12E>>05 uCi/cc Cs-134 4.27E-06 uCi/cc Cs-136 1.49E-06 uCi/cc Cs-137 2.90E-06 uCi/cc TOTAL FILTER SAMPLE 1.99E-05 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. h RX BLDG ELEVATED RELEASE POINT CONC. (T = 04:45) ( 07:45)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1 ft.:

ft.: < 0.1 0.1 mR/hr 1 < mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1

1 ft.:

ft.: <

0.1 0.1 mR/hr per mR/hr per cf cf For 2" lead shield divide dose rate by:2.3E+1 For 4" lead shield divide dose rate by:3.6E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.64

HNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. i RX BLDG ELEVATED RELEASE POINT CONC. (T = 05:00) ( 08:00)

Provide current Chem data 30 minutes after sample recpxest Nuclide Concentration Kr-85m 9 '2E-03 uCi/cc Kr-87 1.31E-02 uCi/cc Kr-88 2 '3E-02 uCi/cc Xe-133 7 55E-02 uCi/cc Xe-133m 2 '0E-03 uCi/cc Xe-135 2 43E-02 uCi/cc Xe-138 6 '9E-03 uCi/cc TOTAL GAS SAMPLE 1.56E-01 uCi/cc Br-83 1.93E-07 uCi/cc I-131 2.37E-06 uCi/cc I-132 2.66E-06 uCi/cc I-133 4.62E-06 uCi/cc I-134 2.75E-06 uCi/cc I-135 3.84E-06 uCi/cc TOTAL CHARCOAL SAMPLE 1.66E-05 uCi/cc Rb-88 9.46E-06 uCi/cc Cs-134 3.65E-06 uCi/cc Cs-136 1.27E-06 uCi/cc Cs-137 2.48E-06 uCi/cc TOTAL FILTER SAMPLE 1.69E-05 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. i RX BLDG ELEVATED RELEASE POINT CONC (T = 05:00) ( 08:00)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate at at 1 ft.:

ft.: < '0.1 0.1 mR/hr mR/hr PASS Sample (14. ml) Dose Rate 1 < \

PASS Sample (charcoal) Dose Rate at 1 ft.:

ft.: < 0.1 mR/hr per cf cf PASS Sample (filter) Dose Rate at 1 < 0.1 mR/hr per For 2" lead shield divide dose rate by:2.3E+1 For 4" lead shield divide dose rate by:3.6E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.64

NNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. j RX BLDG ELEVATED RELEASE POINT CONC. (T = 05:15) ( 08:15)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 8.95E-03 uCi/cc Kr-87 1.23E-02 uCi/cc Kr-88 2.35E-02 uCi/cc Xe-133 7 41E-02 uCi/cc Xe-133m 2.56E-03 uCi/cc Xe-135 2 38E-02 uCi/cc Xe-138 5.04E-03 uCi/cc TOTAL GAS SAMPLE 1.51E-01 uCi/cc Br-83 1.40E-07 uCi/cc I-131 1.76E-06 uCi/cc I-132 1.93E-06 uCi/cc I-133 3.42E-06 uCi/cc I-134 1.92E-06 uCi/cc I-135 2.83E-06 uCi/cc TOTAL CHARCOAL SAMPLE 1.21E-05 uCi/cc Rb-88 8 '9E-06 uCi/cc Cs-134 3 13E-06 uCi/cc Cs-136 1.09E-06 uCi/cc Cs-137 2 12E-06 uCi/cc TOTAL FILTER SAMPLE 1.46E-05 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. j RX BLDG ELEVATED RELEASE POINT CONC. (T = 05:15) ( 08:15)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1 ft.:

ft.: 0.1 0.1 mR/hr 1 mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1 ft.:

ft.: 0.1 0.1 mR/hr per cf cf 1 mR/hr per For 2" lead, shield divide dose rate by:2.3E+1 For 4" lead shield divide dose rate by:3.6E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.64

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. k RX BLDG ELEVATED RELEASE POINT CONC. (T = 05:30) ( 08:30)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Ke-85m 8.69E-03 uCi/cc Kr-87 1.16E-02 uCi/cc Kr-88 2.26E-02 uCi/cc Xe-133 7 '8E-02 uCi/cc Xe-133m 2 '1E-03 uCi/cc Xe-135 2.33E-02 uCi/cc Xe-138 3.97E-03 uCi/cc TOTAL GAS SAMPLE 1.46E-01 uCi/cc Br>>83 1. 02E-07 uCi/cc I-131 1.31E-06 uCi/cc I-132. 1 40E-06 uCi/cc I-133 2.53E-06 uCi/cc I-134 1.34E-06 uCi/cc I-135 2 '8E-06 uCi/cc TOTAL CHARCOAL SAMPLE 8.83E-06 uCi/cc Rb-88 7.22E-06 uCi/cc Cs-134 2 68E-06 uci/cc Cs-136 9.32E-07 uCi/cc Cs-137 1 82E-06 uCi/cc TOTAL FILTER SAMPLE 1.27E-05 uCi/cc

~

CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. k RX BLDG ELEVATED RELEASE POINT CONC. (T = 05:30) ( 08:30)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate at 1 ft-- < 0.1 mR/hr PASS Sample (14. ml) Dose Rate PASS Sample (charcoal) Dose Rate at at 1

1 ft.:

ft.: <

0.1 0.1 mR/hr mR/hr per cf PASS Sample (filter) Dose Rate at 1 ft < 0.1 mR/hr per cf For 2" lead shield divide dose rate by:2.3E+1 For 4" lead shield divide dose rate by:3.6E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.64

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. l RX BLDG ELEVATED RELEASE POINT CONC. (T = 05:45) ( 08:45)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 8.44E-03 uCi/cc Kr-87 1.10E-02 uCi/cc Kr-88 2 '8E-02 uCi/cc Xe-133 7 '5E-02 uCi/cc Xe-133m 2.46E-03 uCi/cc Xe-135 2.27E-02 uCi/cc Xe-138 3.13E-03 uCi/cc TOTAL GAS SAMPLE 1.42E-01 uCi/cc Br-83 7.43E-08 uCi/cc I-131 9 '1E-07 uCi/cc I-132 1.02E-06 uCi/cc I-133 1 '8E-06 uCi/cc I-134 9.42E-07 uCi/cc I-135 1 '4E-06 uCi/cc TOTAL CHARCOAL SAMPLE 6.46E-06 uCi/cc Rb-88 6.48E-06 uCi/cc Cs-134 2.29E-06 uCi/cc Cs-136 7.98E-07 uCi/cc Cs-137 1.56E-06 uCi/cc TOTAL FILTER SAMPLE 1.11E-05 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6 l RX BLDG ELEVATED RELEASE POINT CONC (T = 05 45) ( 08:45)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1

1 ft.:

ft.: <

0.1 0.1 mR/hr mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1

1 ft.:

ft.:

0.1 0.1 mR/hr per mR/hr per cf cf For 2" lead shield divide dose rate by:2 3E+1 For 4" lead shield divide dose rate by:3.6E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.64

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6 ~ m RX BLDG ELEVATED RELEASE POINT CONC. (T = 06:00) ( 09:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 8.20E-03 uCi/cc Kr-87 1.03E-02 uCi/cc Kr-88 2.11E-02 uCi/cc Xe-133 7.03E-,02 uCi/cc Xe-133m 2.42E-03 uCi/cc Xe-135 2.22E-02 uCi/cc Xe-138 2.47E-03 uCi/cc TOTAL GAS SAMPLE 1.38E-01 uCi/cc Br-83 5.41E-08 uCi/cc I-131 7.23E-07 uCi/cc I-132 7 '2E-07 uCi/cc I-133 1.39E-06 uCi/cc I-134 6.61E-07 uCi/cc I-135 1.14E-06 uCi/cc TOTAL CHARCOAL SAMPLE 4.74E-06 uCi/cc Rb-88 5.90E-06 uCi/cc Cs-134 1.96E-06 uCi/cc Cs-136 6.84E-07 uCi/cc Cs-137 1.33E-06 uCi/cc TOTAL FILTER SAMPLE 9.90E-06 uCi/cc CONTINUED ON NEXT PAGE

RP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. m RX BLDG ELEVATED RELEASE POINT CONC. (T = 06:00) ( 09:00)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1

1 ft.:

ft.: <

0.1 mR/hr 0.1 mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1

1 ft.:

ft.: < 0.1 mR/hr per cf

< 0.1 mR/hr per cf For 2" lead shield divide dose rate by:2.3E+1 For 4" lead shield divide dose rate by:3.6E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.64

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. n RX BLDG ELEVATED RELEASE POINT CONC. (T = 06:15) ( 09:15)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 7.96E-03 uCi/cc Kr-87 9<<75E-03 uCi/cc Kr-88. 2 '3E-02 uCi/cc Xe-133 6.90E-02 uCi/cc Xe-133m 2.37E-03 uCi/cc Xe-135 2 '7E-02 uCi/cc Xe-138 1 95E-03 uCi/cc TOTAL GAS SAMPLE 1.34E-01 uCi/cc Br-83 3.96E-08 uCi/cc I-131 5.39E-07 uCi/cc I-132 5.42E-07 uCi/cc I-133 1.04E-06 uCi/cc I-134 4.65E-07 uci/cc I-135 8 '2E-07 uCi/cc TOTAL CHARCOAL SAMPLE 3.48E-06 uCi/cc Rb-88 5 45E-06 uCi/cc Cs-134 1 '8E-06 uCi/cc Cs-136 5.86E-07 uCi/cc Cs-137 1.14E-06 uCi/cc TOTAL FILTER SAMPLE 8.88E-06 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV .0 TABLE P6. n RX BLDG ELEVATED RELEASE POINT CONC. (T = 06:15) ( 09:15)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1

1 ft.:

ft.: <

0.1 0.1 mR/hr mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1

1 ft.:

ft.: <

0.1 0.1 mR/hr per mR/hr per cf cf For 2" lead shield divide dose rate by:2.3E+1 For 4" lead shield divide dose rate by:3.6E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.64

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. o RX BLDG ELEVATED RELEASE POINT CONC. (T = 06:30) ( 09:30)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 7.73E-03 uCi/cc Kr-87 9.20E-03 uCi/cc Kr-88 1.96E-02 uCi/cc Xe-133 6.78E-02 uCi/cc Xe-133m 2 '3E-03 uCi/cc Xe-135 2.12E-02 uCi/cc Xe-138 1.53E-03 uCi/cc TOTAL GAS SAMPLE 1.30E-01 uCi/cc Br-83 2 '0E-08 uCi/cc I-131 4.04E-07 uCi/cc I-132 3.97E-07 uCi/cc I-133 7.76E-07 uCi/cc I-134 3.28E-07 uCi/cc I-135 6.25E-07 uCi/cc TOTAL CHARCOAL SAMPLE 2.57E-06 uCi/cc Rb-8'8 5.07E-06

. Cs-134 uCi/cc uCi/cc'.45E-06 Cs-3.36 5.03E-07 uCi/cc Cs-137 9.82E-07 uCi/cc TOTAL FILTER SAMPLE 8'02E-06 uCi/cc CONTENUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. o RX BLDG ELEVATED RELEASE POINT CONC. (T = 06:30) ( 09:30)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate at 1 ft.:

ft.:

< 0.1 mR/hr PASS Sample (14. ml) Dose Rate at 1 < 0.1 mR/hr PASS Sample (charcoal) Dose Rate at 1 ft.:

ft.: < 0.1 mR/hr per cf 0.1 mR/hr per cf PASS Sample (filter) Dose Rate at 1 <

For 2" lead shield divide dose rate by:2.3E+1 For 4" lead shield divide dose rate by:3.6E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.64

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. p RX BLDG ELEVATED RELEASE POINT CONC. (T = 06:45) ( 09:45)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 7.51E-03 uCi/cc Kr-87 8.67E-03 uCi/cc Kr-88 1.89E-02 uCi/cc Xe-133 6.66E-02 uCi/cc Xe-133m 2.29E-03 uCi/cc Xe-135 2.08E-02 uCi/cc TOTAL GAS SAMPLE 1.27E-01 uCi/cc Br-83 2 ~ 13E-08 uCi/cc I-131 3.04E-07 uCi/cc I-132 2.92E-07 uCi/cc I-133 5.82E-07 uCi/cc I-134 2.32E-07 uCi/cc I-135 4.67E-07 uCi/cc TOTAL CHARCOAL SAMPLE 1.91E-06 uCi/cc Rb-88 4 '7E-06 uCi/cc Cs-134 1 24E-06 uCi/cc Cs-136 4 '2E-07 uC1/cc Cs-137 8 44E-07 uCi/cc TOTAL FILTER SAMPLE 7.30E-06 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6 p RX BLDG ELEVATED RELEASE POINT CONC. (T = 06:45) ( 09:45)

(continued)

Provide current Chem data 30 minutes after sample recpxest Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1 ft.:

ft.: < 0.1 0.1 mR/hr 1 < mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1

1 ft.:

ft.: <

0.1 0.1 mR/hr per mR/hr per cf cf For 2" lead shield divide dose rate by:2.3E+1 For 4" lead shield divide dose rate by:3.6E+2 Hydrogen Concentration: .0%

Oxygen Concentration: 20.64

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. q RX BLDG ELEVATED RELEASE POZNT CONC. (T = 07:00) ( 10:00)

Provide current Chem data 30 minutes after sample request Nuclide 'oncentration Kr-85m 7.30E-03 uCi/cc Kr-87 8 18E-03 uCi/cc Kr-88 1.83E-02 uCi/cc Xe-133 6.54E-02 uCi/cc Xe-133m 2.24E-03 uCi/cc Xe-135 2.03E-02 uCi/cc TOTAL GAS SAMPLE 1.23E-01 uCi/cc Br-83 1.58E-08 uCi/cc Z-131 2 29E-07 uCi/cc Z-132 2.16E-07 uCi/cc Z-133 4.39E-07 uCi/cc Z-134 1.66E-07 uCi/cc Z-135 3.50E-07 uCi/cc TOTAL CHARCOAL SAMPLE 1.42E-06 uCi/cc Rb-88 4.51E-06 uCi/cc Cs-134 1.07E-06 uci/cc Cs-136 3 72E-07 uCi/cc Cs-137 7.26E-07 uCi/cc TOTAL FZLTER SAMPLE 6.68E-06 uCi/cc CONTZNUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. q RX BLDG ELEVATED RELEASE POZNT CONC (T ~ 07:00) ( 10:00)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1 ft.:

ft.: < 0.1 0.1 mR/hr 1 < mR/hr PASS Sample (charcoal) Dose Rate at 1 ft.:

ft.:

< 0.1 mR/hr per cf PASS Sample (filter) Dose Rate at 1 < 0.1 mR/hr per cf For 2" lead shield divide dose rate by:2.3E+1 For 4" lead shield divide dose rate by:3.6E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.64

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. r RX BLDG ELEVATED RELEASE POINT CONC (T = 07 30) ( 10:30)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 6.88E-03 uCi/cc Kr-87 7.28E-03 uCi/cc Kr-88 1.70E-02 uCi/cc Xe-133 6.31E-02 uCi/cc Xe-133m 2.16E-03 uCi/cc Xe-135 1 94E-02 uCi/cc TOTAL GAS SAMPLE 1.17E-01 uCi/cc Br-83 8.84E-09 uCi/cc I-131 1.34E-07 uCi/cc I-132 1.21E-07 uCi/cc I-133 2.56E-07 uCi/cc I-134 8.60E-08 uCi/cc I-135 2.02E-07 uCi/cc TOTAL CHARCOAL SAMPLE 8 '0E-07 uCi/cc Rb-88 4.09E-06 uCi/cc Cs-134 7.94E-07 uCi/cc Cs-137 5.39E-07 uCi/cc TOTAL FILTER SAMPLE 5.70E-06 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. r RX BLDG ELEVATED RELEASE POINT CONC. (T ~ 07:30) ( 10:30)

(continued)

Provide current Chem data 30 minutes after sample recpxest Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1

1 ft.:

ft.: <

0.1 0.1 mR/hr mR/hr PASS Sample (charcoal) Dose Rate PASS Sample,(filter) Dose Rate at at 1 ft.:

ft.: < 0.1 0.1 mR/hr per cf cf 1 < mR/hr per For 2" lead shield divide dose rate by:2.3E+1 For 4" lead shield divide dose rate by:3.7E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.64

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. s RX BLDG ELEVATED RELEASE POINT CONC. (T = 07:45) ( 10:45)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 6 69E-03 uCi/cc Kr-87 6.87E-03 uCi/cc Kr-88 1.64E-02 uCi/cc Xe-133 . 6.20E-02 uCi/cc Xe-133m 2 12E-03 uCi/cc Xe-135 1.90E-02 uCi/cc TOTAL GAS SAMPLE 1.14E-01 uCi/cc Br-83 6 73E-09 uCi/cc I-131 1.04E-07 uCi/cc I-132 9.16E-08 uCi/cc I-133 1.98E-07 uCi/cc I-134 6.30E-08 uCi/cc I-135 1 55E-07 uCi/cc TOTAL CHARCOAL SAMPLE 6 ~ 21E-07 uCi/cc Rb-88 3.91E-06 uCi/cc Cs-134 6.87E-07 uCi/cc Cs-137 4.66E-07 uCi/cc TOTAL FILTER SAMPLE 5.31E-06 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. s RX BLDG ELEVATED RELEASE POINT CONC. (T = 07:45) ( 10:45)

,(continued)

Provide current Chem data 30 'minutes after sample request Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1

1 ft.: <<

ft.: 0.1 0.1 mR/hr mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1 ft.:

ft.:: <

< 0.1 0.1 mR/hr per cf cf 1 mR/hr per For 2" lead shield divide dose rate by:2.3E+1 For 4" lead shield divide dose rate by:3.7E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.64

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6. t RX BLDG ELEVATED RELEASE POINT CONC. (T = 08 00) ( 11:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 6.50E-03 uCi/cc Kr-87 6.48E-03 uCi/cc Kr-88 . 1.58E-02 uCi/cc Xe-133 6.09E-02 uCi/cc Xe-133m 2.09E-03 uCi/cc Xe-135 1.86E-02 uCi/cc TOTAL GAS SAMPLE 1.11E-01 uCi/cc Br-83 5.19E-09 uCi/cc I-131 8.22E-08 uCi/cc I-132 7 06E-08 uCi/cc I-133 1.56E-07 uCi/cc I-134 4.68E-08 uCi/cc I-135 1.22E-07 uCi/cc TOTAL CHARCOAL SAMPLE 4 '3E-07 uei/cc Rb-88 3 '5E-06 uCi/cc

'Cs-134 5.95E-07 uCi/cc Cs-137 4.04E-07 uCi/cc TOTAL FILTER SAMPLE 4 96E-06 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P6.

RX BLDG ELEVATED RELEASE POINT CONC t

(continued)

(T = 08 00) ( 11 00) 0 Provide current Chem data 30 minutes after sample request Normal Sample (1S. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1 ft.:

ft.: 0.1 0.1 mR/hr 1 mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1 ft.:

ft.: 0.1 0.1 mR/hr per cf cf 1 mR/hr per For 2" lead shield divide dose rate by:2.3E+1 For 4" lead shield divide dose rate by:3.7E+2 Hydrogen Concentration: .04 Oxygen Concentration: 20.64

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P7. a RADWASTE BLDG/RADWASTE BLDG EXHAUST (T = 00:00) ( 03:00)

The Radwaste Building cannot be sampled through the PASS system Nuclide Concentration Kr-85m 3 '7E-16 uCi/cc Kr-87 6.42E-16 uCi/cc Kr-88 1.01E-15 uCi/cc Xe-133 3.28E-15 uCi/cc Xe-135 3.72E-15 uCi/cc Xe-138 1.22E-15 uCi/cc TOTAL GAS SAMPLE 1.04E-14 uCi/cc I-131 1.09E-16 uCi/cc I-132 1.46E-16 uCi/cc I-133 3.64E-16 uCi/cc I-134 1.59E-16 uCi/cc I-135 3.99E-16 uCi/cc TOTAL CHARCOAL SAMPLE 1.18E-15 uCi/cc Cs-134 1.94E-17 uCi/cc Cs-136 7.50E-18 uCi/cc Cs-137 1 '9E-17 uCi/cc Np-239 1.12E-17 uCi/cc TOTAL FILTER SAMPLE 5 '0E-17 uCi/cc CONTINUED ON NEXT PAGE

MNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P7. a RADMASTE BLDG/RADMASTE BLDG EXHAUST (T = 00:00) ( 03:00)

(continued)

The Radwaste Building cannot be sampled through the PASS system Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1 ft.:

ft.:

< 0.1 0.1 mR/hr 1 < mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1

1 ft.:

ft.: <

0.1 0.1 mR/hr per mR/hr per cf cf For 2" lead shield divide dose rate by:2.8E+1 For 4" lead shield divide dose rate by:5.0E+2 Hydrogen Concentration: .04 Oxygen Concentration: 21.04 Airborne Beta Dose Rate: < 0.1 mRad/hr Airborne Thyroid Dose Rate: < 0.1 mRem/hr Net Air Sample Contact Rate: < 0.1 cpm/cf sample Floor Contamination: < 0.1 cpm/100cm2 Mall and Equipment Contamination: < 0.1 cpm/100cm2 Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute personnel Contamination Rate: < O.l cpm/100cm2 per minute Stay Time: 2 MPC hr (no mask):5.7E+7 Hours Stay Time: 2 MPC hr (in mask):2.9E+9 Hours Stay Time: 2 MPC hr (in Air Sup. mask):9.9E+9 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P7. b RADWASTE BLDG/RADWASTE BLDG EXHAUST (T = 02:00) ( 05:00)

The Radwaste Building cannot be sampled through the PASS system Nuclide Concentration Kr-85m 7.20E-15 uCi/cc Kr-87 8.07E-15 uCi/cc Kr-88 1.79E-14 uCi/cc Xe-133 6 '3E-14 uCi/cc Xe-133m 2 20E-15 uCi/cc Xe-135 1.69E-14 uCi/cc Xe-138 1.78E-15 uCi/cc TOTAL GAS SAMPLE 1 19E-13 uCi/cc I-131 2.26E-16 uCi/cc I-132 2.01E-16 uCi/cc I-133 4.58E-16 uCi/cc I-134 1.48E-16 uCi/cc I-135 3.73E-16 uCi/cc TOTAL CHARCOAL SAMPLE 1 41E-15 uCi/cc Rb-88 1.19E-15 uCi/cc Cs-134 1.31E-16 uCi/cc Cs-137 8.34E-17 uCi/cc TOTAL FILTER SAMPLE 1.46E-15 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P7. b RADWASTE BLDG/RADWASTE BLDG EXHAUST (continued)

(T = 02:00) ( 05:00) 0 The Radwaste Building cannot'e sampled through the PASS system Normal Sample (15. ml) Dose Rate at 1 ft-: << '0.1 mR/hr PASS Sample (14. ml) Dose Rate at at 1 ft.:

ft.: 0.1

< 0.1 mR/hr cf PASS Sample (charcoal) Dose Rate 1 mR/hr per PASS Sample (filter) Dose Rate at 1 ft.: < 0.1 mR/hr per cf For 2" lead shield divide dose rate by:2.3E+1 For 4" lead shield divide dose rate by:3.7E+2 Hydrogen Concentration: .04 Oxygen Concentration: 21.04 Airborne Beta Dose Rate: < 0.1 mRad/hr Airborne Thyroid Dose Rate: < 0.1 mRem/hr Net Air Sample Contact Rate: < 0.1 cpm/cf sample Floor Contamination: < 0.1 cpm/100cm2 Wall and Equipment Contamination: < 0.1 cpm/100cm2 Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute~

Stay Time: 2 MPC hr (no mask):2.2E+7 Hours Stay Time: 2 MPC hr (in mask):1.1E+9 Hours Stay Time: 2 MPC hr (in Air Sup. mask):9.9E+9 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit, 2 REV 0 TABLE P7. c RADWASTE BLDG/RADWASTE BLDG EXHAUST (T = 04:00) ( 07:00)

The Radwaste Building cannot be sampled through the PASS system Nuclide Concentration Kr-85m 1.38E-13 uCi/cc Kr-87 1.92E-13 uCi/cc Kr-88 3.59E-13 uCi/cc Xe-133 1 15E-12 uCi/cc Xe-133m 3.97E-14 uCi/cc Xe-135 2 '7E-13 uCi/cc Xe-138 1 29E-13 uCi/cc TOTAL GAS SAMPLE 2.30E-12 uCi/cc I-131 5 23E-15 uCi/cc I-132 5 '5E-15 uCi/cc I-133 1 '2E-14 uCi/cc I-134 6.54E-15 uCi/cc I-135 8.55E-15 uCi/cc TOTAL CHARCOAL SAMPLE 3.64E-14 uCi/cc Rb-88 1.33E-14 uCi/cc Cs-134 1.60E-15 uCi/cc Cs-137 1.01E-15 uCi/cc TOTAL FILTER SAMPLE 1.66E-14 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P7. c RADWASTE BLDG/RADWASTE BLDG EXHAUST (T = 04:00) ( 07:00)

(continued)

The Radwaste Building cannot be sampled through the PASS system Normal Sample (15. ml) Dose Rate at at 1 ft.:

ft.:

< 0.1 0.1 mR/hr PASS Sample (14. ml) Dose Rate 1 < mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1

1 ft.:

ft.:

0.1 0.1 mR/hr per mR/hr per cf cf For 2" lead shield divide dose rate by:2.3E+1 For 4" lead shield divide dose rate by:3.7E+2 Hydrogen Concentration: .04 Oxygen Concentration: 21.04 Airborne Beta Dose Rate: < 0.1 mRad/hr Airborne Thyroid Dose Rate: < 0.1 mRem/hr Net A'ir Sample Contact Rate: < 0.1 cpm/cf sample Floor Contamination: < 0.1 cpm/100cm2 Wall and Equipment Contamination: < 0.1 cpm/100cm2 Personnel Contamination Rate: < 0,1 cpm/100cm2 per minute Personnel Contamination Rate: < 0.1 cpm/100cm2 per minut Stay Time: 2 MPC hr (no mask):1.0E+6 Hours Stay Time: 2 MPC hr (in mask):5.0E+7 Hours Stay Time: 2 MPC hr (in Air Sup. mask):2.0E+9 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P7. d RADWASTE BLDG/RADWASTE BLDG EXHAUST (T ~ 06:00) ( 09:00)

The Radwaste Building cannot he sampled through the PASS system Nuclide Concentration Kr-85m 4.43E-09 uCi/cc Kr-87 5.59E-09 uCi/cc Kr-88 1.14E-OS uCi/cc Xe-133 3.80E-08 uCi/cc Xe-133m 1.31E-09 uCi/cc Xe-3.35 1.20E-OS uCi/cc Xe-138 1.33E-09 uCi/cc TOTAL GAS SAMPLE 7.45E-08 uCi/cc Br-83 7.30E-11 uCi/cc I-131 9 74E-10 uCi/cc I-132 1.00E-09 uCi/cc I-133 1.88E-09 uCi/cc I-134 8.90E-10 uCi/cc I-135 1.53E-09 uCi/cc TOTAL CHARCOAL SAMPLE 6.38E-09 uCi/cc Rb-88 1.06E-09 uCi/cc Cs-134 9.88E-10 uCi/cc Cs-136 3.44E<<10 uCi/cc Cs-137 6.71E-10 uCi/cc TOTAL FILTER SAMPLE 3.16E-09 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P7. d RADWASTE BLDG/RADWASTE BLDG EXHAUST (T = 06:00) ( 09:00)

(continued)

The Radwaste Building cannot be sampled through the PASS system Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1 ft.:

ft.: 0.1 0.1 mR/hr 1 mR/hr PASS Sample (charcoal) Dose Rate at 1 ft.:

ft.: 0.1 mR/hr per cf PASS Sample (filter) Dose Rate at 1 0.1 mR/hr per cf For 2" lead shield divide dose rate by:2.6E+1 For 4" lead shield divide dose rate by:4.3E+2 Hydrogen Concentration: .04 Oxygen Concentration: 21.04 Airborne Beta Dose Rate: < 0.1 mRad/hr Airborne Thyroid Dose Rate: 2.9 mRem/hr Net Air Sample Contact Rate: 54. cpm/cf sample Floor Contamination: 3.0 cpm/100cm2 Wall and Ecpxipment Contamination: 0.3 cpm/100cm2 Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Stay Time: 2 MPC hr (no mask):8.3E+0 Hours Stay Time: 2 MPC hr (in mask):4.1E+2 Hours Stay Time: 2 MPC hr (in Air Sup. mask):1.7E+4 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P7. e RADWASTE BLDG/RADWASTE BLDG EXHAUST (T = 08:00) ( 11:00)

The Radwaste Building cannot, be sampled through the PASS system I

Nuclide Concentration Kr-85m 1.20E-08 uCi/cc Kr-87 1.19E-08 uCi/cc Kr-88 2.91E-08 uCi/cc Xe-133 1.12E-07 uCi/cc Xe-133m 3.84E-09 uCi/cc Xe-135 3.41E-08 uCi/cc TOTAL GAS SAMPLE 2.05E-07 uCi/cc Br-83 2.51E-11 uCi/cc I-131 3.97E-10 uCi/cc I-132 3 '1E-10 uCi/cc I-133 7.53E-10 uCi/cc I-134 2.26E-10 uCi/cc I-135 5 88E-10 uCi/cc TOTAL CHARCOAL SAMPLE 2 34E-09 uCi/cc Rb-88 1.80E-09 uCi/cc Cs-134 1.43E-09 uCi/cc Cs-136 4.98E-10 uCi/cc Cs-137 9 72E-10 uCi/cc TOTAL FILTER SAMPLE 4.83E-09 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit. 2 REV 0 TABLE P7. e RADWASTE BLDG/RADWASTE BLDG EXHAUST (T = 08:00) ( 11:00)

(continued)

The Radvaste Building cannot be sampled through the PASS system Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1

1 ft.:

ft.: <

0.1 0.1 mR/hr mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1

1 ft.:

ft.:

0.1 0.1 mR/hr per mR/hr per cf cf For 2" lead shield divide dose rate by:2.4E+1 For 4" lead shield divide dose rate by:3.9E+2 Hydrogen Concentration: .04 Oxygen Concentration: 21.04 Airborne Beta Dose Rate: < 0.1 mRad/hr Airborne Thyroid Dose Rate:" 1.2 mRem/hr Net Air Sample Contact Rate: 41. cpm/cf sample Floor Contamination: 4.8 cpm/100cm2 Wall and Equipment Contamination: 0.5 cpm/100cm2 Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Personnel Contamination Rate: < 0.1 cpm/100cm2 per minut Stay Time: 2 MPC hr (no mask):1.2E+1 Hours Stay Time: 2 MPC hr (in mask):5.8E+2 Hours Stay Time: 2 MPC hr (in Air Sup. mask):2.3E+4 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P8. a TURBINE BLDG/TURBINE BLDG EXHAUST (T = 00:00) { 03:00)

Provide current Chem data 30 minutes after sample request, Nuclide Concentration Kr-85m 1.26E-12 uCi/cc Kr-87 1.99E-12 uCi/cc Kr-88 3.11E-12 uCi/cc Xe-133 9.76E-12 uCi/cc Xe-133m 2.99E-13 uCi/cc Xe-135 2.66E-12 uCi/cc Xe-138 3.20E-12 uCi/cc TOTAL GAS SAMPLE 2.24E-11 uci/cc I-131 8.66E-13 uCi/cc I-132 1.13E-12 uCi/cc I-133 1.86E-12 uCi/cc I-134 1.53E-12 uCi/cc I-135 1.69E-12 uCi/cc TOTAL CHARCOAL SAMPLE 7.08E-12 uCi/cc Cs-134 2.01E-13 uCi/cc Cs-136 8.01E-14 uCi/cc Cs-137 1.28E-13 uCi/cc TOTAL FILTER SAMPLE 4.17E-13 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P8. a TURBINE BLDG/TURBINE BLDG EXHAUST (T = 00-00) ( 03:00)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate at 1 PASS Sample (14. ml) Dose Rate at, 1 ft.: < 0.1 0.1 mR/hr mR/hr-PASS Sample (charcoal) Dose Rate at 1 PASS Sample (filter) Dose Rate at 1 ft.: < 0.1 0.1 mR/hr per cf cf mR/hr per For 2" lead shield divide dose rate by:2.7E+1 For 4" lead shield divide dose rate by:5.0E+2 Hydrogen Concentration: .04 Oxygen Concentration: 21.04 Airborne Beta Dose Rate: < 0.1 mRad/hr Airborne Thyroid Dose Rate: < 0.1 mRem/hr Net Air Sample Contact Rate: < 0.1 cpm/cf sample Floor Contamination: < 0.1 cpm/100cm2 Wall and Equipment Contamination: < 0.1 cpm/100cm2 Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Stay Time: 2 MPC hr (no mask):1.0E+4 Hours Stay Time: 2 MPC hr (in mask):5.0E+5 Hours Stay Time: 2 MPC hr (in Air Sup. mask):2.0E+7 Hours

RP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P8 b TURBINE BLDG/TURBINE BLDG EXHAUST (T = 02:00) ( 05:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 1.20E-11 uCi/cc Kr-87 1.48E-11 uCi/cc Kr-88 2.93E-11 uCi/cc Xe-133 1.02E-10 uCi/cc Xe-133m 3.40E-12 uCi/cc Xe-135 2.35E-11 uCi/cc Xe-138 6.84E-12 uCi/cc TOTAL GAS SAMPLE 1.93E-10 uCi/cc I-131 6 '3E-12 uci/cc I-132 6.91E-12 uCi/cc I-133 1 25E-11 uCi/cc I-134 7 19E-12 uCi/cc I-135 1.04E-11 uCi/cc TOTAL CHARCOAL SAMPLE 4.34E-11 uCi/cc Rb-88 1.92E-12 uCi/cc Cs-134 2.21E-12 uCi/cc Cs-3.36 8.81E-13 uCi/cc Cs-137 1.39E-12 uCi/cc TOTAL FILTER SAMPLE 6.40E-12 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P8. b TURBINE BLDG/TURBINE BLDG EXHAUST (T = 02:00) ( 05:00)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate at 1 0.1 mR/hr PASS Sample (14. ml) Dose Rate at. 1 0.1 mR/hr PASS Sample (charcoal) Dose Rate at, 1 0.1 mR/hr per cf PASS Sample (filter) Dose Rate at 1 0.1 mR/hr per cf For 2" lead shield divide dose rate by:2.7E+1 For 4" lead shield divide dose rate by:4.8E+2 Hydrogen Concentration: .04 Oxygen Concentration: 21.04 Airborne Beta Dose Rate: < 0.1 mRad/hr Airborne Thyroid Dose Rate: < 0.1 mRem/hr Net Air Sample Contact Rate: 0.3 cpm/cf sample Floor Contamination: < 0.1 cpm/100cm2 Wall and Equipment Contamination: < 0.1 cpm/100cm2 Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Stay Time: 2 MPC hr (no mask):1.4E+3 Hours Stay Time: 2 MPC hr (in mask):7.1E+4 Hours Stay Time: 2 MPC hr (in Air Sup. mask):2.8E+6 Hours

NNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P8. c TURBINE BLDG/TURBINE BLDG EXHAUST (T = 04:00) ( 07:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 2.96E-11 uCi/cc Kr-87 2.62E-11 uCi/cc Kr-88 6.70E-11 uCi/cc Xe-133 2.97E-10 uCi/cc Xe-133m 9.80E-12 uCi/cc Xe-135 7.27E-ll uCi/cc TOTAL GAS SAMPLE 5.10E-10 uCi/cc I-131 8.71E-12 uCi/cc I-132 8 '7E-12 uCi/cc I-133 1.67E-11 uCi/cc I-134 7.07E-12 uCi/cc I-135 1.33E-11 uCi/cc TOTAL CHARCOAL SAMPLE 5.39E-11 uCi/cc Rb-88 4.66E-12 uCi/cc Cs-134 4.25E-12 uCi/cc Cs-136 1.69E-12 uCi/cc Cs-137 2.67E-12 uCi/cc TOTAL FILTER SAMPLE 1.33E-11 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P8. c TURBINE BLDG/TURBINE BLDG EXHAUST (T = 04:00) ( 07:00)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1 ft.:

ft.: 0.1 0.1 mR/hr 1 mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1

1 ft.:

ft.: 0.1 0.1 mR/hr per mR/hr per cf cf For 2" lead shield divide dose rate by:2.6E+1 For 4" lead shield divide dose rate by:4.5E+2 Hydrogen Concentrations .04 Oxygen Concentration: 21.04 Airborne Beta Dose Rate: < 0.1 mRad/hr Airborne Thyroid Dose Rate: < 0.1 mRem/hr Net Air Sample Contact Rate: 0.4 cpm/cf sample Floor Contamination: < 0.1 cpm/100cm2 Wall and Equipment. Contamination: < 0.1 cpm/100cm2 Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Stay Time: 2 MPC hr (no mask):1.0E+3 Hours Stay Time: 2 MPC hr (in mask):5.1E+4 Hours Stay Time: 2 MPC hr (in Air Sup. mask):2.0E+6 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P8. d TURBINE BLDG/TURBINE BLDG EXHAUST (T = 06:00) ( 09:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 2 '8E-10 uCi/cc Kr-87 2.66E-10 'Ci/cc Kr-88 5.70E-10 uCi/cc Xe-133 2 04E-09 uCi/cc Xe-133m 6 96E-11 uCi/cc Xe-135 6.29E-10 uCi/cc Xe-138 5.69E-11 uCi/cc TOTAL GAS SAMPLE 3 89E-09 uCi/cc I-131 3.09E-ll uCi/cc I-132 2. 95E-11 uCi/cc I-133 5 93E-11 uCi/cc I-134 2.45E-11 uCi/cc I-135 4.75E-11 uCi/cc TOTAL CHARCOAL SAMPLE 1 94E-10 uCi/cc Rb-88 3.57E-11 uCi/cc Cs-134 3 13E-11 uCi/cc Cs-'136 1 12E-11 uCi/cc

• Cs-137 2.10E-11 uCi/cc TOTAL FILTER SAMPLE 1.02E-10 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE PS. d TURBINE BLDG/TURBINE BLDG EXHAUST (T = 06:00) ( 09:00)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1

1 ft.:

ft.: <

0.1 0.1 mR/hr mR/hr PASS Sample (charcoal) .Dose Rate at 1 ft.:

ft.:

< 0.1 mR/hr per cf PASS Sample (filter) Dose Rate at 1 < 0.1 mR/hr per cf For 2" lead shield divide dose rate by:2.5E+1 For 4" lead shield divide dose rate by:4.1E+2 Hydrogen Concentration: .04 Oxygen Concentration: 21.0%

Airborne Beta Dose Rate: < 0.1 mRad/hr Airborne Thyroid Dose Rate: < 0.1 mRem/hr Net Air Sample Contact Rate: 1.7 cpm/cf sample Floor Contamination: 0.1 cpm/100cm2 Mall and Equipment Contamination: < 0.1 cpm/100cm2 Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Stay Time: 2 MPC hr (no mask):2.5E+2 Hours Stay Time: 2 MPC hr (in mask):1.2E+4 Hours Stay Time: 2 MPC hr (in Air Sup. mask):4.9E+5 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P8. e TURBINE BLDG/TURBINE BLDG EXHAUST (T = 08:00) ( 11:00)

Provide current Chem data 30 minutes after sample request Nuclide Concentration Kr-85m 4 '1E-10 uCi/cc Kr-87 4.70E-10 uCi/cc Kr-88 1.18E-09 uCi/cc Xe-133 4.72E-09 uCi/cc Xe-133m 1.60E-10 uCi/cc Xe-135 1.43E-09 uCi/cc TOTAL GAS SAMPLE 8 52E-09 uCi/cc I-131 1.68E-11 uCi/cc I-132 1.24E-11 uCi/cc I-133 3.14E-11 uCi/cc I-134 7.03E-12 uCi/cc I-135 2.36E-11 uCi/cc TOTAL CHARCOAL SAMPLE 9.17E-11 uCi/cc Rb-88 5.16E-11 uCi/cc Cs-134 3 ~ 01E-11 uCi/cc Cs-136 1.07E-11 uCi/cc Cs-137 2 01E-11 uCi/cc TOTAL FILTER SAMPLE 1.15E-10 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P8. e TURBINE BLDG/TURBINE BLDG EXHAUST (T = 08 00) ( 11:00)

(continued)

Provide current Chem data 30 minutes after sample request Normal Sample {15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at' 1 ft.:

ft.: 0.1 0.1 mR/hr mR/hr PASS Sample {charcoal) Dose Rate at 1 ft.:

ft.: 0.1 mR/hr per cf PASS Sample (filter) Dose Rate at 1 0.1 mR/hr per cf For 2" lead shield divide dose rate by:2.4E+1 For 4" lead shield divide dose rate by:3.9E+2 Hydrogen Concentration: .0%

Oxygen Concentration: 21.04 Airborne Beta Dose Rate: < 0.1 mRad/hr Airborne Thyroid Dose Rate: < 0.1 mRem/hr Net Air Sample Contact Rate: 1.2 cpm/cf sample Floor Contamination: 0.2 cpm/100cm2 Wall and Equipment Contamination: < 0.1 cpm/100cm2 Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Stay Time: 2 MPC hr (no mask):3.1E+2 Hours Stay Time: 2 MPC hr (in mask):1.5E+4 Hours Stay Time: 2 MPC hr (in Air Sup. mask):6.1E+5 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P9 RADIATXON MONXTORXNG SYSTEM DATA (T = 00:00) ( 03:00)

MONXTOR KEY FOR USE WITH TABLES P9.

Monitor TITLE Monitor TITLE ARM-RXS-01 Fuel Pool Area RX 606 CMS-RXS-27D RB l

Elev Release Pt LOCA ARM-RXS-02 Fuel Pool Area RX 606 CMS-RIS-27E In-CTMT LOCA Monitor ARM-RZS-03 New Fuel Area-RX 606 CMS-RXS-27F Xn-CTMT LOCA Monitor ARM-RZS-3A New Fuel Area-RX 606 FD-RIS-1 Sump T-1 Rad Monitor ARM-RZS-04 CRD Equip Area E-RX 522 FD-RIS-2 Sump T-2 Rad Monitor ARM-RXS-05 CRD Equip Area W-RX 522 FD-RZS-3 Sump T-3 Rad Monitor ARM-RXS-06 Equip Access S-RX 572 FDR-RIS-606 Liquid RW Effluent Mon ARM-RZS-07 Neut Mont Drive-RX 501 MS-RXS-610A MS Line Rad Monitor ARM-RXS-08 SGT Filter Area-RX 572 MS-RIS-610B MS Line Rad Monitor ARM-RIS~09 A RHR Pump Rm 2-RX 422 MS-RIS-610C MS Line Rad Monitor ARM-RZS-10 B RHR Pump Rm 1-RX 422 MS-RIS-610D MS Line Rad Monitor ARM-RIS-11 C RHR Pump Rm 4-RX 422 OG-RXS-601A OG Postreat Rad Monitor ARM-RZS-12 RCIC Pump Rm 3-RX 422 OG-RIS-601B OG Postreat Rad Monitor ARM-RIS-13 HPCS Pump Rm 6-RX 422 OG-RIS-611 Charcoal Bed Rad Monitor ARM-RXS-14 Turb Front Std-TB 501 OG-RIS-612 OG Pretreat Rad Monitor ARM-RXS-15 Turb Bldg Entr-TB 441 PSR-RI-507 PASS Encl. Rad Monitor ARM-RZS-16 Rx Feed Pump 1A-TB 441 PSR-RI-665 Pass Liq Rad Monitor ARM-RIS-17 Rx Feed Pump 1B-TB 441, PSR-RZ-704 Pass Gas Rad Monitor ARM-RIS-18 Condensate Pump-TB 441 RCC-RIS-607 RB Closed Cooling Water ARM-RZS-19 Main Control Rm-RW 501 REA-RIS-19 RB Elevated Release Moni ARM-RZS-20 RW Vlv Rm East-RW 467 REA-RIS-19A RB Inter Range Rad Monit ARM-RIS-2 1 RW Vlv Rm West-RW 467 REA-RIS-609A RB Exhaust Plenum Mon.

ARM-RXS-22 Sampling Room-RW 487 REA-RZS-609B RB Exhaust Plenum Mon.

ARM-RXS-2 3 CRD Pump Rm 10-RX 422 REA-RIS-609C RB Exhaust Plenum Mon.

ARM-RXS-24 Equip Access West-RX 471 REA'-RZS>>609D RB Exhaust Plenum Mon.

ARM-RZS-25 Hot Machine Shop-RW 487 RRA-RIS-1 RB Mobile Air Part Mon.

ARM-RXS-26 Contamatd Tool Rm-RW 467 RRA-RZS-2 RB Mobile Air Part Mon.

ARM-RIS-27 Waste Surge Tank-RW 437 RRA-RZS-3 RB In Plant Air Part Mon ARM-RXS-28 Tank Corridor N-RW 437 SW-RIS-604 RHR Service Water Loop A ARM-RIS-29 Tank Corridor S-RW 437 SW-RXS-605 RHR Service Water Loop B ARM-RXS-3 0 RW Control Room-RW 467 TEA-RIS-13 Turb Bldg Vent Monitor ARM-RZS-3 2 Hi Range Monitor-RX 471 TEA-RIS-13A TB Exh Extended Range ARM-RXS-33 Hi Range Monitor-RX 501 TRA-RIS-1 TB In Plant Air Part Mon ARM-RXS-3 4 Hi Range Monitor-RX 606 WEA-RIS-14 RW Bldg Vent Monitor CMS-RXS-12/1A CTMT Part Rad Monitor WEA-RIS-14A RW Bldg Inter Ranger Mon CMS-RZS-12/1B CTMT Part Rad Monitor WOA-RZS-31A CR Fresh Air Intake Mon CMS-RZS-12/3A CTMT Noble Gas Monitor WOA-RIS-31B CR Fresh Air Intake Mon CMS-RZS-12/3B CTMT Noble Gas Monitor WOA-RIS-32A CR Fresh Air Xntake Mon CMS-RXS-27A CTMT LOCA Rad Monitor WOA-RIS-32B CR Fresh Air Intake Mon CMS-RZS-27B CTMT LOCA Rad Monitor WRA RIS-1 RW In Plant Air Part Mon CMS-RIS-27C RB Elev Release Pt LOCA WRA-RIS-2 RW ln Plant Air Part Mon

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P9. a RADIATION MONITORING SYSTEM DATA (T = 00:00) ( 03:00)

NOTE: ~OSH~ = Offscale High ALL MONITOR VALUES ARE 1 MINUTE AVERAGES Monitor value units Monitor value units ARM-RZS-0 1 ARM-RIS-02 250 5.0 mR/hr mR/hr CMS-RIS-27D CMS-RIS-27E 0 '1 1 2 R/hr R/hr ARM-RIS-03 180 ~ mR/hr CMS-RIS-27F 10 R/hr ARM-RZS-3A 300. mR/hr FD-RIS-1 '300.

cpm ARM-RZS-04 1.1 mR/hr FD-RIS-2 850. cpm ARM-RIS-05 11. mR/hr FD-RIS-3 8500. cpm ARM-RIS-06 4 ' mR/hr FDR-RIS-606 50. cps ARM-RIS-07 7.6 mR/hr MS-RIS-610A 1000. mR/hr ARM-RIS-08 2.5 mR/hr MS-RIS-610B 1000. mR/hr ARM-RIS-09 49 mR/hz MS-RZS-610C 1000. mR/hr ARM-RIS-10 ' mR/hr

'9 MS-RZS-610D 1000. mR/hz ARM-RZS-1 1 ' mR/hr OG-RIS-601A 1.5E5 cpm ARM-RIS-12 7.6 mR/hr OG-RIS-601B 1.5E5 cpm ARM-RIS-13 6 4 mR/hr OG-RZS-611 2 5 mR/hz ARM-RZS-14 200 mR/hr OG-RIS-612 140. mR/hr ARM-RIS-15 3 ' mR/hr PSR-Rl-507 1 0 mR/hr ARM-RIS-16 5' mR/hr PSR-RZ-665 0. 01 R/hr ARM-RIS-17 21 ~ mR/hr PSR-Rl-704 1.0 mR/hr ARM-RIS-18 5.5 mR/hr RCC-RIS-607 40. cps ARM-RZS-19 5.0 REA-RZS-19 100. cpm ARM-RZS-2 0 5 ' mR/hr REA-RIS-19A 1 8 pmu ARM-RIS-2 1 7.0 mR/hr REA-RIS-609A 0 ~ 41 mR/hr ARM-RIS-22 7' mR/hr REA-RIS-609B 0.38 mR/hr ARM-RIS-23 11 mR/hr REA-RIS-609C 0.35 mR/hr ARM-RIS-24 7.9 mR/hr REA-RIS-609D 0.35 mR/hr ARM-RIS-25 4.0 mR/hz RRA-RZS-1 2000 cpm ARM-RIS-26 3.0 mR/hr RRA-RIS>>2 '60 cpm

'RM-RIS-27 10 mR/hr RRA-RIS-3 '900.

cpm ARM-RIS-28 8i1 mR/hr SW-RIS-604 4 3 cps ARM-RIS-29 30. mR/hr SW-RIS-605 5.6 cps

, ARM-RIS-3 0 3.0 mR/hr TEA-RZS-13 57. cpm ARM-RIS-32 0 1 R/hr TEA-RIS-13A 2 6 pmu ARM-RIS-33 , 0,1 R/hz'/hr TRA-RIS-1 110. cpm ARM-RIS-34 0 1 WEA-RZS-14 45. cpm CMS-RIS-12/1A 160 cpm WEA-RIS-14A 1 4 pmu CMS-RZS-12/1B 440 cpm WOA-RIS-31A 350. cpm CMS-RZS-12/3A 93. cpm WOA-RZS-3 1B 18. cpm

'CMS-RIS-12/3B 150 cpm WOA-RIS-32A 75. cpm CMS-RIS-27A 0.01 R/hr WOA-RZS-32B 110. cpm CMS-RIS-27B 1.3 R/hz'/hr WRA-RZS-1 410. cpm CMS-RIS-27C 0.01 WRA-RIS-2 300. cpm

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE A.l.a NEW RADIATION MONITOR SYSTEM ALARMS (T = 00:00) ( 03:00)

B RHR Pump Rm 1-RX 422 (ARM-RZS-10 ) HIGH Sump T-3 Rad Monitor (FD-RIS-3 ) HIGH Sump T-3 Rad Monitor (FD-RIS-3 ) HIHZ OG Postreat Rad Monitor (OG-RIS-601A ) HIGH OG Postreat Rad Monitor (OG-RIS-601B ) HIGH

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P9. b RADIATION MONITORING SYSTEM DATA (T = 03:00) ( 06: 00)

NOTE: iOSHi = Offscale High ALL MONITOR VALUES ARE 1 MINUTE AVERAGES Monitor value units Monitor value units ARM-RZS-01 250 mR/hr CMS-RXS-27D 0 01 R/hr ARM-RZS-02 5' mR/hr CMS-RZS-27E 1 2 R/hr ARM-RZS-03 180. mR/hr CMS-RIS-27F 10. R/hr ARM-RIS-3A 300 mR/hr FD-RIS-1 1300. cpm ARM-RIS-04 '.1 mR/hr FD-RIS-2 860 cpm ARM-RIS-05 11. mR/hr FD-RIS-3 '.1E4 cpm ARM-RIS-06 4.0 mR/hr FDR-RIS-606 50. CPS ARM-RIS-07 7.6 mR/hr MS-RIS-610A 1000. mR/hr ARM-RIS-08 2.5 mR/hr MS-RIS-610B 1000 mR/hr ARM-RXS-09 49 mR/hr MS-RZS-610C '000.

mR/hr ARM-RIS-10 '9 mR/hr MS-RXS-610D 1000. mR/hr ARM-RZS-11 '.7 mR/hr OG-RIS-601A 1.7E5 cpm ARM-RXS-12 7.6 mR/hr OG-RIS-601B 1.7E5 cpm ARM-RIS-13 6 4 mR/hr OG-RZS 611 2.5 mR/hr ARM-RIS-14 200. mR/hr OG-RIS-612 140. mR/hr ARM-RIS-15 3.0 mR/hr PSR-RI-507 1.0 mR/hr ARM-RIS-16 ARM-RZS-17 6.2 21 mR/hr mR/hr PSR-RI-665 PSR-RI-704 0 '1 1.0 R/hr mR/hr ARM-RIS-18 '.9 mR/hr RCC-RIS-607 40. CPS ARM-RIS-19 5.0 mR/hr REA-RIS-19 110. cpm ARM-RIS-2 0 5 0 mR/hr REA-RIS-19A 1 8 pmu ARM-RIS-2 1 7' mR/hr REA-RIS-609A 0 ~ 41 mR/hr ARM-RZS-22 7.0 mR/hr REA-RIS-609B 0.38 mR/hr ARM-RIS-23 11 ~ mR/hr REA-RIS-609C 0.35 mR/hr ARM-RIS-24 7.9 mR/hr REA-RZS-609D 0.35 mR/hr ARM-RIS-25 4.0 mR/hr RRA-RIS-1 2000. cpm ARM-RIS-26 3.0 mR/hr RRA-RZS-2 680. cpm ARM-RXS-27 10 mR/hr RRA-RZS-3 2000 cpm ARM-RXS-28 '.3 mR/hr SW-RIS-604 4 3 cps ARM-RIS-29 30 ' mR/hr SW-RIS-605 5~6 CPS ARM-RIS-3 0 0 mR/hr TEA-RXS-13 57. cpm ARM-RXS-3 2 0 1 R/hr TEA-RXS-13A 2 ' pmu ARM-RXS-33 0 1 R/hr TRA-RZS-1 110. cpm ARM-RIS-34 0~1 R/hr WEA-RIS-14 45. cpm CMS-RIS-12/1A 160. cpm WEA-RIS-14A 1.4 pmu CMS-RIS-12/1B 440 ~ cpm WOA-RZS-31A 1800. cpm CMS-RIS-12/3A 94. cpm WOA-RIS-3 1B 40. cpm CMS-RZS-12/3B 150 cpm WOA-RZS-32A 310. cpm CMS-RZS-27A 0 01 R/hr WOA-RIS-32B 350. cpm CMS-RIS-27B 1 3 R/hr WRA-RIS-1 410. cpm CMS-RZS-27C 0 F 01 R/hr WRA-RZS-2 300. cpm

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE A.1.b NEW RADIATION MONITOR SYSTEM ALARMS (T = 03:00) ( 06:00)

CR Fresh Air Intake Mon (WOA-RIS-31A ) HIGH

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P9. c RADIATION MONITORING SYSTEM DATA {T = 03:30) { 06:30)

NOTE: 'OSH~ = Offscale High ALL MONITOR VALUES ARE 1 MINUTE AVERAGES Monitor value units Monitor value units ARM-RIS-0 1 250. mR/hr CMS-RIS-27D 0. 01 R/hr ARM-RIS-02 5.0 mR/hr CMS-RZS-27E 1.2 R/hr ARM-RIS-03 180. mR/hr CMS-RIS-27F 10. R/hr ARM-RZS-3A 300. mR/hr FD-RIS-1 1300 cpm ARM-RIS-04 870. mR/hr FD-RIS-2 860 cpm ARM-RZS-05 11. mR/hr FD-RIS-3 1 1E4 cpm ARM-RIS-06 4.5 mR/hr FDR-RIS-606 50 cps ARM-RIS-07 320. mR/hr MS-RIS-610A '.2 mR/hr ARM-RZS-08 3 7. mR/hr

~ MS-RZS-610B 13 ~ mR/hr ARM-RIS-09 49. mR/hr MS-RIS-610C 18 ~ mR/hr ARM-RZS-10 49. mR/hr MS-RZS-610D 6.2 mR/hr ARM-RIS-1 1 6.7 mR/hr OG-RZS-601A 1.7E5 cpm ARM-RIS-12 7.6 mR/hr OG-RIS-601B 1.7E5 cpm ARM-RZS-13 6.4 mR/hr OG-RIS-611 2.5 mR/hr ARM-RIS-14 46. mR/hr OG-RZS-612 140 mR/hr ARM-RIS-15 3.0 mR/hr PSR-RI-507 1 0 mR/hr ARM-RIS-16 ARM-RIS-17 6'

21 mR/hr mR/hr PSR-RI-665 PSR-RI-704 0 '1 1.0 R/hr mR/hr ARM-RZS-18 5.9 mR/hr RCC-RIS-607 40 cps ARM-RIS-19 5.0 mR/hr REA-RIS-19 '10.

cpm ARM-RXS-20 5.0 mR/hr REA-RIS-19A 1.8 pmu ARM-RIS-2 1 7 0 mR/hr REA-RZS-609A 0.41 mR/hr ARM-RZS-22 7.0 mR/hr REA RIS-609B 0.38 mR/hr ARM-RIS-23 11. mR/hr REA-RIS-609C 0.35 mR/hr ARM-RIS-24 7' mR/hr REA-RIS-609D 0.35 mR/hr ARM-RIS-25 4.0 mR/hr RRA-RIS-1 2000. cpm ARM-RZS-2 6 3.0 mR/hr RRA-RZS-2 680 cpm ARM-RIS-27 10 mR/hr RRA-RIS-3 '

'000 cpm ARM-RZS-28 8.3 mR/hr SW-RIS-604 3 cps ARM-RIS-29 30. mR/hr SW-RZS-605 5.6 cps ARM-RZS-3 0 3 ~ 0 mR/hr TEA-RIS-13 57 cpm ARM-RIS-32 0.1 R/hr TEA-RZS-13A 2 ' pmu ARM-RIS-33 0.1 R/hr TRA-RIS-1 110 cpm ARM-RIS-34 0~1 R/hr WEA-RIS-14 45 ' cpm CMS-RIS-12/ lA 160. cpm WEA-RZS-14A 4 pmu CMS-RIS-12/1B 440. cpm WOA-RIS-31A 2000 cpIn CMS-RZS-12/3A 94. cpm WOA-RIS-31B 43 cpm CMS-RZS-12/3B 150. cpm WOA-RIS-32A '40.

cpm CMS-RIS-27A 0 01 R/hr WOA-RIS-32B 380. cpm CMS-RXS-27B 1.3 R/hr WRA-RIS-1 410 cpm CMS-RIS-27C 0 01 R/hr WRA-RIS-2 300. cpm

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P9. d RADIATION MONITORING SYSTEM DATA (T = 03:40) ( 06:40)

NOTE: ~OSH' Offscale High ALL MONITOR VALUES ARE 1 MINUTE AVERAGES Monitor value units Monitor value units ARM-RIS-01 250. mR/hr CMS-RIS-27D CMS-RIS-27E 0 '1 1'

R/hr R/hr ARM-RZS-02 5.5 mR/hz ARM-RZS-03 180. mR/hr CMS-RIS-27F 10. R/hr ARM-RIS-3A 300 mR/hr FD-RZS-1 1300. cpm ARM-RZS-04 '100 mR/hr FD-RIS-2 850. cpm ARM-RZS-05 11 ~ mR/hr FD-RIS-3 1.0E4 cpm ARM-RIS-06 310 mR/hr FDR-RIS-606 50. cps ARM-RIS-07 'SH mR/hr MS-RIS-610A 5.1 'R/hr ARM-RIS-08 37 mR/hr MS-RIS-610B 13 mR/hr ARM-RIS-09 43. mR/hr MS-RZS-610C '7.

mR/hr ARM-RIS-10 mR/hr MS-RZS-610D 6.0 mR/hr ARM-RZS-11 6.9 mR/hz OG-RZS-601A 1. OE5 cpm ARM-RIS-12 7.8 mR/hr OG-RIS-601B 1.0E5 cpm ARM-RIS-13 6.6 mR/hr OG-RZS-611 2.5 mR/hr ARM-RZS-14 46 mR/hr OG-RIS-612 140. mR/hr ARM-RIS-15 mR/hr PSR-RI-507 1.0 mR/hr

'1

'.0 ARM-RZS-16 6.1 mR/hr PSR-RI-665 0 R/hr ARM-RIS-17 21. mR/hr PSR-RI-704 1.0 mR/hr ARM-RIS-18 5 8 mR/hr RCC-RIS-607 40. cps ARM-RZS-19 5.0 mR/hr REA-RIS-19 920 ~ cpm ARM-RZS-2 0 5.0 mR/hr REA-RIS-19A 1.8 pmu ARM-RIS-2 1 7.0 mR/hr REA-RIS-609A 0 71 mR/hr ARM-RIS-22 7.0 mR/hr REA-RIS-609B 0. 68 mR/hr ARM-RIS-23 12. mR/hz REA-RIS-609C 0 65 mR/hr ARM-RIS-24 7' mR/hr REA-RZS-609D 0. 65 mR/hr ARM-RIS-25 4.0 mR/hr RRA-RIS-1 1. 4E4 cpm ARM-RZS-26 3.0 mR/hr RRA-RIS-2 2. 1E4 cpm ARM-RIS-27 10 mR/hr RRA-RZS-3 2 ~ OE4 cpm ARM-RIS-28 8.3 mR/hr SW-RZS-604 4.2 cps ARM-RIS-29 30. mR/hr SW-RIS-605 5.7 cps ARM-RIS-3 0 3.0 mR/hr TEA-RIS-13 57. cpm ARM-RIS-3 2 0' R/hr TEA-RIS-13A 2.6 pmu ARM-RIS-3 3 0.1 R/hr TRA-RIS-1 110. cpm ARM-RIS-34 0.1 R/hr WEA-RIS-14 45. cpm CMS-RIS-12/1A 160. cpm WEA-RIS-14A 1.4 pmu CMS-RIS-12/1B 440. cpm WOA-RIS-31A 1900 cpm CMS-RZS-12/3A 94 cpm WOA-RIS-31B '1.

cpm CMS-RIS-12/3B 150 cpm WOA-RZS-32A 320 ~ cpm CMS-RZS-27A 0.01 R/hz WOA-RIS-32B 360. cpm CMS-RIS-27B 1 3 R/hr WRA-RIS-1 410. cpm CMS-RIS-27C 0.01 R/hr ,WRA-RIS-2 300. cpm

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Vnit 2 REV 0 TABLE A.l.c NEW RADIATION MONITOR SYSTEM ALARMS (T = 03:40) ( 06:40)

Ecgxip Access S-RX 572 (ARM-RIS-06 HIGH SGT Filter Area-RX 572 (ARM-RIS-08 HIGH RB Mobile Air Part Mon. (RRA-'RIS-1 HIGH RB Mobile Air Part Mon. (RRA-RIS-2 HIGH RB In Plant Air Part Mon (RRA-RIS-3 HIGH

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit, 2 REV 0 TABLE P9. e RADIATION MONITORING SYSTEM (T = 03:50) ( 06:50)

IOSH'ATA NOTE: Offscale High ALL MONITOR VALUES ARE 1 MINUTE AVERAGES Monitor value units Monitor value units ARM-RXS-01 250 mR/hr CMS-RIS-27D 0.01 ARM-RIS-02 5.6 mR/hr CMS-RIS-27E 1 2 R/hr ARM-RIS-03 180 ~ mR/hr CMS-RIS-27F 10 R/hr ARM-RIS-3A 300. mR/hr FD-RIS-1 '300 CPR ARM-RXS-04 3400. mR/hr FD-RXS-2 850. CPR ARM-RZS-05 11. mR/hr FD-RIS-3 9600. CPR ARM-RIS-06 350. mR/hr FDR-RIS-606 50 cps ARM-RIS-07 OSH mR/hr MS-RZS-610A 5.1 RR/hr ARM-RIS-08 51- mR/hr MS-RZS-610B ~

12 ~ mR/hz ARM-RIS-09 ARM-RIS-10 ARM-RIS-11 43 44

~

'.9 mR/hr mR/hr mR/hr MS-RXS-610C MS-RIS-610D OG-RIS-601A 6 6E4 17

'/hr

'.8 RR/hz mR/hr cpm ARM-RIS-12 7.9 mR/hr OG-RZS-601B 6 ~ 6E4 cpm ARM-RIS-13 6.7 mR/hr OG-RZS-611 2.5 mR/hr ARM-RIS-14 46. mR/hr OG-RIS-612 140. mR/hr ARM-RIS-15 3.0 mR/hr PSR-RZ-507 1 0 mR/hr ARM-RXS-16 6.1 mR/hr PSR-RI-665 0.01 R/hr ARM-RIS-17 21. mR/hr PSR-RI-704 1.0 mR/hr ARM-RIS-18 5.7 mR/hr RCC-RIS-607 40. cps ARM-RIS-19 5.0 mR/hr REA-RIS-19 1200. cpm ARM-RIS-20 5.0 mR/hr REA-RIS-19A 1 8 pRu ARM-RZS-2 1 7.0 mR/hr REA-RIS-609A 0.75 mR/hr ARM-RIS-22 7.0 mR/hr REA-RXS-609B 0.73 mR/hr ARM-RIS-23 12 ~ mR/hr REA-RIS-609C 0.69 mR/hr ARM-RXS-24 7.6 mR/hr REA-RIS-609D 0.69 mR/hr ARM-RXS-25 4.0 mR/hr RRA-RIS-1 1.5E4 cpm ARM-RIS-2 6 3.0 mR/hr RRA-RIS-2 2.4E4 cpm ARM-RXS-27 10 ~ mR/hr RRA-RXS-3 3 'E4 CPR ARM-RXS-28 8.3 mR/hz SW-RIS-604 4.2 cps ARM-RXS-2 9 30 mR/hz SW-RXS-605 5 7 cps ARM-RXS-3 0 3.0 mR/hr TEA-RIS-13 57. cpm ARM-RXS-3 2 0.1 R/hr TEA-RXS-13 A 2.6 pmu ARM-RIS-33 0.1 R/hr TRA-RIS-1 110 cpm ARM-RXS-34 0.1 R/hr WEA-RIS-14 45. CPR CMS-RIS-12/1A 160. cpm WEA-RXS-14A 1.4 pmu CMS-RIS-12/1B 440. cpm WOA-RIS-31A 1800. cpm CMS-RXS-12/3A 110 cpm WOA-RIS-31B 40 cpm CMS-RXS-12/3B 160 CPR WOA-RIS-32A '00 cpm CMS-RIS-27A '.01 R/hr WOA-RIS-32B. '40.

cpm CMS-RZS-27B 1.3 R/hr WRA-RIS-1 410 .cpm CMS-RXS-27C 0.01 R/hr WRA-RXS-2 300 cpm

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P9. f RADIATION MONITORING SYSTEM DATA (T = 04:00) ( 07:00)

NOTE: 'OSH'ffscale High ALL MONITOR VALUES ARE 1 MINUTE AVERAGES Monitor value units Monitor value units ARM-RIS-01 250 ~ mR/hr CMS-RIS-27D 0. 01 R/hr ARM-RZS-02 5.5 mR/hr CMS-RZS-27E 1.2 R/hr ARM-RIS-03 180 mR/hr CMS-RZS-27F 10 R/hr ARM-RIS-3A 300. mR/hr FD-RXS-1 '300 cpm ARM-RZS-04 3300. mR/hr FD-RIS-2 '50.

cpm ARM-RIS-05 11 mR/hr FD-RZS-3 9200 cpm ARM-RIS-06 '30 mR/hr FDR-RIS-606 50 cps ARM-RIS-07 'SH mR/hr MS-RXS-610A '.0 mR/hr ARM-RIS-08 58. mR/hr MS-RIS-610B 12 mR/hr ARM-RIS-09 43 mR/hr MS-RIS-610C 17 mR/hr ARM-RIS-10 '4 mR/hr MS-RZS-610D 5.7 mR/hr ARM-RIS-11 '.9 mR/hr OG-RZS-601A 4 5E4 cpm ARM-RXS-12 7.9 mR/hr OG-RZS-601B 4 'E4 cpm ARM-RIS-13 6.6 mR/hr OG-RZS-611 2.5 mR/hr ARM-RIS-14 46. mR/hr OG-RIS-612 140 mR/hr ARM RZS-15 3.0 mR/hr PSR-RI-507 1~0 mR/hr ARM-RIS-16 6.0 mR/hr PSR-RI-665 0 01 R/hr ARM-RXS-17 21. mR/hr PSR-RI-704 1~0 mR/hr ARM-RXS-18 5' mR/hr RCC-RIS-607 40. cps ARM-RIS-19 5.0 mR/hr REA-RZS-19 1200. cpm ARM-RIS-20 5.0 mR/hr REA-RIS-19A 1 8 pmu ARM-RZS-2 1 7.0 mR/hr REA-RIS-609A 0.73 mR/hr ARM-RIS-22 7.0 mR/hr REA-RIS-609B 0.71 mR/hr ARM-RIS-23 12 ~ mR/hr REA-RXS-609C 0.68 mR/hr ARM-RIS-24 7.6 mR/hr REA-RIS-609D 0.68 mR/hr ARM-RIS-25 4.0 mR/hr RRA-RIS-1 1 5E4 cpm ARM-RIS-2 6 3.0 mR/hr RRA-RZS-2 2 ~ 3E4 cpm ARM-RIS-27 10. mR/hr RRA-RIS-3 3 ~ 8E4 cpm ARM-RZS-28 8.3 mR/hr SW-RXS-604 4 2 cps ARM-RIS-29 30. mR/hr SW-RIS-605 5.7 cps ARM-RIS-3 0 3.0 mR/hr TEA-RIS-13 57 ~ cpm ARM-RZS-3 2 0..1 R/hr TEA-RIS-13A 2.6 pmu ARM-RIS-33 0.1 R/hr TRA-RZS-1 110. cpm ARM-RIS-34 0'1 R/hr WEA-RIS-14 '45 "

cpm CMS-RIS-12/ 1A 160. cpm WEA-RIS-14A 1 4 pmu CMS-RIS-12/1B 440. cpm WOA-RIS-31A 1700 cpm CMS-RIS-12/3A 110 'pm WOA-RIS-3 1B 48 cpm CMS-RIS-12/3B '60. "'pm WOA-RIS-32A '00 cpm CMS-RZS-27A 0.01 R/hr WOA-RIS-32B 340. cpm CMS-RXS-27B 1.3 R/hr WRA-RIS-1 410 cpm CMS-RIS-27C 0 01 R/hr WRA-RIS-2 300.- cpm

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P9. g RADIATION MONITORING SYSTEM DATA (T = 04:10) ( 07:10)

NOTE: 'OSH' Offscale High ALL MONITOR VALUES ARE 1 MINUTE AVERAGES Monitor value units Monitor value units ARM-RIS-01 1. 2E4 mR/hr CMS-RIS-27D 0.31 R/hr ARM-RIS-02 OSH mR/hr CMS-RIS-27E 1.3 R/hr ARM-RIS-03 1.2E4 mR/hr CMS-RIS-27F 10 R/hr ARM-RIS-3A 1.2E4 mR/hr FD-RIS-1 '300 cpm ARM-RIS-04 OSH mR/hr FD-RIS-2 850 cpm ARM-RZS-05 7700. mR/hr FD-RIS-3 8900 cpm ARM-RIS-06 OSH mR/hz FDR-RIS-606 50. cps ARM-RIS-07 OSH mR/hz MS-RIS-610A 5.6 mR/hz ARM-RZS-08 OSH mR/hr MS-RIS-610B 13. mR/hr ARM-RZS-09 5300. mR/hr MS-RIS-6 10C 18. mR/hr ARM-RIS-10 5900. mR/hz MS-RIS-610D 6.7 mR/hr ARM-RIS-11 4700. mR/hz OG-RIS-6 01A 3. 2E4 cpm ARM-RZS-12 4800. mR/hz OG-RIS-601B 3 ~ 2E4 cpm ARM-RIS-13 5300 mR/hr OG-RIS-611 2' mR/hr ARM-RIS-14 '4.

mR/hr OG-RIS-612 140 mR/hr ARM-RZS-15 3 ' mR/hr PSR-RZ-507 '500.

mR/hr ARM-RZS-1 6 6.0 mR/hr PSR-RZ-665 6.5 R/hr ARM-RIS-17 21. mR/hr PSR-RI-704 6500. mR/hr ARM-RIS-18 5.5 mR/hr RCC-RZS-607 1100. cps ARM-RIS-19 5.0 mR/hz REA-RZS-19 5.7E6 cpm ARM-RIS-20 5.0 mR/hr REA-RIS-19A 9.2 pmu ARM-RIS-2 1 7.0 mR/hr REA-RIS-609A OSH mR/hr ARM-RIS-22 7' mR/hr REA-RIS-609B OSH mR/hr ARM-RIS-23 5200. mR/hr REA-RZS-609C OSH mR/hr ARM-RIS-24 6600. mR/hr REA-RIS-609D OSH . mR/hr ARM-RZS-25 4.0 mR/hz RRA-RIS-1 OSH cpm ARM-RIS-2 6 3.0 mR/hr RRA-RIS-2 OSH cpm ARM-RZS-27 10. mR/hz RRA-RZS-3 OSH cpm ARM-RIS-28 8.3 mR/hr SW-RIS-604 230 cps ARM-RIS-29 30. mR/hr SW-RIS-605 1600 cps ARM-RIS-3 0 3.0 mR/hr TEA-RIS-13 57. cpm ARM-RIS-32 7 2 R/hz'/hz TEA-RIS-13A 2.6 pmu ARM-RIS-33 4.9 TRA-RZS-1 5100. cpm ARM-RZS-34 12 ~ R/hr WEA-RZS-14 '45. cpm CMS-RIS-12/1A 1500. cpm WEA-RIS-14A 1 4 pmu CMS-RZS-12/1B 1800. cpm WOA-RIS-31A 1700 ~ cpm CMS-RIS-12/3A 7.5E4 cpm WOA-RIS-31B 160 cpm CMS-RIS-12/3B 7.5E4 cpm WOA-RIS-32A '70 cpm CMS-RIS-27A 0 01 R/hr WOA-RZS-32B 440. cpm CMS-RZS-27B 1.4 R/hr WRA-RZS-1 7500. cpm CMS-RIS-27C 0 32 R/hr WRA-RZS-2 4700. cpm

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE A.1.d NEW RADIATION MONITOR SYSTEM ALARMS (T = 04:10) ( 07 10)

Fuel Pool Area RX 606 (ARM-RIS-01 HXGH Fuel Pool Area RX 606 (ARM-RZS-02 HIGH New Fuel Area-RX 606 (ARM-RZS-03 HIGH New Fuel Area-RX 606 (ARM-RIS-3A HXGH CRD Equip Area W-RX 522 (ARM-RIS-05 HIGH A RHR Pump Rm 2-RX 422 (ARM-RIS-09 HIGH B RHR Pump Rm 1-RX 422 (ARM-RIS-10 HXGH C RHR Pump Rm 4-RX 422 (ARM-RIS-11 HIGH RCIC Pump Rm 3-RX 422 (ARM-RIS-12 HIGH HPCS Pump Rm 6-RX 422 (ARM-RZS-13 ) HIGH CRD Pump Rm 10-RX 422 (ARM-RIS-23 ) HXGH Equip Access West-RX 471 (ARM-RIS-24 ) HIGH PASS Encl. Rad Monitor (PSR-RI-507 ) HIGH PASS Encl. Rad Monitor (PSR-RX-507 ) HIHX RB Closed Cooling Water (RCC-RIS-607 HZHZ RB Elevated Release Moni (REA-RIS-19 ) HIGH RB Elevated Release Moni (REA-RZS-19 ) HIHZ RB Exhaust Plenum Mon. (REA-RIS-609A ) HXGH RB Exhaust Plenum Mon. (REA-RIS-609A HXHI RB Exhaust Plenum Mon. (REA-RIS-6098 ) HXGH RB Exhaust Plenum Mon. (REA-RXS-609B ) HXHI RB Exhaust Plenum Mon. (REA-RIS-609C HIGH RB Exhaust Plenum Mon. (REA-RZS-609C HXHI RB Exhaust Plenum Mon. (REA-RIS-609D HIGH RB Exhaust Plenum Mon. (REA-RZS-609D HZHI RHR Service Water Loop A (SW-RIS-604 HIGH RHR Service Water Loop B (SW-RIS-605 HXGH CR Fresh Air Intake Mon (WOA-RIS-32B HIGH

WNP.-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P9 h RADIATION MONITORING SYSTEM DATA (T = 04:20) ( 07:20)

NOTE ~OSH~ Offscale High ALL MONITOR VALUES ARE 1 MINUTE AVERAGES Monitor value units Monitor value units ARM-RIS-01 =

1 5E4 mR/hr .CMS-RIS-27D 0.52 R/hr ARM-RIS-02 OSH mR/hr 'CMS-RIS-27E 1 3 R/hr ARM-RIS-03 1.5E4 mR/hz'R/hr CMS-RZS-27F 10 R/hr ARM-RIS-3A 1.5E4 FD-RIS-1 '300.

cpm ARM-RIS-04 OSH mR/hr FD-RIS-2 850. cpm ARM-RIS-05 9600 mR/hr FD-RXS-3 8800. cpm ARM-RIS-06 'SH mR/hr FDR-RIS-606 50 cps ARM-RIS-07 OSH mR/hr MS-RZS-610A '.8 mR/hz'R/hr ARM-RIS-08 OSH mR/hr MS-RIS-610B 13 ARM-RZS-09 6600. mR/hr MS-RIS-610C '9 mR/hz ARM-RIS-10 7300. mR/hr MS-RIS-610D 7.0 mR/hr ARM-RIS-11 5800 mR/hr OG-RIS-601A 2 'E4 cpm ARM-RIS-12 6100 mR/hr OG-RZS-601B 2 'E4 cpm ARM-RIS-13 6600. mR/hr OG-RZS-611 2.8 mR/hz ARM-RIS-14 56 mR/hr OG-RZS-612 140- mR/hr ARM-RIS-15 '.0 mR/hr PSR-RZ-507 8200. mR/hr ARM-RIS-16 6.0 mR/hr PSR-RI-665 8 2 R/hr ARM-RIS-17 21 ~ mR/hr PSR-RZ-704 8200. mR/hr ARM-RIS-1S 5.5 mR/hr RCC-RIS-607 1300 cps ARM-RIS-19 5' mR/hr REA-RZS-19 9 'E6 cpm ARM-RIS-2 D 5 ' mR/hr REA-RIS-19A 15. pmu ARK-RIS-2 1 7.0 mR/hz REA-RIS-609A OSH mR/hr ARM-RIS-22 7' mR/hr REA-RIS-609B OSH mR/hr ARM-RIS-23 6400. mR/hr REA-RZS-609C OSH mR/hr ARM-RIS-24 820D. mR/hz REA-RIS-609D OSH mR/hr ARM-RIS-25 4.0 mR/hr RRA-RIS-1 OSH cpm ARM-RIS-2 6 3.0 mR/hr RRA-RZS-2 OSH cpm ARM-RIS-27 10 mR/hr RRA-RZS-3 OSH cpm ARM-RZS-28 8' mR/hr SW-RIS-604 290 cps ARM-RIS-29 30. mR/hr SW-RIS-605 2000. cps ARM-RIS-3 0 3.0 mR/hr TEA-RIS-13 57 cpm ARM-RIS-3 2 9.0 R/hr TEA-RIS-13A 2.6 pmu ARM-RIS-3 3 6.1 R/hz TRA-RZS-1 6500 ~ cpm ARM-RIS-3 4 15 R/hz WEA-RIS-14 45. cpm CMS-RIS-12/1A 1300 cpm WEA-RZS-14A 1 4 pmu CMS-RIS-12/1B 1600 cpm WOA-RIS-31A 1600. cpm CMS-RIS-12/3A 7 'E4 cpm WOA-RIS-31B 180. cpm CMS-RIS-12/3B 7.2E4 cpm WOA-RXS-32A 380. cpm CMS-RIS-27A 0. 01 R/hr WOA-RIS-32B 470 cpm CMS-RIS-27B 1.4 R/hr WRA-RXS-1 9400. cpm CMS-RIS-27C 0.53 R/hr WRA-RIS-2 5900. cpm

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P9 i RADIATION MONITORING SYSTEM DATA (T = 04: 30) ( 07: 30)

NOTE: 'OSH' Offscale High ALL MONITOR VALUES ARE 1 MINUTE AVERAGES Monitor value units Monitor value units ARM-RIS-01 1 6E4 mR/hr CMS-RXS-27D 0 63 R/hr ARM-RIS-02 OSH mR/hr CMS-RIS-27E 1.3 R/hr ARM-RIS-03 1.5E4 mR/hz CMS-RIS-27F 10 R/hz ARM-RZS-3A 1.6E4 mR/hr FD-RIS-1 1300 cpm ARM-RIS-04 OSH mR/hr FD-RIS-2 850. cpm ARM-RIS-05 9000 mR/hr FD-RIS-3 8600 cpm ARM-RXS-06 'SH mR/hr FDR-RIS-606 50. cps ARM-RIS-07 OSH mR/hr MS-RIS-610A 5 9 mR/hr ARM-RXS-08 OSH mR/hr MS-RIS-610B 14 ~ mR/hr ARM-RXS-09 6800. mR/hr MS-RIS-610C 19 mR/hz ARM-RIS-10 7600. mR/hr MS-RIS-610D '.5 mR/hr ARM-RIS-11 6100 mR/hr OG-RIS-60 1A 2.3E4 cpm ARM-RZS-12 6300. mR/hr OG-RIS-601B 2 'E4 cpm ARM-RIS-13 6900. mR/hr OG-RIS-611 2.6 mR/hr ARM-RIS-14 57 ' mR/hr OG-RIS-612 140.

ARM-RIS-15 0 mR/hr PSR-RI-507 8500. mR/hr ARM-RIS-16 5' mR/hr PSR-RI-665 8.5 R/hr ARM-RIS-17 21 mR/hz PSR-RI-704 8500 mR/hr ARM-RIS-18 5.5 mR/hr RCC-RIS-607 1400. cps ARM-RIS-19 5.0 mR/hr REA-RZS-19 OSH cpm ARM-RIS-2 0 5.0 mR/hr REA-RIS-19A 18 pmu ARM-RIS-21 7.0 mR/hr REA-RIS-609A 'SH mR/hr ARM-RIS-22 7.5 mR/hr REA-RIS-609B OSH mR/hr ARM-RIS-23 6700. mR/hr REA-RIS-609C OSH mR/hz ARM-RIS-24 8500 mR/hr REA-RIS-609D OSH mR/hr ARM-RIS-25 4 ' mR/hz RRA-RIS-1 OSH cpm ARM-RZS-2 6 3 ' mR/hz RRA-RIS-2 OSH cpm ARM-RIS-27 10 mR/hr RRA-RIS-3 OSH cpm ARM-RIS-28 '.2 mR/hz SW-RIS-604 300. cps ARM-RIS-29 '30 ~ mR/hr SW-RXS-605 1800. cps ARM-RIS-30 3.0 mR/hr TEA-RIS-13 57 cpm ARM-RIS-32 9.4 R/hr TEA-RIS-13A '.6 pmu ARM-RZS-33 6' R/hr TRA-RIS-1 2 ~ 5E4 cpm ARM-RIS-34 15 R/hr WEA-RIS-14 46 ~ cpm CMS-RIS-12/1A 1100 cpm WEA-RZS-14A 1.4 pmu CMS-RIS-12/1B 1400'.9E4 cpm WOA-RZS-31A 8 1E4 cpm CMS-RIS-12/3A cpm WOA-RIS-31B 1 OE5 cpm CMS-RXS-12/3B 6.9E4 cpm WOA-RXS-32A 'E4 cpm CMS-RIS-27A CMS-RZS-27B 0 '1 1.4 R/hr R/hr WOA-RZS-32B WRA-RIS-1 8

9.6E4 2 'E4 cpm cpm CMS-RIS-27C 0

0.64 R/hr WRA-RXS-2 2 OE4 cpm

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE A.1.e NEW RADIATION MONITOR SYSTEM ALARMS (T = 04:30) ( 07:30)

TB In Plant Air Part Mon (TRA-RIS-1 ) HXGH CR Fresh Air Intake Mon (WOA-RIS-31A ) HXHX CR Fresh Air Intake Mon (WOA-RZS-31B ) HIGH CR Fresh Air Intake Mon (WOA-RIS-31B ) HIHI CR Fresh Air Intake Mon (WOA-RZS-32A ) HIGH CR Fresh Air Intake Mon (WOA-RZS-32A ) HIHI CR Fresh Air Intake Mon (WOA-RZS-32B ) HZHX RW Zn Plant Air Part Mon (WRA-RIS-1 ) HIGH RW In Plant Air Part Mon (WRA-RIS-2 HIGH

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P9. j RADIATION MONITORING SYSTEM DATA (T = 04:40) ( 07: 40)

NOTE: ~OSH~ = Offscale High ALL MONITOR VALUES ARE 1 MINUTE AVERAGES Monitor value units Monitor value units ARM-RIS-01 1. 3E4 mR/hr CMS-RIS-27D 0 61 R/hr ARM-RXS-02 OSH mR/hr CMS-RIS-27E 1.3 R/hr ARM-RXS-03 1.3E4 mR/hz CMS-RZS-27F 10. R/hz'pm ARM-RIS-3A 1.3E4 mR/hr FD-RIS-1 1300.

ARM-RXS>>04 OSH mR/hr FD-.RIS-2 850 cpm ARM-RIS-05 7700. mR/hr FD-RIS-3 8500. cpm ARM-RIS-06 OSH mR/hr FDR-RIS-606 50. CPS ARM-RIS-07 OSH mR/hr MS-RZS-610A 5 8 mR/hr ARM-RIS-08 OSH mR/hr MS-RZS-610B 14. mR/hr ARM-RIS-09 5900. mR/hr 'S-RIS-610C

19. mR/hz ARM-RIS-10 6500. mR/hr MS-RZS-610D 7 7 mR/hr ARM-RIS-11 5200 mR/hr OG-RIS-601A 2.0E4 cpm ARM-RIS-12 5400. mR/hz OG-RZS-601B 2.0E4 cpm ARM-RZS-13 ~

5900 mR/hz OG-RIS-611 2.8 mR/hz ARM-RIS-14 '5.

mR/hr OG-RIS-612 140 mR/hr ARM-RIS-15 3 ' mR/hr PSR-RI-507 ' mR/hr

'300 ARM-RIS-16 5.9 mR/hr 'SR-RZ-665 3 R/hr ARM-RIS-17 21. mR/hr PSR-RI-704 7300. mR/hr ARM-RIS-18 5.5 mR/hr RCC-RIS-607 1200. cps ARM-RXS-19 5.0 mR/hr REA-RZS-19 OSH cpm ARM-RZS-2 0 5~0 mR/hr REA-RZS-19A 17. pmu ARM-RIS-2 1 7.0 mR/hr REA-RIS-609A OSH mR/hr ARM-RZS-22 7.5 mR/hr REA-RIS-609B OSH mR/hr ARM-RIS-23 5800 mR/hr . REA-RIS-609C OSH mR/hr ARM-RIS-24 '300.

mR/hr REA-RIS-609D OSH mR/hr ARM-RIS-25 4.4 mR/hr RRA-RIS-1 OSH cpm ARM-RIS-2 6 3.0 mR/hr RRA-RIS-2 OSH cpm ARM-RZS-2 7 10. mR/hr RRA-RZS-3 OSH 4=pm ARM-RIS-2 8 8.2 mR/hr SW-RIS-604 260 cps ARM-RZS-29 30. mR/hr SW-RIS-605 1500. cps ARM-RXS-3 0 3.0 mR/hr TEA-RIS-13 58 ' cpm ARM-RZS-3 2 8.1 R/hr TEA-RIS-13A 6 pmu ARM-RXS-33 5.4 R/hr TRA-RZS-1 2. 5E4 cpm ARM-RIS-34 13 R/hr WEA-RZS-14 47. cpm CMS-RIS-12/1A '000.

cpm WEA-RZS-14A 1.4 pmu CMS-RIS-12/1B 1300. cpm WOA-RIS-31A 8.1E4 cpm CMS-RZS-12/3A 6.7E4 cpm WOA-RZS-31B 1.0E5 cpm CMS-RIS-12/3B 6.7E4 cpm WOA-RIS-32A 8.6E4 cpm CMS-RZS-27A CMS-RIS-27B 0 '1 1.4 R/hr R/hr WOA-RZS-32B WRA-RIS-1 9.6E4 2.2E4 cpm cpm CMS-RIS-27C 0 '1 R/hr WRA-RIS-2 2.0E4 cpm

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P9. k RADIATION MONITORING SYSTEM DATA (T = 04:50) ( 07:50)

NOTE: 'OSH~ = Offscale High ALL MONITOR VALUES ARE 1 MINUTE AVERAGES Monitor value units Monitor value units ARM-RIS-01 1. 2E4 mR/hr CMS-RZS-27D 0.58 R/hr ARM-RXS-02 OSH mR/hr CMS-RZS-27E 1.3 R/hr ARM-RIS-03 1. 2E4 mR/hr CMS-RIS-27F 10 R/hr ARM-RIS-3A 1. 2E4 mR/hr FD-RZS-1 '300.

cpm ARM-RZS-04 OSH mR/hr FD-RIS-2 850. cpm ARM-RIS-05 6700. mR/hr FD-RIS-3 8400. CPR ARM-RIS-06 OSH mR/hr FDR-RIS-606 50. cps ARM-RIS-07 OSH mR/hr MS-RZS-610A 5.7 mR/hr ARM-RIS-08 OSH mR/hr MS-RZS-610B 13 mR/hr ARM-RIS-09 5100. mR/hr MS-RZS-610C '8.

mR/hr ARM-RIS-10 5700. mR/hr MS-RIS-610D 6.7 mR/hr ARM-RIS-11 4500. mR/hr OG-RIS-601A 1.7E4 cpm ARM-RIS-12 4700. mR/hr OG-RIS-601B 1.7E4 cPR ARM-RIS-13 5100. mR/hr OG-RIS-611 2 ' mR/hr ARM-RIS-14 54. mR/hr OG-RZS-612 140 mR/hr ARM-RXS-15 3.0 mR/hr PSR-RI-507 '300.

mR/hr ARM-RIS-16 5.9 mR/hr PSR-RI-665 6.3 R/hr ARM-RIS-17 21. mR/hr PSR-RI-704 6300. mR/hr ARM-RIS-18 5.4 mR/hr RCC-RIS-607 1100. cps ARM-RIS-19 5.0 mR/hr REA-RIS-19 OSH cpm ARM-RZS-2 0 5.0 mR/hr REA-RZS-19A 17 pmu ARM-RIS-2 1 7 0 mR/hr REA-RXS-609A OSH mR/hr ARM-RIS-22 7.0 mR/hr REA-RIS-609B OSH RR/hr ARM-RIS-23 5000. mR/hr REA-RIS-609C OSH mR/hr ARM-RIS-24 6400. mR/hr REA-RZS-609D OSH mR/hr ARM-RIS-25 4 ' mR/hr RRA-RXS-1'RA-RZS-2 OSH CPR ARM-RIS-2 6 3.0 mR/hr OSH 'cpm ARM-RIS-27 10. mR/hr RRA-RZS-3 OSH cpm ARM-RIS-28 8.2 mR/hr SW-RIS-604 230 cps ARM-RIS-29 30. RR/hr SW-RIS-605 '300.

cps ARM-RIS-3 0 3 ' mR/hr TEA-RZS-13 57. cpm ARM-RZS-3 2 7.0 R/hr TEA-RXS-13A 2 ' pmu ARM-RZS-33 4 7 R/hr TRA-RZS-1 5900. cPR ARM-RIS-34 11. R/hr WEA-RZS-14 47. cpm CMS-RIS-12/1A 890. cpm WEA-RZS-14A 1.4 pmu CMS-RIS-12/1B 1200. cpm WOA-RIS-31A 1500 cpm CMS-RIS-12/3A 6.4E4 cPR WOA-RZS-31B '80.

cpm CMS-RIS-12/3B 6.4E4 cpm WOA-RXS-32A 370 cpm CMS-RIS-27A CMS-RIS-27B 0 '1 1 4 R/hr R/hr WOA-RZS-32B WRA-RIS-1 8300

'60.

cpm cpm CMS-RZS-27C 0 '9 R/hr WRA-RIS-2 '200.

cpm

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P9 l RADIATION MONITORING SYSTEM DATA (T = 05 00) ( 08:00)

NOTE: 'OSH'ffscale High ALL MONITOR VALUES ARE 1 MINUTE AVERAGES Monitor value Monitor value units ARM-RIS-01 1. OE4 mR/hr CMS-RIS-27D 0.56 R/hr ARM-RXS-02 1.0E4 mR/hr CMS-RIS-27E 1 2 R/hr ARM-RIS-03 1.0E4 mR/hr CMS-RZS-27F 10. R/hr ARM-RXS-3A 1. OE4 mR/hr FD-RIS-1 1300. cpm ARM-RIS-04 OSH mR/hr FD-RIS-2 850. cpm ARM-RZS-05 5800 ~ mR/hr FD-RIS-3 8200 cpm ARM-RZS-06 OSH mR/hr FDR-RZS-606 50. cps ARM-RIS-07 OSH mR/hr MS-RIS-610A 5.6 mR/hr ARM-RIS-08 OSH mR/hr MS-RIS-610B 13 ~ mR/hr ARM-RIS-09 4500. , mR/hr MS-RZS 610C 18. mR/hr ARM-RIS-10 5000 mR/hr MS-RIS-610D 6' mR/hr ARM-RIS-11 '000.

mR/hr OG-RIS-601A 1.5E4 cpm ARM-RIS-12 4100. mR/hr OG-RXS-601B 1.5E4 cpm ARM-RIB-13 4500 mR/hr OG-RIS-611 2 ' mR/hr ARM-R1S-14 '3

~ mR/hr OG-RIS-612 140 ~ mR/hr ARM-RIS-15 3~0 mR/hr PSR RZ-507 5500. mR/hr ARM-RIS-16 5 9 mR/hr PSR-RI-665 5~5 R/hr ARM-RIG-17 21. mR/hr PSR-RX-704 5500. mR/hr ARM-RIS-18 5.4 mR/hr RCC-RIS-607 930. CPS ARM-RIS-19 5 0 mR/hr REA-RZS-19 OSH cpm ARM-RZS-20 5' mR/hr REA-RXS-19A 17 pmu ARM-RIS-21 7 0 mR/hr REA-RXS-609A OSH mR/hr

,ARM-RIS-22 7~4 mR/hr REA-RIS-609B OSH mR/hr ARM-RIS-23 4400. mR/hr REA-RXS-609C OSH mR/hr ARM-RIS-24 5600. mR/hr REA-RIS-609D OSH mR/hr ARM-RZS-25 4' mR/hr RRA-RXS-1 OSH cpm ARM-RIS-26 3 0 mR/hr RRA-RIS-2 OSH cpm ARM-RIS-27 10. mR/hr RRA-RIS-3 OSH cpm ARM-RIS-28 8.2 mR/hr SW-RIS-604 200. CPS ARM-RIS-29 30. mR/hr SW-RZS-605 1200 CPS ARM-RZS-3 0 3 ' TEA-RIS-13 57. cpm ARM-RIS-3 2 ,6.1 R/hr TEA-RXS-13A 2 6 pmu ARM-RIS-3 3 4.'1 R/hr TRA-RIS-1 2.2E4 cpm ARM-RZS-34 10 R/hr WEA-RZ8-14 48 ' cpm CMS-RIS-12/1A 780. cpm WEA-RIS-14A ' pmu CMS-RZS-12/1B 1100 cpm "WOA-RZS-31A 7.2E4 cpm CMS-RIS-12/3A '.2E4 cpm WOA-RXS-31B 9 'E4 cpm CMS-RIS-12/3B 6.2E4 cpm WOA-RIS-32A 7 'E4 cpm CMS-RIS-27A CMS-RIS-27B 0 '1 1.4 R/hr R/hr WOA-RIS-32B WRA-RIS-1 8.6E4 1.9E4 cpm

. cpm CMS-RZS-27C 0.56 R/hr WRA-RXS-2 1.7E4 cpm

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE A.1 f NEW RADIATION MONITOR SYSTEM ALARMS (T = 05:00) ( 08:00)

TB Zn Plant Air Part Mon (TRA-RIS-1 ) HIGH CR Fresh Air Intake Mon (WOA-RIS-31A ) HIHI CR Fresh Air Intake Mon (WOA-RZS-3 1B ) HIGH CR Fresh Air Intake Mon (WOA-RIS-3 1B ) HZHZ CR Fresh Air Intake Mon (WOA-RIS-32A ) HIGH CR Fresh Air Intake Mon (WOA-RIS-32A ) HZHI CR Fresh Air Intake Mon (WOA-RIS-32B ) HZHI RW Zn Plant Air Part Mon (WRA-RZS-1 ,) HIGH RW In Plant Air Part Mon (WRA-RZS-2 ) HIGH

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P9 m RADIATION MONITORING SYSTEM DATA (T = 05-15) .( 08:15)

NOTE: 'OSH'LL

~ Offscale High MONITOR VALUES ARE 1 MINUTE AVERAGES Monitor value units Monitor value units ARM-RIS-01 8500. mR/hr CMS-RIS-27D 0. 53 R/hr ARM-RIS-02 8300 mR/hr CMS-RZS-27E 1.2 R/hr ARM-RZS-03 8400. mR/hr CMS-RIS-27F 10 R/hr ARM-RZS-3A 8600. mR/hz FD-RXS-1 1300. cpm ARM-RIS-04 OSH mR/hr FD-RIS-2 850. cpm ARM-RIS-05 4800. mR/hr FD-RIS-3 8100 ~ cpm ARM-RIS-06 OSH mR/hr FDR-RIS-606 50. CPS ARM-RIS-07 OSH mR/hr MS-RZS-610A 5.5 mR/hz ARM-RIS-08 OSH mR/hr MS-RIS-610B 13 mR/hz ARM-RZS-09 3700. mR/hz MS-RZS-610C 18. mR/hr ARM-RIS-10 4100. mR/hr MS-RIS-610D 6.7 mR/hr ARM-RIS-11 3300. mR/hr OG-RIS-601A 1.2E4 cpm ARM-RIS-12 3400. mR/hr OG-RIS-601B 1.2E4 cpm ARM-RZS-13 3700. mR/hr OG-RZS-611 2 7 mR/hz ARM-RIS-14 52 ' mR/hr OG-RIS-612 140 ~ mR/hr ARM-RIS-15 0 mR/hr PSR-RI 507 4600. mR/hr ARM-RZS-16 5' mR/hr PSR-RI-665 4.6 R/hz'R/hr ARM-RZS-17 21. mR/hr PSR-RI-704 4600.

ARM-RZS-18 5.4 mR/hr RCC-RZS-607 790 CPS ARM-RIS-19 5 0 mR/hr REA-RIS-19 OSH cpm ARM-RZS-2 0 5 0 mR/hr REA-RIS-19A 16 pmu ARM-RIS-2 1 7.0 mR/hr REA-RIS-609A 'SH mR/hr ARM-RZS-22 7.4 mR/hr REA-RIS-609B OSH mR/hr ARM-RIS-23 3600 mR/hr REA-RIS-609C OSH mR/hr ARM-RIS-24 4600. mR/hr REA-RIS-609D OSH mR/hr ARM-RIS-25 4 3 mR/hr RRA-RIS-1 OSH cpm ARM-RZS-2 6 3~0 mR/hr RRA-RIS-2 OSH cpm ARM-RXS-27 10 ' mR/hr RRA-RIS-3 OSH cpm ARM-RIS-28 2 mR/hr SW-RIS-604 170 ~ cps ARM-RIS-29 30. mR/hr SW-RIS-605 970 cps ARM-RIS-3 0 3 ' mR/hr TEA-RIS-13 57 ' cpm ARM-RIS-32 5 1 R/hr TEA-RIS-13A ' pmu ARM-RZS-33 3' R/hr TRA RIS-1 2.0E4 cpm ARM-RZS-34 8' R/hr WEA-RZS-14 48 ' cpm CMS-RZS-12/1A 650. cpm WEA-RZS-14A 4 pmu CMS-RIS-12/1B 930. cpm WOA-RIS-31A 6 SE4 cym CMS-RIS-12/3A 5 'E4 cpm WOA-RIS-31B 8. 7E4 cpm CMS-RZS-12/3B 5.9E4 cpm WOA-RIS-32A 7 3E4 cym CMS-RIS-27A CMS-RIS-27B 0 '1 1.4 R/hr R/hr WOA-RZS-32B WRA-RXS-1

8. 1E4 1.8E4 cpm cpm CMS-RIS-27C 0 53 R/hr WRA-RZS-2 1.6E4 cpm

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P9. n RADIATION MONXTORING SYSTEM DATA (T = 05 30) ( 08:30)

NOTE: ~OSH~ Offscale High ALL MONITOR VALUES ARE 1 MINUTE, AVERAGES Monitor value units Monitor value ARM-RIS-01 7200. mR/hr CMS-RIS-27D 0 50 R/hr ARM-RIS-02 7000. mR/hr CMS-RZS-27E 1 2 R/hr ARM-RIS-03 7200. mR/hr CMS-RIS-27F 10 R/hr ARM-RIS-3A 7300. mR/hr FD-RIS-1 1300. cpm ARM-RIS-04 OSH mR/hr FD-RIS-2 850. cpm ARM-RZS-05 4100. mR/hr FD-RIS-3 7900. cpm ARM-RIS-06 OSH mR/hr FDR-RZS-606 50. cps ARM-RZS-07 OSH mR/hr MS-RIS-610A 5' mR/hr ARM-RIS-08 OSH mR/hr MS-RIS-610B 13. mR/hr ARM-RZS-09 3100. mR/hr ~

MS-RIS-610C 18 mR/hr ARM-RIS-10 3500. mR/hr MS-RIS-610D 6.6 mR/hr ARM-RIS-11 2800. mR/hr OG-RXS-601A 9900 cpm ARM-RIS-12 2900. mR/hr OG-RIS-601B '800.

cpm ARM-RIS-13 3100 mR/hr OG-RIS-611 2' mR/hr ARM-RZS-14 51. mR/hr OG-RZS-612 140. mR/hr ARM-RIS-15 3 ' mR/hr PSR-RZ-507 3900. mR/hr ARM-RIS-16 5.9 mR/hr PSR-RI-665 3 ' R/hr ARM-RIS-17 21. mR/hr PSR-RI-704 3900. mR/hr ARM-RIS-18 5 4 mR/hr ,

RCC-RIS-607 680. cps ARM-RIS-19 5 0 mR/hr REA-RZS-19 OSH cpm ARM-RIS-2 0 5.0 mR/hr REA-RIS-19A 15. pmu ARM-RIS-2 1 7' mR/hr REA-RIS-609A OSH mR/hr ARM-RIS-22 7 4 mR/hr REA-RIS-609B OSH mR/hr ARM-RIS-23 3100. mR/hr REA-RIS-609C OSH mR/hr ARM-RZS-24 3900. mR/hr REA-RZS-609D OSH mR/hr ARM-RIS-25 4.3 mR/hr RRA-RIS-1 OSH cpm ARM-RIS-2 6 3 0 mR/hr RRA-RIS-2 OSH cpm ARM-RIS-27 10. mR/hr RRA-RIS-3 OSH cpm ARM-RIS-28 8 2 mR/hr SW-RIS-604 140 cps ARM-RIS-29 30 mR/hr SW-RIS-605 '20.

cps ARM-RIS-3 0 3 ' mR/hr TEA-RIS-13 57. cpm ARM-RIS-32 4.3 R/hr TEA-RXS-13A 2.6 pmu ARM-RIS-33 2 ' R/hr TRA-RIS-1 1 9E4 cpm ARM-RIS-34 7: 1 R/hr WEA-RIS-14 49. cpm CMS-RZS-12/1A. 550. WEA-RIS-14A CMS-RZS-12/1B CMS-RIS-12/3A CMS-RIS-12/3B

'.830.

6E4 5.6E4 cpm cpm cpm cpm WOA-RZS-31A WOA-RIS-31B WOA-RIS-32A 1 4 6 SE4 8.3E4 6.9E4 pmu cpm cpm cpm CMS-RZS-27A 0. 01 R/hr WOA-RIS-32B 7.7E4 cpm CMS-RIS-27B 1 4 R/hr WRA-RIS-1 1.7E4 cpm CMS-RIS-27C 0 51 R/hr WRA-RIS-2 1.5E4 cpm

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P9. o RADIATION MONITORING SYSTEM DATA (T = 05:45) ( 08:45)

NOTE: iOSHi = Offscale High ALL MONITOR VALUES ARE 1 MINUTE AVERAGES Monitor value units Monitor value units ARM-RZS-01 ARM-RIS-02 6200 6000.

mR/hr mR/hr CMS-RXS-27D CMS-RIS-27E 0 '8 1.2 R/hr R/hr ARM-RIS-03 6200. mR/hz CMS-RIS-27F 10. R/hr ARM-RZS-3A 6300 mR/hr FD-RIS-1 1300 cpm ARM-RIS-04 OSH mR/hr FD-RIS-2 '50 cpm ARM-RIS-05 3500. mR/hr FD-RZS-3 '800.

cpm ARM-RIS-06 OSH mR/hr FDR-RIS-606 50. cps ARM-RZS-07 OSH mR/hr MS-RIS-610A 5 4 mR/hr ARM-RIS-08 OSH mR/hr MS-RXS-610B 13 ~ mR/hr ARM-RIS-09 2700 mR/hr MS-RIS-610C 18. mR/hr ARM-RIS-10 3000 mR/hr MS-RIS-610D 6.4 mR/hr ARM-RXS-11 2400. mR/hr OG-RIS-601A 8000 cpm ARM-RIS-12 2500. mR/hz OG-RIS-601B '000.

cpm ARM-RXS-13 2700 mR/hr OG-RIS-611 2 ' mR/hr ARM-RZS-14 50 ' mR/hr OG-RIS-612 140 mR/hr ARM RIS-15 ~ 0 mR/hr PSR-RZ-507 '300.

mR/hr ARM-RZS-16 5 8 mR/hr PSR-RZ-665 3.3 R/hr ARM-RIS-17 21 ~ mR/hr PSR-RZ-704 3300. mR/hr ARM-RIS-18 5.3 mR/hz RCC-RZS-607 600. cps ARM-RIS-19 5.0 mR/hr REA-RZS-19 OSH cpm ARM-RIS-2 0 5.0 mR/hr REA-RZS-19A 15 pmu ARM RIS-21 7' mR/hr REA-RZS-609A OSH mR/hr ARM-RIS-22 7.4 mR/hr REA-RZS-609B OSH mR/hr ARM-RIS-23 2600 mR/hr REA-RXS-609C OSH mR/hr ARM-RIS-24 3300 mR/hr REA-RIS-609D OSH mR/hr ARM-RIS-25 4.3 mR/hr RRA-RZS-1 OSH cpm ARM-RIS-26 3 ' mR/hr RRA-RZS-2 OSH cpm ARM-RIS-27 10 mR/hr RRA-RIS-3 OSH cpm ARM-RIS-28 8 2 mR/hr SW-RIS-604 120. cps.

ARM-RIS-29 30. mR/hr SW-RIS-605 710. cps ARM-RIS-3 0 3.0 mR/hr TEA-RXS-13 58.

ARM-RIS-32 ARM-RIS-33

'.7 2.5 R/hr R/hr TEA-RIS-13A TRA-RIS-1 2'

1 SE4 cpm pmu cpm ARM-RIS-34 6.1 R/hz'pm WEA-RIS-14 50. cpm CMS-RXS-12/1A 470 WEA-RIS-14A 1.4 pmu CMS-RIS-12/1B 750. cpm WOA-RIS-31A 6 ~ 2E4 cpm CMS-RXS-12/3A 5.4E4 cpm WOA-RIS-31B 7 ~ 9E4 cpm CMS-RIS-12/3B 5.4E4 cpm WOA-RIS-32A 6.6E4 cpm CMS-RZS-27A 0.01 R/hr WOA-RIS-32B 7.3E4 cpm CMS-RZS-27B 1 4 R/hr WRA-RIS-1 1.6E4 cpm CMS-RIS-27C 0.48 R/hr WRA-RIS-2 1.4E4 cpm

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P9. p.

RADIATION MONITORING SYSTEM DATA (T = 06:00) ( 09:00)

NOTE: ~OSH~ = Offscale High ALL MONITOR VALUES ARE 1 MINUTE AVERAGES Monitor value units Monitor value units ARM-RXS-01 5500. mR/hr CMS-RIS-27D 0.46 R/hr ARM-RIS-02 5300 mR/hz CMS-RIS-27E 1.2 R/hr ARM-RIS-03 5400. mR/hr CMS-RIS-27F 10. R/hr ARM-RZS-3A 5600. mR/hr FD-RIS-1 1300 cpm ARM-RXS-04 OSH mR/hr FD-RIS-2 850. cpm ARM-RIS-05 3100 mR/hr FD-RIS-3 7600. cpm ARM-RIS-06 OSH mR/hr FDR-RIS-606 50. cps ARM-RIS-07 OSH mR/hr MS-RIS-610A 5.3 mR/hr ARM-RZS-08 OSH mR/hr MS-RZS-610B 13 mR/hr ARM-RIS-09 2400 mR/hr MS-RIS-610C '8 mR/hr ARM-RIS-10 2600 mR/hr MS-RIS-610D '.3 mR/hr ARM-RZS-11 2100. mR/hr OG-RZS-601A 6600. cpm ARM-RXS-12 2200 mR/hz OG-RIS-601B 6600. cpm ARM-RIS-13 '400 mR/hz OG-RIS-611 2.6 mR/hr ARM-RIS-14 ' mR/hr

'0 OG-RXS-612 140 ~ mR/hr ARM-RZS-15 ' mR/hr PSR-RI-507 2900. mR/hz ARM-RIS-16 5.8 mR/hr PSR-RI-665 2.9 R/hr ARM-RXS-17 20 mR/hr PSR-RZ-704 2900. mR/hr ARM-RIS-18 5 ' mR/hr RCC-RIS-607 530. cps ARM-RIS-19 5.0 mR/hr REA-RIS-19 9 'E6 cpm ARM-RIS-20 5.0 mR/hr REA-RIS-19A 15. pmu ARK-RIS-2 1 7.0 mR/hr REA-RIS-609A OSH mR/hr ARM-RZS-22 7.4 mR/hr REA-RZS-609B OSH mR/hr ARM-RIS-23 2300 ~ mR/hz REA-RIS-609C OSH mR/hr ARM-RXS-24 2900. mR/hr REA-RIS-609D OSH mR/hr ARM-RIS-25 4.3 mR/hr RRA-RIS-1 OSH cpm ARM-RZS-2 6 3.0 mR/hr RRA-RIS-2 OSH cpm ARM-RIS-27 10- mR/hr RRA-RIS-3 OSH cpm ARM-RIS-28 8 ' mR/hr SW-RZS-604 110. cps ARM-RXS-29 30. mR/hr SW-RZS-605 620 ~ cps ARM-RZS-3 0 3.0 mR/hz TEA-RIS-13 58 cpm ARM-RZS-3 2 3 3 R/hz'/hz TEA-RIS-13A '.6 pmu ARM-RZS-3 3 2 ' TRA-RIS-1 1.7E4 cpm ARM-RIS-34 5 ' R/hr WEA-RIS-14 '50 cpm CMS-RIS-12/1A 410 cpm WEA-RIS-14A 1.4 pmu CMS-RIS-12/1B 690 cpm WOA-RIS-3 1A 5. 9E4 cpm CMS-RIS-12/3A 5.2E4 cpm WOA-RIS-31B 7. 5E4 cpm CMS-RZS-12/3B 5.2E4 cpm WOA-RIS-32A 6. 3E4 cpm CMS-RZS-27A 0.01 R/hr WOA-RZS-32B 7.0E4 cpm CMS-RZS-27B 1.4 R/hr WRA-RIS-1, 1.5E4 cpm 0 CMS-RIS-27C 0.46 R/hr WRA-RIS-2 1.3E4 cpm

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P9. q RADIATION MONITORING SYSTEM DATA (T = 06 15) ( 09:15)

NOTE: ~OSH' Offscale High ALL MONITOR VALUES ARE 1 MINUTE AVERAGES Monitor value units Monitor value units ARM-RIS-01 4900. mR/hr CMS-RXS-27D 0.44 R/hr ARM-RIS-02 4700. mR/hr CMS-RIS-27E 1 2 R/hr

"'RM-RZS-03 4900. mR/hr CMS-RIS-27F 10 R/hr ARM-RZS-3A 5000 mR/hx FD-RIS-1 '300 cpm ARM-RZS-04 OSH mR/hr FD-RZS-2 '50 cpm ARM-RXS-05 2800 mR/hr FD-RZS-3 '500 cpm ARM-RIS-06 'SH mR/hx FDR-RIS-606 ~

'0 cps ARM-RXS-07 . OSH mR/hr MS-RIS-610A 5.3 mR/hr ARM-RXS-08 OSH mR/hr MS-RIS-610B 12 mR/hr ARM-RIS-09 2100 mR/hr MS-RIS-610C 8 mR/hr ARM-RXS-10 mR/hr MS-RIS-610D 1 mR/hr OG-RIS-601A

'400'900 ARM-RXS-11 mR/hr 5400 cpm ARM-RIS-12 1900 mR/hr OG-RIS-601B '400.

cpm ARM-RZS-13 '100 mR/hr OG-RIS-611 2 ' mR/hr ARM-RZS-14 49 ' mR/hr OG-RIS-612 140 ~ mR/hz ARM RXS-15 ' mR/hr PSR-RI-507 2600. mR/hr ARM-RIS-16 5.8 mR/hr PSR-RI-665 2~6 R/hr ARM-RZS-17 20 mR/hr PSR-RI-704 2600. mR/hr ARM-RIS-18 '.3 RCC-RIS-607 480 cps ARM-RXS-19 5.0 mR/hr REA-RIS-19 '.4E6 cpm ARM-RXS-2 0 5.0 mR/hr REA-RIS-19A 14. pmu ARM-RXS-2 1 7' mR/hr REA-RIS-609A OSH mR/hx ARM-RZS-22 7 2 mR/hr REA-RXS-609B OSH mR/hr ARM-RIS-23 2100 mR/hr REA-RIS-609C OSH mR/hr ARM-RXS-24 2600. mR/hr REA-RIS-609D OSH mR/hr ARM-RXS-25 4 2 mR/hr RRA-RIS-1 OSH cpm ARM-RXS-2 6 3.0 mR/hr RRA-RIS-2 OSH cpm ARM-RZS-27 10 mR/hr RRA-RIS-3 OSH cpm ARM-RIS-28 8' mR/hr SW-RIS-604 96. cps ARM-RXS-29 30. mR/hr SW-RIS-605 560. cps ARM-RIS-3 0 3.0 mR/hr TEA-RIS-13 57. cpm ARM-RZS-3 2 2 9 R/hr TEA-RIS-13A 2 6 pmu ARM-RIS-33 2 0 R/hz'/hr TRA-RIS-1 1 2E4 cpm ARM-RIS-34 4.8 WEA-RIS-14 51. cpm CMS-RIS-12/1A 360 cpm WEA-RIS-14A 1.4 pmu CMS-RIS-12/1B '40.

cpm WOA-RIS-31A 3 8E4 .cpm CMS-RZS-12/3A 5.0E4 cpm WOA-RIS-31B 4 8E4 cpm CMS-RIS-12/3B 5.0E4 'pm WOA-RIS-32A 4 'E4 cpm CMS-RZS-27A 0.01 R/hr WOA-RIS-32B 4 5E4 cpm CMS-RXS-27B 1 4 R/hr WRA-RIS-1 CMS-RIS-27C 0 44 '/hr WRA-RIS-2 1 1E4 9500.

cpm cpm

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P9. r RADIATION MONITORING SYSTEM DATA (T = 06:30) ( 09:30)

NOTE: 'OSH' Offscale High ALL MONITOR VALUES ARE 1 MINUTE AVERAGES Monitor value units Monitor value units ARM-RIS-01 4500. mR/hr CMS-RIS-27D 0. 42 R/hr ARM-RZS-02 4200. mR/hr CMS-RIS-27E 1 2 R/hr ARM-RIS-03 4400 mR/hr CMS-RIS-27F 10 R/hr ARM-RIS-3A 4500. mR/hr FD-RIS-1 '300.

cpm ARM-RIS-04 OSH mR/hr FD-RXS-2 850. cpm ARM-RIS-05 2500. mR/hr FD-RXS-3 7300. cpm ARM-RZS-06 OSH mR/hr FDR-RIS-606 50. cps ARM-RIS-07 OSH mR/hr MS-RIS-610A 5.2 mR/hr ARM-RIS-08 OSH mR/hr MS-RZS-610B 12 mR/hr ARM-RZS-09 1900. mR/hr MS-RXS-610C '8.

mR/hr ARM-RIS-10 2100. mR/hr MS-RIS-610D 6' mR/hr ARM-RIS-11 1700 mR/hr OG-RIS-601A 4500. cpm ARM-RIS-12 1700. mR/hr OG-RIS-601B 4400. cpm ARM-RIS-13 1900 mR/hr OG-RXS-611 2 ' mR/hr ARM-RIS-14 '9.

mR/hr OG-RIS-612 140 mR/hr ARM-RIS-15 3.0 mR/hr PSR-RI-507 '

'400 mR/hr ARM-RIS-1 6 5.8 mR/hr PSR-RX-665 ' ~

R/hr ARM-RIS-17 20. mR/hr PSR-RI-704 2400. mR/hr ARM-RZS-18 5.2 mR/hr RCC-RIS-607 440 cps ARM-RIS-19 5.0 'R/hr REA-RZS-19 '.1E6 cpm ARM-RIS-2 0 5.0 mR/hr REA-RIS-19A 14 pmu ARM-RIS-21 7.0 mR/hr REA-RIS-609A 'SH ARM-RIS-22 7 2 mR/hr REA-RIS-609B OSH mR/hr ARM-RIS-23 1900. mR/hr REA-RIS-609C OSH mR/hr ARM-RZS-24 2400. mR/hr REA-RIS-609D OSH mR/hr ARM-RIS-2.5 4.2 mR/hr RRA-RZS-1 OSH cpm ARM-RZS-2 6 3.0 mR/hr RRA-RZS-2 OSH cpm ARM-RIS-27 10. mR/hr RRA-RIS-3 OSH cpm ARM-RIS-28 8.2 mR/hr SW-RIS-604 87. cps ARM-RIS-29 30 mR/hr SW-RXS-605 500. cps ARM-RXS-3 0 3~0 mR/hr TEA-RIS-13 58. cpm ARM-RZS-32 F 7 R/hr TEA-RZS-13A 2 ' pmu ARM-RIS-33 1.8 R/hr TRA-RIS-1 1. 1E4 cpm ARM-RIS-34 4.3 R/hr WEA-RZS-14 52. cpm CMS-RIS-12/ 1A 320. cpm WEA-RZS-14A 1.4 pmu CMS-RZS-12/1B 600. cpm WOA-RXS-31A 3.7E4 cpm CMS-RIS-12/3A 4 SE4 cpm WOA-RZS-31B 4.6E4 cpm CMS-RIS-12/3B 4 SE4 cpm WOA-RIS-32A 3.8E4 cpm CMS-RZS-27A 0. 01 R/hr WOA-RIS-32B 4 'E4 cpm CMS-RIS-27B 1.4 R/hr WRA-RIS-1 1.0E4 cpm CMS-RIS-27C 0.42 R/hr WRA-RIS-2 9100. cpm

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P9. s RADIATION MONITORING SYSTEM DATA (T = 06:45) ( 09 45)

NOTE: iOSHi ~ Offscale High ALL MONITOR VALUES ARE 1 MINUTE AVERAGES Monitor value units Monitor value units ARM-RIS-01 4100 CMS-RIS-27D 0.40 ARM-RIS-02 3900 mR/hr CMS-RZS-27E 1' R/hr ARM-RIS-03 '100 mR/hr CMS-RIS-27F 10 R/hr ARM-RXS-3A 4200>> mR/hr FD-RIS-1 1300. cpm ARM-RIS-04 OSH mR/hr FD-RIS-2 850. cpm ARM-RIS-05 2300 mR/hr FD-RIS-3 7200 cpm ARM-RIS-06 OSH mR/hr FDR-RZS-606 '0.

cps ARM-RIS-07 OSH mR/hr MS-RIS-610A 5.2 mR/hr ARM-RZS-08 OSH mR/hr MS-RIS-610B 12 mR/hr ARM-RIS-09 ARM-RIS-10 ARM-RIS-11 1800 1500.

'000.

mR/hr mR/hr mR/hr MS-RIS-610C MS-RIS-610D OG-RZS-601A 18 5.9 3700.

'/hr mR/hr mR/hr cpm ARM-RXS-12 1600. mR/hr OG-RIS-601B 3700 cpm ARM-RIS-13 1700. mR/hr OG-RIS-611 2 7 mR/hr ARM-RZS-14 49 ' mR/hr OG-RZS-612 140 mR/hr ARM-RIS-15 0 mR/hr PSR RI-507 '

'200 mR/hr ARM-RXS-16 5 8 mR/hr PSR-RZ-665 2 R/hr ARM-RIS-17, 20 ~ mR/hx PSR-RI-704 2200 mR/hr ARM-RIS-18 5 2 mR/hx RCC-RIS-607 410. cps ARM-RXS-19 5 0 mR/hr REA-RIS-19 8.8E6 cpm ARM-RIS-2 0 5.0 mR/hr REA-RZS-19A 13 ~ pmu ARM-RIS-2 1 7' mR/hr REA-RZS-609A OSH mR/hx

.ARM-RXS-22 7 2 mR/hr REA-RIS-609B OSH mR/hr ARM-RZS-23 1700 ~ mR/hr REA-RIS-609C OSH mR/hr ARM-RIS-24 2200 mR/hr REA-RIS-609D OSH mR/hr ARM-RX8-25 4' mR/hr RRA-RIS-1 OSH cpm ARM-RIS-2 6 3 0 mR/hx RRA-RIS-2 OSH cpm ARM-RIS-27 10 mR/hr RRA-RIS-3 OSH cpm ARM-RZS-28 8 2 mR/hr SW-RXS-604 80 ~ cps ARM-RIS-29 30. mR/hr SW-RIS-605 460 ~ cps ARM-RIS-3 0 3 0 TEA-RIS-13 58 cpm ARM-RIS-32 2.4 R/hr TEA-RZS-13A '-6 pmu ARM-RZS-33, 1 7 R/hr - TRA-RIS-1 1.1E4 cpm ARM-RIS-34 4 0 R/hr WEA-RIS-14 53 cpm CMS-RIS-12/ 1A 290 cpm WEA-RIS-14A 1 4 pmu CMS-RIS-12/1B 570. cpm WOA-RIS-31A 3.5E4 cpm CMS-RZS-12/3A 4 7E4 cpm WOA-R1S-31B 4 'E4 cpm

'MS-RIS-12/3B 4 7E4 cpm WOA-RIS-32A 3.7E4 cpm CMS-RIS-27A 0.01 R/hr WOA-RZS-32B 4 1E4 cpm CMS-RIS-27B 1 4 R/hr WRA-RIS-1 9900. cpm CMS-RZS-27C 0 40 R/hr WRA-RIS-2 8700 cpm

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P9 ~ t RADIATION MONITORING SYSTEM DATA (T = 07 00) ( 10:00)

NOTE: ~OSH~ = Offscale High ALL MONITOR VALUES ARE 1 MINUTE AVERAGES Monitor value units Monitor value units ARM-RIS-01 3800. mR/hr CMS-RIS-27D 0.38 R/hr ARM-RIS-02 3600. mR/hr CMS-RIS-27E 1' R/hr ARM-RIS-03 3800 mR/hr CMS-RIS-27F 10 R/hr ARM-RIS-3A '900.

mR/hr FD-RZS-1 '300 cpm ARM-RZS-04 OSH mR/hr FD-RIS-2 '50 cpm ARM-RIS-05 2100. mR/hr FD-RIS-3 '100 cpm ARM-RIS-06 OSH mR/hz FDR-RZS-606 '0

.cps ARM-RIS-07 OSH mR/hr MS-RIS-610A 5.1 mR/hr ARM-RIS-08 OSH mR/hr MS-RIS-610B 12 mR/hr ARM-RIS-09 1600. mR/hr MS-RIS-610C '8 mR/hr ARM-RXS-10 1800 mR/hr MS-RIS-610D '.7 mR/hr ARM-RIS-11 1400 mR/hr OG-RIS-601A 3100 cpm ARM-RIS-12 '500.

mR/hr OG-RIS-601B 3100 ' cpm ARM-RIS-13 1600. mR/hr OG-RIS-611 ' mR/hr ARM-RIS-14 49. mR/hz OG-RIS-612 140 mR/hr ARM-RIS-15 3 ' mR/hz PSR-RI-507 2000 mR/hr ARM-RIS-16 5.8 mR/hz PSR-RI-665 2 ' R/hr ARM-RIS-17 20. mR/hz PSR-RI-704 2000 mR/hr ARM-RZS-18 5' mR/hr RCC-RIS-607 390. cps ARM-RIS-19 5 0 mR/hz REA-RXS-19 8.5E6 cpm ARM-RIS-20 5~0 mR/hr REA-RIS-19A 13 pmu ARM-RZS-2 1 7.0 mR/hr REA-RIS-609A OSH mR/hr ARM-RIS-22 7' mR/hz REA-RIS-609B OSH mR/hr ARM-RIS-23 1600. mR/hr REA-'RZS-609C OSH mR/hr ARM-RIS-24 2000. mR/hr REA-RIS-609D OSH mR/hr ARM-RIS-25 4~1 mR/hr RRA-RIS-1 OSH cpm ARM-RIS-26 3~0 mR/hr RRA-RIS-2 OSH cpm ARM-RIS-27 10. mR/hr RRA-RIS-3 OSH cpm ARM-RIS-28 8' mR/hr SW-RIS-604 74 cps ARM-RIS-29 30. mR/hr SW-RIS-605, 430. cps ARM-RIS-3 0 3.0 mR/hr TEA-RIS-13 58. cpm ARM-RIS-32 2 ' R/hr TEA-RIS-13A 2 ' pmu ARM-RIS-33 1 5 R/hr TRA-RIS-1 6700 cpm ARM-RIS-34 3 7 R/hz'pm WEA-RZS-14 53. cpm CMS-RIS-12/1A 260 WEA-RIS-14A 1.4 pmu CMS-RZS-12/1B 550. cpm WOA-RIS-31A 1.8E4 cpm CMS-RIS-12/3A 4.6E4 cpm WOA-RIS-31B 2.1E4 cpm CMS-RIS-12/3B 4.6E4 cpm WOA-RZS-32A 1 8E4 cpm CMS-RXS-27A CMS-RZS-27B 0 '1 1.4 R/hr R/hz WOA-RZS-32B WRA-RIS-1 2.0E4 6800 cpm cpm CMS-RIS-27C 0.39 R/hr WRA-RIS-2 '500 cpm

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P9. u RADIATION MONXTORZNG SYSTEM DATA (T = 07:30) ( 10:30)

NOTE: 'OSH' Offscale High ALL MONITOR VALUES ARE 1 MINUTE AVERAGES Monitor value units Monitor value units ARM-RZS-01 3400 mR/hr CMS-RIS-27D 0.36 R/hz ARM-RZS-02 3100. mR/hr CMS-RZS-27E 1 2 R/hr ARM-RIS-03 3300. mR/hz CMS-RZS-27F 10 R/hr ARM-RZS-3A 3400. mR/hr FD-RZS-1 '300.

cpm ARM-RIS-04 OSH mR/hr FD-RIS-2 850. cpm ARM-RZS-05 1900 mR/hr FD-RIS-3 6900. CPln ARM-RIS-06 'SH mR/hr FDR-RZS-606 50. CPS ARM-RIS-07 OSH mR/hr MS-RIS-610A 5 1 mR/hr ARM-RIS-08 OSH mR/hz MS-RIS-610B 12 mR/hr ARM-RZS-09 1400. mR/hr MS-RIS-610C '7'.6 mR/hr ARM-RIS-10 1600. mR/hr MS-RIS-610D mR/hz ARM-RIS-11 1200. mR/hz OG-RIS-6 01A 2200 cpm ARM-RIS-12 1300 mR/hr OG-RIS-601B '200.

cpm ARM-RXS-13 1400. mR/hr OG-RZS-611 3 0 mR/hr ARM-RIS-14 48 mR/hz OG-RIS-612 140 ~ mR/hr ARM-RZS-15 '.0 mR/hr PSR-RI-507 1700 ~ mR/hr ARM-RIS-16 5.7 mR/hr PSR-RZ-665 1~7 R/hr ARM-RZS-17 20. mR/hr PSR-RZ-704 1700. mR/hr ARM-RIS-18 5.2 mR/hr RCC-RIS-607 350. CPS ARM-RZS-19 5 0 mR/hr REA-RZS-19 8.0E6 cpm

- ARM-RZS-20 5 0 mR/hr ,

REA-RIS-19A 12. pmu ARM-RIS-2 1 7 0 mR/hr REA-RIS-609A OSH mR/hr ARM-RIS-22 7' mR/hr REA-RIS-609B OSH mR/hr ARM-RIS-23 1400 mR/hz REA-RZS-609C OSH mR/hr ARM-RZS-24 '700.

mR/hr REA-RZS-609D OSH mR/hr ARM-RX8-25 4 1 mR/hr RRA-RZS-1 OSH cpm ARM-'RIS-26 3 0 mR/hr RRA-RZS-2 OSH cpm ARM-RZS-'27 10. mR/hr RRA-RZS-3 OSH cpm ARM-RXS-28 8 2 mR/hz SW-RZS-604 65. cps ARM-RIS-29 30. mR/hz SW-RZS-605 380 cps ARM-RIS-3 0 3 0 mR/hr TEA-RIS-13 '8.

cpm ARM-RZS-32 2' R/hr TEA-RIS-13A 2' pmu ARM-RIS-3 3 1.4 R/hr TRA-RIS-1 6300 cpm ARM-RZS-34 3 2 R/hr WEA-RIS-14 '6.

cpm CMS-RZS-12/ 1A 230. cpm WEA-RIS-14A 1.4 pmu CMS-RIS-12/1B 510. cpm WOA-RIS-31A 1-6E4 cpm CMS-RIS-12/3A 4. 3E4 cpm WOA-RZS-31B 2 'E4 cpm CMS-RIS 12/3B 4. 3E4 cpm WOA-RIS-32A 1.7E4 cpm CMS-RIS-27A 0 01 R/hr WOA-RZS-32B 1.9E4 cpm CMS-RIS-27B 1.4 R/hr WRA-RZS-1 6400.. cpm CMS-RIS-27C 0 36. R/hr WRA-RIS-2 5200. cpm

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 i TABLE P9. v RADIATION MONITORING SYSTEM DATA (T = 08:00) ( 11:00)

NOTE: IOSHI Offscale High ALL MONITOR VALUES ARE 1 MINUTE AVERAGES Monitor value units Monitor value units ARM-RIS-01 3000. mR/hr CMS-RXS-27D 0.33 R/hr ARM-RZS-02 2800. mR/hx CMS-RZS-27E, 1 2 R/hr ARM-RIS-03 3000 mR/hr CMS-RIS-27F 10 R/hr ARM-RIS-3A 3100 mR/hx FD-RIS-1 '300 cpm ARM-RZS-04 'SH mR/hr FD-RIS-2 '50.

cpm ARM-RIS-05 1700. mR/hx FD-RIS-3 6600 cpm ARM-RZS-06 OSH mR/hr FDR-RZS-606 '0.

cps ARM-RXS-07 OSH mR/hx MS-RIS-610A 5' mR/hr ARM-RIS-08 OSH mR/hr MS-RIS-610B 12 mR/hr ARM-RIS-09 1300. mR/hr MS-RZS-610C 7 mR/hr ARM-RZS-10 1400. mR/hr MS-RIS-610D ' mR/hr ARM-RZS-11 1100. mR/hr OG-RIS-601A 1600. cpm ARM-RZS-12 1200 mR/hr OG-RIS-601B 1600 ' cpm ARM-RZS-13 '300 mR/hr OG-RIS-611 0 mR/hr ARM-RZS-14 48 ' mR/hr OG-RIS-612 140 ~ mR/hr ARM-RIS-15 ' mR/hx PSR-RZ-507 1600. mR/hr ARM-RIS-16 5.7 mR/hr PSR-RI-665 1 6 R/hr ARM-RIS-17 20 mR/hr PSR-RI-704 1600 mR/hr ARM-RIS-1S 5.1 mR/hr RCC-RXS-607 '20.

cps ARM-RZS-19 5.0 mR/hr REA-RIS-19 7.6E6 cpm ARM-RZS-2 0 5.0 mR/hr REA-RIS-19A 12 pmu ARM-RIS-2 1 7.0 mR/hx REA-RZS-609A 'SH mR/hr ARM-RXS-22 7 1 mR/hr REA-RIS-609B OSH mR/hr ARM-RZS-2 3 1200. mR/hr REA-RZS-609C OSH mR/hr ARM-RZS-2 4 1600 mR/hr REA-RIS-609D OSH mR/hr ARM-RIS-25 4 ' mR/hr RRA-RIS-1 OSH cpm ARM-RIS-2 6 3.0 mR/hr RRA-RIS-2 OSH cpm ARM-RZS-27 10. mR/hr RRA-RIS-3 OSH cpm ARM-RXS-28 8.2 mR/hr SW-RIS-604 59 cps ARM-RIS-29 30 mR/hr SW-RIS-605 340. cps ARM-RIS-3 0 '.0 mR/hr TEA-RIS-13 58. cpm ARM-RIS-32 1.8 R/hr TEA-RIS-13A 2.6 pmu ARM-RIS-3 3 1 2 R/hr TRA-RIS-1 5800. cpm ARM-RZS-34 2 9 R/hx'pm WEA-RIS-14 59 ' cpm CMS-RXS-12/1A 210 WEA-RXS-14A 4 pmu CMS-RIS-12/1B 490 cpm WOA-RIS-31A 1. 5E4 cpm CMS-RZS-12/3A 4 'E4 cpm WOA-RIS-31B 1.8E4 cpm CMS-RIS-12/3B 4.1E4 cpm WOA-RIS-32A 1.5E4 cpm CMS-RIS-27A 0 F 01 R/hz'/hr WOA-RIS-32B 1.7E4 cpm CMS-RIS-27B 1' WRA-RIS-1 5900. cpm CMS-RZS-27C 0.33 R/hr WRA-RIS-2 4800 cpm

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WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P10.a IN-PLANT SURVEY AND SAMPLING DATA (T = 00:00) ( 03:00)

CLOSED OPEN CLOSED OPEN LOCATION WINDOW WINDOW LOCATION WINDOW WINDOW (mR/hr) (mR/hz) (mR/hz) (mR/hz)

RBC 422 A 0-1 0~1 RBC 548 B 0~1 < 0,1 RBC 422 B 0~1 0~1 RBC 548 C 0.4 0,4 RBC 422 C F 1 0.1 RBC 548 D 0~1 0.1 RBC 422 D 0.1 0.1 RBC 548 E 0.1 0.1 RBC 441 A 0~8 0.8 RBC 572 A 0.1 0~1 RBC 441 B 0.1 0.1 RBC 572 B 0~1 0~1 RBC 441 C 0.1 0.1 RBC 572 C 0.1 F 1 RBC 441 D 0 1 0.1 RBC 572 D 0.1 0~1 RBC 441 E 0 1 0.1 RBC 607 A 0.1 0.1 RBC 441 F 0-1 0~1 RBC 607 B < 0.1 0.1 RBC 441 G 0-1 0.1 RBC 607 C < 0.1 < 0.1 RBC 441 H 6.8 6' RWC 452 A 0.1 0~1 RBC 441 I 2.0 '2. 0 TBC 441 A 0.1 0.1 RBC 471 A 0~1 0.1 TBC 441 B 0.1 0.1 RBC 471 B 0 1 0 1 TBC 441 C 0.1 0.1 RBC 471 C 0~7 0.7 TBC 441 D < 0.1 0~1 RBC 471 D 0.1 0.1 TBC 456 A 0~2 0~2 RBC 501 A 0.1 0.1 TBC 456 B 0~1 0.1 RBC 501 B 0.1 0.1 TBC 456 C 0~1 0.1 RBC 501 C 0.1 0.1 TBC 471 A 0.1 0.1 RBC 501 D 0~9 0~9 TBC 471 B 0~1 0~1 RBC 52'2 A F 1 0.1 TBC 471 C 0~1 0.1 RBC 522 B 0.1 0~1 TBC 501 A 0.1 0.1 RBC. 522 C 1.1 1 1 TBC 501 B < 0.1 0.1 RBC 522 D 0~1 0~1 TBC 501 C 0.1 < 0.1 RBC 548 A 0~1 0.1

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P10.c IN-PLANT SURVEY AND SAMPLING DATA (T = 03-30) ( 06:30)

CLOSED OPEN CLOSED OPEN LOCATION WINDOW WINDOW LOCATION WINDOW WINDOW (mR/hr) (mR/hr) (mR/hr) (mR/hr)

RBC 422 A 0' 0.1 RBC 548 B 0~1 0.1 RBC 422 B 0' 0 1 RBC 548 C 0' 0 '

RBC 422 C 0.1 0' RBC 548 D 0.1 F 1 RBC 422 D 0 1 0.1 RBC 548 E < 0.1 0 1 RBC 441 A 4.6 4 6 RBC 572 A 0 1

~ 0.1 RBC 441 B 0~1 0~1 RBC 572 B 0.1 0~1 RBC 441 C 0.1 0 1 RBC 572 C 0.1 0' RBC 441 D 0~1 0 1 RBC 572 D 0~1 0 1 RBC 441 E 0~1 0' RBC 607 A 0.1 0.1 RBC 441 F 0.1 0 1 RBC 607 B 0~1 0.1 RBC 441 G 0.1 0-1 RBC 607 C 0~1 <,0 1

~

RBC 441 H 6.8 6' RWC 452 A 0.1 0.1 RBC 441 I 2.1 0.1 2.1 0.1 TBC 441 A 0~1 0~1 RBC 471 A TBC 441 B 0.1 0 1 RBC 471 B 0.1 0.1 TBC 441 C 0.1 0' RBC 471 C 0.7 0.7 TBC 441 D 0.1 0' RBC 471 D 0.1 0 1 TBC 456 A 0.3 0' RBC 501 A 0~1 0.1 TBC 456 B 0.1 RBC 501 B 0.1 0 1 TBC 456 C 0 1 ( 0.1 RBC 501 C 0 '1 0~1 TBC 471 A 0~1 0~1 RBC 501 D 0.9 0.9 TBC 471 B 0~1 0 1 RBC 522 A 0.1 0 1 TBC 471 C 0~1 0 1 RBC 522 B < '0.1 0.1 TBC 501 A 0.1 0 1 RBC. 522 C 1.1 1.1 TBC 501 B 0.1 0' RBC 522 D 0~1 0 1 TBC 501 C 0~1 < 0.1 RBC 548 A 0.1 0.1

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P10.d IN-PLANT SURVEY AND SAMPLING DATA (T = 03 45) ( 06:45)

CLOSED OPEN CLOSED OPEN LOCATION WINDOW WINDOW LOCATION WINDOW WINDOW (mR/hr) (mR/hr) (mR/hr) (mR/hr)

RBC 422 A 0 ' 1 2 RBC 548 B 0 3 1..3 RBC 422 B 0.2 1.2 RBC 548 C 0' 1.2 RBC 422 C 0.1 1 1 RBC 548 D 0 2 1.2 RBC 422 D 0~1 1~1 RBC 548 E 0~1 1~1 RBC 441 A 4' 5.3 RBC 572 A 0.3 1.3 RBC 441 B 0.2 1 1 RBC 572 B 0.3 1 3 RBC 441 C 0.2 1.2 RBC 572 C 0.3 1.3 RBC 441 D 0.2 1.2 RBC 572 D 0.3 1.3 RBC 441 E 0.2 1.2 RBC 607 A 0' 1.5 RBC 441 F 0.2 1.2 RBC 607 B 0' 1.5 RBC 441 G 0' 1 3 RBC 607 C 0.5 1.5 RBC 441 H 0.2 1.2 RWC 452 A 0.1 0 1 RBC 441 I 0.3 0.4 1.3

'1. 3 TBC TBC 441 441 A

B 0 1 0~1 0~1 0.1 RBC 471 A RBC 471 B 0~1 1.1 TBC 441 C 0.1 0.1 RBC 471 C 0 ' 1.3 TBC 441 D 0~1 0.1 RBC 471 D 0.4 1.3 TBC 456 A 0.2 0.2 RBC 501 A 0.2 1.2 TBC 456 B 0~1 0.1 RBC 501 B 0' 1.3 TBC 456 C 0.1 0~1 RBC 501 C 0.3 1.3 TBC 471 A 0~1 F 1 RBC 501 D 0.3 1.3 TBC 471 B 0~1 0.1 RBC 522 A 0.3 1' TBC 471 C 0~1 0.1 RBC 522 B 0.2 1.2 TBC 501 A 0 1 0.1 RBC 522 C 0.3 1 3 TBC 501 B 0~1 0.1 RBC 522 D 0.3 1.2 TBC 501 C 0~1 0.1 RBC 548 A 0.2 1~2

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P10.e ZN-PLANT SURVEY AND SAMPLING DATA (T = 04:00) ( 07:00)

CLOSED OPEN CLOSED OPEN LOCATION WINDOW WINDOW LOCATION WINDOW WINDOW (mR/hr) (mR/hr) (mR/hr) (mR/hr)

RBC 422 A 0 ' 1.2 RBC 548 B 0 3 1.3 RBC 422 B 0.2 1.2 RBC 548 C 0 ' 1.2 RBC 422 C 0.1 1.1 RBC 548 D 0.2 1.2 RBC 422 D 0 1 1.1 RBC 548 E 0 1 1.1 RBC 441 A 4~1 5.1 RBC 572 A 0' 1.3 RBC 441 B 0 2 1.2 RBC 572 B 0.3 1.3 RBC 441 C 0 2 1.2 RBC 572 C 0' 1.3 RBC 441 D 0-2 1.2 RBC 572 D 0.3 1.3 RBC 441 E 0 2 1.2 RBC 607 A 0.5 1.5 RBC 441 F 0.2 1 2 RBC 607 B 0 5 1.5 RBC 441 G 0 3 1.3 RBC 607 C 0.5 1.5 RBC 441 H 0 2 1.2 RWC 452 A 0 1 0.1 RBC 441 471 I 0.3 1.3 1.3 TBC 441 441 A 0.1 0.1 <

0.1 0.1 RBC A 0 TBC B RBC 471 B 0.1 1.1 TBC 441 C 0.1 0' RBC 471 C 0 3 1.3 TBC 441 D 0 1 0' RBC 471 D 0 ' 1.3 TBC 456 A 0 2 0.2 501 A ' 1.2 456 RBC RBC RBC 501 501 B

C 0

0 '

0 3 1'

1.3 TBC TBC TBC 456 471 B

C A

0~1 0~1 0 1 0.

0~1 1

RBC 501 D 0.3 1.3 TBC 471 B 0.1 0.1 0.3 0.1 0.1 RBC RBC RBC 522 522 522 A

B C

'.2 0 3 1 3 1.2 1.3 TBC TBC TBC 471 501 501 C

A B

( 0.1 0.1 0~1 0.1 RBC 522 D 0.3 1.3 TBC 501 C 0.1 0.1 RBC 548 A 0.2 1.2

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P10.f IN-PLANT SURVEY AND SAMPLING DATA (T = 04:15) ( 07:15)

CLOSED OPEN CLOSED OPEN LOCATION WINDOW WINDOW LOCATION WINDOW WINDOW (mR/hr) (mR/hr) (mR/hr) (mR/hr)

RBC 422 A 5900 1. 4E4 RBC 548 B 7300. 1. 6E4 RBC 422 B '800.

l. 4E4 RBC 548 C 4100. 1. 2E4 RBC 422 C 3000 1 1E4 RBC 548 D 5700. 1. 4E4 RBC 422 D 3200. 1 1E4 RBC 548 E 3000. 1. 1E4 RBC 441 A 3500 1.2E4 RBC 572 A 7400. 1. 6E4 RBC 441 B '700 1.2E4 RBC 572 B 8000. 1.6E4 RBC 441 C '800.

1.4E4 RBC 572 C 7400. 1 6E4 RBC 441 D 5900 1.4E4 RBC 572 D 8000. 1.6E4 RBC 441 E 4800. 1.3E4 RBC 607 A 1.2E4 2 'E4 RBC 441 F 5300. 1.4E4 RBC 607 B 1.2E4 2 'E4 RBC 441 G 5500. 1 4E4 RBC 607 C 1.2E4 2 'E4 RBC 441 H 5900. 1 4E4 RWC 452 A 0' 0.1 RBC 441 I 6600. 1. 5E4 TBC 441 A 0.1 0.1 RBC 471 A 8500. 1. 7E4 TBC 441 B 0.1 0~1 RBC 471 B 3000. 1 1E4 TBC 441 C 0.1 0 1 RBC 471 C 7500. 1 'E4 TBC 441 D 0~1 0~1 RBC 471 D 8400. 1.7E4 TBC 456 A 0' 0.2 RBC 501 A 4300 1.3E4 TBC 456 B ( 0.1 0.1 RBC 501 B 7500 1 6E4 TBC 456 C 0~1 Owl RBC 501 C '500.

1 6E4 TBC 471 A 0~1 F 1 RBC 501 D 6500. 1.5E4 TBC 471 B 0.1 0.1 RBC 522 A 7700. 1 6E4 TBC 471 C 0' 0 '

RBC 522 B 6000. 1.4E4 TBC 501 A 7' 7 7 RBC 522 C 7700. 1.6E4 TBC 501 B 4' 4.0 RBC 522 D 6500. 1 5E4 TBC 501 C .5 ' 5.0 RBC 548 A 5700. 1. 4E4

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P10.g IN-PLANT SURVEY AND SAMPLING DATA (T = 04 30) ( 07:30)

CLOSED OPEN CLOSED O PEN LOCATION WINDOW WINDOW LOCATION WINDOW WINDOW (mR/hr) (mR/hr) (mR/hr) (mR/hr)

RBC 422 A 6900 1.8E4 RBC 548 B 8400 2.0E4 RBC 422 B 6700 1 8E4 RBC 548 C 4800. 1.6E4 RBC 422 C 3400 1.5E4 RBC 548 D 6600 1 'E4 RBC 422 D '700 1 5E4 RBC 548 E '400.

1.5E4 RBC 441 A 4000 1. 5E4 RBC 572 A 8700 2 'E4 RBC 441 B '300

1. 6E4 RBC 572 B '200.

2 'E4 RBC 441 C '700.

1. 8E4 RBC 572 C 8500. 2 'E4 RBC 441 D 6900. 1 8E4 RBC 572 D 9200 ' 2.1E4 RBC 441 E 5500 1. 7E4 RBC 607 A 4E4 2 'E4 RBC 441 F 6100. 1. 7E4 RBC 607 B 1. 4E4 2.5E4 RBC 441 G 6300 1. 8E4 RBC 607 C 1 4E4 2.5E4 RBC 441 H 6800. 1. 8E4 RWC 452 A 0.1 F 1 RBC 441 I 7600. 1. 9E4 TBC 441 A 0.1 0.1 RBC 471 A 9800. 2 ~ 1E4 TBC 441 B 0.1 0~1 RBC 471 B 3500. 1 SE4 TBC 441 C 0.1 RBC 471 C 8600. 2.0E4 TBC 441 D 0.1 RBC 471 D 9700 2.1E4 TBC 456 A 0.2 RBC 501 A '000 1 6E4 TBC 456 B 0.1 RBC 501 B '600 2 'E4 TBC 456 C ( 0.1 RBC 501 C '600.

2.0E4 TBC 471 A 0~1 RBC 501 D 7500. 1.9E4 TBC 471 B ( 0.1 0~1 RBC 522 A 8900 2.0E4 TBC 471 C 0.3 0' RBC 522 B '900 1.8E4 TBC 501 A 9' 9.2 RBC 522 C '900 2.0E4 TBC 501 B 4.8 4 '

RBC 522 D '500.

1.9E4 TBC 501 C 5.8 5.8 RBC 548 A 6600. 1.8E4

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P10.h IN-PLANT SURVEY AND SAMPLING DATA (T = 04:45) ( 07:45)

CLOSED OPEN CLOSED OPEN LOCATION WINDOW WINDOW LOCATION WINDOW WINDOW (mR/hr) (mR/hr) (mR/hr) (mR/hr)

RBC 422 A 5500. 1. 6E4 RBC 548 B 6700. 1.7E4 RBC 422 B 5400. 1.6E4 RBC 548 C 3800. 1.5E4 RBC 422 C 2700. 1 3E4 RBC 548 D 5200. 1.6E4 RBC 422 D 3000 1. 4E4 RBC 548 E 2700. 1.3E4 RBC 441 A '200.

1. 4E4 RBC 572 A 7100. 1 8E4 RBC 441 B 3500. 1. 4E4 RBC 572 B 7400 1.8E4 RBC 441 C 5400. 1. 6E4 RBC 572 C '800.

1.8E4 RBC 441 D 5500. 1. 6E4 RBC 572 D 7400. 1.8E4 RBC 441 E 4400. 1. 5E4 RBC 607 A 1.1E4 2 2E4 RBC 441 F 4900 1. 6E4 RBC 607 B 1.1E4 2 ~ 2E4 RBC 441 G '000.

1. 6E4 RBC 607 C 1.1E4 2 2E4 RBC 441 H 5400. 1. 6E4 RWC 452 A 0 ' 0' RBC 441 I 6000.

7800

1. 7E4

1. 9E4 TBC 44-1 A TBC 441 B 0 1 0'

0' 0.1 RBC 471 A RBC 471 B '800.

1. 4E4 TBC 441 C 0' 0 1 RBC 471 C 6900. 1.8E4 TBC 441 D 0' 0~1 RBC 471 D 7700. 1.8E4 TBC 456 A 0.2 0.2 RBC 501 A 4000. 1.5E4 TBC 456 B 0~1 0.1 RBC 501 B 6900. 1.8E4 TBC 456 C 0.1 0.1 RBC 501 C 6900. 1 'E4 TBC 471 A 0.1 0.1 RBC 501 D 6000. 1. 7E4 TBC 471 B < 0.1 0.1 RBC 522 A 7100. 1.8E4 TBC 471 C 0 3 0' RBC 522 B 5500. 1.6E4 TBC 501 A 7 7 7.7 RBC 522 C 7100 1 8E4 TBC 501 B 3~9 3 '

RBC 522 D 6000. 1 7E4 TBC 501 C 4.8 4.8 RBC 548 A 5200. 1 6E4

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P10.i IN-PLANT SURVEY AND SAMPLING DATA (T = 05:00) ( 08:00)

CLOSED OPEN CLOSED OPEN LOCATION WINDOW WINDOW LOCATION WINDOW WINDOW (mR/hr) (mR/hr) (mR/hr) (mR/hr)

RBC 422 A 4500 1.5E4 RBC 548 B 5400. 1.6E4 RBC 422 B 4400. 1 5E4 RBC 548 C 3100. 1.3E4 RBC 422 C 2200 1.2E4 RBC 548 D 4300. 1.4E4 RBC 422 D 2400. 1.3E4 RBC 548 E 2200. 1.2E4 RBC 441 A 2600. 1 3E4 RBC 572 A 5900. 1.6E4 RBC 441 B 2800 1 3E4 RBC 572 B 6000. 1.6E4 RBC 441 C 4400. 1 'E4 RBC 572 C 5600. 1. 6E4 RBC 441 D 4500. 1 5E4 RBC 572 D 6000. 1. 6E4 RBC 441 E 3600 1 4E4 RBC 607 A 9100. 1. 9E4 RBC 441 F '900.

1 4E4 RBC 607 B 9100. 1. 9E4 RBC 441 G 4100; 1. 4E4 RBC 607 C 9200. 1. 9E4 RBC 441 H 4400. 1 5E4 RWC 452 A ( 0.1 ( 0~1 RBC 441 I 4900 1. 5E4 TBC 441 A 0' 0.1 RBC 471 A 6400 1. 7E4 TBC 441 B 0' 0.1 RBC 471 B 2300 1. 2E4 TBC 441 C 0.1 RBC 471 C 5600. 1 6E4 TBC 441 D 0.1 RBC 471 D 6300 1 6E4 TBC 456 A 0.2 RBC 501 A '200 1.3E4 TBC 456 B 0' RBC 501 B 5600. 1 6E4 TBC 456 C 0.1 RBC 501 C 5600 1.6E4 TBC 471 A ( 0.1 RBC 501 D '900

1. 5E4 TBC 471 B ( 0.1 ( 0.1 RBC 522 A '800 1 ~ 6E4 TBC 471 C 0.2 0~2 RBC 522 B 4500 1 SE4 TBC 501 A 6.5 6.5 RBC 522 C 5800. 1 6E4 TBC 501 B 3.3 3' RBC 522 D 4900 1.5E4 TBC 501 C 4 ' 4 '

RBC 548 A 4300. 1.4E4

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P10.$

IN-PLANT SURVEY AND SAMPLING DATA (T = 05:30) ( 08:30)

CLOSED OPEN CLOSED OPEN LOCATION WINDOW WINDOW LOCATION WINDOW WINDOW (mR/hr) (mR/hr) (mR/hr) (mR/hr)

RBC 422 A 3100. 1. 2E4 RBC 548 B 3800. 1. 3E4 RBC 422 B 3100. 1 2E4 RBC 548 C 2200. 1. 1E4 RBC 422 C 1600. 1. 1E4 RBC 548 D 3000. 1. 2E4 RBC 422 D 1700. 1 1E4 RBC 548 E 1600. 1. 1E4 RBC 441 A 1800 1 1E4 RBC 572 A 4300. 1. 4E4 RBC 441 B '000.

1 1E4 RBC 572 B 4200 1. 3E4 RBC 441 C 3100. 1. 2E4 RBC 572 C '900.

1. 3E4 RBC 441 D 3100 1 2E4 RBC 572 D 4200. 1 3E4 RBC 441 E '500.

1 2E4 RBC 607 A 6400. 1. 6E4 RBC 441 F . 2800 1 2E4 RBC 607 B 6400. 1.6E4 RBC 441 G 2900 1 2E4 RBC 607 C 6500. 1 6E4 RBC 441 H 3100. 1. 2E4 RWC 452 A 0.1 < 0.1 RBC 441 I 3400. 1 3E4 TBC 441 A 0.1 0' RBC 471 A 4500. 1. 4E4 TBC 441 B < 0.1 0.1 RBC 471 B 1600 1 1E4 TBC 441 C 0.1 0' RBC 471 C 3900. 1 3E4 TBC 441 D 0.1 0.1 RBC 471 D 4400. 1. 4E4 TBC 456 A 0.2 0.2 RBC 501 A 2300 1.1E4 TBC 456 B 0.1 0.1 RBC 501 B '900.

1.3E4 TBC 456 C 0.1 0.1 RBC 501 C 3900. 1.3E4 TBC 471 A 0~1 < 0.1 RBC 501 D 3400. 1.3E4 TBC 471 B 0.1 0' RBC 522 A 4000. 1 3E4 TBC 471 C 0.2 0.2 RBC 522 B 3100. 1 2E4 TBC 501 A 4 9 4.9 RBC 522 C 4000. 1 3E4 TBC 501 B 2.5 2.5 RBC 522 D 3400. 1 3E4 TBC 501 C 2 ' 2.9 RBC 548 A 3000 1. 2E4

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P10.k IN-PLANT SURVEY AND SAMPLING DATA (T = 05:45) ( 08:45)

CLOSED OPEN CLOSED OPEN LOCATION WINDOW WINDOW LOCATION WINDOW WINDOW (mR/hr) (mR/hr) (mR/hr) (mR/hr)

RBC 422 A 2700. 1 1E4 RBC 548 B 3300. 1 ~ 2E4 RBC 422 B 2600. 1. 1E4 RBC 548 C 1900 1.1Z4 RBC 422 C 1300 1 OE4 RBC 548 D 2600. 1 1E4 RBC 422 D 1500. 1.0E4 RBC 548 E 1300 1.0E4 RBC 441 A 1600. 1.0E4 RBC 572 A 3800 1.3E4 RBC 441 B 1700. 1.0E4 RBC 572 B '600 1 2E4 RBC 441 C 2600 1.1E4 RBC 572 C '300

1. 2E4 RBC 441 D '700.

1.1E4 RBC 572 D '600.

1 ~ 2E4 RBC 441' 2200 1.1E4 RBC 607 A 5500. 1. 4E4 RBC 441 F 2400. 1.1E4 RBC 607 B 5500 1. 4E4 RBC 441 G 2500. 1.1E4 RBC 607 C 5600. 1. 4E4 RBC 441 H 2700 1 lE4 RWC 452 A 0.1 0 1 I

~

RBC 441 '000 1 2E4 TBC 441 A 0.1 0.1 RBC 471 A '800.

1. 3E4 TBC 441 B 0.1 0.1 RBC 471 B 1400 1.0E4 TBC 441 C 0.1 0.1 RBC 471 C 3400 1.2E4 TBC 441 D 0.1 0.1 RBC 471 D 1.3E4 TBC 456 A 0' 0.2 l.

'800.

RBC RBC 501 501 A

B 2000 3400 1E4

1. 2E4 TBC TBC 456 456 B

C 0~1 0.1 Q.

RBC 501 C '400.

1 2E4 TBC 471 A 0~1 0.1 RBC 501 D 2900 1. 2E4 TBC 471 B 0~1 0.1 RBC 522 A 3500 1. 2E4 TBC 471 C 0.2 0.2 RBC 522 B '700 1 lE4 TBC 501 A 4.4 4' RBC 522 C 3500. 1 2E4 TBC 501 B 2 ' 2 2 RBC 522 D 2900 1. 2E4 TBC 501 C 2.6 2.6 RBC 548 A 2600. 1 ~ 1E4

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P10.1 IN-PLANT SURVEY AND SAMPLING DATA (T = 06:00) ( 09:00)

CLOSED CLOSED OPEN LOCATION WINDOW WINDOW LOCATION WINDOW WINDOW (mR/hr) (mR/hr) (mR/hr) (mR/hr)

RBC 422 A 2400. 1. 1E4 RBC 548 B 2900. 1. 1E4 RBC 422 B 2300. 1. 1E4 RBC 548 C 1600. 1.0E4 422 1200 9600. RBC 548 D 2300. 1.1E4 RBC RBC RBC 422 441 C

D A

1300.

1400

'PEN 9700.

9800 RBC RBC 548 572 E

A 1200.

3400.

9600.

1.2E4 RBC 441 B '500.

'900 RBC 572 B 3200. 1.2E4 RBC 441 C 2300. '.1E4 RBC 572 C 2900. 1.1E4 RBC 441 D 2400. 1.1E4 RBC 572 D 3200. 1.2E4 RBC 441 E 1900. 1 OE4 RBC 607 A 4800. 1.3E4 RBC 441 F 2100. 1 1E4 RBC 607 B 4800. 1.3E4 RBC 441 G 2200. 1.1E4 RBC 607 C 5000. 1.3E4 RBC 441 H 2300. 1.1E4 RWC 452 A 0' 0.1 RBC RBC 441 471 I

A 2600.

3400.

1.1E4 1 2E4 TBC TBC 441 441 A

B 0 1 0 1 0.1 0.1 RBC 471 B 1200. 9600 TBC 441 C 0~1 0.1 RBC 471 C 3000. '.1E4 TBC 441 D 0.1 0.1 RBC 471 D 3300 1.2E4 TBC 456 A 0.2 0 '

RBC 501 A 1700. 1 OE4 TBC 456 B 0 1 0.1 RBC 501 B 3000. "

1 1E4 TBC 456 C 0.1 0~1 RBC 501 C 3000 1.1E4 TBC 471 A 0.1 0.1 RBC 501 D '600.

1 1E4 TBC 471 B 0.1 0.1 RBC 522 A 3000 1.1E4 TBC 471 C 0.1 0.1 RBC 522 B '400.

1 1E4 TBC 501 A 4 ' 4.0 RBG 522 C 3000 ~ 1.1E4 TBC 501 B 2 ' 2.0 RBC 522 D 2600. 1.1E4 TBC 501 C 2 3 2~3 RBC 548 A 2300 1.1E4

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE Plp.m IN-PLANT SURVEY AND SAMPLING DATA (T ~ 06:30) ( 09,30)

CLOSED OPEN CLOSED O PEN LOCATION WINDOW WINDOW LOCATION WINDOW WINDOW (mR/hr) (mR/hr) (mR/hr) (mR/hr)

RBC 422 A 1900. 9600. 548 B 2300. 1.0E4 RBC 422 B 1900. 9600. RBC 548 C 1300. 9109 RBC 422 C 950. 8700. RBC 548 D 1800. 9600.

RBC 422 D 1000. 8800. RBC 548 E 940. 8700.

RBC 441 A 1100 8800. RBC 572 A 2800. 1'1E4 RBC 441 B '200.

8900. RBC 572 B 2500. 1.0E4 RBC RBC RBC RBC RBC 441 441 441 441 441 C

D E

F G

1900.

1900.

1500.

1700.

1700.

9600.

9600.

9300.

9400.

9500

'BC RBC RBC RBC RBC RBC 572 572 607 607 607 C

D A

B C

2400.

2500.

3900.

3900.

4000.

1.0E4 1.0E4 1 2E4

1. 2E4

1. 2E4 RBC 441 H 1900. RWC 452 A 0~1 F 1 I

'600.

RBC 441 2100 9800. TBC 441 A 0.1 0~1 RBC 471 A '700 1 OE4 TBC 441 B < 0.1 0.1 RBC 471 B '70.

8700. TBC 441 C < 0.1 0~1 RBC 471 C 2400. 1.0E4 TBC 441 D 0 RBC 471 D 2700. 1 OE4 TBC 456 A 0.2 RBC 501 A 1400. 9100. TBC 456 B 0.1 RBC 501 B 2400. 1.0E4 TBC 456 C 0.1 RBC 501 C 2400. 1.0E4 TBC 471 A 0.1 RBC 501 D 2100. 9800. TBC 471 B 0 1 0.1 RBC 522 A 2400. 1.0E4 TBC 471 C 0~1 0~1 RBC 522 B 1900. 9600 TBC 501 A 3 2 3 '

RBC 522 C 2400. 1 OE4 TBC 501 B 1.7 1.7 RBC 522 D 2100. 9800. TBC 501 C 1.9 1.9 RBC 548 A 1800. 9600

WNP-2 Nuclear Generating Station Scenario '3e Annual Exercise Unit 2 REV 0 TABLE P10.n IN-PLANT SURVEY AND SAMPLING DATA (T = 07:00) ( 10:00)

CLOSED OPEN CLOSED OPEN LOCATION WINDOW WINDOW LOCATION WINDOW WINDOW (mR/hr) (mR/hr) (mR/hr) (mR/hr)

RBC 422 A 1600. 8800. RBC 548 B 1900. 9100.

RBC 422 B 1600. 8700. RBC 548 C 1100. 8300.

RBC 422 C 800. 8000. RBC 548 D 1500. 8700.

RBC 422 D 860. 8000. RBC 548 E 790. 7900.

RBC 441 A 940 8100. RBC 572 A 2500. 9600 RBC 441 B 1000 8200. RBC 572 B 2100. '300.

RBC 441 C 1600 8700. RBC 572 C 2000. 9100.

RBC 441 D 1600. 8800. RBC 572 D 2100. 9300 '

RBC 441 E 1300. 8400. RBC 607 A 3300. OE4 RBC 441 F 1400 8600. RBC 607 B 3300 1.0E4 RBC 441 G '500.

8600. RBC 607 C 3400. 1. 1E4 RBC 441 H 1600. 8700. RWC 452 A 0.1 0~1 RBC 441 I 1800. 8900 TBC 441 A 0.1 0.1 RBC 471 A 2300. '400.

TBC 441 B 0 1 0.1 RBC 471 B 810 8000. TBC 441 C F 1 0.1 RBC 471 C '000.

9200. TBC 441 D 0.1 0~1 RBC 471 D 2200 9400. TBC 456 A 0 ' 0' RBC 501 A 1200. 8300. TBC 456 B 0.1 0.1 RBC 501 B 2000. 9200 TBC 456 C 0 1 < 0.1 RBC 501 C 2000. '200.

TBC 471 A 0~1 0.1 RBC 501 D 1700 8900 TBC 471 B 0~1 0~1 RBC 522 A 2100. '200.

TBC 471 C 0.1 0.1 RBC 522 B 1600. 8800. TBC 501 A 2 ' 2.6 RBC 522 C 2100. 9200. TBC 501 B 1 5 1.5 RBC 522 D 1700. 8900 TBC 501 C 1.7 1.7 RBC 548 A 1500. '700.

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P10.o IN-PLANT SURVEY AND SAMPLING DATA (T = 07-30) ( 10:30)

CLOSED OPEN CLOSED OPEN LOCATION WINDOW WINDOW LOCATION WINDOW WINDOW (mR/hr) (mR/hr) (mR/hr) (mR/hr)

RBC 422 A 1400 8000. RBC 548 B 1700 ~ 8300.

RBC 422 B 1400 8000. RBC 548 C 970 7600.

RBC 422 C 700. 7300. RBC 548 D 1300 8000.

RBC 422 D 760. 7400. RBC 548 E '90.

7300.

RBC 441 A 820. 7500 RBC 572 A 2200 8800.

RBC 441 B 880 '500.

RBC 572 B 1900 8500.

RBC 441 C 1400 8000. RBC 572 C 1700 8400 RBC 441 D 1400. 8000. RBC 572 D 1900 '500 RBC 441 E 1100 7800 RBC 607 A '900

'500.

RBC 441 F '200 '900.

RBC 607 B 2900 9500.

RBC 441 G 1300 7900 RBC 607 C 3000 ' 9600 '

RBC 441 H 1400. RWC 452 A 1 1 I ~ ~

'000.

RBC 441 1500. 8200. TBC 441 A 0.1 0.1 RBC 471 A 2000 8600. TBC 441 B 0~1 0 1 471 B 'BC 710 7300. TBC 441 C 0' 0~1 RBC 471 C 1800. 8400. TBC 441 D 0.1 0~1 RBC 471 D 2000. 8600 TBC 456 A 0.2 0.2 RBC RBC 501 501 A

B 1000

'800.

7700 8400.

TBC TBC 456 456 B

C 0.1 0.1 0.

RBC 501 C '1800. 8400. TBC 471 A 0.1 0~1 RBC 501 D 1500. 8200. TBC 471 B 0.1 < 0.1 RBC 522 A 1800. 8400 TBC 471 C 0.1 0~1 RBC 522 B 1400. '000.

TBC 501 A 2~3 2 3 RBC 522 C 1800. 8400 TBC 501 B 1~3 1 3 RBC 522 D 1500. '200.

TBC 501 C 1.5 1.5 RBC 548 A 1300. 8000.

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P10.p IN-PLANT SURVEY AND SAMPLING DATA (T = 08:00) ( 11:00)

CLOSED OPEN CLOSED OPEN LOCATION WINDOW WINDOW LOCATION WINDOW WINDOW (mR/hr) (mR/hr) (mR/hr) (mR/hr)

RBC 422 A 1300 ~ 7400. RBC 548 B 1500. 7700.

RBC 422 B 1200 7400 RBC 548 C 870. 7000.

RBC 422 C '30.

6800. RBC 548 D 1200. 7400.

RBC 422 D 680. 6900. RBC 548 E 620. 6800.

RBC 441 A 730. 6900. RBC 572 A 2000. 8200.

RBC 441 B 790. 7000. RBC 572 B 1700. 7900 RBC 441 C 1200. 7400. RBC 572 C 1600. '700.

RBC 441 D 1300. 7400. RBC 572 D 1700. 7900.

RBC 441 E 1000. 7200. RBC 607 A 2600. 8700.

RBC 441 F 1100. 7300. RBC 607 B 2600. 8700.

RBC 441 G 1100. 7300. RBC 607 C 2700. 8900 '

RBC 441 H 1200. 7400. RWC 452 A 0 ' 1 RBC 441 I 1400. 7600 TBC 441 441 A 0.1 0 1 0.1 0'

RBC 471 A 1800 '000.

TBC B RBC 471 B '40.

6800 TBC 441 C 0 1 0.1 RBC 471 C 1600. '700 TBC 441 D 0.1 0' RBC 471 D 1800. '900.

TBC 456 A 0' 0.2 RBC 501 A 910. 7100. TBC 456 B 0~1 0' RBC 501 B 1600. 7700 TBC 456 C 0 1 0' RBC 501 C 1600 '700.

TBC 471 A 0.1 F 1 RBC 501 D '400.

7500. TBC 471 B 0.1 0.1 RBC 522 A 1600. 7800. TBC 471 C 0.1 0' RBC 522 B 1300. 7400. TBC 501 A 2 ' 2.1 RBC 522 C 1600. 7800. TBC 501 B 1 2 1 2 RBC 522 D 1400. 7500. TBC 501 C 1.4 1.4 RBC 548 A 1200. 7400.

1/2 Mile Site Plan Survey Location

~

QS

~ Water Steel/Equip Buildinga Varehouaea

~ Grid. Lines Bndry Lines

lf 1

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P11.a ONSITE SURVEY AND SAMPLING DATA (T = 00:00) ( 03:00)

CLOSED OPEN AIR SAMPLE LOCATION WlNDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/cf)

A 0.1 0.1 0-1 B 0.1 0' 0.1 C 0.1 0.1 0 1 D 0.1 0.1 0.1 E 0.1 0.1 0-1 F 0 1 0.1 0~1 G 0~1 0.1 0~1 H 0~1 0' 0~1

HNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P11.b ONSITE SURVEY AND SAMPLING DATA (T = 02:00) ( 05:00)

CLOSED OPEN AIR SAMPLE LOCATION WINDOW HINDOOS COUNT RATE (mR/hr) (mR/hr) (cpm/cf)

A 0~1 0~1 0 1 B 0.1 0 1 0.1 C 0 1 0 1 0.1 D 0~1 0.1 0~1 E 0'1 0 1 0~1 F 0' 0 1 0~1 G 0 1 0.1 0.1 H 0 1 0.1 0'

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P11.d ONSITE SURVEY AND SAMPLING DATA (T ~ 03:30) ( 06:30)

CLOSED OPEN AIR SAMPLE LOCATION WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/cf )

A 0.1 0~1 0~1 B 0~1 0-1 0' C 0 ' 0 1 0' D 0.1 0~1 0' E 0.1 0~1 0' F 0.1 0~1 0~1 G 0.1 0~1 0' H 0.1 0~1 0~1

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE 'P11.e ONSITE SURVEY AND SAMPLING DATA (T = 04:00) ( 07:00)

CLOSED OPEN AIR SAMPLE LOCATION WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/cf)

A 0' 0~1 0.1 B 0 1 0~1 0.1 C 0 1 0~1 0.1 D 0~1 0~1 0~1 E 0~1 0~1 0.1 F 0.1 0~1 0.1 G 0 1 0~1 0.1 H 0.1 0~1 0.1

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P11.f ONSITE SURVEY AND SAMPLING DATA (T = 04:15) ( 07:15)

CLOSED OPEN AIR SAMPLE LOCATION WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/cf)

A 0.6 0.6 140.

B 0.9 0.9 140 C 3.1 3.1 '5.

D 3.0 3.0 76.

E 0.7 0.7 40.

F 390. 390 75.

G 0.7 0.7 10 H 1.4 1.4 5.3

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P11.g ONSITE SURVEY AND SAMPLING DATA (T = 04:30) ( 07:30)

CLOSED OPEN AIR SAMPLE LOCATION WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/cf)

A 0.8 0.8 50.

B 1.1 .1 1 50.

C 3.7 3.7 19.

D 3.5 3.5 27.

E 0.9 0.9 14.

F 460. 460 26.

G 0 ' 0.8 3.6 H 1.7 1.7 1 9

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P11.h ONSITE SURVEY AND SAMPLING DATA (T = 04:45) ( 07:45)

CLOSED OPEN AIR SAMPLE LOCATION WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/cf)

A 0.8 0 8 120.

B 1.0 1.0 120.

C 3.0 3.0 44 D 2' 2.9 '2.

E 0.7 0 7 33 F 360. 360. '1.

G 0.7 0.7 8.3 H 1.4 1.4 4.3

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE Pll.i ONSITE SURVEY AND SAMPLING DATA (T = 05:00) ( 08:00)

CLOSED OPEN AIR SAMPLE LOCATION WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/cf)

A 0.7 0.7 86.

B 0.8 0.8 86.

C 2 5 2.5 33.

D 2' 2.5 46.

E 0.6 0.6 24.

F 300. 300. 45.

G 0.6 0.6 6 2 H 1~2 1~2 3-2

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0

, ~ TABLE P11.j ONSITE SURVEY AND SAMPLING DATA (T = 05:30) ( 08:30)

CLOSED OPEN AIR SAMPLE LOCATION WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/cZ)

A 0.6 0.6 48.

B 0.7 0.7 48.

C 1.9 1 9 19.

D 1.9 1 9 26.

E 0.5 0.5 14.

F 210. 210. 26.

G 0.4 0.4 3.5 H 0.9 0.9 1.8

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P11.k ONSITE SURVEY AND SAMPLING DATA (T = 06:00) ( 09:00)

CLOSED OPEN AIR SAMPLE LOCATION WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/cf )

A 0.6 0 6 28 ~

B 0.6 0' 28 C 1.5 1.5 11 D 1.5 1 5 15.

E 0.4 0.4 7.9 F 160. 160. 15.

G 0.4 0 ' 2.0 H ~

0.7 0 7 1.0

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P11.1 ONSITE SURVEY AND SAMPLING DATA (T = 06:30) ( 09:30)

CLOSED OPEN AIR SAMPLE LOCATION WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/cf)

A 0' 0.4 38.

B 0.4 0 ' 38 C 1-2 1.2 '5 D .1 ~ 2 1 2 '0.

E 0.3 0.3 11.

F 130- 130. 20 ~

G 0' 0' 2~7 H 0 6 0 6 1.4

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE Pll.m ONSITE SURVEY AND SAMPLING DATA (T = 07:00) ( 10:00)

CLOSED OPEN AIR SAMPLE LOCATION WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/cf)

A 0 2 0' 24.

B 0.3 0 4 24 C 1.0 1.0 '.1 D 1 0 1.0 13 ~

E 0 ' 0 ' 6.7 F 110. 110. 12 G 0' 0.2 1.7 H 0 5 0.5 0.9

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P11.n ONSXTE SURVEY AND SAMPLING DATA (T = 07:30) ( 10:30)

CLOSED OPEN AIR SAMPLE LOCATION WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/cf)

A 0.2 0 2 63.

B 0.3 0.3 63.

C 0.9 0.9 24.

D 0 9 0 ' 34.

E 0.3 0.3 18 ~

F 94 94. 33.

G '.2 0<<2 4.6 H 0.4 0.4 2.4

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P11.o ONSITE SURVEY AND SAMPLING DATA (T = 08:00) ( 11:00)

CLOSED OPEN AIR SAMPLE LOCATION WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/cf)

A 0.2 0.2 44 B 0.3 0 3

'4

~

C 0 8 0.9 17.

D 0.8 0.8 24 E 0 2 0.2 '2 F 84. 84. 23 G 0.2 0 2 3 '

H 0.4 0.4 1.6

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P12.a AIRBORNE ACTIVITY (PLANT VICINITY) (T = 00:00) ( 03:00)

The Environment cannot he sampled through the PASS system Nuclide Concentration Kr-85m 1 97E-15 uCi/cc Kr-87 3.40E-15 uCi/cc Kr-88 5.32E-15 uCi/cc Xe-133 1 48E-14 uCi/cc Xe-133m 5.00E-16 uCi/cc Xe-135 4.72E-15 uCi/cc Xe-138 6 40E-15 uCi/cc TOTAL GAS SAMPLE 3.73E-14 uCi/cc I-131 5.86E-16 uCi/cc I-132 7.69E-16 uCi/cc I-133 1.35E-15 uCi/cc I-134 1.01E-15 uCi/cc I-135 1.27E-15 uCi/cc TOTAL CHARCOAL SAMPLE 4.99E-15 uCi/cc Cs-134 1.30E-16 uCi/cc Cs<<136 5.18E-17 uCi/cc Cs-137 8.39E-17 uCi/cc Np-239 1.76E-17 uCi/cc TOTAL FILTER SAMPLE 2.88E-16 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P12.a AIRBORNE ACTIVITY (PLANT VICINITY) (T = 00:00) ( 03:00)

(continued)

The Environment cannot be sampled through the PASS system Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1 ft.:

ft.: 0.1 0.1 mR/hr 1 mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1

1 ft.:

ft.: 0.1 0.1 mR/hr per mR/hr per cf cf For 2" lead shield divide dose rate by:2.5E+1 For 4" lead shield divide dose rate by:4.4E+2 Hydrogen Concentration: .04 Oxygen Concentration: 21.04 Airborne Beta Dose Rate: < 0.1 mRad/hr Airborne Thyroid Dose Rate: < 0.1 mRem/hr Net Air Sample Contact Rate: < 0.1 cpm/cf sample Floor Contamination: < 0.1 cpm/100cm2 Wall and Equipment Contamination: < 0.1 cpm/100cm2 Personnel Contamination Rate: < O.l cpm/100cm2 per minute Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Stay Time: 2 MPC hr (no mask):1.3E+7 Hours Stay Time: 2 MPC hr (in mask):6.6E+8 Hours Stay Time: 2 MPC hr (in Air Sup. mask):9.9E+9 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 1 TABLE P12.c AIRBORNE ACTIVITY (PLANT VICINITY) (T ~ 04: 00) ( 07: 00)

The Environment cannot be sampled through the PASS system Nuclide Concentration Kr-85m 9. 62E-13 uCi/cc Kr-87 1.45E-12 uCi/cc Kr-88 2.56E-12 uCi/cc Xe-133 7.63E-12 uCi/cc Xe-133m 2 65E-13 uCi/cc Xe-135 1 98E-12 uCi/cc Xe-138 1.05E-12 uCi/cc TOTAL GAS SAMPLE 1.60E-11 uCi/cc I-131 3. 19E-14 uCi/cc I-132 3 '9E-14 uCi/cc I-133'-134 6 '3E-14 uci/CC 4 '5E-14 uCi/cc I-135 5 '2E-14 uCi/cc TOTAL CHARCOAL SAMPLE 2 ~ 23E-13 uCi/cc Rb-88 4.10E-14 uCi/cc Cs-134 8.57E-15 uCi/cc Cs-136 3 42E-15 uCi/cc Cs-137 5.38E-15 uCi/cc TOTAL FILTER SAMPLE 5.84E-14 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P12.c AIRBORNE ACTIVITY (PLANT VICINITY) (T = 04 00) ( 07:00)

. (continued)

The Environment cannot, be sampled through the PASS system Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1

1 ft.:

ft.: 0.1 0.1 mR/hr mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1 ft.:

ft.: 0.1 0.1 mR/hr per cf cf 1 mR/hr per For 2" lead shield divide dose rate by:2.3E+1 For 4" lead shield divide dose rate by:3.7E+2 Hydrogen Concentration: .04 Oxygen Concentration: 21.04 Airborne Beta Dose Rate: < 0.1 mRad/hr Airborne Thyroid Dose Rate: < 0.1 mRem/hr Net Air Sample Contact Rate: < 0.1 cpm/cf sample Floor Contamination: < 0.1 cpm/100cm2 Wall and Equipment Contamination: < 0.1 cpm/100cm2 Personnel Contamination Rate: < 0.1 cpm/100cm2 per minut Personnel Contamination Rate: < 0.1 cpm/100cm2 per minut Stay Time: 2 MPC hr (no mask):1.5E+5 Hours Stay Time: 2 MPC hr (in mask):7.6E+6 Hours Stay Time: 2 MPC hr (in Air Sup. mask):3.0E+8 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P12.d AIRBORNE ACTIVITY (PLANT VICINITY) (T = 04:30) ( 07:30)

The Environment cannot he sampled through the PASS system Nuclide Concentration Kr-85m 8.87E-10 uCi/cc Kr-87 1 33E-09 uCi/cc Kr-88 2.37E-09 uCi/cc Xe-133 7.11E-09 uCi/cc Xe-133m 2.45E-10 uCi/cc Xe-135 2.30E-09 uCi/cc Xe-138 9.28E-10 uCi/cc TOTAL GAS SAMPLE 1.53E-08 uCi/cc Br-83 8.71E-11 uCi/cc I-131 1. 02E-09 uCi/CC I-132 1 20E-09 uCi/cc I-133 2.00E-09 uCi/cc I-134 1 33E-09 uCi/cc I-135 1.68E-09 uCi/cc TOTAL CHARCOAL SAMPLE 7.40E-09 uCi/cc Rb-88 6 19E-10 uCi/cc Cs-134 3.58E-10 uCi/cc Cs-136 1 '5E-10 uCi/cc Cs-137 2.43E-10 uCi/cc TOTAL FILTER SAMPLE 1.38E-09 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P12.d AIRBORNE ACTIVITY (PLANT VICINITY) (T = 04 30) ( 07:30)

(continued)

The Environment cannot be sampled through the PASS system Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1

1 ft.:

ft.: <

0.1 0.1 mR/hr mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1

1 ft.:

ft.: <

0.1 0.1 mR/hr per mR/hr per cf cf For 2" lead shield divide dose rate by:2.9E+1 For 4" lead shield divide dose rate by:5.5E+2 Hydrogen Concentration: .04 Oxygen Concentration: 21.04 Airborne Beta Dose Rate: < 0.1 mRad/hr Airborne Thyroid Dose Rate: 3.1 mRem/hr Net Air Sample Contact Rate: 50. cpm/cf sample Floor Contamination: 0.7 cpm/100cm2 Wall and Ecpxipment Contamination: < 0.1 cpm/100cm2 Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute~

Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Stay Time: 2 MPC hr (no mask):9.1E+0 Hours Stay Time: 2 MPC hr (in mask):4.5E+2 Hours Stay Time: 2 MPC hr (in Air Sup. mask):1.8E+4 Hours

RG?-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P12.e AIRBORNE ACTIVITY (PLANT VICINITY) (T = 05:00) ( 08:00)

The Environment cannot he sampled through the PASS system 1

Nuclide Concentration Kr-85m 3.64E-09 uCi/cc Kr-87 5.16E-09 uCi/cc Kr-88 9.60E-09 uCi/cc Xe-133 2.98E-08 uCi/cc Xe-133m 1.03E-09 uCi/cc Xe-135 9.59E-09 uCi/cc Xe-138 2 '2E-09 uCi/cc TOTAL GAS SAMPLE 6.17E-08 uCi/cc Br-83 1 44E-10 uci/cc I-131 1.77E-09 uCi/cc I-132 1.98E-09 uCi/cc I-133 3.44E-09 uCi/cc I-134 2.05E-09 uCi/cc I-135 2.86E-09 uCi/cc TOTAL CHARCOAL SAMPLE 1.23E-08 uCi/cc Rb-88 1.12E-09 uCi/cc Cs-134 8.21E-10 uCi/cc Cs-136 2.86E-10 uCi/cc Cs-137 5.57E-10 uCi/cc TOTAL FILTER SAMPLE 2.87E-09 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P12.e AIRBORNE ACTIVITY (PLANT VICINITY) (T = 05:00) ( 08:00)

,(continued)

The Environment cannot be sampled through the PASS system Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1 ft.:

ft.: < 0.1 0.1 mR/hr 1 < mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1

1 ft.:

ft.: <

0.1 0.1 mR/hr per mR/hr per cf cf For 2" lead shield divide dose rate by:2.7E+1 For 4" lead shield divide dose rate by:4.8E+2 Hydrogen Concentration: .04 Oxygen Concentration: 21.04 Airborne Beta Dose Rate: < 0.1 mRad/hr Airborne Thyroid Dose Rate: 5.3 mRem/hr Net Air Sample Contact Rate: 86. cpm/cf sample Floor Contamination: 1.5 cpm/100cm2 Wall and Equipment Contamination: 0.1 cpm/100cm2 Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Stay Time: 2 MPC hr (no mask):5.0E+0 Hours Stay Time: 2 MPC hr (in mask):2.5E+2 Hours Stay Time: 2 MPC hr (in Air Sup. mask):1.0E+4 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P12.f AIRBORNE ACTIVITY (PLANT VICINITY) (T = 05 30) ( 08:30)

The Environment cannot be sampled through the PASS system Nuclide Concentration Kr-85m 3.45E-09 uCi/cc Kr-87 4.61E-09 uCi/cc Kr-88 8.98E-09 uCi/cc Xe-133 2 89E-08 uCi/cc Xe-133m 9.95E-10 uCi/cc Xe-135 9.22E-09 uCi/cc Xe-138 1.57E-09 uCi/cc TOTAL GAS SAMPLE 5 '0K-08 uCi/cc Br-83 7.63E-11 uCi/cc I-131 9.77E-10 uCi/cc I-132 1.05E-09 uCi/cc I-133 1.89E-09 uCi/cc I-134 1.00E<<09 uCi/cc I-135 3..56E-09 uCi/cc TOTAL CHARCOAL SAMPLE 6.60E-09 uCi/cc Rb-88 6.89E-10 uCi/cc Cs-134 6 '3E-10 uCi/cc Cs-136 2.10E-10 uCi/cc Cs-137 4.10E-10 uCi/cc TOTAL FILTER SAMPLE 1 '7K-09 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P12 ~ f AIRBORNE ACTIVITY (PLANT VICINITY) (T = 05:30) ( 08:30)

(continued)

The Environment cannot be sampled through the PASS system Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1 ft.:

ft.:

< 0.1 0.1 mR/hr 1 mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1 ft.:

ft.:

< 0.1 0.1 mR/hr per cf cf 1 < mR/hr per .

For 2" lead shield divide dose rate by:2.6E+1 For 4" lead shield divide dose rate by:4.4E+2 Hydrogen Concentration: .0%

Oxygen Concentration: 21.04 Airborne Beta Dose Rate: < 0.1 mRad/hr Airborne Thyroid Dose Rate: 2.9 mRem/hr Net Air Sample Contact Rate: 48. cpm/cf sample Floor Contamination: 1. 9 cpm/100cm2 Hall and Equipment Contamination: 0.2 cpm/100cm2 Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Stay Time: 2 MPC hr (no mask):8.7E+0 Hours Stay Time: 2 MPC hr (in mask):4.4E+2 Hours Stay Time: 2 MPC hr (in Air Sup. mask):1.7E+4 Hours

NNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P12.g AIRBORNE ACTIVITY (PLANT VICINITY) (T = 06:00) ( 09:00)

The Environment cannot be sampled through the PASS system Nuclide Concentration Kr-85m 3 26E-09 uCi/cc Kr-87 4.11E-09 uCi/cc Kr-88 8.38E-09 uCi/cc Xe-133 2.79E-08 uCi/cc Xe-133m 9.61E-10 uCi/cc Xe-135 8 84E-09 uCi/cc Xe-138 9 80E-10 uCi/cc TOTAL GAS SAMPLE 5.48E-08 uCi/cc Br-83 4.06E-11 uCi/cc I-131 5.42E-10 uCi/cc I-132 5.56E-10 uCi/cc I-133 1.05E-09 uCi/cc I-134 4.95E>>10 uCi/cc I-135 8.52E-10 uCi/cc TOTAL CHARCOAL SAMPLE 3.55E-09 uCi/cc Rb-88 4.58E-10 uCi/cc Cs-134 4.44E-10 uCi/cc Cs-136 1.54E-10 uCi/cc Cs-137 3 01E-10 uCi/cc TOTAL FILTER SAMPLE 1;40E-09 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P12.g AIRBORNE ACTIVITY (PLANT VICINITY) (T = 06:00) ( 09:00)

(continued)

The Environment cannot be sampled through the PASS system Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1 ft.:

ft.: < 0.1 0.1 mR/hr 1 < mR/hr PASS Sample (charcoal) Dose Rate at 1 ft..: < 0.1 mR/hr per cf PASS Sample (filter) Dose Rate at 1 ft.: < 0.1 mR/hr per cf For 2" lead shield divide dose rate by:2.5E+1 For 4" lead shield divide dose rate by:4.2E+2 Hydrogen Concentration: .04 Oxygen Concentration: 21.04.

Airborne Beta Dose Rate: < 0.1 mRad/hr Airborne Thyroid Dose Rate: 1.6 mRem/hr Net Air Sample Contact Rate: 28. cpm/cf sample Floor Contamination: 2.1 cpm/100cm2 Wall and Ecpxipment Contamination: 0.2 cpm/100cm2 Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Stay Time: 2 MPC hr (no mask):1.5E+1 Hours Stay Time: 2 MPC hr (in mask):7.3E+2 Hours Stay Time: 2 MPC hr (in Air Sup. mask):2.9E+4 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P12.h AIRBORNE ACTIVITY (PLANT VICINITY) (T = 06:30) ( 09:30)

The Environment cannot he sampled through the PASS system Nuclide Concentration Kr-85m 6.00E-09 uCi/cc Kr-87 7.13E-09 uCi/cc Kr-88 1.52E-08 uCi/cc Xe-133. 5.26E-08 uCi/cc Xe-133m 1.81E-09 uCi/cc Xe-135 1.65E-08 uCi/cc Xe-138 1 19E-09 uCi/cc TOTAL GAS SAMPLE 1.01E-07 uCi/cc Br-83 4.94E-11 uCi/cc I-131 6.88E-10 uCi/cc I-132 6.75E-10 uCi/cc I-133 1.32E-09 uCi/cc I-134 5.58E-10 uCi/cc I-135 1.07E-09 uCi/cc TOTAL CHARCOAL SAMPLE 4. 38E-09 uCi/cc Rb-88 7.53E-10 uCi/cc Cs-134 7 '2E-10 uCi/cc Cs-136 2.58E-10 uCi/cc Cs-137 5.04E-10 uCi/cc TOTAL FILTER SAMPLE 2.32E-09 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P12.h AIRBORNE ACTIVITY (PLANT VICINITY) (T = 06:30) ( 09:30)

(continued)

The Environment cannot be sampled through the PASS system Normal Sample (15. ml) Dose Rate at 1 0.1 mR/hr PASS Sample (14. ml) Dose Rate at 1 0.1 mR/hr PASS Sample (charcoal) Dose Rate at 1 0.1 mR/hr per cf PASS Sample (filter) Dose Rate at 1 ft.: 0.1 mR/hr per cf For 2" lead shield divide dose rate by:2.5E+1 For 4" lead shield divide dose rate by:4.0E+2 Hydrogen Concentration: .04 Oxygen Concentration: 21.04 Airborne Beta Dose Rate: < 0.1 mRad/hr Airborne Thyroid Dose Rate: 2.1 mRem/hr Net Air Sample Contact Rate: 38. cpm/cf sample Floor Contamination: 2.2 cpm/100cm2 Wall and Equipment Contamination: 0.2 cpm/100cm2 Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Stay Time: 2 MPC hr (no mask):1.1E+1 Hours Stay Time: 2 MPC hr (in mask):5.4E+2 Hours Stay Time: 2 MPC hr (in Air Sup. mask):2.1E+4 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Ecercise Unit 2 REV 0 P TABLE P12 i AIRBORNE ACTIVITY (PLANT VICINITY) (T = 07:00) ( 10:00)

The Environment cannot be sampled through the PASS system Nuclide Concentration Kr-85m 5.67E-09 uCi/cc Kr-87 6.36E-09 uCi/cc Kr-88 1.42E-08 uCi/cc Xe-133 5.08E<<08 uCi/cc Xe-133m 1.74E-09 uCi/cc Xe-135 1.58E-08 uCi/cc TOTAL GAS SAMPLE 9.58E-08 uCi/cc Br-83 2.69E-11 uCi/cc I-131 3 '2E-10 uCi/cc I-132 3.68E-10 uCi/cc I-133 7 49E-10 uCi/cc I-134 2 '2E-10 uCi/cc I-135 5.97E-10 uCi/cc TOTAL CHARCOAL SAMPLE 2 '2E-09 uCi/cc Rb-88 5.91E-10 uCi/cc Cs-134 5.49E-10 uCi/cc Cs-136 1.91E-10 uCi/cc Cs-137 3.73E-10 uCi/cc TOTAL FILTER SAMPLE 1.75E-09 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P12 i AIRBORNE ACTIVITY (PLANT VECINETY) (T = 07:00) ( 10:00)

(continued)

The Environment cannot be sampled through the PASS system Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1 ft.:

ft.:

< 0.1 0.1 mR/hr 1 < mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1

1 ft.:

ft.: <

0.1 0.1 mR/hr per mR/hr per cf cf For 2" lead shield divide dose rate by:2.4E+1 For 4" lead shield divide dose rate by:3.9E+2 Hydrogen Concentration: .04 Oxygen Concentration: 21.04 Airborne Beta Dose Rate: < 0.1 mRad/hr Airborne Thyroid Dose Rate: 1.2 mRem/hr Net Air Sample Contact Rate: 24. cpm/cf sample Floor Contamination: 2.3 cpm/100cm2 Mall and Ecpxipment Contamination: 0.2 cpm/100cm2 Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute~

Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Stay Time: 2 MPC hr (no mask):1.7E+1 Hours Stay Time: 2 MPC hr (in mask):8.3E+2 Hours Stay Time: 2 MPC hr (in Air Sup. mask):3.3E+4 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 P TABLE P12. j AIRBORNE ACTIVITY (PLANT VICINITY) (T = 07 30) ( 10:30)

The Environment cannot be sampled through the PASS system Nuclide,'oncentration Kr-85m 1 '3E-08 uCi/cc Kr-87 1.93E-08 uCi/cc Kr-88 4.51E-08 uCi/cc Xe-133 1.68E-07 uCi/cc Xe-133m 5.74E-09 uCi/cc Xe-135 5.15E-08 uCi/cc TOTAL GAS SAMPLE 3 '1E-07 uCi/cc Br-83 6.18E-11 uCi/cc I-131 9.38E-10 uCi/cc I-132 8.42E-10 uCi/cc I-133 1.79E-09 uCi/cc I-134 6.01E-10 uCi/cc I-135 1 41E-09 uCi/cc TOTAL CHARCOAL SAMPLE 5 '6E-09 uCi/cc Rb-88 2.01E-09 uCi/cc Cs-134 1.67E-09 uCi/cc

. Cs-136 5.81E-10 uCi/cc Cs-137 1.13E-09 uCi/cc TOTAL FILTER SAMPLE 5.54E-09 uCi/cc CONTINUED ON NEXT PAGE

r WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P12.j AIRBORNE ACTIVITY (PLANT VICINITY) (T = 07:30) ( 10:30)

(continued)

The Environment cannot be sampled through the PASS system Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1

1 ft.:

ft.: 0.1 0.1 mR/hr mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1

1 ft.:

ft.: 0.1 0.1 mR/hr per mR/hr per cf cf For 2" lead shield divide dose rate by:2.4E+1 For 4" lead shield divide dose rate by:3.9E+2 Hydrogen Concentration: .Ot Oxygen Concentration: 21.04 Airborne Beta Dose Rate: < 0.1 mRad/hr Airborne Thyroid Dose Rate: 2.8 mRem/hr Net Air Sample Contact Rate: 63. cpm/cf sample Floor Contamination: 2.7 cpm/100cm2 Wall and Equipment Contamination: 0.3 cpm/100cm2 Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Personnel Contamination Rate: < 0.1 cpm/100cm2 per minute Stay Time: 2 MPC hr (no mask):6.2E+0 Hours Stay Time: 2 MPC hr (in mask):3.1E+2 Hours Stay Time: 2 MPC hr (in Air Sup. mask):1.2E+4 Hours

WNP-2 Nuclear Generating Station Scenario 9 3e Annual Exercise Unit 2 REV 0 TABLE P12 k AIRBORNE ACTIVITY (PLANT VICINITY) (T = 08:00) ( 11:00)

The Environment cannot be sampled through the PASS system Nuclide Concentration Kr-85m 1.73E-OS uCi/cc Kr-87 1.72E-08 uCi/cc Kr-88 4.21E-08 uCi/cc Xe-133 1.62E-07 uCi/cc Xe-133m 5.54E-09 uCi/cc Xe-135 4.93E-08 uCi/cc TOTAL GAS SAMPLE 2.96E-07 uCi/cc Br-83 3 63E-11 uCi/cc I-131 5.76E-10 uCi/cc I-132 4.94E-10 uCi/cc I-133 1.09E-09 uCi/cc I-134 3.27E-10 uCi/cc I-135 8.51E-10 uCi/cc TOTAL CHARCOAL SAMPLE 3.39E-09 uCi/cc Rb-88 1.76E-09 uCi/cc Cs-134 1.2SE-09 uCi/cc Cs-136 4.36E-10 uCi/cc Cs-137 8.51E-10 uCi/cc TOTAL FILTER SAMPLE 4.39E-09 uCi/cc CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P12.k AIRBORNE ACTIVITY (PLANT VICINITY) (T = 08 00) ( 11:00)

(continued)

The Environment cannot be sampled through the PASS system Normal Sample (15. ml) Dose Rate PASS Sample (14. ml) Dose Rate at at 1

1 ft.:

ft.: <

0.1 0.1 mR/hr mR/hr PASS Sample (charcoal) Dose Rate PASS Sample (filter) Dose Rate at at 1

1 ft.:

ft.: <

0.1 0.1 mR/hr per mR/hr per cf cf For 2" lead shield divide dose rate by:2.4E+1 For 4" lead shield divide dose rate by:3.8E+2 Hydrogen Concentration: .04 Oxygen Concentration: 21.04 Airborne Beta Dose Rate: < 0.1 mRad/hr Airborne Thyroid Dose Rate: 1.7 mRem/hr Net Air Sample Contact Rate: 44. cpm/cf sample Floor Contamination: 2.8 cpm/100cm2

'no Mall and Equipment Contamination:

Personnel Contamination Rate: <

Personnel Contamination Rate: <

Stay Time: 2 MPC hr 0.3 cpm/100cm2 0.1 cpm/100cm2 per minute 0.1 cpm/100cm2 per minute mask):8.6E+0 Hours

~

~

Stay Time: 2 MPC hr (in mask):4.3E+2 Hours Stay Time: 2 MPC hr (in Air Sup..mask):1.7E+4 Hours

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P13.a CRITICAL PLANT PARAMETER

SUMMARY

'For Controller and Observer Use Only Reactor Level (inch) 36. 36. 36 ~ 36. 36. 36. -36 -52.

Reactor Press (psig) 1005. 1005. 1005. 1000. 1005. 1000. '00 900.

Reactor Power (4) 100.0 100.0 100 0 100.0 100 0 .0 ~ 0 .0 Core Flow (M lb/hr) 1.0E+7 1 OE+7 1.0E+7 1.0E+7 1 OE+7 O.OE+0 O.OE+0 0 OE+0 ~

Steam Flow (M lb/hr) 1 4E+7 1.4E+7 1 'E+7 1.4E+7 1.4E+7 0 OE+0 O.OE+0 O OE+0 B Fdwtr Flow (M lb/hr) 1.4E+7 1.4E+7 1.4E+7 1.4E+7 1.4E+7 O.OE+0 O.OE+0 O.OE+0 Condenser Vac (inHg) 29 '0 29. 29. 29 '0 29 '0 29 '0 29 '0 29.

Hotwell Level (inch) ~ 0 ~ 0 ~ 0 Drywell H2 Conc (4) .0 0 .0 .0 .0 ~ 0 ~ 0 ~ 0 Drywell 02 Conc (4) 3 ' 3 ' 3 ' 3.8 3.8 3.8 3.8 3~8 SGTS Flow (cfm) 1~ 4585. 4455. 4455. 4455. 4455. 4455. 4455.

Drywell Press (psig) 1.0 1 0 1 0 1.0 1.0 1.0 1-0 1.0 Drywell Temp (deg F) 103 ~ 103 103. 103 103 '03. 103. 103.

Supp Pool Temp (F) 88. 88. 88. '8.

88. 88 88 88.

Supp Pool Level (ft) 31 ' 31.0 31 0 31.0 31. 0 0

'1 31.0 31 0 Main Stm Rad (mR/hr) 1 OE+3 1.0E+3 1. OE+3 1.0E+3 1.0E+3 1 7E+1 1.7E+1 1.7E+1 Contnmnt Rad (R/hr) 1 OE+1 1.0E+1 1.0E+1 1 OE+1 1.0E+1 1 OE+1 1.0E+1 1.0E+1 Cond Stor Tnk (ft) 26.0 26 ' 26.0 26 ' 26.0 26 0 26.0 26 '

Wetwell Press (psig) 2.9 5.1 ~ 2 1' 1 7

~ 1 7

~ 1 7

~ -1.8 T-Time (hr:min) 00:00 01:00 02000 03:15 03: 29 03: 30 03 35 03:40 Clock Time (hr".min) 03:00 04:00 05000 06 15 06:29 06:30 06:35 06040 Drywell Delta-P 0 3 ' 2~2 1.5 1' 1.4 1.4 1.4 Drywell Delta-T 0 0. 0. 0. 0. 0 0 0.

Wetwell Delta>>T 0~ 0. 0. 0 0. 0~ 0 0.

NOTE:

Drywell Pressure is the pressure calculated by the simulator.

Drywell Delta P is the pressure differential due to hydrogen generation and any containment leakage.

Drywell Delta P must be provided to operators of any "live time" plant parameter display screens.

(Tables list the sum of Simulator Drywell Pressure and the Delta P, and the sum of the Reactor Pressure and the Delta P)

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P13 b CRITICAL PLANT PARAMETER

SUMMARY

For Controller and Observer Use Only Reactor Level (inch) -68. -85. -95 -100. -275 -300. -310 -'100.

Reactor Press (psig) 900 ' 900 '00.

900m 200. 120 ~ 100. 15.

Reactor Power (4)

'0

.0 .0 .0 .0 .0 ~ 0 Core Flow (M lb/hr) O.OE+0 O.OE+0 O.OE+0 O.OE+0 O OE+0 B O.OE+0 0. OE+0 O.OE+0 Steam Flow (M lb/hr) O.OE+0 O.OE+0 O OE+0 O.OE+0 O.OE+0 O.OE+0 O.OE+0 O.OE+0 B

Fdwtr Flow (M lb/hr) O.OE+0 O.OE+0 O.OE+0 O.OE+0 O.OE+0 O.OE+0 O.OE+0

29. 29. 29 O B OE+0 29 '

Condenser Vac (inHg) 29 29. 29 29 Hotwell Level (inch) ~ 0 ~ 0 ~ 0 .0 .0 .0 ~ 0 0 Drywell H2 Conc (%) ~ 0 .0 ~ 0 ~ 0 .0 ~ 0 .0 ~ 0 Drywell 02 Conc (4) .0 ~ 0 ~ 0 ~ 0 .0 .0 ~ 0 3.8 SGTS Flow (cfm) 4455 4455 4455. 4455 4455. 4455. 4455. 4455.

Drywell Press (psig) 1.0 3 ' 2 ' 2 ' 2 0 2~0 2 ' 1.0 Drywell Temp (deg F) 103. 103 103. 103 103. 103 ~ 103. 103.

Supp Pool Temp (F) 88 88. 88 88. 95. 95 95 95 Supp Pool Level (ft) '1.0 31 0 0

'1 31 0 32.0 '2.0 '2.0 1 'E+1 1.9

'2.0 Main Stm Rad (mR/hr) 1.7E+1 1.7E+1 1 7E+1 1.7E+1 1 'E+1 1.8E+1 Contnmnt Rad (R/hr) 1.0E+1 1.0E+1 1.0E+1 1 'E+1 1.0E+1 1.0E+1 1 OE+1 1 0 Cond Stor Tnk (ft) 26 0 26 ' 26 ~ 0 26 0 26.0 26.0 26 0 26.

Wetwell Press (psig) -1.8 22 ' 10 2 6 ' 8.4 6 ' 4 ' 3~1 T-Time (hr:min) 03:45 03:50 03:55 04 00 04 05 04:10 04:25 04:30 Clock Time (hr:min) 06:45 06050 06:55 07:00 07:05 07:10 07:25 07:30 Drywell Delta-P 1.4 4~5 4~6 4 5 4 ' 4' 4~3 4.2 Drywell Delta-T 0. 0. 0. 0. 0~ 0. 0. 0~

Wetwell Delta-T 0~ 0~ 0. 0. 0~ 0. 0 0 NOTE

.Drywell Pressure is the pressure calculated by the simulator.

Drywell Delta P is the pressure differential due to hydrogen generation and any containment leakage.

Drywell Delta P must be provided to.operators of any "live time" plant parameter display screens.

(Tables list, the sum of Simulator Drywell Pressure and the Delta P, and the sum of the Reactor Pressure and the Delta P)

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE V

P13.c CRITICAL PLANT P2Q&METER

SUMMARY

For Controller and Observer Use Only Reactor Level (inch) 36. 36 ~ 36.

Reactor Press (psig) 10. 5. 0.

Reactor Power (4) .0 ~ 0 ~ 0 Core Flow (M lb/hr) O.OE+0 O.OE+0 O.OE+0 Steam Flow (M lb/hr) O.OE+0 O.OE+0 O.OE+0 Fdwtr Flow (M lb/hr) O.OE+0 O.OE+0 O.OE+0 Condenser Vac (inHg) 29 29 '0 29.

Hotwell Level (inch) '0

~ 0 Drywell H2 Conc (4) .0 .0 0 Drywell 02 Conc (4) 3.8 3.8 3 '

SGTS Flow (cfm) 4455. 4455. 4455.

Drywell Press (psig) 1.0 1.0 1 0 Drywell Temp (deg F) 103. 103. 103.

Supp Pool Temp (F) 95. 95 95.

Supp Pool Level (ft) 32 ' 32.0 32 '

Main Stm Rad (mR/hr) 1.9E+1 1 7E+1 1.7E+1 Contnmnt Rad (R/hr) 1 OE+1 1.0E+1 1.0E+1 Cond Stor Tnk (ft) 26.0 26 ' 26.0 Wetwell Press (psig) 2' -1.5 -1.6

,T-Time (hr:min) 04035 07 30 08:00 Clock Time (hr:min) 07:35 10 30 11:00 Drywell Delta-P 4.2 2 ' 2 '

Drywell Delta-T 0~ 0. 0~

Wetwell Delta-T 0. 0. 0.

NOTE:

Drywell Pressure is the pressure calculated by the simulator.

Drywell Delta P is the pressure differential due to hydrogen generation and any containment leakage.

Drywell Delta P must be provided to operators of any "live time" plant parameter display screens.

(Tables list the sum of Simulator Drywell Pressure and the Delta P, and the sum of the Reactor Pressure and the Delta P)

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P14.a PUMP AND FAN STATUS

SUMMARY

(T = 00:00) ( 03:00)

PUMP STATUS FAN STATUS Lo Press Core Spray'FF Standby Gas Treat, A OFF Hi Press Core Spray OFF Standby Gas Treat B OFF Suppres Pool Cleanup OFF Standby Gas Treat A OFF Resid Ht Removal A ON Standby Gas Treat B OFF Resid Ht Removal B OFF 18" to SGTA OFF Resid Ht Removal C OFF 18" to SGTB OFF Drywell Spray A OFF 30" to RBV Exhaust OFF Drywell Spray B OFF RBV Exhaust A CFM ON Wetwell Spray A OFF RBV Exhaust B CFM OFF Wetwell Spray B OFF Turb Bld Exst 1A CFM ON Low Pres Coolant A OFF Turb Bld Exst 1B CFM ON Low Pres Coolant B OFF Turb Bld Exst 1C CFM ON Low Pres Coolant C OFF Turb Bld Exst 1D CFM ON RX Cool Inject Steam ON RBV Supply A CFM ON RX Cool Inject Water OFF RBV Supply B CFM OFF Control Rod Drive ON Turb Bld Sply 1A CFM ON Reactor Water Clean OFF Turb Bld Sply 1B CFM ON Post Accid Samp Lip OFF Turb Bld Sply 2A CFM ON Post Accid Samp GAS OFF Turb Bld Sply 2B CFM ON ADS Actuation 1 OFF ADS Actuation 2 OFF ADS Actuation 3 OFF RADW Bld Sply 1A CFM OFF RADW Bld Sply 1B CFM ON RADW Bld Exst 1A CFM OFF RADW Bld Sply 1B CFM ON

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 r TABLE P14.b PUMP AND FAN STATUS

SUMMARY

(T = 01 00) ( 04 00)

PUMP STATUS FAN STATUS Lo Press Core Spray OFF Standby Gas Treat A OFF Hi Press Core Spray OFF Standby Gas Treat B OFF Suppres Pool Cleanup OFF Standby Gas Treat A OFF Resid Ht Removal A ON Standby Gas Treat B OFF Resid Ht Removal B OFF 18" to SGTA OFF Resid Ht Removal C OFF 18n to SGTB OFF Drywell Spray A OFF 30" to RBV Exhaust OFF Drywell Spray B OFF RBV Exhaust A CFM ON Wetwell Spray A OFF RBV Exhaust B CFM OFF Wetwell Spray B OFF Turb Bld Exst 1A CFM ON Low Pres Coolant A OFF Turb Bld Exst 1B CFM ON Low Pres Coolant B OFF Turb Bld Exst 1C CFM ON Low Pres Coolant C OFF Turb Bld Exst 1D CFM ON RX Cool Inject Steam ON RBV Supply A CFM ON RX Cool Inject Water OFF RBV Supply B CFM OFF Control Rod Drive ON Turb Bld Sply 1A CFM ON Reactor Water Clean OFF Turb Bld Sply 1B CFM ON Post Accid Samp Liq OFF Turb Bld Sply 2A CFM ON Post Accid Samp GAS OFF Turb Bld Sply 2B CFM ON ADS Actuation 1 OFF ADS Actuation 2 OFF ADS Actuation 3 OFF RADW Bld Sply 1A CFM OFF RADW Bld Sply 1B CFM ON RADW Bld Exst 1A CFM OFF RADW Bld Sply 1B CFM ON

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P14.c PUMP AND FAN STATUS

SUMMARY

(T = 01: 10) ( 04: 10)

PUMP STATUS FAN STATUS Lo Press Core Spray'. OFF Standby Gas Treat A ON Hi Press Core Spray OFF Standby Gas Treat B OFF Suppres Pool Cleanup OFF Standby Gas Treat A ON Resid Ht Removal A ON Standby Gas Treat B OFF Resid Ht Removal B OFF 18" to SGTA OFF Resid Ht Removal C OFF 18" to SGTB OFF Drywell Spray A OFF 30" to RBV Exhaust OFF Drywell Spray B OFF RBV Exhaust A CFM . OFF Wetwell Spray A OFF RBV Exhaust B CFM OFF Wetwell Spray B OFF Turb Bld Exst 1A CFM OFF Low Pres Coolant A OFF Turb Bld Exst 1B CFM OFF Low Pres Coolant B OFF Turb Bld Exst 1C CFM OFF Low Pres Coolant C OFF Turb Bld Exst 1D CFM OFF RX Cool Inject Steam ON RBV Supply A CFM OFF RX Cool Inject Water OFF RBV Supply B CFM OFF Control Rod Drive ON Turb Bld Sply 1A CFM OFF Reactor Water Clean OFF Turb Bld Sply 1B CFM OFF Post Accid Samp Liq OFF Turb Bld Sply 2A CFM OFF Post Accid Samp GAS OFF Turb Bld Sply 2B CFM OFF ADS Actuation 1 OFF ADS Actuation 2 OFF ADS Actuation 3 ,OFF RADW Bld Sply 1A CFM OFF RADW Bld Sply 1B CFM OFF RADW Bld Exst 1A CFM OFF RADW Bld Sply 1B CFM OFF

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P14.d PUMP AND FAN STATUS

SUMMARY

(T = 02:00) ( 05:00}

PUMP STATUS FAN STATUS Lo Press Core Spray'FF Standby G'as Treat A ON Hi Press Core Spray OFF Standby Gas Treat B OFF Suppres Pool Cleanup OFF Standby Gas Treat A ON Resid Ht Removal A ON Standby Gas Treat B OFF Resid Ht Removal B OFF 18" to SGTA OFF Resid Ht Removal C OFF 18" to SGTB OFF Drywell Spray A OFF 30" to RBV Exhaust OFF Drywell Spray B OFF RBV Exhaust A CFM OFF Wetwell Spray A OFF RBV Exhaust B CFM OFF Wetwell Spray B OFF Turb Bld Exst 1A CFM OFF Low Pres Coolant A OFF Turb Bld Exst 1B CFM OFF Low Pres Coolant B OFF Turb Bld Exst 1C CFM QFF Low Pres Coolant C OFF Turb Bld Exst 1D CFM OFF RX Cool Inject Steam ON RBV Supply A CFM OFF RX Cool Inject Water OFF RBV Supply B CFM OFF Control Rod Drive ON Turb Bld Sply 1A CFM OFF Reactor Water Clean OFF Turb Bld Sply 1B CFM OFF Post Accid Samp Liq OFF . Turb Bld Sply 2A CFM OFF Post Accid Samp GAS OFF Turb Bld Sply 2B CFM OFF ADS Actuation 1 OFF ADS Actuation 2 OFF ADS Actuation 3 OFF RADW Bld Sply 1A CFM OFF RADW Bld Sply 1B CFM OFF RADW Bld Exst 1A CFM OFF RADW Bld Sply 1B CFM OFF

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P14.e PUMP AND FAN STATUS

SUMMARY

(T = 03: 00) ( 06: 00)

PUMP STATUS FAN STATUS Lo Press Core Spray OFF Standby Gas Treat A ON Hi Press Core Spray OFF Standby Gas Treat B OFF Suppres Pool Cleanup OFF Standby Gas Treat A ON Resid Ht Removal A ON Standby Gas Treat B OFF Resid Ht Removal B OFF 18" to SGTA OFF Resid Ht Removal C OFF 18" to SGTB OFF Drywell Spray A OFF 30" to RBV Exhaust OFF Drywell Spray B OFF RBV Exhaust A CFM OFF Wetwell Spray A OFF RBV Exhaust B CFM OFF Wetwell Spray B OFF Turb Bld Exst 1A CFM OFF Low Pres Coolant A OFF Turb Bld Exst 1B CFM OFF Low Pres Coolant B OFF Turb Bld Exst 1C CFM OFF Low Pres Coolant C OFF Turb Bld Exst 1D CFM OFF RX Cool Inject Steam ON RBV Supply A CFM OFF RX Cool Inject Water OFF RBV Supply B CFM OFF Control Rod Drive ON Turb B1d Sply 1A CFM OFF Reactor Water Clean OFF Turb Bld Sply 1B CFM OFF Post Accid Samp Lip OFF Bld Sply 2A CFM OFF 'urb Post Accid Samp GAS OFF Turb Bld Sply 2B CFM OFF ADS Actuation 1 OFF ADS Actuation 2 OFF ADS Actuation 3 OFF RADW Bld Sply 1A CFM OFF RADW Bld Sply 1B CFM OFF RADW Bld Exst. 1A CFM OFF RADW Bld Sply 1B CFM OFF

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P14 f PUMP AND FAN STATUS

SUMMARY

(T = 03:30) ( 06:30)

PUMP STATUS FAN STATUS Lo Press Core Spray'FF t

Standby Gas Treat A ON Hi Press Core Spray OFF Standby Gas Treat B OFF Suppres Pool Cleanup OFF Standby Gas Treat A ON Resid Ht Removal A ON Standby Gas Treat B OFF Resid Ht Removal B OFF 18" to SGTA OFF Resid Ht Removal C OFF 18" to SGTB OFF Drywell Spray A OFF 30" to RBV Exhaust OFF Drywell Spray B OFF RBV Exhaust A CFM OFF Wetwell Spray A OFF RBV Exhaust B CFM OFF Wetwell Spray B OFF Turb Bld Exst 1A CFM OFF Low Pres Coolant A OFF Turb Bld Exst 1B CFM OFF Low Pres Coolant B OFF Turb Bld Exst 1C CFM OFF Low Pres Coolant C OFF Turb Bld Exst 1D CFM OFF RX Cool Inject Steam OFF RBV Supply A CFM OFF RX Cool Inject Water OFF RBV Supply B CFM OFF Control Rod Drive ON Turb Bld Sply 1A CFM OFF Reactor Water Clean OFF Turb Bld Sply 1B CFM OFF Post Accid Samp Liq OFF Turb Bld Sply 2A CFM OFF Post, Accid Samp GAS OFF Turb Bld Sply 2B CFM OFF ADS Actuation 1 OFF ADS Actuation 2 OFF ADS Actuation 3 OFF RADW Bld Sply 1A CFM OFF RADW Bld Sply 1B CFM OFF RADW Bld Exst 1A CFM OFF RADW Bld Sply 1B CFM OFF

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P14.g PUMP AND FAN STATUS SUMMAR'Z (T = 04:00) { 07:00)

PUMP STATUS FAN STATUS Lo Press Core Spray OFF Standby Gas Treat A ON Hi Press Core Spray OFF Standby Gas Treat B OFF Suppres Pool Cleanup OFF Standby Gas Treat A ON Resid Ht Removal A OFF Standby Gas Treat B OFF Resid Ht Removal B OFF 18" to SGTA OFF Resid Ht Removal C OFF 18" to SGTB OFF Drywell Spray A OFF 30" to RBV Exhaust OFF Drywell Spray B OFF RBV Exhaust A CFM OFF Wetwell Spray A OFF RBV Exhaust B CFM OFF Wetwell Spray B OFF Turb Bld Exst 1A CFM OFF Low Pres Coolant A OFF Turb Bld Exst 1B CFM OFF Low Pres Coolant B OFF Turb Bld Exst 1C CFM OFF Low Pres Coolant C OFF Turb Bld Exst 1D CFM OFF RX Cool Inject Steam OFF RBV Supply A CFM OFF RX Cool Inject Water OFF RBV Supply B CFM OFF Control Rod Drive ON Turb Bld Sply 1A CFM OFF Reactor Water Clean OFF Turb Bld Sply 1B CFM OFF Post Accid Samp Lip OFF Turb Bld Sply 2A CFM OFF Post Accid Samp GAS OFF Turb Bld Sply 2B CFM OFF ADS Actuation 1 ON ADS Actuation 2 ON ADS Actuation 3 OFF RADW Bld Sply 1A CFM OFF RADW Bld Sply 1B CFM OFF RADW Bld Exst 1A CFM OFF RADW Bld Sply 1B CFM OFF

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P14.h PUMP AND FAN STATUS

SUMMARY

(T = 05:00) ( 08:00)

PUMP STATUS FAN STATUS Lo Press Core Spray OFF Standby Gas Treat A ON Hi Press Core Spray OFF Standby Gas Treat B OFF Suppres Pool Cleanup OFF Standby Gas Treat A ON Resid Ht Removal A OFF Standby Gas Treat B OFF Resid Ht Removal B OFF 18>> to SGTA OFF Resid Ht, Removal C OFF 18>> to SGTB OFF Drywell Spray A OFF 30>> to RBV Exhaust OFF Drywell Spray B OFF RBV Exhaust A CFM OFF Wetwell Spray A OFF RBV Exhaust B CFM OFF Wetwell Spray B OFF Turb Bld Exst 1A CFM OFF Low Pres Coolant A OFF Turb Bld Exst 1B CFM OFF Low Pres Coolant B OFF Turb Bld Exst 1C CFM OFF Low Pres Coolant C OFF Turb Bld Exst 1D CFM OFF RX Cool inject Steam OFF RBV Supply A CFM OFF RX Cool Ingect Water OFF RBV Supply B CFM OFF Control Rod Drive ON Turb Bld Sply 1A CFM OFF Reactor Water Clean OFF Turb Bld Sply 1B CFM OFF Post Accid Samp Liq OFF Turb Bld Sply 2A CFM OFF Post, Accid Samp GAS OFF Turb Bld Sply 2B CFM OFF ADS Actuation 1 ON ADS Actuation 2 ON ADS Actuation 3 OFF RADW Bld Sply 1A CFM OFF RADW Bld Sply 1B CFM OFF RADW Bld Exst 1A CFM OFF RADW Bld Sply 1B CFM OFF

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P14.i E

PUMP AND FAN STATUS

SUMMARY

(T = 05:30) ( 08:30)

PUMP STATUS FAN STATUS Lo Press Core Spray'FF Standby Gas Treat A ON Hi Press Core Spray OFF Standby Gas Treat B OFF Suppres Pool Cleanup OFF Standby Gas Treat A ON Resid Ht Removal A OFF Standby Gas Treat B OFF Resid Ht Removal B OFF 18" to SGTA OFF Resid Ht Removal C OFF 18" to SGTB OFF Drywell Spray A OFF 30" to RBV Exhaust OFF Drywell Spray B OFF RBV Exhaust A CFM OFF Wetwell Spray A OFF RBV Exhaust B CFM OFF Wetwell Spray B OFF Turb Bld Exst 1A CFM OFF Low Pres Coolant A OFF Turb Bld Exst 1B CFM OFF Low Pres Coolant B OFF Turb Bld Exst 1C CFM OFF Low Pres Coolant C OFF Turb Bld Exst 1D CFM OFF RX Cool Inject Steam OFF RBV Supply A CFM OFF RX Cool Inject Water OFF RBV Supply B CFM OFF Control Rod Drive ON Turb Bld Sply 1A CFM OFF Reactor Water Clean OFF Turb Bld Sply 1B CFM OFF Post Accid Samp Liq OFF Turb Bld Sply 2A CFM OFF Post Accid Samp GAS OFF Turb Bld Sply 2B CFM OFF ADS Actuation 1 ON ADS Actuation 2 ON ADS Acguation 3 OFF RADW Bld Sply 1A CFM OFF RADW Bld Sply 1B CFM OFF RADW Bld Exst 1A CFM OFF RADW Bld Sply 1B CFM OFF

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P14.j PUMP AND FAN STATUS

SUMMARY

(T = 06:00) ( 09:00)

PUMP STATUS FAN STATUS Lo Press Core Spray'FF Standby Gas Treat A ON Hi Press Core Spray OFF Standby Gas Treat B OFF Suppres Pool Cleanup OFF Standby Gas Treat A ON Resid Ht Removal A OFF Standby Gas Treat B OFF Resid Ht Removal B OFF 18" to SGTA OFF Resid Ht Removal C OFF 18" to SGTB OFF Drywell Spray A OFF 30" to RBV Exhaust OFF Drywell Spray B OFF RBV Exhaust A CFM OFF Wetwell Spray A OFF RBV Exhaust B CFM OFF Wetwell Spray B OFF Turb Bld Exst 1A CFM OFF Low Pres Coolant A OFF Turb Bld Exst 1B CFM OFF Low Pres Coolant B OFF Turb Bld Exst 1C CFM OFF Low Pres Coolant C OFF Turb Bld Exst 1D CFM OFF RX Cool Inject Steam OFF RBV Supply A CFM OFF RX Cool Inject Water OFF RBV Supply B CFM OFF Control Rod Drive ON Turb Bld Sply 1A CFM OFF Reactor Water Clean OFF Turb Bld Sply 1B CFM OFF Post Accid Samp Lip OFF Turb Bld Sply 2A CFM OFF Post Accid Samp GAS OFF Turb Bld Sply 2B CFM OFF ADS Actuation 1 ON ADS Actuation 2 ON ADS Actuation 3 OFF RADW Bld Sply 1A CFM OFF RADW Bld Sply 1B CFM OFF RADW Bld Exst 1A CFM OFF RADW Bld Sply 1B CFM OFF

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P14.k PUMP AND FAN STATUS

SUMMARY

(T = 07:00) ( 10:00)

PUMP STATUS FAN STATUS Lo Press Core Spray'FF Standby Gas Treat A ON Hi Press Core Spray OFF Standby Gas Treat B OFF Suppres Pool Cleanup OFF Standby Gas Treat A ON Resid Ht Removal A OFF Standby Gas Treat B OFF Resid Ht Removal B OFF 18" to SGTA OFF Resid Ht Removal C OFF 18" to SGTB OFF Drywell Spray A OFF 30" to RBV Exhaust OFF Drywell Spray B OFF RBV Exhaust A CFM OFF Wetwell Spray A OFF RBV Exhaust B CFM OFF Wetwell Spray B OFF Turb Bld Exst 1A CFM OFF Low Pres Coolant A OFF Turb Bld Exst 1B CFM OFF Low Pres Coolant B OFF Turb Bld Exst 1C CFM OFF Low Pres Coolant C OFF Turb Bld Exst 1D CFM OFF RX Cool Inject Steam OFF RBV Supply A CFM OFF RX Cool Inject Water OFF RBV Supply B CFM OFF Control Rod Drive ON Turb Bld Sply 1A CFM OFF Reactor Water Clean OFF Turb Bld Sply 1B CFM OFF Post Accid Samp Liq OFF Turb Bld Sply 2A CFM OFF Post Accid Samp GAS OFF Turb Bld Sply 2B CFM OFF ADS Actuation 1 ON ADS Actuation 2 ON ADS Actuation 3 OFF RADW Bld Sply 1A CFM OFF RADW Bld Sply 1B CFM OFF RADW Bld Exst, 1A CFM OFF RADW Bld Sply 1B CFM OFF

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P14.1 PUMP AND FAN STATUS

SUMMARY

(T = 08: 00) ( 11- 00)

PUMP STATUS FAN STATUS Lo Press Core Spray'. OFF Standby Gas Treat A ON Hi Press Core Spray OFF Standby Gas Treat B OFF Suppres Pool Cleanup OFF Standby Gas Treat A ON Resid Ht Removal A OFF Standby Gas Treat B OFF Resid Ht Removal B OFF 18" to SGTA OFF Resid Ht Removal C OFF 18" to SGTB OFF Drywell Spray A OFF 30" to RBV Exhaust OFF Drywell Spray B OFF RBV Exhaust A CFM OFF Wetwell Spray A OFF RBV Exhaust B CFM OFF Wetwell Spray B OFF Turb Bld Exst 1A CFM OFF Low Pres Coolant A OFF Turb Bld Exst 1B CFM OFF Low Pres Coolant B OFF Turb Bld Exst 1C CFM OFF Low Pres Coolant C OFF Turb Bld Exst 1D CFM OFF RX Cool Inject Steam OFF RBV Supply A CFM OFF RX Cool Inject Water OFF RBV Supply B CFM OFF Control Rod Drive ON Turb Bld Sply 1A CFM OFF Reactor Water Clean OFF Turb Bld Sply 1B CFM OFF Post Accid Samp Liq OFF Turb Bld Sply 2A CFM OFF Post Accid Samp GAS OFF Turb Bld Sply 2B CFM OFF ADS Actuation 1 ON ADS Actuation 2 ON ADS Actuation 3 OFF RADW Bld Sply 1A CFM OFF RADW Bld Sply 1B CFM OFF RADW Bld Exst 1A CFM OFF RADW Bld Sply 1B CFM OFF

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE PE1 a EMERGENCY RESPONSE FACILITY DATA (T = 00:00) ( 03:00)

CLOSED OPEN AIR SAMPLE Emergency Center WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/min)

MCR < 0.1 0~1 0 1 OSC 1 0.1 0.1 0.1 OSC 2 0.1 < 0.1 0.1 TSC 0~1 0.1 0~1 EOF 0 1 0.1 0.1 PASS Sample St. 0 1 0~1 0.1

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE PE1 b EMERGENCY RESPONSE FACILITY DATA (T = 03:30) ( 06:30)

CLOSED OPEN AIR SAMPLE Emergency Center 'INDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/min)

MCR 0~1 0~1 0 1 OSC 1 0.1 0.1 0.1 OSC 2 0.1 0~1 0.1 TSC 0' 0~1 0.1 EOF 0.1 0.1 0.1 PASS Sample St. 0.1 0~1 0'

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 C TABLE PE1 c EMERGENCY RESPONSE FACILITY DATA (T ~ 04:00) ( 07:00)

CLOSED OPEN AIR SAMPLE Emergency Center WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/min)

MCR 0' 0 1 0~1 OSC 1 0.1 0.1 0.1 OSC 2 0 1 0 1 0~1 TSC 0~1 0.1 0 1 EOF 0~1 F 1 0~1 PASS Sample St. 0.1 0.1 0~1

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE PEl d EMERGENCY RESPONSE FACILITY DATA (T = 04-15) ( 07:15)

CLOSED OPEN AIR SAMPLE Emergency Center WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/min)

MCR 0 ' ( 0.1 0.1 OSC 1 0.6 0.6 140.

OSC - 2 0.6 0.6 140.

TSC 0' 0.1 1.2 EOF 0~1 0.1 1.2 PASS Sample St. 0.1 < 0.1 140 '

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE PE1 e EMERGENCY RESPONSE FACILITY DATA (T = 04:30) ( 07:30)

CLOSED OPEN AIR SAMPLE Emergency Center WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/min)

MCR 0.1 0~1 0~1 OSC 1 0 9 0.9 50.

OSC - 2 0' 0' 50.

TSC F 1 F 1 0.4 EOF 0 1 0' 0.4 PASS Sample St. F 1 0.1 50 ~

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise 0

Unit 2 REV 0 TABLE PE1 f EMERGENCY RESPONSE FACILITY DATA (T = 05:00) ( 08:00)

CLOSED OPEN AIR SAMPLE Emergency Center WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/min)

MCR 0~1 0 1 0.1 OSC - 1 0.8 0' 86.

OSC 2 0.8 0.8 86.

TSC 0.1 0~1 0.7 EOF 0 ' < 0.1 0.7 PASS Sample St. 0 1 0~1 86.

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE PE1 g EMERGENCY RESPONSE FACILITY DATA (T = 06:00) ( 09:00)

CLOSED OPEN AIR SAMPLE Emergency Center WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/min)

MCR 0.1 0.1 < 0.1 OSC 1 0.6 0~6 28.

OSC - 2 0.6 0.7 28.

TSC 0.1 0 1 0.2 EOF 0~1 0 1 0.2 PASS Sample St. 0 1 0 1 28.

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE PE1 h EMERGENCY RESPONSE FACILITY DATA (T = 06:30) ( 09:30)

CLOSED OPEN AIR SAMPLE Emergency Center WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/min)

MCR 0.1 0.1 0~1 OSC 1 0.4 0.4 38 OSC - 2 0' 0.4 '8 TSC 0.1 0.1 0' EOF < 0.1 0.1 0' PASS Sample St. 0 1 < 0.1 38 '

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0

/

TABLE PE1 i EMERGENCY RESPONSE FACILITY DATA (T = 07:00) ( 10:00)

CLOSED OPEN AIR SAMPLE Emergency Center WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) , (cpm/min)

MCR 0.1 0 1 0.1 OSC- 1 0 2 0' 24.

OSC 2 0.2 0 2 24 '

TSC 0.1 0~1 1 EOF 0.1 0~1 0.1 PASS Sample St. 0.1 0.1 24

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE PE1 j EMERGENCY RESPONSE FACILITY DATA (T = 07 30) ( 10:30)

CLOSED OPEN AIR SAMPLE Emergency Center WINDOW WINDOW - COUNT RATE (mR/hr) (mR/hr) (cpm/min)

,MCR 0~1 0~1 0 1 OSC 1 0~2 0~2 63 ~

OSC 2 0.2 0.2 63 TSC 0.1 0.1 0.4 EOF 0.1 0 1 0.4 PASS Sample St. 0.1 0.1 63 '

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 t TABLE PE1 k EMERGENCY RESPONSE FACILITY DATA (T ~ 08:00) ( 11:00)

CLOSED OPEN AIR SAMPLE Emergency Center WINDOM WINDOM COUNT RATE (mR/hr) (mR/hr) (cpm/min)

MCR 0 1 0 1 0.1 OSC - 1 0.2 0~2 44 OSC - 2 0.2 0.2 '

'4 TSC 0.1 0 1 2 EOF 0.1 0~1 0 '

PASS Sample St. 0~1 0~1 44.

4 WASH'LNGTON tOSKIC tOW$ %

SUPPLY SYSTEM CONTROLLER INFORMATION SCENARIO MESSAGES RILL NO. PAGE EXERCISE 93 1OF1 MESSAGE NO. REAL TIME OF: ORILL TIME OF:

0330 0000 CONTROLLER LOCATION CONTROL ROOM (SlMULATOR) 5 EOFCC CONTROLLER NAME ORGANIZATION MESSAGE FOR: ALL'PERSONNEL MESSAGE FROM: CONTROL ROOM (SIMULATOR) 8c LEAD EOFCC CONTROLLERS MESSAGE:

Please make the following announcements on the Plant and PSF PA's.

THIS IS AN EXERCISE... THIS IS AN KKRCISE.

EXERCISE 93 IS NOW IN PROGRESS. PERSONNEL NOT IDERI'IFD:D AS PARTICIPAIWS IN THE EXERCISE SHOULD CON'ANTE WITH TEKIR NORMM. WORK SCHEDULE.

THIS IS AN EXERCISE... THIS IS AN EXERCISE.

REFERENCE GENERAL DATA SHEETS:

'I'~i%'~ ~ g", '~r ~>'4w c~)'k ~+< '~o, i,).."ac~,gY'., ";~ jPOR'CONTROLL'ER',USE'ONL+ry~4+~ ~ %4F+<%~k:;. *'4p8~>~<<w~'+Pg~g c" ~~

REPEAT THIS PA ANNOUNCEMENT APPROXIMATELYEVERY HOUR.

'4 SUPPLY SYSTEM WASRlNGTON tIIbL'IC PO'Wbb CONTROLLZR INFORMATION SCENARIO MESSAGES DRILL NO. PAGE EXERCISE 93 1of'I MESSAGE NO. REAI. TIME OF: DRILL TIME OF:

0900 CONTROLLER LOCATION SSDC CONTROLLER NAME ORQANI7ATION MESSAGE FOR: RECOVERY MANAGER MESSAGE FROM: LEAD CONTROLLER SSDC MESSAGE:

"THIS IS A DEFAULT MESSAGE" Coordinate with the other Emergency Centers to conduct shift turnover at or near 0900.

"THIS IS A DEFAULT MESSAGE" REFERENCE GENERAL DATA SHEETS:

cog'<'.. ~ %~+ ~+ RN P<"0~(".'< Ag'+4'> '<<'"'<%%%7&~~,.y <<ggR CONIOLLER Ug Ogy <<oiydg%<Pa;1<<g++~g%<<+<y~@~":-'Sg<<:. e'A$ A'>j4g>(N'PgBcv~ 'g This message may need to be discussed with the Recovery Manager early in the drill so that all centers can plan on shift turnover at around the same time.

4 W AS N 1 w G T 0 N SUPPLY SYSTEM CONTROLLER INFORMATION l'TLlC I> 0W II SCENAMO MESSAGES RILL NO. PAGE ~

EXERCISE 93 1 OF 1 MESSAGE NO. REAL TIME OF: DRILL TIME OF:

1000 0000 CONTROLLER LOCATION CONTROL ROOM (SIMULATOR) 5 EOFCC CONTROLLER NAME ORGANIZATION MESSAGE FOR: ALLPERSONNEL MESSAGE FROM: CONTROL ROOM (SIMULATOR) k LEAD EOFCC CONTROLLERS MESSAGE:

Please make the following announcements on the Plant and PSF PA's.

THIS IS AN EXERCISE... THIS IS AN E3CERCISE.

EXERCISE 93 IS NO%'EKUQNATED. PERSONNEL IDENI'II"IEDAS PARTICIPANTS IN THE DRILL SHOULD RETURN TO THEIR EMERGENCY CENTER TO CONDUCT POST EXERCISE CRXI'IQUE.

THIS IS AN EXERCISE... THIS IS AN EXERCISE.

REFERENCE GENERAL DATA SHEETS:

PP+CP~iP~:USE'ONLY>'<< <<~>>.~~> w>c'<<"-:".t>'j 'g8": ~

'> c, '~g.~~~ ..zm.c

'6 SUPPLY SYSTEM WASNlNGTON PCS'Llc POWER CONTROLLER INFORMATION GENERAL DATA SHEET RILL NO. Exercise 93 PAGE SHEET NO. REsPDNsisLEcoNTRDLLER /LocATIDNI Control Room (Simulator), MUDAC & TSC REAL TIME OF: 03I00 TO: 12I00 DRILL TIME OF: 00:00 TO: 09:00 ASSOCIA TED WITH MESSA GES INFORMATIONAPPLIES TO ff TABLE OF CONTENTS TAB HEA DIN P1 REACTOR WATER ACTIVITYCONCENTRATION P2 DRYWELL GAS ACTIVITYCONCENTRATION P3 WETWELL GAS ACTIVITYCONCENTRATION WETWELL WATER ACTIVITYCONCENTRATION PS RX BLDG 8L REFUEL FLOOR ACT. CONC.

P6 RX BLDG ELEVATED RELEASE POINT CONC.

P7 RADWASTE BLDG/RADWASTE BLDG EXHAUST PB TURBINE BLDG/TURBINE BLDG EXHAUST P9 RADIATION MONITORING SYSTEM DATA P10 IN-PLANT SURVEY AND SAMPLING DATA P11 ONSITE SURVEY AND SAMPLING DATA P12 AIRBORNE ACTIVITY(PLANT VICINITY)

P13 CRITICAL PLANT PARAMETER

SUMMARY

P14 PUMP AND FAN STATUS

SUMMARY

El METEOROLOGICAL DATA

SUMMARY

E2 OFFSITE SURVEY AND SAMPLING DATA E3 ENVIRONMENTALSAMPLING DATA PE1 EMERGENCY RESPONSE FACILITY DATA

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE PE1 a EMERGENCY RESPONSE FACILITY DATA (T = 00:00) ( 03:00)

CLOSED OPEN AIR SAMPLE Emergency Center . WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/min)

MCR 0' 0.1 0.1 OSC - 1 0' 0.1 0.1 OSC 2 0' 0~1 0.1 TSC 0' 0~1 0~1 EOF 0.1 0.1 0.1 PASS Sample St. 0.1 ( 0~1 0.1

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE PE1 b EMERGENCY RESPONSE FACILITY DATA {T = 03-30) { 06:30)

CLOSED OPEN AIR SAMPLE Emergency Center WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/min)

MCR 0.1 0.1 0.1 OSC 1 0.1 0.1 < 0.1 OSC 2 0.1 0~1 0.1 TSC 0.1 0.1 < 0.1 EOF 0.1 0.1 < 0.1 PASS Sample St. 0.1 < 0.1 < 0.1

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE PE1 c EMERGENCY RESPONSE FACILITY DATA (T = 04:00) ( 07:00)

CLOSED OPEN AIR SAMPLE Emergency Center WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/min)

MCR 0.1 0.1 0.1 OSC 1 0.1 < 0.1 0.1 OSC - 2 0' 0~1 0.1 TSC 0.1 0.1 0' EOF 0.1 0.1 0.1 PASS Sample St. 0.1 0.1 0.1

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE PE1 d EMERGENCY RESPONSE FACZLZTY DATA (T = 04:15) ( 07:15)

CLOSED OPEN AZR SAMPLE Emergency Center WZNDOW WZNDOW. COUNT RATE (mR/hr) (mR/hr) (cpm/min)

MCR

- ( 0.1 < 0.1 0.1 OSC 1 0.6 0 6 140 OSC - 2 0.6 0.6 140.

TSC 0' 0.1 1.2 EOF 0.1 0~1 1~2 PASS Sample St. 0.1 0.1 140 ~

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 0 TABLE PE1 e EMERGENCY RESPONSE FACILITY DATA (T = 04-30) ( 07-30)

CLOSED OPEN . AIR SAMPLE Emergency Center WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/min)

MCR 0.1 0.1 0~1 OSC 1 0.9 0.9 50.

OSC 2 0 ' 0.9 50.

TSC ( 0.1 0.1 0.4

. EOF 0.1 0.1 0 '

PASS Sample St. 0 ' 0.1 50.

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE PE1 f EMERGENCY RESPONSE FACILITY DATA (T = 05:00) ( 08:00)

CLOSED OPEN AIR SAMPLE Emergency Center WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/min)

MCR 0.1 0.1 0~1 OSC 1 0.8 0.8 86.

OSC 2 0.8 0.8 86.

TSC 0.1 0' 0.7 EOF 0.1 0.1 0 '

PASS Sample St. 0.1 0.1 86.

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE PE1 g EMERGENCY RESPONSE FACILITY DATA (T = 06-00) ( 09:00)

CLOSED OPEN AIR . SAMPLE Emergency Center WINDOW WINDOW'OUNT RATE (mR/hr) (mR/hr) (cpm/min)

MCR 0.1 0.1 0~1 OSC 1 0.6 0.6 28 OSC - 2 0.6 0.7 '8.

TSC 0.1 0.1 0' EOF 0.1 ( 0.1 0' PASS Sample St. < 0.1 < 0.1 28.

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE PE1 h EMERGENCY RESPONSE FACILITY DATA (T = 06:30) ( 09:30)

CLOSED OPEN AIR SAMPLE Emergency Center WINDOW WINDOW'OUNT RATE (mR/hr) (mR/hr) (cpm/min)

- MCR 0~1 0.1 0.1 OSC 1 0.4 0.4 38.

OSC 2 0.4 0.4 38.

TSC 0.1 0.1 0' EOF 0.1 0.1 0.3 PASS Sample St. 0.1 0~1 38 '

WP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE PE1 i EMERGENCY RESPONSE FACILITY DATA (T = 07:00) ( 10:00)

CLOSED OPEN AIR SAMPLE Emergency Center HINDOOS NINDON COUNT RATE (mR/hr) (mR/hr) (cpm/min)

MCR ( 0.1 0.1 0.1 OSC 1 0.2 0 2 24 OSC - 2 0.2 0 ' '4.

TSC 0.1 0.1 0' EOF 0.1 0 1 0 1 PASS Sample St. 0' F 1 24

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE PE1 j EMERGENCY RESPONSE FACILITY DATA (T = 07:30) ( 10:30)

CLOSED OPEN AIR SAMPLE Emergency Center WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/min)

MCR 0 1 0 0 1 OSC 1 0' 0 2 63.

OSC 2 0.2 0.2 63 ~

TSC 0.1 0 1 0.4 EOF < 0.1 0 1 0 4 PASS Sample St. < 0.1 0 1 63.

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE PE1 k EMERGENCY RESPONSE FACILITY DATA (T = 08:00) ( 11:00)

CLOSED OPEN AIR SAMPLE Emergency Center WINDOW WINDOW'OUNT RATE (mR/hr) (mR/hr) (cpm/min)

. MCR 0.1 0.1 0.1 OSC 1 0.2 0 2 44 OSC 2 0.2 0.2 '4 TSC 0.1 0' '.2 EOF 0.1 F 1 0' PASS Sample St. 0.1 0 1 44 '

1/8 Mile Site Plan Survey Looation

~

QS

~ Water Steel/Equip Buildings Varehouses

~ Grid Lines Bndry Lines

I

/

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P11 o ONSITE SURVEY AND SAMPLING DATA (T = 08:00) ( 11:00)

CLOSED OPEN AIR SAMPLE LOCATION WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/cf)

A 0.2 0.2 44 B 0.3 0.3 '4 C 0.8 0.9 '7 D 0.8 0' 24 ~

E 0.2 0.2 12 ~

F 84. 84. 23 G 0.2 0.2 '.2 H 0.4 0.4 1.6

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P11.n ONSITE SURVEY AND SAMPLING DATA (T = 07:30) .( 10:30)

CLOSED OPEN AIR SAMPLE LOCATION WINDOW . WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/<<)

A 0.2 0.2 63.

B 0' 0.3 63.

C 0.9 0' 24.

D 0 ' 0.9 34.

E 0.3 0.3 18 F 94. 94 33 ~

G 0-2 '.2 4'

H 0.4 0.4 2 4

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P11.m ONSITE SURVEY AND SAMPLING DATA (T = 07-00) ( 10-00)

CLOSED OPEN AIR SAMPLE LOCATION WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/cf)

A 0.2 0.2 24.

B 0.3 0 4 24.

C 1.0 1.0 9.1 D 1.0 1.0 13 ~

E 0.3 0' 6.7 F 110. 110. 12.

G 0.2 0.2 1.7 H 0.5 0' 0.9

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P11.1 ONSITE SURVEY AND SAMPLING DATA (T = 06:30) ( 09:30)

CLOSED OPEN AIR SAMPLE LOCATION WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/cf)

A 0.4 0.4 38.

B 0.4 0.4 38 C 1' 1.2 15.

D 1 2 1 2 20.

E 0.3 0.3 11 F 130. 130 '0.

G 0.3 0.3 2 '

H 0.6 0.6 1.4

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 i TABLE P11 k ONSITE SURVEY AND SAMPLING DATA (T = 06:00) ( 09:00)

CLOSED OPEN AIR SAMPLE LOCATION WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/cf)

A 0.6 0~6 28.

B 0.6 0.6 28.

C 1.5 1.5 11.

D 1~5 1 5 15.

E 0.4 0.4 7.9 F 160. 160. 15.

G 0.4 0.4 2.0 H 0.7 0.7 1.0

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P11.$

ONSITE SURVEY AND SAMPLING DATA (T = 05:30) ( 08:30)

CLOSED OPEN AIR SAMPLE LOCATION WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/cf)

A 0' 0.6 48.

B 0.7 0.7 48.

C 1.9 1.9 19.

D 1~9 1.9 26.

E 0.5 0.5 14 F 210 210 '6.

G 0.4 '.4 3.5 H 0.9 0.9 1'

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P11.i ONSITE SURVEY AND SAMPLING DATA (T = 05:00) ( 08:00)

CLOSED OPEN AIR SAMPLE LOCATION WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/cf)

A 0.7 0.7 86.

B 0.8 0.8 86.

C 2.5 2.5 33.

D 2 5 2.5 46.

E 0.6 0.6 24 F 300. 300. 45.

G 0.6 0.6 6.2 H 1 2 1' 3.2

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P11 h ONSITE SURVEY AND SAMPLING DATA (T = 04:45) ( 07:45)

CLOSED OPEN AIR SAMPLE LOCATION WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/cf)

A 0.8 0.8 120.

8 1.0 1-0 120.

C 3.0 3.0 44 ~

D 2.9 2.9 62.

E 0.7 0.7 33.

F 360. 360. 61.

G 0.7 0.7 8.3 H 1.4 1.4 4.3

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 i TABLE P11.g ONSITE SURVEY AND SAMPLING DATA (T = 04:30) ( 07:30)

CLOSED OPEN AIR SAMPLE LOCATION WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/cf)

A 0.8 0.8 50 B 1 1 1.1 50.

C 3.7 3.7 19 D 3.5 3.5 '7 E 0.9 0.9 14.

F 460. 460. 26.

G 0.8 0.8 3.6 H 1.7 1.7 1.9

I WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P11 f ONSITE SURVEY AND SAMPLING DATA (T = 04:15) ( 07:15)

CLOSED OPEN AIR SAMPLE LOCATION WINDOW WINDOW COUNT RATE

,(mR/hr) (mR/hr) (cpm/cf)

A 0.6 0~6 140.

B 0.9 0.9 140.

C 3 ' 3.1 55.

D 3 ' 3.0 76.

E 0 ' 0.7 40.

F 390. 390. 75.

G 0 ' 0.7 10.

H 1.4 1.4 5.3

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P11.e ONSITE SURVEY AND SAMPLING DATA (T = 04:00) ( 07:00)

CLOSED OPEN AIR SAMPLE LOCATION WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/cf)

A 0.1 0-1 0 1 B 0.1 0 1 0.1 C 0.1 0 1 0 1 D 0~1 0 1 0.1 E 0.1 F 1 0 1 F 0 1 0.1 0.1 G 0.1 0 1 < 0.1 H 0~1 0 1 0 1

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P11.6 ONSITE SURVEY AND SAMPLING DATA (T = 03:30) ( 06:30)

CLOSED OPEN AIR SAMPLE LOCATION WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/cf)

A < 0.1 0.1 0.1 B < 0.1 0 1 0.1 C 0' 0.1 0.1 D 0.1 0.1 0 1 E 0~1 0.1 0.1 F 0~1 0.1 0.1 G 0~1 0~1 0. 1.

H 0.1 0.1 0'

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P11.b ONSITE SURVEY AND SAMPLING DATA '(T = 02:00) ( 05:00)

CLOSED OPEN AIR SAMPLE LOCATION WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm/cf)

A 0~1 0' 0.1 B ( 0.1 ( 0' 0.1 C 0.1 0~1 0.1 D 0.1 0.1 0' E 0.1 0~1 0.1 F 0' 0~1 0.1 G 0-1 ( 0 1 0.1 H 0' 0.1 0 1

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE P11.a ONSITE SURVEY AND SAMPLING DATA (T = 00:00) ( 03:00)

CLOSED OPEN AIR SAMPLE LOCATION WINDOW WINDOW COUNT RATE (mR/hr) (mR/hr) (cpm'/cf)

A 0.1 0.1 0.1 B 0 1 0 1 0.1 C 0 1 0 1 ( 0.1 D 0 1 0.1 0.1 E 0-1 0' 0.1 F 0~1 0 1 0.1 G 0~1 0.1 0.1 H 0 1 0 1 0.1

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0 WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. a OFFSITE SURVEY AND SAMPLING DATA (T = 00:00) ( 03:00)

HONITOR READINGS AIR SANPLES 15.min RAD DATA *CONTROLLER INFO (10 CF)

FIELD CI.OSED 'NINDSI OPEN MINDOM bare filter- change contam 1-131 SRD percent HONITOR Maist ground Nafst ground absorb absorb in SRD cpm/ conc. dose contrib POINT (mR/hr) (mR/hr) (mR/hr ) (mR/hr) CPH CPH mR 100 cmZ uCi/cc Plm Plt Grd Air Sample Background 3s 60 CPH ALL < 0.1 < 0.1 < 0.1 < 0.1 60. 60. < 0.1 < 0.1 O.DE+00 0 0 0

• FOR CONTROLLER/OBSERVER USE ONLY*

(Not to be Provided to Players):

Current Stability Class F Primary Release Pt: PS Flow: 3.9E+1 m3/sec Release Concentration-GIP (uCi/cc): 2.7E-09 3.0E-10 1.5E-11 (Flow & Release Integrated & Averaged over previous 15 minutes)

Whole Body Dose Projection: < 0.1 mRem/hr Thyroid Dose Projection: < 0.1 mRem/hr at a distance of: 3.60 miles downwind Maximums and Projections do not include plant shine or ground shine Maximum Plume Whole-Body Dose Rate: < 0.1 mRem/hr at a distance of: .25 miles downwind Maximum Thyroid Dose Commitment: < 0.1 mRem/hr at a distance of: .25 miles downwind

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. c OFFSITE SURVEY AND SAMPLING DATA (T = 03:30) ( 06:30)

MONITOR READINGS AIR SANPLES 'l5-min RAD DATA *CONTROLLER INFO (10 CF)

FIELD CLOSED llINDQI OPEN WINDOM bare filter- change contea I-131 SRD percent HONITOR uaist ground usist ground absorb absorb in SRD cpe/ cence dose contr ib POINT (ag/hr) (aSI/hr) (aSI/hr) (sR/hr) CPH CPM eR 100cmZ uCI/cc Plm Plt Grd Air Sea@le Background is 60 CPM ALL < 0.1 < 0 1 < 0.1 < 0.1 60. 60. < 0.1 < 0.1 0.DE+00 0 0 0

• FOR CONTROLLER/OBSERVER USE ONLY*

(Not to be Provided to Players):

Current Stability Class F Primary Release Pt: PS Flow: 2.1E+0 m3/sec Release Concentration-GIP (uCi/cc): 1.9E-07 1.0E-12 1.6E-11 (Flow & Release Integrated & Averaged over previous 15 minutes)

Whole Body Dose Projection: < 0.1 mRem/hr

. Thyroid Dose Projection: < 0.1 mRem/hr at a distance of: 1.20 miles downwind Maximums and Projections do not include plant shine or ground shine Maximum Plume Whole-Body Dose Rate: < 0.1 mRem/hr at a distance of: 2.49 miles downwind Maximum Thyroid Dose Commitment: < 0.1 mRem/hr at a distance of: 2.73 miles downwind

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. d OFFSITE SURVEY AND SAMPLING DATA (T = 03:45) ( 06:45)

HONITOR READINGS AIR SAHPLES 15-min RAD DATA <<CONTROLLER INFO (10 CF)

FIELD . CLOSED MINDOM OPEN MINDINI bare f f Iter- change cont+a l-131 SRD percent HONITOR mist ground mist ground absorb absorb fn SRO cpa/ 'conc+ dose contrib POINT (aR/hr) (aN/hr) (aR/hr) (sR/hr) CPH CPH sR 100 an2 uCI/cc Pfm Plt Grd Afr Saapfe Background fs 60 CPH ALL < 0.1 < 0.1 < 0.1 < 0.1 60. 60. < 0.1 < 0.1 O.DE+00 0 0 0

• FOR CONTROLLER/OBSERVER USE ONLY*

(Not to be Provided to Players):

Current Stability Class F Primary Release Pt: PS Flow: 2.1E+0 m3/sec Release Concentration-GIP (uCi/cc): 7.1E-06 3.0E-10 4.2E-09 (Flow & Release Integrated & Averaged over previous 15 minutes)

Whole Body Dose Projection: < 0.1 mRem/hr Thyroid Dose Projection: < 0..1 mRem/hr at a distance of: 1.20 miles downwind Maximums and Projections do not include plant shine or ground shine Maximum Plume Whole-Body Dose Rate: < 0.1 mRem/hr at a distance of: 1.20 miles downwind Maximum Thyroid Dose Commitment: < 0.1 mRem/hr at a distance of: 2.98 miles downwind

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. e OFFSITE SURVEY AND SAMPLXNG DATA (T = 04:00) ( 07:00)

HONITOR READINGS AIR SAHPLES 15-min RAD DATA <<CONTROLLER INFO (10 CF)

FIELD CLOSED llINDOM OPEN llIND(AI bare filter- change contam 1-131 SRD percent HONITOR uaist ground uaist ground absorb absorb in SRD cpa/ conc. dose contrib POINT (mR/hr) (mR/hr) (mR/hr) (mR/hr) CPH CPH mR 100cm2 uCi/cc Pim Pit Grd Air Sanple Background is 60 CPH

.SA c 0.1 c 0.1 c 0.1 < 0.1 60. 61. < 0.1 c 0.1 6.7E-14 100 0 0

.5CL c 0.1 c 0.1 c 0.1 < 0.1 60. 61. < 0.1 c 0.1 6.7E-14 100 0 0

.5a < 0.1 c 0.1 <01 c 0.1 60. 61. c 0.1 < 0.1 6.7E-14 100 0 0 OTHERS < 0.1 < 0.1 < 0.'1 < 0.1 60. 60. < 0.1 c 0.1 O.DE+00 0 0 0 t

• FOR CONTROLLER/OBSERVER USE ONLY*

(Not to be Provided to Players):

Current Stability Class E Primary Release Pt: PS Flow: 2.1E+0 m3/sec Release Concentration-GIP (uCi/cc): 1.4E-05 4.4E-10 4.3E-09 (Flow 6 Release Integrated 6 Averaged over previous 15 minutes)

Whole Body Dose Projection: < 0.1 mRem/hr Thyroid Dose Projection: < 0.1 mRem/hr at a distance of: 1.20 miles downwind Maximums and Projections do not include plant shine or ground shine Maximum Plume Whole-Body Dose Rate: < 0.1 mRem/hr at a distance of: 1.18 miles downwind Maximum Thyroid Dose Commitment: < 0.1 mRem/hr at a distance of: 3.23 miles downwind

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. f OFFSITE SURVEY AND SAMPLING DATA (T = 04:15) ( 07:15)

HON I TOR READINGS AIR SAHPLES 15-adn RAD DATA <<CONTROLLER INFO (10 CF)

F IELD CLOSED MINDOM OPEN MINDOM bare fliter- change contaa I o131 SRD percent HONITOR uaist ground uaist ground absorb absorb in SRD cpn/ conco dose contr ib POINT (aN/hr) (aN/hr) (aN/hr) (aN/hr) CPH CPH aN 1 00cm2 uCf/cc Pie Pit Grd Air Sample gackground is 60 CPH

.SF 1.3 1.3 2.2 2.2 62. 63. 0.3 < 0.1 1.7Eo10 100 0 0

.5E 2.8 2.8 4.6 4.6 64. 66. ~ 0.7 < 0.1 3.5Eo10 100 0 0

.5D 5.0 5.0 8.3 8.3 67. 70. 1.3 < 0.1 6.2Eo10 100 0 0

.SC 7.1 7.1 12. 12. 69. 74. 1.8 < 0.1 B.BEo10 100 0 0

.58 7.4 7.4 12. 12. 70. 75. 1.8 c 0.1 9.2Eo10 100 0 0

.5A 7.5 7.5 13. 13. 75 ~ 1.9 < 0.1 9.4Eo10 100 0 0

.5CL 7.6 7.6 13. 13. 75. 1.9 < 0.1 9.4Eo10 100 0 0

.Sa 75 7.5 13. 13. 75. 1.9 c 0.1 9.4Eo10 100 0 0

.Sb 7.4 7.4 12. 12. 75 o 1.8 c 0.1 9.2Eo10 100 0 0

.5c 7.1 7.1 12. 12. 69. 74. 1.8 c 0.1 B.BEo10 100 0 0

.5d 5.0 5.0 8.3 8.3 67, 70 1.3 c 0.1 6.2Eo10 100 0 0

.5e 2.8 2.8 4.6 4.6 64. 66. 0.7 < 0.1 3.5Eo10 100 0 0

.5f 1.3 1.3 2.2 2.2 62. 63. 0.3 c 0.1 1.7Eo10 100 0 0 1F 1E OA 0.9 '.9 oo OA o

0.7 1.5 0.7 1.5 61.

61.

o oo 61, 62.

0.1 0.2 o o

< 0.1 c 0.1 o

S.DEo11 1.1Eo10 o

100 100 o

0 0

0 0

oo o 1D 1.9 1.9 3.1 3.1 62. 64. 0.5 c 0.1 2.4Eo10 100 0 0 1C 3.2 3.2 5.3 5.3 64. 67. 0.8 c 0.1 4.0Eo10 100 0 0 18 3.5 3.5 5.8 5.8 65 ~ 68. 0.9 < 0.1 4.3E 10 100 0 0 1A 3.7 3.7 6.1 6.1 65. 68. 0.9 < 0.1 4.6Eo10 100 0 0 1a 3.7 '.7 6.1 6.1 65, 68. 0.9 c 0.1 4.6Eo10 100 0 0 OTHERS c 0.1 c D.1 c 0.1 c 0.1 60. 60. c 0.1 c 0.1 O.DE+00 0 0 D CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. f OFFSITE SURVEY AND SAMPLING DATA (T = 04:15) ( 07:15)

(continued)

• FOR CONTROLLER/OBSERVER USE ONLY*

(Not to be Provided to Players):

Current Stability Class E Primary Release Pt: PS Flow: 2.1E+0 m3/sec Release Concentration-GIP (uCi/cc): 4.5E-02 1.9E-05 9.1E-06 (Flow & Release Integrated & Averaged over previous 15 minutes)

Whole Body Dose Projection: 1.8 mRem/hr Thyroid Dose Projection: 0.7 mRem/hr at a distance of: 1.20 miles downwind Maximums and Projections do not include plant shine or ground shine Maximum Plume Whole-Body Dose Rate: 1.9 mRem/hr at a distance of: 1.20 miles downwind Maximum Thyroid Dose Commitment: 0.7 mRem/hr at a distance of: 1.20 miles downwind

NNP-2 Nuclear Generating Station ~ Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. g OFFSITE SURVEY AND SAMPLING DATA 04:30) ( 07:30)

HONI TOR READ lNGS ATR SAHPLES 15.sin RAD DATA <<CONTROLLER lNFD<<

(10 CF)

F lELD CLOSED MlNDNI OPEN MTNDOI bare filter- cont%I l-131 SRO percent HONlTOR mist gr ound mist ground absorb absorb in SRO cps/ conc dose contrib POlNT (aN/hr) (aN/hr) (aN/hr) (aN/hr) CPH CPH aN 100 cm2 uCi/cc Pie Plt Grd Air Sample Background is 60 CPH 5F 4.1 4.1 6.9 6.9 64. 67. 1.0 <<0.1 4.1E-10 100 0 0

.5E 8.5 B.S 14. 14. 69. 74. 2.1 <<0.1 B.SE-10 100 0 0 LSD 15. 15. 26. 26. 76. 86. 3.8 <<0.1 1.5E-09 100 0 0

.SC 22 0 22 e 36 36. 83. 96. 5.5 0.1 2.2E-09 100 0 0

.58 23. 23 0 38. 38. 83. 98. 5.7 0.1 2.3E.09 100 0 0

.5A 23. 23. 39. 39. 84. 99. 5.8 0.1 2.3E.09 100 0 0

.5CL 23. 23. 39. 39. 84. 99. 5.8 0.1 2.3E-09 100 0 0

.5a 23. 23. 39. 39 84. 99. 5.8 0.1 2.3E-09 100 0 0

.5b 23o 23e 38. 38. 83. 98. 5.7 0.1 2.3E.09 100 0 0

.5c 22. 22. 36. 36. 83. 96. 5.5 0. t 2.2E-09 100 0 0

.Sci 15. 15. 26. 26 76. 86. 3.8 0.1 1.5E-09 100 0 0

.58 8.5 8.5 14. 14 69. 74. 2.1 0.1 8.5E-10 100 0 0

.5f 4.1 4.1 6.9 6.9 64. 67. 1.0 0.1 4.1E-10 100 0 0 1F 1.2 1.2 2.1 2.1 61. 62. 0.3 0.1 1.2E-10 100 0 0 1E 2.8 2.8 4.7 4.7 63. 65. 0.7 0.1 2.8E-10 100 0 0 1D 5.8 , 5.8 9.7 9.7 66. 70. 1.5 <<0.1 5.8E-10 100 0 0 1C 9.8 9.8 16. . 16. 70. 76. 2.5 <<0.1 9.8E-10 100 0 0 18 tt. 1t. 18. 18. 71. 78. 2.7 <<0.'l t.tE-09 'l00 0 0 1A 11. 11. 19. 19. 72. 79. 2.8 <<0.1 1.1E.09 100 0 0 1a 11. 11. 19. 19. 720 790 2.8 <<0.1 1.1E.09 100 0 0 1.5F 0.2 0.2 0.3 0.3 60. 89. <<0.1 <<0.1 2.0E-11 100 0 0 1.5E 0.4 0.4 0.7 0.7 61. 130. <<0.'l <<0.1 5.2E-11 100 0 0 1.5D 0.9 0 9 1.4 1,4 61. 230. 0.2 <<01 1.1E-10 100 0 0 1.5C 1.6 1.6 2.6 2.6 62. 350. 0.4 <<0.1 2.0E-10 1DD 0 0 1.5B 2.D 2.0 3.3 3.3 63. 420. 0.5 0.1 2.6E-10 100 0 0 1.5A 2 1 2.1 3.6 3.6 63. 450. 0.5 0.1 2.9E- 10 100 0 0 1.5a 2.1 2.1 3.6 3.6 63. 450. 0.5 0.1 2.9E-10 100 0 0 1.5b 2.0 2.0 3.3 3.3 63. 420. 0.5 0.1 2.6E-10 100 - 0 0 1.5c 1.6 1.6 2.6 2.6 62. 350. 0.4 <<0.1 2.0E-10 100 0 0 1.5d 0 9 0.9 1.4 1.4 61. 230. 0.2 <<0.1 1 1E-10 100 0 0 1.5e 0.4 0.4 0.7 0.7 61. 130. << 0.1' 0.1 5.2E-11 100 0 0 CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. g OFFSITE SURVEY AND SAMPLING DATA (T = 04:30) ( 07:30)

(continued)

HONITOR READINGS AIR SAHPLES 15-min RAD DATA <<CONTROLLER INFO a

(10 CF)

F IELD CLOSED QINDDM OPEN NINDOM bare f f (ter- change contea I-131 SRD percent HONITOR waist ground wsfst ground absorb absorb in SRD cpm/ cence dose contrib POINT (anR/hr) (sN/hr) (mR/hr) (afl/hr) CPH CPH mR 100 cm2 uCi/cc Pim Plt Grd Afr Saapfe Sackground fs 60 CPH 1.5f 0.2 0.2 0.3 0.3 60. 89. << 0.1 < 0.1 2.0E-11 100 0 0 1CL 3.4 3.4 5.7 5.7 65. 68D 0.9 0.2 4.5E-1D 100 0 0 1b 3.0 3.0 5.1 5.1 64. 620. 0.8 0.2 4.0E-10 100 0 0 1c 2.4 2.4 3.9 3.9 63. 480. 0.6 0.1 3.0E-10 100 0 0 1d 1.3 1.3 2.1 2.1 62. 290. 0.3 < 0.1 1.6E-10 100 0 0 1e 0.6 0.6 1.0 1.0 61. 170. 0.'I < 0.1 7.9E-11 100 0 0 1f < 0.1 < 0.1 c 0.1 c 0.1 60. 69. <01 c 0.1 6.1E-12 100 0 0 1.2F 0.2 0 2 0.4 0.4 60. 110. <01 c 0.1 3.3E-11 100 0 0 1.2E 0.6 0.6 1.0 1.0 61. 170. 0.1 < 0.1 7.9E-11 100 0 0 1.20 1.3 1.3 2.1 2.1 62. 300. 0.3 < 0.1 1.6E-10 100 0 0 1.2C 2.2 2.2 3.7 3.7 63. 470. 0.6 0.1 2.9E-10 100 0 0 1.28 2.6 2.6 4.3 4.3 64. 530. 0.6 0.1 3.4E-10 100 0 0 1.2A .2.8 2.8 4.6 4.6 64. 560. 0.7 0.1 3.6E-10 100 0 0 1.2CL 2.8 2.8 4.7 4.7 64. 570. 0.7 0.2 3.7E-10 100 0 0 1.2a 2.8 2.8 4.6 4.6 64. 560. 0,7 0.1 3.6E-10 100 0 0 1.2b 2.6 2.6 4.3 4.3 64. 530. 0.6 0.1 3.4E<<10 100 0 0 1.2c 2.2 2.2 3.7 3,7 63. 470. 0.6 0.1 2.9E-10 100 0 0 1.2d 'I.3 1.3 2.1 2,1 62. 300. 0.3 c 0.1 1.6E-10 100 0 0 1.2e 0.6 0.6 1.0 1.0 61. 170. 0.1 < 0.1 7.9E-11 100 0 0 1.2f 0.2 0.2 0.4 0.4 60. 110. < 0.1 c 0.1 3.3E-11 100 0 0 OTHERS c 0.1 c 0.1 c 0.1 c 0.1 60. 60. < 0.1 c 0.1 O.DE+00 0 0 0

'a CONTINUED ON NEXT PAGE 1

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2 ~ g OFFSITE SURVEY AND SAMPLING DATA (T = 04:30) ( 07:30)

(continued)

• FOR CONTROLLER/OBSERVER USE ONLY*

(Not to be Provided to Players):

Current Stability Class E Primary Release Pt: PS Flow: 2.1E+0 m3/sec Release Concentration-GIP (uCi/cc): 1.4E-01 4.7E-05 2.5E-05 (Flow & Release Integrated & Averaged over previous 15 minutes)

Whole Body Dose Projection: 5.6 mRem/hr Thyroid Dose Projection: 1.7 mRem/hr at a distance of: 1.20 miles downwind Maximums and Projections do not include plant shine or ground shine Maximum Plume Whole-Body Dose Rate: 6.0 mRem/hr at a distance of: 1.20 miles downwind Maximum Thyroid Dose Commitment: 1.9 mRem/hr at a distance of: 1.20 miles downwind

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. h OFFSITE SURVEY AND SAMPLING DATA (T = 04:45) ( 07:45)

HONITOR READINGS AIR SAHPLES 15-min RAD DATA iCONTROLLER INFO (10 CF)

FIELD'LOSED NINDOM OPEN QINDOM bare fliter- change contam 1-131 SRD percent HONITOR mist ground mist ground absorb absorb in SRD cpa/ cones dose contrib POINT (sR/hr) (mR/hr) (mR/hr) (mR/hr) CPH CPH mR 100cm2 uCi/cc Plm Plt Grd Air Sample Background is 60 CPH

.SF 4.6 4.6 7.6 7.6 64. 66. 1.1 < 0.1 3.9E-10 100 0 0

.5E 9A 9.4 16. 16. 68. 73. 2A < 0.1 B.OE-'l0 100 0 0

.5D 17. 17. 28. 28. 75. 84. 4.2 < 0.1 1.4E-09 100 0 0

~ SC 24. 24. 40. 40. 81. 94. 6.0 < 0.1 2.0E.09 100 0 0

.58 25 ~ 25. 42. 42. 81. 96. 6.3 < 0.1 2.1E.09 100 0 0

.SA 26. 26. 43. 43. 82. 96. 6.4 <01 2.2E 09 100 0 0

.5CL 26. 26. 43. Q. 82. 97. 6A < 0.1 2.2E-09 100 0 0

.5a 26. 26 43. Q. 82. 96. 6A < 0.1 2.2E-09 100 0 0

.Sb 25 0 25. 42. 42. 81. 96. 6.3 < 0.1 2.1E-09 100 0 0

.Sc 24. 24. 40. 40. 81. 94. 6.0 < 0.1 2.0E-09 100 0 0

.Sd 17. 17. 28. 28. 75. 84. 4.2 < 0.1 1.4E.09 100 0 0

.5e 9.4 9.4 16. 16. 68. 75. 2.4 < 0.1 B.OE-10 100 0 0

.Sf 4.6 4.6 7.6 7.6 64. 66. 1 1 <0.1 3.9E-10 100 0 0 1F 1A 1.4 2.3 2.3 61. 62. 0.3 < 0.1 1.2E-10 100 0 0 1E 3.1 3.1 5.2 5.2 63. 64. 0.8 < 0.1 2.6E-10 100 0 0 1D 6 C 6A 11 11. 66. 69. 1.6 < 0.1 5.4E-10 '100 0 0 1C 11. 11. 18. 18. 69. 2.7 < 0.1 9.2E-10 100 0 0 18 12. 12. 20. 20+ 70. 3.0 < 0.1 1.0E 09 100 0 0 1A 12. 12. 21. 21- 71. 3.1 < 0.1 1.1E.09 100 0 0 1a 12. 12. 21. 21. 71. 3.1 < 0.1 1.1E 09 100 0 0 1.5F 0.5 0.5 0.8 0.8 61 140. 01 <0.1 S.OE-11 99 0 0 1.5E 1.2 1.2 2.1 2.1 61 260. 0.3 < 0.1 1.3E-10 99 0 0 1.5D 2.7 2.7 4.5 4.5 63. 510. 0.7 0.1 2.9E-10 99 0 0 1.5C 4.8 4.8 8.1 8,1 65. 870. 1.2 0.2 5.2E-10 99 0 0 1.58 6.2 6.2 10. 10. 67. 1100. 1.5 0.3 6.4E 10 99 0 0 1.5A 6.6 6.6 11. 11. 67. 1200. 1.7 0.3 7.0E-10 99 0 0 1.5CL 2.0 2.0 3A 3.4 63. 660. 0.5 0.2 2.8E-10 100 0 0 1.5a 6.6 6.6 11 11. 67. 1200. 1.7 0.3 7.0E-10 99 0 0 1.5b 6.2 6.2 10. 10. 67. 1100. 1.5 0.3 6.4E-10 99 0 0 1.5c C.B C.B 8.1 8.1 65 870. 1.2 0.2 5.2E-10 99 0 0 1.5d 2.7 2.7 4.5 4.S 63. 510. 0.7 0.1 2.9E-10 99 0 0 CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2 ~ h OFFSITE SURVEY AND SAMPLING DATA (T = 04:45) ( 07:45)

(continued)

HOHITOR READINGS AIR SAMPLES 15-min RAD DATA *CONTROLLER INFO (10 CF)

FIELD CLOSED HIMDOH OPEN MIMDOM bare f I Lter- change contam l-131 SRD percent MONITOR us i st ground uaist ground absorb absorb in SRD cpm/ conc. dose contrib POINT <aN/hr) (mR/hr) <aN/hr) (aR/hr) CPM CPH aN 100cm2 uCI/cc Pim Pit Grd 0

Air SnapLe Background is 60 CPM 1.5e 1.2 1.2 2.1 61. 260. 0.3 < 0.1 1.3E-10 99 D 0 1.5f 0.5 0.5 0.8 61. 140. 0.1 < 0.1 5.0E 11 99 0 0 2F < 0.1 < 0.1 0.1 60. BZ. < 0.1 c 0.1 1.0E-11 100 0 0 2E 0.2 0.2 0.4 60. 120. < 0.1 < 0.1 2.9E-11 100 0 0 2D 0.5 0.5 0.8 0.8 61. 200. 0.1 < 0.1 6.7E-11 100 0 0 2C 1.0 1.0 1.6 1.6 61. 340. , 0.2 < 0.1 1.3E-10 100 0 0 28 1.3 1.3 2.1 2.1 62. 430. 0.3 0 1 1.8E 10 100 0 0 2A 1.5 1.5 2.4 2.4 62. 480. 0.4 0.1 Z.OE-10 100 0 0

~ 2CL 1.5 1.5 2.5 2.5 62. 490. 0.4 0.1 2.1E-10 100 0 0 2a 1.5 1.5 2.4 2.4 62. 480. 0.4 0.1 Z.OE-10 100 0 0 2b 1.3 1 3 2.1 2.1 62. 430. 0.3 0.1 1.8E-10 100 0 0 2c 1.0 1.0 1.6 1.6 61 340. 0.2 < 0.1 1.3E-10 100 0 0 2d 0.5 0.5 0.8 0.8 61. 200. 0+1 < 0.1 6.7E-'l1 100 0 0 2e 0.2 0.2 0.4 0.4 60. 120. < 0.1 <01 2.9E-11 100 0 0 2f <<0.1 c 0.1 0.1 0.1 60. 82. < 0.1 <01 1.0E-'l1 100 0 0 1CL 11 11. 18. 18. 71. 1700. 2.6 0.5 1.1E.09 99 0 0 1b 9.2 9.2 15. 16. 70o 1600. 2.3 OA 9.9E-10 99 0 0 1c 7.0 7.0 12. 12. 68. 1200. 1.8 0.3 7.7E-10 99 0 0 1d 3.9 3.9 6.6 6.6 64. ?10. 1 0 0.2 4.2E-10 99 0 0 1e 1.8 1.8 3,1 3.1 62. 360. 0.5 c 0.1 2.0E-10 99 0 0 1f 0.1 0.1 0.2 0.2 84. c 0.1 < 0.1 1.5E-11 99 0 0 1.2F 0.7 0.7 1.3 1.3 61. 180. 0.2 < 0.1 8.1E-11 99 0 0 1.2E 1.9 1.9 3.2 3.2 380. 0.5 < 0.1 2.0E-10 99 0 0 1.2D 3.9 3.9 6.6 6.6 710. 1.0 0.2 4.2E-10 99 0 0 1.2C 7.0 7.D 12. 12 67. 1200. 1.8 0.3 7.3E-10 99 0 0 1.28 7.9 7 9 13. 'l3. 1400. 2.0 OA 8.4E-10 99 0 0 1.2A e.4 8.I 14. 14. 69. 1500. 2.1 OA 8.9E-10 99 0 0 1.2CL 8.8 8.8 15. 15. 1500. 2.2 0.4 9.2E-10 99 0 0 1.2a 8.4 8.4 14. 14. 69. 1500. 2.1 DA 8 9E-10 99 0 0 1.2b 7.9 7.9 13. 13. 68. 1400. 2.0 0.4 8AE-10 99 0 0 CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. h OFFSITE SURVEY AND SAMPLING DATA (T = 04 45) ( 07:45)

(continued)

HONITOR READINGS AIR SANPLES 15-min RAD DATA <<CONTROLLER INFO (10 CF)

FIELD CLOSED IJIND(Q OPEN NINOON bare f I l ter- change contra I-131 . SRD percent NON I TOR mist ground us 1 st ground absorb absorb in SRD cpm/ cones dose contrib POI NT (mR/hr) (mR/hr) (aR/hr) (aR/hr) CPN CPN IR 1 00cm2 uCI/cc Pim Pit Drd Air Sample Background is 60 CPN

'1.2c 7.0 7.0 12. 12. 67. 1200. 1.8 0.3 7.3E-10 99 0 0 1.2d 3.9 3.9 6.6 6.6 64. 710. 1.'0 0.2 4.2E-10 99 0 0 1 2e 1.9 1.9 3.2 3.2 62. 380. 0.5 c 0.1 2.0E-10 99 0 0 1.2f 0.7 0.7 1.3 1.3 6'I. 180. 0.2 c 0.1 8.1E-11 99 0 0 OTHERS < 0.1 + 0.1 c 0.1 < 0.1 60. 60. < 0.1 ~ 0.1 O.DE+00 0 0 0

• FOR CONTROLLER/OBSERVER USE ONLY*

(Not to be Provided to Players):

Current Stability Class E Primary Release Pt: PS Flow: 2.1E+0 m3/sec Release Concentration-GIP (uCi/cc): 1.6E-01 4.3E-05 2.4E-05 (Flow & Release Integrated & Averaged over previous 15 minutes)

Whole Body Dose Projection: 6.2 mRem/hr Thyroid Dose Projection: 1.6 mRem/hr at a distance of: 1.20 miles downwind Maximums and Projections do not include plant shine or ground shine Maximum Plume Whole-Body Dose Rate: 6.6 mRem/hr at a distance of: 1.20 miles downwind Maximum Thyroid Dose Commitment: 1.8 mRem/hr at a distance of: 1.18 miles downwind

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2 ~ i OFFSITE SURVEY AND SAMPLING DATA 05:00) ( 08:00)

HOKfTOR READ I NGS AIR SAHPLES 15 min RAD DATA <<CONTROLLER INFO (10 CF)

FIELD CLOSED NINDON OPEN llINDOM bare fflter. con'tam I-131 SRD percent HOKITOR waist ground wsfst ground absorb absorb in SRD cpm/ cence dose contrib POIKT (mR/hr) (mR/hr) (mR/hr) (mR/hr) CPH CPH mR 100cm2 uCi/cc Pfm Plt Grd Air Sample Background fs 60 CPH

.SF 4.3 4.3 7.2 7.2 63. 65. 1.1 < 0.1 2.9E-10 99 0 0

.5E 8.9 8.9 'IS. 15. 66. 70. 2.2 < 0.1 5.9E-10 99 0 0

.50 16. 16. 27. 27. 71. 79. 4.0 < 0.1 1.1E.09 99 0 0

.SC 23. 23. 38. 38. 75. 86. 5 7 < 0.1 1.5E-09 99 0 0

.58 24. 24. 39. 40. 76. 87. 5.9 <<0.1 1.6E-09 99 0 0

.5A 24. 24. 40. 40. 76. 88. 6.0 < 0.1 1.6E.09 99 0 0

.SCL 24. 24. 41. 41 76 88. 6.1 < 0.1 1.6E-09 99 0 0

.5a 24. 24. 40. 40. lb. 88. 6.0 <<0.1 1.6E-09 99 0 0

.Sb 24. 24 39 4D. 76. 87. 5.9 < 0.1 1.6E 09 99 0 0

.5c 23. 23 ~ 38. 38. 86. 5.7 < 0.1 1.5E.09 99 0 0

.5d 16. 16. 27. 27. 71. 79. 4.0 < 0.1 1.1E.09 99 0 0

.Se 8.9 8.9 15. 15. 66. 70. 2.2 < 0.1 5.9E-10 99 0 0 .

.5f 4.3 4.3 7.2 7.2 Q. 65. < 0.1 2.9E-10 99 0 0 1F 1.3 1.3 2.2 2.2 61. 61. 0.3 < 0.1 8.6E-11 99 0 0 1E 2.9 2.9 4.9 4.9 62. 63. 0.7 < 0.1 2.0E-10 99 0 0 1D 6.0 6.0 10. 10. 64. 67. 1.5 < 0.1 4.0E-10 99 0 0 1C 10. 10. 17. 17. 67. 72. 2.6 < 0.1 6.8E-10 99 0 0 18 11 11. 19. 19. 67. 73. 2.8 < 0.1 7.4E-10 99 0 0 1A 12. 12. 20. 20. 68. 74. 2.9 < 0.1 7.8E-10 99 0 0 1a 12. 12. 20. 20. 68. 74. 2.9 < 0.1 7.8E-10 99 0 0 1.5F 0.5 0.5 0.9 0.9 60. 140. 0.1 < 0.1 4.7E-11 99 0 0 1.5E 1.4 1.4 2.3 2.3 61. 260. 0.3 < 0.1 1.2E-10 99 0 0 1.5D 3.0 3.0 5.0 5.1 Q. 480. 0.8 0.1 2.7E-10 99 0 0 1.5C 5.6 5.6 94 9.5 65. 840. 1.4 0.2 4.8E-10 99 0 0 1.5B 6.9 6.9 12. 12. 66. 1000. 1.7 0.3 6.0E-10 99 0 0 1.5A 7.3 7.3 .12. 12. 67. 1100. 1.8 0.3 6.5E-10 99 0 1.5CL 6.4 64 , 11. 11. 67. 1700. 1.6 0.5 7.0E-10 99 0 1.5a 7.3 7.3 12. 12. 67. 1100. 1.8 0.3 6.5E-10 99 0 1.5b 6.9 6.9 12. 12. 66. 1000. 1.7 0.3 6.0E.10 99 0 1.5c 5.6 5.6 94 9.5 65. 840. 1,4 0.2 4.8E-10 99 0 1.5d 3.0 3.0 5.0 5.1 Q. 480. 0.8 0.1 2.7E-10 99 0 0 CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2.

OFFSITE SURVEY AND SAMPLING DATA (T = 05:00) ( 08:00)

(continued)

MONITOR READINGS AIR SANPLES 15.mfn RAD DATA <<CONTROLLER INFO (10 CF)

FIELD CLOSED lfINDOM OPEN llINDOM bare f liter- change contaa 1-131 SRD percent NONITOR wafst ground uafst ground absorb absorb in SRD cpa/ conc+ dose contr lb POINT (eR/hr) (sN/hr) (aR/hr) (sk/hr) CPN CPN sk 100 cm2 uCI/cc Pla Plt Grd Air Sanple Background is 60 CPN 1.5e 1.4 1.4 2.3 2.3 61. 260. 0.3 < 0.1 1.2E-10 99 0 0 1.5f 0.5 0.5 0.9 0.9 60. 140. 0.1 < 0.1 4.7E-11 99 0 0 2F 0.2 0.2 0.4 0.4 60. 120. <<0.1 < 0.1 2.6E-11 99 0 0 2E 0.6 0.6 1.1 1.1 61. 220. 0.2 < 0.1 7.2E-11 99 0 0 2D 1.5 1.5 2.5 2.5 62. 460. 0.4 0.1 1.7E 10 0 0 2C 3.0 3.0 5.0 5.0 63. 820. D.7 0.2 3.3E.10 0 0 28 4.0 4.0 6.7 6.7 64. 1100. 1.0 0.3 4.4E-10 0 0 2A 4.3 4.3 7.2 7.2 65. 1200. 1.1 0.3 4.88-10 0 0 2CL 4.7 4.7 7.9 8.0 65. 1300. 1.2 0.3 5.1E-10 0 0 2a 4.3 4.3 7.2 7.2 65. 1200. 1.1 0.3 4.8E-10 0 0 2b 4.0 4.0 6.7 6.7 64. 1100. 1.0 0.3 4.4E-10 0 0 2c 3.0 3.0 5.0 5.0 63. 820. 0.7 0.2 3.3E-10 D D 2d 1.5 1.5 2.5 2.5 62. 460. 0.4 0.1 1.7E-10 0 0 2e 0.6 0.6 1.1 1.1 61. 22D. 0.2 < 0.1 7.2E-11 0 0 2f 0.2 0.2 0.4 0.4 60. 120. < 0.1 < 0.1' 2.6E-11 99 0 0 2.5F << 0.1 << 0.1 < 0.1 < 0.1 60. 75. < 0.1 0.1 5.8E-12 100 0 0 2.5E 0.1 0.1 0.2 0.2 60. 100. < 0.1 <01 1.8E-11 100 0 0 2.5D 0.3 0.3 0.5 0.5 60. 170. < 0.1 < 0.1 4.4E-11 100 0 0 2.5C 0.6 0.6 1.1 1,1 61. 280. 0.2 <<0.1 8.8E-11 100 0 0 2.5B 0.9 0.9 1.5 1.5 61. 390. 0.2 < 0.1 1.3E-10 100 0 0 2.5A 1.0 1.0 1.7 1.7 61. 430. 0.3 0.1 1.4E-10 100 0 0 2.5CL 1.1 1.1 1.8 1.8 62. 450. 0.3 0.1 1.6E-10 100 0 0 2.5a 1.0 1.0 1.7 1.7 61. 430. 0;3 01 1 4E-10 100 0 0 2.5b 0.9 0.9 '1.5 1.5 61 390. 0.2 < 0.1 1.3E-10 100 0 0 2.5c 0.6 0.6 1.1 1.1 61. 280. 0.2 <<0.1 8.8E-11 100 0 0 2.5d 0.3 0.3 0.5 0.5 60. 170. < 0.1 < 0.1 4.4E-11 100 0 0 2.5e 0.1 0.1 0.2 0.2 60. 100. < 0.1 <<01 1.8E-11 100 0 0 2.5f 0.1 < 0.1 < 0.1 < 0.1 60. 75. < 0.1 < 0.1 5.8E-12 100 0 0 1CL 12. 12. 19. 20. 70. 1700. 2.9 0.5 1.0E 09 99 0 0 1b 10. 10. 17. 17. 69. 1500. 2.6 0.4 9.2E-10 99 0 0 CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. i OFFSITE SURVEY AND SAMPLING DATA (T = 05:00) ( 08:00)

(continued)

HONITOR READINGS AIR SAHPLES 15-win RAD DATA *CONTROLLER INFO (10 CF)

F IELD CLOSED MINDOM OPEN MINDOM bare fliter- change contaa I-131 SRD percent HONITOR uaist ground wafst ground absorb absorb in SRD cpa/ conc. dose contrib P01NT (sfI/hr) (sfI/hr) (sfI/hr) (sR/hr) CPH CPH aR 100cmZ uCI/cc Plm Pit Grd Air Saeple Background is 60 CPH 1c 8.2 8.2 14. 14. 67. 1200. 2 0 0.3 7.1E.10 99 0 0 1d 4.3 4.3 7.2 7.3 64, 680. 1.1 0.2 3.8E-10 99 0 0 1e 2.1 2.1 3.5 3.5 ~ 62. 350. 0.5 < 0.1 1.8E-10 99 0 0 1f 0.2 0.2 0.3 0.3 60. 83. < 0.1 < 0.1 1 4E-11 99 0 0 1.2F 0.9 0.9 1.4 1.5 61. 180. 0.2 < 0.1 7.5E-11 99 0 0 1.2E 2.1 2 1 3.5 3.6 62. 360. 0.5 < 0.1 1.8E.10 99 0 0 1.20 4.3 4.3 7.2 7.3 64 ~ 680. 1.1 0.2 3.8E-10 99 0 0 1.2C 7.7 7.7 13. 13. 67. 1100. 1.9 0.3 6.8E-10 99 0 0 1.28 9.0 9.0 15. 15. 68. 1300. 2.3 0.4 7.8E-10 99 0 0 1.2A 9.5 9.5 16. 16. 68. 1400. 2.4 0.4 8.4E-10 99 0 0 1.2CL 9.5 9.5 16. 16. 68. 1400. 2.4 0.4 8.5E-10 99 0 0 1.2a 9.5 9.5 16. 16. 68. 1400. 2.4 0.4 8.4E-10 99 0 0 1.2b 9.0 9.0 15. 15. 6$ . 1300. 2.3 0.4 7.8E.10 99 0 0 1.2c 7.7 7.7 13. 13. 67. 1100. 1.9 0.3 6.8E-10 99 0 0 1.2d 4.3 4.3 7.2 7.3 64. 680. 1.1 0.2 3.8E-10 99 0 0 1.2e 2.1 2.1 3.5 3.6 62, 360. 0.5 < 0.1 1.8E-10 99 0 0 1.2f 0.9 0.9 1.4 1.5 61. 180. 0.2 < 0.1 7.5E.11 99 0 0 OTHERS < 0.1 < 0.1 < 0.1 < 0.1 60. 60. < 0.1 < 0.1 O.DE+00 0 0 0 CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2.

OFFSITE SURVEY AND SAMPLING DATA i

(T = 05-00) ( 08:00) 0 (continued)

• FOR CONTROLLER/OBSERVER USE ONLY*

(Not to be Provided to Players):

Current Stability Class E Primary Release Pt: PS Flow: 2.1E+0 m3/sec Release Concentration-GIP (uCi/cc): 1.6E-01 3.1E-05 2.1E-05 (Flow & Release Integrated & Averaged over previous 15 minutes)

Whole Body Dose Projection: 5.9 mRem/hr Thyroid Dose Projection: 1.2 mRem/hr at a distance of: 1.20 miles downwind Maximums and Projections do not include plant shine or ground shine Maximum Plume Whole-Body Dose Rate: 6.2 mRem/hr at a distance of: 1.20 miles downwind Maximum Thyroid Dose Commitment: 1.7 mRem/hr at a distance of: 1.18 miles downwind

NNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 r TABLE E3. f ENVIRONMENTAL SAMPLING DATA (T = 05 00) ( 08:00)

OFFSITE LEAFY GROUND MONITORING VEGETATION DEPOSITION LOCATION iodine total (pCi/kg) (pCi/kg) (cpm/100cm2)

.5F 4600. 4800. 0.4

.5E 9600 9900. 0.9

.5D '.7E4 1 'E4 1.6

.5C 2.4E4 2.5E4 2~2

~ 5B 2.5E4 2.6E4 2.3

.5A 2.6E4 2.6E4 2.3

.5CL 2.6E4 2.7E4 2.4

.5a 2.6E4 2.6E4 2 '

.Sb 2.5E4 2 'E4 2.3

.5c 2 'E4 2.5E4 2'

~ 5d 1.7E4 1 'E4 1.6

.5e 9600 9900. 0.9

~ 5f '600.

4800. 0.4 1F 1400. 1400. 0' 1E i 3200. 3300. 0.3 1D 6700 6900. 0.6 1C 1.1E4 1.1E4 1.0 1B 1.2E4 1.2E4 1.1 1A 1.3E4 1.3E4 1.2 1a 1 3E4 1.3E4 1'

1. 5F 340. 3300. 0.3 1.5E 890. 8500. 0.8 1.5D 1900. 1 'E4 1.6 1.5C 3500. 3.4E4 3.0 1.5B 4500. 4.2E4 3.8

1. SA 4800. 4.6E4 4.1 1 5CL 1400. 1.9E4 1-7 1.5a 4800. 4.6E4 4.1 1.5b 4500. 4.2E4 3.8 1.5c 3500 3.4E4 3.0 1 5d 1900 1.9E4 1.6

1. 5e 890 8500 0.8

1. 5f 340. 3300 0.3 2F 50. 700. 0.1 2E 140 2000 0 2 2D 320. 4600 0.4 2C 650. 8900 0.8 2B 850 1.2E4 1 .1 2A 950 1.3E4 1.2 2CL 1000 1."4E4 1' CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E3 ~ g ENVIRONMENTAL SAMPLING DATA (T = 05:00) ( 08:00)

(continued)

OFFSZTE LEAFY GROUND MONITORING VEGETATION - DEPOSITION LOCATION iodine total (pCi/kg) (pCi/kg) (cpm/100cm2) 2a 950. 1. 3E4 1 2 2h 850. 1.2E4 1 1 2c 650. 8900. 0.8 2d 320 4600 0.4 2e 140. 2000. 0 2 2f 50. 700. 0 1 2 5E 0 1 0.4 0 1 2 5D 0' 1.2 0.1 2.5C 0.6 2.7 0~1 2 5B 1.4 4.5 0 1 2 'A 2.4 6.0 0.1 2.5CL 2.9 6.5 0.1 2.5a 2.4 6.0 0.1 2.5h 1.4 4.5 0 1 2.5c 0.6 2' 0.1 2.5d 0.2 1.2 0.1 2.5e 0.1 0.4 0 1 3D 0 1 0.2 0.1 3C 0.5 0.5 0~1 3B 1.2 1.3 0~1 3A 2 ' 2 1 0~1 3CL 2' 2.5 0.1 3a 2' 2.1 0-1 3h 1.2 1.3 0.1 3c 0.5 0.5 0.1 3d 0 1 0.2 0.1 4D 0.1 0.1 0.1 4C 0.4 0.4 0.1 4B 1.0 1 1 0' 4A 1.7 2.0 0.1 4CL 2-1 2.4 0.1 4a 1.7 2.0 0 1 4b 1.0 1.1 0 4c 0.4 0.4 0~1 4d 0' 0~1 0~1 4.5C 0.2 0.2 0-1 4 SB 0.5 0.6 0.1 4 'A 1.0 1 1 0.1 4.5CL 1' 1.4 0.1 4.5a 1.0 1.1 0~1 CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E3. g ENVIRONMENTAL SAMPLING DATA (T = 05:00) ( 08:00)

(continued)

OFFSZTE LEAFY GROUND MONITORING VEGETATION DEPOSITION LOCATION iodine total (pCi/kg) (pCi/kg) (cpm/100cm2) 4 5b 0' 0.6 F 1 4.5c 0.2 0.2 < 0.1 5B 0.2 0.2 < 0.1 SA 0.3 0.4 0.1 5CL 0.4 0.4 F 1 Sa 0.3 0.4 0.1 5b 0' 0.2 0.1 1CL 7600. 7 'E4 6.3 lb 6600. 6 'E4 5.7 lc 5200. 5.0E4 4 '

ld 2800. 2 'E4 2.4 le 1400 1.3E4 1.1 1.2F lf 100.

550.

990.

5300.

< 0.1 0.5 1.2E 1400. 1.3E4 1.2 1.2D 2800. 2 'E4 2.4 1.2C 4900. 4 'E4 4.1 1.2B 5600. 5 'E4 4.8 1 2A 6200. 5 'E4 5.1

1. 2CL 6200. 6 OE4 5.3 1 2a 6200 5.7E4 5.1 1.2b '600.

5 'E4 4.8 1 ~ 2c 4900. 4.7E4 4.1 1.2d 2800. 2.7E4 2.4 1 ~ 2e 1400 1.3E4 1.2 1.2f 550. 5300. 0.5 OTHER SAMPLES LESS THAN MDA

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. j OFFSZTE SURVEY AND SAMPLING DATA 05:30) ( 08:30)

HONlTOR READlNGS AlR SAHPLES 15-min RAD DATA <<CONTROLLER lNFO (10 CF)

FIELD CLOSED M1NDOM OPEN NNDQI bare fi lter- change "contm l-131 SRD percent HONlTOR wist ground mist ground absorb absorb in SRD cpm/ . conc+ dose contrib POl NT (mR/hr) (mR/hr) (mR/hr) (mR/hr) CPH CPH mR 100cm2 uCf/cc Plm Pit Grd r Air Sample Background is 60 CPH SF 3.8 3.8 6.5 6.5 62 63. 1.0 c 0.1 1.6E-10 99 0 0

~ 5E 7.9 7.9 13. 13. 63. 66. 2.0 < 0.1 3.3E-10 99 0 0

.5D 14. 14. 24. 24. 66, 71 3.6 < 0.1 5.9E-10 99 0 0

.SC 20. 20. 34. 34. 68. 76. 5.1 c 0.1 8.3E-10 99 0 0

.SB 21. 21. 35. 36. 68. 77 53 < 0.1 8.6E-10 99 0 0

.5A 22 0 22 0 36. 36. 68. 77. 5.4 c 0.1 B.BE-10 99 0 0

~ SCL 22 0 22 0 36. 36. 69. 77. 5.4 c 0.1 8.9E-10 99 0 0

.5a 22 0 22 0 36. 36. 68. 770 5.4 c 0.1 B.BE-10 99 0 0

.5b 21. 21. 35. 36. 68. 770 5.3 c 0.1 8.6E-'f0 99 0 0

.Sc 20. 20. 34. 34. 68. 76. 5.1 c 0.1 8.3E-10 99 0 0

.Sd 14'4. Z4 24. 66, 71. 3.6 < 0.1 5.9E-10 0 0

.Se 7.9 7.9 13. 13. 63. 66. 2.0 c 0.1 3.2E-10 0 0

.54 3.8 3.8 6.5 6.5 62. 63. 1.0 < 0 1 1 6E-10 0 0 1F 1.2 1.2 1.9 1.9 60. 61. 0.3 c 0.1 4.7E-11 0 0 1E 2.6 2.6 4.4 4.4 61 ~ 62. 0.7 c 0.1 1.1E-10 99 0 0 1D 5.4 , 5.4 9.1 9.1 62. 64. 1.4 c 0.1 2.2E-10 0 0 1C 9.1 9.1 15. 15. 64. 67. 2.3 c 0.1 3.7E-10 0 0 18 10. 10. 17 17. 64. 68. 2.5 c 0.1 4.1E-10 0 0 1A 11. t1. t8. 18. 64. 68. 2.6 c 0.1 4.3E-10 0 0 1a 11. 11. 18. 18. 64. 68. 2.6 < 0.1 4.3E.10 0 0 1.5F 0.5 0.5 0+8 0.8 110. 0.1 < 0.1 2.6E-11 99 0 0 1.5E 1.2 1 2 2.1 2.1 61. 190. 0.3 < 0.1 6.8E 11 99 0 0 1.5D 2.7 2.7 4.6 4.7 61. 360. 0.7 < 0.1 1.5E-10 99 0 0 1.5C 4.9 4.9 8.3 8.5 600. 1.2 0.2 2.6E-10 99 0 0 1.58 6.2 6.2 10. 11. 720. 1.5 0.2 3.4E-10 99 0 0 1 5A 6.6 6.6 11 11. 63. 780. 1.6 0.2 3.5E-10 99 0 1+SCL 6.6 6.6 11. 11. 65. 1400. 1.6 0.4 4.8E-10 99 0 1.5a 6.6 6.6 11. 11. 63. 780. 1.6 0.2 3.5E-10 99 0 1.5b 6.2 6.2 10. 11. 63. 720. 1.5 0.2 3.4E-10 99 0 1.5c 4.9 4.9 8.3 8.5 63. 600. 1 2 0.2 2.6E-10 99 0 1.5d 2.7 2.7 4.6 4.7 61. 360. 0,7 < 0.1 1.5E-10 99 0 0 CONTINUED ON NEXT PAGE

NNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. j OFFSITE SURVEY AND SAMPLING DATA (T = 05:30) ( 08:30)

(continued)

HONI TOR READINGS AIR SAHPLES 15-sin RAD DATA <<CONTROLLER INFO (10 CF)

FIELD CLOSED MINDNI OPEN lltNDON bare filter- change contin '-131 SRD percent HONITOR wrist ground waist ground absorb absorb in SRD cpa/ conc. dose contr lb POINT (aN/hr) (aR/hr) (eR/hr ) (aSI/hr) CPH CPH eR 100aa2 uCI/cc Pla PIt Grd Air Seeple Background is 60 CPH 1.5e 1.2 1.2 2.1 2.1 61. 190. 0.3 < 0.1 6.8E.11 99 0 0 1.5f 0.5 0.5 0.8 0.8 60. 110. 0.1 < 0.1 2.6E-11 99 0 0 2F 0.2 0.2 0.4 0.4 60. 110. < 0.1 < 0.1 1.8E-11 0 0 2E 0.7 0.7 1.2 1.2 60. 200. 0.2 < 0.1 S.OE-11 99 0 0 1.6 1.6 2.8 2.8 61. 370. 0.4 < 0.1 1.2E-10 99 0 0 2C 3.2 3.2 5.3 5.5 62. 670. 0.8 0.2 2.2E-10 99 0 0 2$ 4.1 4.1 6.9 7.1, 63. 880. 1.0 0.2 3.1E-10 99 0 0 4.9 4.9 8.3 8.S 63. 990. 1.2 0.3 3.4E-10 99 0 0 2CL 4.9 4.9 8.3 8.5 63. 1000. 1.2 0.3 3.5E-10 99 0 0 2a 4.9 4.9 8.3 8.5 63. 990. 1.2 0.3 3.4E-10 99 0 0 2b 4.1 4.1 6.9 7.1 63. 880. 1,0 0.2 3 1E-10 99 0 0 2c 3.2 3.2 5.3 5.5 62. 670. 0.8 0.2 2.2E-10 99 0 0 2d 1.6 1.6 2.8 2.8 61. 370. 0.4 < 0.1 1.2E-10 99 0 0 2e 0.7 0.7 1.2 1.2 60. 190. 0.2 < 0.1 S.OE-11 99 0 0 2f 0.2 ~ 0.2 0.4 0.4 60. 110 0.1 < 0.1 1.8E-11 99 0 0 2.5F 0.1 0.1 0.2 0.2 60- 99. 0.1 < 0.1 1.4E 11 99 0 0 2.5E 0.5 0.5 0.8 0.8 60. 180. 0.1 < 0.1 4.1E.11 99 0 0 2.5D 1.1 1.1 1.9 1.9 61. 360. 0.3 < 0.1 1.0E-10 99 0 0 2.5C 2.2 2.2 3.7 3.8 62. 660. 0.6 0.2 2.1E-10 99 0 0 2.5B 3.2 3.2 5.4 5.5 63. 930. 0.8 0.2 2.9E-10 99 0 0 2.5A 3.7 3,7 6.2 6.3 63. 1000. 0.9 0.3 3.4E-10 99 0 0 2.5CL 3.8 3.8 "6 4 6.6 63. 1100. 1.0 0.3 3.5E-10 99 0 0 2.5a 3.7 3.7 6.2 6.3 63. 1000. 0.9 0.3 3.4E-10 99 0 0 2.5b 3.2 3.2 5.4 5.5 63. 930. 0.8 0.2 2.9E-10 99 0 0 2.5c '2.2 2.2 '3.7 3.8 62. 660. 0.6 0.2 2.1E.10 0 0 2.5d 1.1 '1.1 '1 9 '1.9 61. 360. 0.3 < 0.1 1.0E-10 0 0 2.5e 0.5 0.5 0.8 0.8 60. 180. 0.1 < 0.1 4.1E-11 0 0 2.5f 0.1 0.1 0.2 0.2 60. 99. < 0.1 < 0.1 1 4E-11 0 0 3F < 0.1 c 0.1 0.1 0.1 60. 88 <<0.1 < 0.1 9.1E-12 0 0 3E 0.3 0'3 0.4 0.4 60. 150. c 0.1 < 0.1 2.9E-11 99 D 0 CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. j OFFSITE SURVEY AND SAMPLING DATA (T = 05 30) ( 08:30)

" (continued)

HONITOR READINGS AIR SAHPLES 15-nfn RAD DATA ~CONTROLLER INFO (10 CF)

F IELD CLOSED MINDOM OPEN MINDOM bare f f lter- change contaa 1-131 SRD percent HONITOR mist ground usfst ground absorb absorb fn SRD cps/ cence dose contr fb POINT (aN/hr) (sN/hr) (aN/hr) (aN/hr) CPH CPH aN 100cl2 uCf/cc Ple Plt Grd Afr Sample Background fs 60 CPH 30 0.7 0.7 1.1 1.1 61. 300. 0.2 c 0.1 7.6E-11 99 0 0 3C 1A 1A 2A ZA 62. 550. 0.3 0.1 1.6E-10 99 0 0 38 2.1 2.1 3.6 3.6 62. 820. 0.5 0.2 2.5E-10 99 0 0 3A 2.5 2.5 4.2 4.3 63. 940. D.6 0.2 2.9E-10 99 0 0 3CL 2.6 2.6 4.4 4.5 63. 990. 0.7 0.3 3.1E-10 99 0 0 3a 2.5 2.5 4.2 4.3 63. 940. 0.6 0.2 2.9E-10 99 0 0 3b 2.1 2.1 3.6 3.6 62. 820. 0.5 0.2 2.5E-10 99 0 0 3c 1A 1A 2.4 2.4 62. 550. 0.3 0.1 1.6E-10 99 0 0 3d 0.7 0.7 1.1 1 1 61. 300. 0.2 < 0.1 7.6E-11 99 0 0 3e 0.3 0.3 0.4 0.4 60. 150. 0.1 c 0.1 2.9E-11 99 0 0 3F c 0.1 c 0.1 0.1 0.1 60. 88. c 0.1 c 0.1 9.1E-12 99 0 0 1CL '11. 11 18. 18. 66. 1200 ~ 2.7 0.3 5.7E-10 99 0 0 1b 9.5 9.5 16. 16. 65. 1100. 2A 0.3 5.0E-10 99 0 0 Tc 7.4 7.4 12. 13 64. 850 1.9 0.2 4.0E-10 99 0 0

'fd 4.0 4.0 6.6 6.8 62. 490. 1.0 0.1 2.2E-10 99 0 1e 1.9 1.9 3.1 3.2 61 270. 0.5 c 0.1 1.0E-10 99 0 1f 0.1 0.1 0.2 0.3 60. 76. c 0.1 c 0.1 7.9E-12 99 0 1.2F 0.8 0.8 1.3 1.3 60. 140. 0.2 c 0.1 4.1E-11 99 0 1.2E 1.9 1.9 3.2 =3.3 61. 270. 0.5 c 0.1 1.0E-10 99 0 1.2D 4.0 4.0 6.6 6.8 62. 490. 1.0 0.1 2.2E-10 99 0 0 1.2C 7.0 7.0 12. 12. 64. 810. 1.7 0.2 3.8E-10 99 0 0 1.28 7.S 7.8 13. 13. 64. 930. 2.0 0.2 4.3E-10 99 0 0 1.2A 8.6 8.7 15. 15. 64. 990. 2.2 0.3 4.5E-10 99 0 0 1.2CL 8.6 8.7 15. 15. 65. 1000. 2.2 0.3 4.7E-10 99 0 0 1.2a 8.6 8.7 15. 15. 64. 990. 2.2 0.3 4.5E-10 99 0 0

• 1.2b " 7 8. 7.8 .= 13 13. 64. 930. 2.0 0.2 4.3E-10 99 0 0 1.2c 7.0 7.0 12. ,,12. 64. 810. 1.7 0.2 3.8E-10 99 0 0 1.2d 4.0 4.0 . 6.6 6.8 62. 490. 1.0 0.1 2.2E-10 99 0 0 1.2e 1.9 1 9 3.2 3.3 .61, 270. 0.5 < 0.1 1.0E-10 99 0 0

.1.2f 0.8 . 0.8 .,:1.3 1.3 60. '140, 0.2 < 0.1 4.1E-11 99 0 0 CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. j OFFSITE SURVEY AND SAMPLING DATA (T = 05:30) ( 08:30)

(continued)

HONITOR READINGS AIR SANPLES 15-min RAD DATA iCONTROLLER INFO (10 CF)

F IELD CLOSED MINDOM OPEN WINDOM bare f ilter- change contaa 1-131 SRD percent HONITOR uaist ground mist ground absorb absorb in SRD cpm/ conc. dose contrib POINT (aR/hr) (mR/hr) (aN/hr) (mR/hr) CPH CPH mR 100cm2 uCf/cc Plm Plt Grd 0 0 W Air Sample Background is 60 CPH OTHERS c 0.1 c 0.1 c 0.1 c 0.1 60. 60. c Oo1 c 0+1 O.DE+00 0 0 0

• FOR CONTROLLER/OBSERVER USE ONLY*

(Not to be Provided to Players):

Current Stability Class E Primary Release Pt: PS Flow: 2.1E+0 m3/sec Release Concentration-GIP (uCi/cc): 1.4E-01 1.7E-05 1.5E-05 (Flow 6 Release Integrated 6 Averaged over previous 15 minutes)

Whole Body Dose Projection: 5.3 mRem/hr Thyroid Dose Projection: 0.7 mRem/hr at a distance of: 1.20 miles downwind Maximums and Projections do not include plant shine or ground shine Maximum Plume Whole-Body Dose Rate: 5.6 mRem/hr at a distance of: 1.18 miles downwind Maximum Thyroid Dose Commitment: 1.2 mRem/hr at a distance of: 1.18 miles downwind

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2 k OFFSITE SURVEY AND SAMPLING DATA 06 :00) ( 09:00)

I HON TOR READINGS AIR SAHPLES 55-sin RAD DATA ~CONTROLLER INFO (10 CF)

FIELD CLOSED NINDOM OPEN QINDOM bare fi (ter- change -contae I-131 SRD Percent HONITOR Heist ground Ma 1st ground absor b absorb in SRD cpe/ conc+ dose contr lb POINT (aN/hr) (aN/hr) (aN/ht ) (aN/hr) CPH CPH aN 1 00an2 uCi/cc PLm PLt grd Air SaepLe Background is 60 CPH

.5F 3.5 3.5 5.9 5.9 61. 62. 0.9 <<0.1 8.7E-11 99 0 0

.5E 7.2 7.2 12. 12. 62. 64. 1.8 <<0.1 1.8E-10 99 0 0

.5D 13. 13. 22. 22 0 63. 67. 3.2 < 0.1 3.2E-10 99 0 0

~ SC 18. 18. 31. 31. 64. 70 0 4.6 <<0.1 4.6E 10 99 0 0 SB 19. 19. 32. 32. 64. 71. 4.8 c 0.1 4.8E-10 99 0 0

.5A 19. 19. 33 33 0 65. 71 ~ 4.9 c 0.1 4.9E-10 0 0

.5CL 20. 20, 33. 33. 65. 71. 4.9 c 0.1 49E 10 0 0

.Sa 19. 59, 33. 33 0 65. 71. 4.9 c 0.1 4.9E-10 0 0

.Sb 19. 19. 32. 32. 71. 4.8 <<0.1 4.8E-10 0 0

.5c 'IB. 18. 31. 31. 70 0 4.6 < 0.1 4.6E-10 0 0

.5d 13. 13. 22 0 22 e 63. 67. 3.2 < 0.1 3.2E-10 99 0

.Se 72 7.2 12. 12 62. 64. 1.8 <<0.1 1.8E-10 99 0

.Sf 3.5 3.5 5.9 5.9 61. 62. 0.9 <<05 8.7E-11 99 0 1F 1.0 1.0 1.8 1.8 60. 61. 0.3 <<0.1 2.6E-11 99 0 1E 2.4 2.4 4.0 4.0 61 ~ 61. 0.6 c O.f 6.DE-11 99 0 1D 4.9 49 8.3 83 65 63. 1.2 c 0.1 1.2E-10 99 0 0 1C 8.3 8.3 14. 14. 62. 65. 2.1 c 0.1 2.1E-10 99 0 0 1B 9.0 9;0 15. 15 62. 65. 2.3 < 0.1 2.3E-10 99 0 0 1A 9.5 9.5 16. 16. 62. 65. 2.4 < 0.1 2AE-10 99 0 0 la 9.5 9.5 16. 16. 62. 65. 2.4 < 0.1 2.4E-10 99 0 0 1.5F 0.4 OA 0.7 0.8 60. 97. 0.1 <<0.1 1.4E-11 99 0 0 1.5E 1.1 1.1 1.9 1.9 60. 160. 0.3 < 0.1 3.6E-11 99 0 0 1 5D 2.5 2.5 4.2 4.3 61. 270. 0.6 < 0.1 8.2E-11 99 0 0 1.5C 4.4 4A 7.4 7.6 61. 450. 1.1 0.1 1.5E-10 99 0 0 1.58 5.6 5.6 9.4 9.6 62. 540. 1.4 0.1 1 BE-10 99 0 0 1.5A 6.0 6.0 10. 10, 62. 580. 1.5 0.1 2.0E-10 99 0 1.5CL 6.3 6.4 11. 'll. 63. 990. 1.6 0.3 2.7E-'10 99 0 1.5a 6.0 6.0 10. 10. 62. 580. 1.5 0.1 2.0E-10 99 0 1.5b 5.6 5.6 9A 9.6 62. 540. fA 0.1 1.8E-10 99 0 1.5c 4.4 4.4 7A 7.6 61. 450. 1.1 0.1 15E10 99 0 1.5d 2.5 2.5 4.2 4.3 61. 270. 0.6 < 0.1 8.2E-11 99 0 0 CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. k OFFSITE SURVEY AND SAMPLING DATA (T = 06:00) ( 09:00)

(continued)

HONI TOR READINGS AIR SAHPLES 15.efn RAD DATA <<CONTROLLER INFO (10 CF)

FIELD CLOSED MINDOM OPEN IIINDON bare f I l ter- change contra I-131 SRD percent HONITOR Mafst ground Mafst ground absorb absorb in SRD cpm/ cones dose contrfb POINT (mR/hr) (mR/hr) (mR/hr) (mR/hr) CPH CPH SR 100 cm2 uCf/cc Pfm Plt Grd Afr Sample Background fs 60 CPH 1.5e 1.1 1.1 1.9 1.9 60. 160. 0.3 < 0.1 3.6E-1'I 99 0 0 1.5f 0.4 OA 0.7 0.8 &0. 97. 0.1 < 0.1 1AE-11 99 0 0 2F 0.2 0.2 0.4 0.4 60. 94. < 0.1 < 0.1 9.7E.12 99 0 0 2E 0.6 0.6 1.1 1.1 60. 160. 0.2 <01 2.7E-11 99 0 0 2D 1.5 1.5 2.5 2.6 61. 280. OA < 0.1 6.4E-11 99 0 0 2C 2.9 2.9 4.9 5.1 61. 490. 0.7 0.1 1.2E-10 99 0 0 28 3.9 3.9 6.6 6.9 62. 640. 1.0 0.2 1 7E 10 99 0 0 2A 4A 4.4 7.4 7.6 62. 720. 1.1 0.2 1.8E-10 99 0 0 2CL 4.4 4A 7.4 7.7 62. 730. 1.1 0.2 2.0E-10 99 0 0 2a 4.4 4.4 7A 7.6 62. 720. 1.1 0.2 1.8E-10 99 0 0 2b 3.9 3.9 6.6 6.9 62. 640. 1.0 0.2 1.7E-10 99 0 0 2c, 2.9 2.9 4.9 5.1 61. 490. 0.7 0.1 1.2E.10 99 0 0 2d 1.5 1.5 2.5 2.6 61. 280. OA < 0.1 6.4E-11 99 0 0 2e 0.6 0.6 1.1 1.1 60. 160. 0.2 <<0.1 2.7E-11 99 0 0 2f 0.2 0.2 0.4 OA 60. < 0.1 < 0.1 9.7E-12 99 0 0 2.5F 0.1 0+1 0.2 0.2 60. 87. < 0.1 < 0.1 7.4E-12 99 0 0 2.5E 0.4 0.4 0.7 0.7 60. 140. < 0.1 < 0.1 2.3E-11 99 0 0 2.5D 1.0 1.0 1.7 1.7 61. 270. 0.2 < 0.1 5.6E-11 99 0 0 2.5C 2.0 2.0 3.4 3.6 61. 0.5 0.1 1 ~ 1E 10 99 0 0 2.58 2.9 2.9 4.9 5.2 62. 660. 0.7 99 0 0 2.5A 3A 3A 5.7 5.9 62. 750. 0.8 99 0 0 2.5CL 3.5 3.5 6.0 6.2 62. 780. 0.9 99 0 0 2.5a 3.4 3.4 5.7 5.9 62. 750. 0.8 99 0 0 2.5b 2.9 2.9 4.9 5.2 62. 660. 0.7 99 0 0 2.5c 2.0 2.0 3.4 3.6 61. 480. 0.5 0.1 1.1E-10 99 0 0 2.5d 1.0 1.0 1.7 1.7 6'I ~ 270. 0.2 < 0.1 5.6E-11 99 0 0 2.5e 0.4 OA 0.7 0.7 60. 140. < 0.1 < 0.1 2.3E-'I1 99 0 0 2.5f 0.1 0.1 0.2 0.2 60. 87. < 0 1 < 0.1 7.4E-12 99 0 0 3F 0.1 < 0.1 0.1 0.2 60. 82. << 0.1 < 0.1 6.4E-12 99 0 0 3E 0.3 0.3 0.5 0.5 60. 130. < 0 1 < 0.1 2.0E-11 99 0 0

" 'ONTINUED ON NEXT PAGE

MNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. k OFFSITE SURVEY AND SAMPLING DATA {T = 06 00) { 09:00)

{continued)

HONITOR READINGS AIR SAHPLES 15-mIn RAD DATA <<CONTROLLER INFO (10 CF)

F IELD CLOSED illNDM OPEN MINDOM bare f I lter- change contam 1-131 SRD percent HONITOR us(st ground wsIst ground absorb absorb in SRD cpm/ conc. dose contr lb POINT (mR/hr) (mR/hr) (mR/hr) (mR/hr) CPH CPH mR 1 ooom2 uCI/cc Plm Plt Grd Alr Sample Backgrourxl Is 60 CPH 3D 0.7 0.7 1.2 1.2 60. 24D. 0.2 < 0.1 5.3E-11 99 0 0 3C 1.5 1.5 2.5 2.6 61 450. 0.4 0.1 1.1E-10 99 0 0 38 2.3 2.3 3.9 4.1 62, 660. 0.6 0.2 1,7E-10 99 0 0 3A 2.7 2.7 4.5 4.7 62. 760. 0.7 0.2 2.0E-10 99 0 0 QP 3CL 2.9 2.9 4.8 5.0 62. 790. 0.7 0.2 2.1E-10 99 0 0 3a 2.7 2.7 4.5 4.7 62. 760. 0.7 0.2 2.OE-10 99 0 0 3b 2.3 2.3 3.9 4.1 62. 660. 0.6 0.2 1,7E-10 99 0 0 3c 1.5 1.5 2.5 2.6 61. 450. 0.4 0.1 1.1E-10 99 0 0 3d 0.7 0.7 1.2 1.2 60. 240. 0.2 c 0.1 5.3E-11 99 0 0 3e 0.3 0.3 0.5 0.5 60. 130. c 0.1 < 0.\ 2.0E-11 99 0 0 3$ 0.1 < 0.1 0.1 0.2 60. 82. <<0.1 < 0.1 6 4E-12 99 0 0 4F c 0.1 c 0.1 c 0.1 c 0.1 60. 73. c 0,1 < 0.1 4.1E-12 99 0 0 4E 0.1 0.1 0.2 0.2 60. 110. c 0.1 c 0.1 1.5E-11 99 0 0 40 0.4 0.4 0.6 0.6 60. 200. c 0.1 < 0.1 4.2E-11 99 0 0 i"

' %00 OO 4C 0.8 0.8 1.3 1.3 61. 370. 0.2 < 0.1 9.5E-11 99 0 0 48 1.3 '.3 2.3 2.3 62. 580. 0.3 0.1 1.7E-10 99 0 0 4A 1.6 1.6 2.7 2.8 62. 700. 0.4 0.2 2.0E-10 99 0 0 4CL 1.7 1.7 2.9 3.0 62. 750. 0.4 0.2 2.1E-10 99 0 0 4a 1.6 1.6 2.7 2.8 62...700. 0.4 0.2 2.0E-10 99 0 0 4b '1.3 1.3 2.3 2.3 62. 580. 0.3 0 1 1 7E-10 99 0 0 4o 0.8 0.8 1.3 1.3 61. 370. 0.2 c 0.1 9.5E-11 99 0 0 4d 0.4 0.4 0.6 0.6 60. 200. < 0.1 c 0.1 4.2E-11 99 0 0 4e 0.1 0.1 0.2 0.2 60. 110 < 0.1 c 0.1 1.5E-11 99 0 D 4f <<0.1 c 0.1 << 0.1 <<0.1 60. 73. c 0.1 <<0.1 4 1E-12 99 0 0 4.5F .< 0 1 c 0.1 < 0.1 <<0.1 64. c 0.1 <01 1.2E-12 100 0 0

< O,l < 0.1 < 0.1 73 0 < 0.1 < 0.1 4.4E-12 100 0 0 4.5D < 0.1 < 0.1 0.1 0.1 100. c 0.1 <<01 1.3E-11 100 0 0 4.5C 0.2 0.2 0.3 0.3 150. c 0.1 <01 3.0E-11 100 0 0 4.58 0.3 0.3 0.6 0.6 220. c 0.1 <<0.1 5.3E-11 100 0 0 4.SA O.4 O.4 O.7 O.7 61. 2SO. O.1 c O.1 6.7E-11 1OO O O CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2 ~ k OFFSXTE SURVEY AND SANPLXNG DATA (T = 06:00) ( 09:00)

(continued)

HONITOR READ INGS AIR SAHPLES 15-sin RAD DATA <<CONTROLLER INFO (10 CF)

F IELD CLOSED llINODM OPEN MINDOM bare f i Lter- change contaa '-131 SRO percent HONITOR wsi st ground waist ground absorb absorb in SRO cpa/ conc+ dose contrib POINT (afI/hr) (afI/hr) <afI/hr) <NR/hr) CPH CPH sN 100cNZ uCi/cc Plm Pit Ord Air Saap le Background is 60 CPH 4.5CL 0.5 0,5 0.8 0.8 61. 270 0.1 < 0.1 7.1E-11 100 0 0 4.5a 0.4 0.4 0.7 0.7 61. 250. 0.1 < 0.1 6.7E-11 100 0 0 4.5b 0.3 0.3 0.6 0.6 60. 220. c 0.1 c 0.1 5.3E-11 100 0 0 4.5c 0.2 0.2 D.3 0.3 60. 150. c 0.1 c 0.1 3.0E-11 100 0 0 OO 4.5d < 0.1 < 0.1 0.1 0.1 60. 100. c 0.1 < 0.1 1.3E-11 1M 0 0 4.5e c 0.1 < 0.'I c 0.1 c 0,1 60. 73. < 0.1 c 0.1 4.4E-12 100 0 0 4.5f < 0.1 < 0.1 < 0.1 < 0.1 60. 64. < 0.1 < 0.1 1.2E-1Z 100 0 0 1CL 9.5 9.5 16. 16. 63. 880. 2.4 0.2 3.2E-10 99 0 0 1b 8.7 8.7 15. 15. 63. 790. 2.2 0.2 2.7E-10 99 0 0 1c 6.7 6.7 11 12. 62. 630. 1.7 0.2 2.1E-10 99 0 0 1d 3.6 3.6 6.1 6.2 61. 370., 0.9 << 0.1 1.2E-10 99 0 0 1e 1.7 1.7 2.9 3.0 61. 210. 0.4 < 0.1 5.6E-11 99 0 0 0.1 0.1 0.2 0.2 60. 72. c 0.'I c 0.1 4.4E-12 0 0 1.2F 0.7 0.7 1.2 1.2 60. 120. 0.2 c 0.1 2.3E 11 99 0 0 1.2E '1.7 1 7 2.9 3.0 6'I. 210. 0.4 < 0.1 5.6E-11 99 0 0 1.2D 3.6 3.6 6.1 6.2 61. 370 ~ 0.9 < 0.1 1.2E-10 99 0 0 1,2C 6.3 6.4 11 11. 62. 600, 1.6 0.2 2.1E-10 99 0 0 1.28 7.1 7.1 12. 12. 62. 690. 1.8 0.2 2.4E.10 99 0 0 1.2A 7.9 7.9 13. 14. 62. 720. 2.0 0.2 2.6E-10 99 0 0 1.2CL 7.9 7.9 13. 14. 62. 73D. 2.D 0.2 2.6E-ID 99 0 0 1.2a 7.9 7.9 13. 14. 62 720. 2.0 0.2 2 6E-10 99 0 0 1.2b 7.1 7.1 12. 12. 62. 690. 1.8 0.2 2.4E.10 99 0 0 1.2c 6.3 6.4 11. 11. 62. 6M. 1.6 0.2 2 1E-10 99 0 0 1.2d 3.6 3.6 6.1 6.2 61; 370. 0.9 c 0.1 1.2E-10 99 0 0 1.2e 1.7 1.7 2.9 3.0 61. 210. 0.4 < 0.1 5.6E-11 99 0 0 1.2f 0.7 0.7 1.2 1.2 60. 120. 0.2 c 0.1 2.3E-11 99 0 0 OTHERS < 0.1 < 0.1 c 0.1 < 0.1 60. 60. c 0.1 < 0,1 O.DE+00 0 0 0 CONTXNUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. k OFFSITE SURVEY AND SAMPLING DATA (T = 06:00) ( 09:00)

(continued)

• FOR CONTROLLER/OBSERVER USE- ONLY*

(Not to be Provided to Players):

Current Stability Class E Primary Release Pt: PS Flow: 2.1E+0 m3/sec Release Concentration-GIP (uCi/cc): 1.4E-01 8.9E-06 1.2E-05 (Flow & Release Integrated & Averaged over previous 15 minutes)

Whole Body Dose Projection: 4.8 mRem/hr Thyroid Dose Projection: 0.4 mRem/hr at a distance of: 1.20 miles downwind Maximums and Projections do not include plant shine or ground shine Maximum Plume Whole-Body Dose Rate: 5.0 mRem/hr at a distance of: 1.18 miles downwind Maximum Thyroid Dose Commitment: 0.6 mRem/hr at a distance of: 1.18 miles downwind

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2 1 OFFSITE SURVEY AND SAMPLING DATA 06: 30) ( 09:30)

HONITOR READINGS AIR SAHPLES 15-min RAD DATA *CONTROLLER INFO (10 CF)

F 1ELD CLOSED WINDOM OPEN MINDON bare f liter- change contea I-131 SRD percent HONITOR mist ground waist ground absorb absorb in SRD cpai/ 'ence dose contrib POINT (aR/hr) (aR/hr) (aR/hr) (aR/hr) CPH CPH aR 100 cmZ uCi/cc Plo Plt Grd Air Saaple Background is 60 CPH

.5F 2.1 2.1 3.6 3.6 61. 61. 0.5 < 0.1 5.9E.11 99 0 0

.SE 4.4 4A 7A 7A 61. 63. 1.1 c 0.1 1.2E-10 99 0 0

.5D 7.9 7.9 13. 13. 62, 65. 2.0 c 0.1 2.2E-10 99 0 0

.SC 11. 11 19. 19. 63. 67. 2.8 c 0.1 3.1E-10 99 0 0

~ 5B 12. 12. 20. 20. 63. 67. 2.9 c 0.1 3.3E-10 99 0 0

.5A 12. 12. 20. 20. 63. 67. 3.0 < 0.1 3.3E-10 99 0 0

.5CL 12. 12. 20 0 20. 63. 67 3.0 < 0.1 3.3E-10 99 0 0

.5a 12. 12. 20. 20. 63. 67. 3.0 < 0.1 3.3E-10 99 0 0

.5b 'l2. 12. 20. 20. 63. 67. 2.9 c 0.1 3.3E-10 99 0 D

.5c 11. 11. 19. 19 63. 67 2.8 < 0.1 3.1E-10 99 0 0

.5d 7.9 7,9 13. 13. 62. 65. 2.0 < 0.1 2.2E-10 99 0 0

.5e 4.4 4.4 7.4 7A 61. 63. 1.1 c 0.1 1.2E-10 99 0 0

.Sf 2.1 2.1 3.6 3.6 61, 61. 0.5 < 0.1 5.9E-11 99 0 0 1F 0.6 0.6 1 ' 1.1 60. 60. 0.2 c 0.1 1.8E.11 99 0 0 1E 1.5 1.5 . 2.5 '.5 60. 61. OA c 0.1 4.1E-11 99 0 0 1D 3.0 3.0 5.0 5.1 61. 0.7 < 0.1 8.3E-11 99 0 0 1C 5.0 5.0 8.5 8.5 61 ~ 1.3 c 0.1 1.4E-10 99 0 0 18 5.5 5.5 9.3 9.3 61. 1.4 c 0.1 1.5E.10 99 0 0 1A 5.8 5.8 9.8 9.8 61. 1.5 <01 1.6E-10 99 0 0 1a 5.8 5.8 9.8 9.8 61. 1.5 <01 1.6E-10 99 0 0 1.5F 0.3 0.3 0.5 0.5 60. 60. c 0.1 c 0.1 7.5E-12 0 D 1.5E 07 07 1.2 1.2 60. 60. 0.2 c 0.1 1.9E-11 0 0 1.5D 1 5 1 2.6 2.7 60. 61. 0.4 c 0.1 4.3E-11 0 0 2.8 2.85'1.5C 4,7 4.9 61. 62. 0.? < 0.1 7.8E-11 0 0 1.58 3A 3.4 5.8 6.0 61. 62. 0.9 c 0.1 9.6E-11 0 0 3.7 3.7 6.3 6.5 61. 62. 0.9 c 0.1 1.0E-10 99 0 0 9.6 9.6 16. 17. 62. 1000. 2A 0.4 2.2E-10 99 0 0 3.7 3.7 6.3 6.5 61 62. 0.9 c 0.1 1.0E-10 99 0 0 3.4 3A 5,8 6.0 61 ~ 62. 0.9 < 0.1 9.6E.11 99 0 0 2.8 2.8 4 7 4.9 61. 62. 0.7 < 0.1 7.8E-11 99 0 0 1.5d '.5 1.5 2.6 2.7 60. 61 0.4 c 0.1 4.3E-11 99 0 0

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WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. 1 OFFSITE SURVEY AND SAMPLING DATA (T = 06:30) ( 09:30)

(continued)

HONITOR READINGS AIR SAHPLES 15-Iin RAD DATA <<CONTROLLER IN'10 CF)

FIELD CLOSED MINDOM OPEN 1J INDN bare fliter. change contm . 1-131 SRD percent HONITOR mist ground uaist ground absorb absorb in SRD cpe/ conc. dose contrib POINT (aR/hr) (aN/hr) (aN/hr) (aN/hr) CPH CPH aR 100cm2 uCI/cc Pie Plt Grd Air Saaple Background is 60 CPH 1.5e 0.7 0.7 1 2 1.2 60. 60. 0.2 < 0.1 1 9E-11 99 0 0 1.5f 0.3 0.3 0.5 0.5 60, 60. < 0 1 < 0.1 7 SE-12 99 0 0 2F 0.3 0.3 0.6 0.6 60,, 96. < 0.1 < 0.1 8.3E-12 99 0 0 2E 1.0 1.0 1.6 1 7 60. 160. 0.2 < 0.1 2.3E-11 99 0 0 2D 2.3 2.3 3.9 4.0 60. 280. 0.6 < 0.1 5.5E-11 99 0 0 2C 4.6 4.6 7.8 8.0 61 ~ 490. 1.2 0.2 1.0E-10 99 0 0 2$ 6.1 6.1 10. 11. 61. 660. 1.5 0.2 1.4E-10 99 0 0 2A 6.5 6.5 11. 11. 61. 730. 1.6 0.3 1.6E-10 99 0 0 2CL 6.9 6.9 12. 12. 61. 750. 1.7 0.3 1.6E-10 99 0 0 2a 6.5 6.5 11. 11. 61. 730. 1.6 0.3 1.6E 10 99 0 0 2b 6.1 6.1 10. 11. 61. 660. 1.5 0.2 1AE-10 99 0 0 2c 4.6 4.6 7.8 8.0 61. 490. 1.2 0.2 1.0E-10 99 0 0 2d 2.3 2.3 3.9 4.0 60. 280. 0.6 < 0.1 5.5E-11 99 0 0 2e 1.0 1.0 1.6 .1.7 60. 160. 0.2 < 0.1 2.3E-11 99 0 0 2f 0.3 0.3 0.6 0.6 60. 96. < 0.1 < 0.1 8.3E-12 99 0 0 0.1 0.1 0.2 0.2 60. 79 < 0.1 < 0.1 4.2E-12 99 0 0 2.5F 2.5E 0.4 0.4 0.6 0.7 1.6 60 60.

'20, 210.

<<0.1 0.2

<01 0.1 1.3E-11 3.1E-11 99 99

'0 0

0 0

2.SD 0.9 0.9 1.6 2.5C 1.9 1.9 3.2 3.3 61. 360. 0.5 0.1 6.2E-11 99 0 0 2.5B 2.7 2.7 4.5 .4.8 61. 490 0.7 0.2 9.2E-11 99 0 2.5A 3.1 3.1 5.2 5A 61. 550. 0.8 0.2 1.0E-10 99 0 3.2 3.2 5A 5.7 61. 580. 0.8 0.2 1.1E-10 99 0 2.5CL 2.5a 3.1 3.1 5.2 SA 4.8 61 '50. 0.8 0.7 0.2 0.2 1.0E-10 9.2E-11 99 99 0

0 2.5b 2.7 2.7 4.5 61. 490.

2.5c 1.9 1 9 ,3.2 3.3 61. 360. 0.5 0.1 6.2E-11 0 0 ir 25d 09 0.9 ,,1.6 ~ 1.6 60. 210. 0.2 < 0.1 3.1E-11 0 0 2.5e ~ '0.4 OA 0.6 0.7 60. 120. < 0.1 < 0.1 13E-11 0 0 2.5f . 0.1 0.1 0.2 0.2 60, 79. < 0.1 < 0.1 4.2E-12 0 0 3F < 0.1 < 0.1 0.1 i 0.1 60, 76. < 0.1 < 0.1 3.4E-12 0 0 3E 0.3 0.3 OA,OA 60. 110. < 0.1 < 0.1 1.1E-11 99 0 0

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WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2 ~ l OFFSITE SURVEY AND SAMPLING DATA (T = 06:30) ( 09:30)

(continued)

HONITOR READINGS AIR SAMPLES 15-win RAD DATA ~CONTROLLER INFO (10 CF)

FIELD CLOSED MINDOM OPEN MINDSI bare f flter- change contea 1-131 SRD percent NONITOR uaist ground uafst ground absorb absorb fn SRD cpm/ conc. dose contrfb POINT (sR/hr) (mR/hr) (mR/hr) (mR/hr) CPH CPH mR 100 cm2 uCf/cc Pli Plt Grd Air Sample Background fs 60 CPN 3D 0.7 0.7 1.1 1.2 60. 190. 0.2 < 0.1 3.0E-11 99 0 0 3C 1.4 1.4 2.3 2.5 61. 330. 0.3 0.1 6.1E-11 99 0 0 3B 2.2 2.2 3.6 3.8 61 ~ 480. 0.5 0.2 9.5E-11 99 0 0 3A 2.5 2.5 4.2 4.4 61. 550. 0.6 0.2 1.1E-10 99 0 0 3CI. 2.7. 2.7 4.5 4.7 61. 5N. 0.7 0.2 1.2E-10 99 0 0 3a 2.5 2.5 4.2 4.4 61. 550. 0.6 0.2 .1.1E-10 99 0 0 3b 2.2 2.2 3.6 3.8 61. 480. 0.5 0.2 9.5E-11 99 0 0 3c 1A 1A 2.3 2.5 61. 330. 0.3 0.1 6.1E-11 99 0 0 3d 0.7 0.7 1.1 1.2 60. 190. 0.2 < 0.1 3.0E-11 99 0 0 3e 0.3 0.3 0.4 OA 60. 110. < 0.1 < 0.1 1.1E 11 99 0 0 3f < 0.1 < 0.1 0.1 0.1 60. 76. < 0.1 < 0.1 3.4E-12 99 0 0 4F < 0.1 <<0.1 <0.1 << 0.1 60. 71. < 0.1 < 0.1 2.8E-12 99 0 0 4E 01 0 1 0.2 0.2 60. 99. <<0.1 < 0.1 1.0E-11 99 0 0 40 OA OA 0.6 0.7 60. 170. < 0.1 < 0.1 3.0E-11 99 0 0 4C 0.9 0.9 1.5 1.6 61. 310. 0.2 0.1 6.6E 11 0 0 48 1.5 1.5 2.5 2.6 61. 480. 0.4 0.2 1.1E-10 0 0 4A 1.8 1.8 3.0 3.1 61. 570. 0.4 0.2 1 AE-10 0 0 4CL 1.9 1.'9 3.2 3.4 61. 600. 0.5 0.2 1.4E-10 0 0 4a 1.8 1.8 3.0 3.1 61. 570. D.4 0.2 1.4E-10 0 0 4b 1.5 1.5 2.5 2.6 61. 480. OA 0.2 1.1E- IO 99 0 0 4c 0.9 0.9 1.5 1.6 61. 310. 0.2 0.1 6.6E-11 99 0 0 4d 0.4 0.4 0.6 0.7 170. < 0.1 < 0.1 3.0E-11 99 0 0 4e 0.1 0.1 0.2 0.2 99. < 0.1 < 0.1 1.0E-11 99 0 0 4j < 0.1 <01 < 0.1 < 0.1 71. < 0.1 < 0.1 2.8E-12 99 0 0 4.5F < 0.1 < 0.1 < 0.1 < 0.1 60. 69. < 0.1 < 0.1 2.8E-12 99 0 0 4.5E 0.1 ~

0.1 0.2 0.2 60 96. < 0.1 < 0.1 1.OE-11 99 0 0 4.5D 0.3 0.3 0.5 0.5 60. 160. < 0.1 < 0.1 3.1E-11 99 0 0 4.5C 0.7 0.7 1.2 ~ 1.3 61. 300. 0.2 < 0.1 7.2E-11 99 0 0 4.58 1.3 1.3 2.1 2.2 61. 490. 0.3 0.2 1.2E-10 99 0 0 4.5A 1.5 '1.5 2.6 2.7 61 600 DA 0.2 1.6E-10 99 0 0 CONTINUED ON NEXT PAGE

NNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2.

OFFSITE SURVEY AND SAMPLING DATA (T = 06:30) ( 09:30)

.(continued)

HONITOR READINGS AIR SAHPLES 15.min RAD DATA ~CONTROLLER INFO (10 CF)

F IELD CLOSED WINDOM OPEN MINDDM bare f I (ter- change cantos I-131 SRD percent HONITOR wrist - ground mist ground absorb absorb in SRD cps/ canc. dose cant rib POINT (sN/hr) (sN/hr) (sN/hr) (aN/hr) CPH CPH mR 100cm2 uCI/cc PIm Plt Grd Air Sample Background is 60 CPH 4.5CL 1.7 1 7 2.8 2.9 62. 630, 0.4 0.2 1.7E-10 99 0 0 4.5a 1.5 1.5 2.6 2.7 61 600. OA 0.2 'l.6E-10 99 0 0 4.5b 1.3 1.3 2.1 2.2 61. 490. 0.3 0.2 1.2E" 10 99 0 0 4.5c 0.7 0.7 1.2 1.3 61 300. 0.2 c 0.1 7.2E 11 99 0 0 4.5d 0.3 0.3 0.'5 0.5 160. c O.t < 0.1 3.1E-11 99 0 0 4.5e 0.1 0.1 0.2 0.2 60. 96. < 0.1 c O.l 'I.OE- I 1 99 0 0 4.5f < 0.1 c 0.1 < 0.1 < 0.1 69. c 0.1 < 0.1 2.8E-12 99 0 0 5F c 0.1 c 0.1 c 0.1 < 0.1 67. c 0.1 c 0*t 2.2E-12 99 0 0

'SE < 0.1 c 0.1 0.1 0.1 60. 88. c 0.1 < 0.1 8.4E 12 99 0 0 SD 0.2 0+2 OA 0.4 60. 150. c 0.1 < 0.1 2.7E-11 99 0 0 5C 0.5 0.5 0.8 0.9 61. 270. 0.1 c 0.1 6.2E-11 99 0 0 5B 0.9 0.9 1.6 1.6 61. 450. 0.2 0.2 1.1E 10 99 0 0 5A 1.2 1.2 1.9 2.0 6'I. 550. 0.3 Oi2 1.4E-10 99 0 0 SCL 1.3 1.3 2.1 2.2 61. 580. 0.3 0.2 1.5E-10 99 0 0 5a 1.2 1.2 1.9 2.0 61. 550. 0 3 0.2 1AE-10 99 0 0 5b 0.9 09 t.6 1.6 61. 450. 0.2 0.2 1.1E-10 99 0 0 Sc 0.5 0.5 0.8 0.9 61. 270. 0.1 < 0.1 6.2E 11 99 0 0 5d 0.2 0.2 OA 0.4 60. 150. < 0.1 c 0.1 2.7E-11 99 0 0 Se < 0.1 c 0.1 0.1 0.1 60. 88. c 0.1 c 0.1 8AE-12 99 0 0 Sf <01 c O.t O.t c 0.1 60. 67. c 0.1 c 0.1 2.2E-12 99 0 0 1CL 5.9 5.9 10. 10. 61. 64, 1.5 c 0.1 1.7E.10 99 0 0 1b 5.3 5.3 8.9 92 61 63. 1.3 < O.t 1.5E-10 99 0 0 1c 4.1 4.1 6.9 7.1 '1.

62, 1.0 c 0,1 1.1E-10 99 0 0 1d 2.2 2.2 ' 3.7 3.9 61. 61. 0.6 c 0.1 6.2E-11 99 0 0

.1f te 1.0

<<0.'t 1.0

<<0.1 .

1.8 0.1 1.8 0.1 60. ,

61 60.

'.3 < O.t

<01

< 0.1 2.9E-11 2.3E-12 99 99 0

0 0

0

'1 2F OA OA 0 7 0.8 60. 60, 0.1 c 0.1 1.2E-11 99 0 0 1.2E 1.1 1.1 . 1.8 1.9 60. 61 0.3 c 0.1 3.0E-11 99 0 0 1.2D 2e2 2+2 3.8 3.9 61 61 ~ 0.6 c 0.1 6.2E-11 99 0 0

'l.2C 3.9 .3.9 6.6 6.8 61 . 62, 1 0 c 0 1 1 1E-10 99 D 0'

CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. l OFFSITE SURVEY AND SAMPLING DATA (T = 06:30) ( 09:30)

(continued)

MONITOR READINGS AIR SABLES 15-ain RAD DATA iCONTROLLER INFO (10 CF)

F I ELD CLOSED MI NOD OPEN WINDOM bare fI I ter- change contea "

1-13'I SRD percent MONITOR waist ground mist ground absorb absorb ln SRD cpa/ conc i dose contrlb POINT (aN/hr) (aN/hr) (aN/hr) (aN/hr ) CPH CPN aN 100anZ uCi/cc Pte PIt Ord Air Serpie Background fs 60 CPS 1.28 4.5 4.5 7.6 7.8 61. 63. 1.1 < 0.1 1.2E-10 99 0 0 1.2A 4.8 4.8 8.1 8.4 61. 63. 1.2 < 0.1 1.3E.10 99 0 0 1.2CL 4.9 4.9 8.2 S.5 61. 63. 1.2 < 0.1 1.4E-10 99 0 0 1.2a 4.8 4.8 8.1 8.4 61. 63. 1.2 < 0.1 1.3E-10 99 0 0 1.2b 4.5 4.5 7.6 7.8 6'I. 63. 1.1 < 0.1 1.2E 10 99 0 0 1.2c 3.9 3.9 6.6 6.8 61. 62. 1.0 < 0.1 1.1E 10 99 0 0 1.2d 2.2 2.2 3.8 3.9 61. 61. 0.6 < 0.1 6.2E-11 99 0 0 1.2e 1.1 1.1 1.8 1.9 60. 61. 0.3 < 0.1 3.0E.11 99 0 0 1.2f 0.4 0.4 0.7 0.8 60. 60. 0.1 < 0.1 1.2E" 11 99 0 0 OTHERS < D.1 < D.1 < 0.1 < 0.1 60. 60. < 0.1 < 0.1 D.DE+00 0 0 0

• FOR CONTROLLER/OBSERVER USE ONLY*

(Not to be Provided to Players):

Current Stability Class E Primary Release Pt: PS Flow: 2.1E+0 m3/sec Release Concentration-GIP (uCi/cc): 1.3E-01 8.8E-06 1.1E-05 (Flow & Release Integrated E Averaged over previous 15 minutes)

Whole Body Dose Projection: 3.1 mRem/hr Thyroid Dose Projection: 0.3 mRem/hr at a distance of: 1.20 miles downwind Maximums and Projections do not include plant shine or ground shine Maximum Plume Whole-Body Dose Rate: 4.5 mRem/hr at a distance of: 1.18 miles downwind Maximum Thyroid Dose Commitment: 0.4 mRem/hr at a distance of: 1.18 miles downwind

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2 ~ m OFFSITE SURVEY AND SAMPLING DATA (T = 07 00) ( 10:00)

HONI TOR READ I NOS AIR SAHPLES 15-min RAD DATA <<CONTROLLER INFO (10 CF)

FIELD CLOSED MINDOM OPEN NINOCM bare fliter- change contaa l-131 SRD percent HONITDR mist ground mist ground absorb absorb in SRD cpa/ conc. dose contr ib POINT (mR/hr) (mR/hr) (aR/hr) (mR/hr) CPH CPH mR 1 00cm2 uCI/cc Plm Plt Grd Air Sample Background is 60 CPH

.5C 0+2 0.2 DA 0.5 60. 60. c 0.1 < 0.1 4.1E-12 98 0 1

.58 5.2 5.2 8.9 8.9 61. 62. 1.3 < 0.1 9.0E-11 99 0 0

~ 5A 9.5 9.5 16. 16. 61. 64. 2A c 0.1 1.6E-10 99 0 0

.5CL 10. 10. 17, 17. 62. 65. 2.S < 0.1 1.7E-10 99 0 0

.5a 9.5 9.5 16. 16. 61. 64. 2.4 < 0.1 1.6E-10 99 0 0

.Sb 5.2 5.2 8.9 8.9 61. 62. 1.3 < 0.1 9 OE-11 99 0

.5c 0.2 0.2 0.4 0.5 60. c 0.1 c 0.1 4.1E-12 98 0 1E < 0.1 c 0.1 0.'I 0.1 60. c 0.1 < 0.1 1.2E-12 99 0 1D 0.4 0.4 0.7 0,7 60. 0.1 < 0.1 7.4E-12 99 0 1C 1.6 1.6 2.7 2.7 61. 0.4 c 0.1 2.8E-11 99 0 18 3.4 3A 5.8 5.8 61 62. D.9 c 0.1 5 9E-11 99 0 0 4.3 4.3 7.3 7,3 62. < 0.1 7.4E-11

'1 1A 1.1 99 0 0 1a 4.3 4.3 7.3 7.3 6t. 62. 1.1 c 0.1 7AE-'it 99 0 0 t.5E < 0.1 0.1 0.1 0.2 60. 60. < 0.1 <01 1.4E-12 99 0 0 1.5D 0.3 0.3 0.6 0.6 60, 60, c 0.1 < 0.1 5.9E-12 99 0 0 1.5C 1.0 1.0 1 7 1.8 -

60. 60. 0.3 <01 1.8E-11 99 0 0 1.5e 2.0 2.0 3.3 3.5 60. 61, 0.5 c 0.1 3.4E-11 99 D 0 1.5A 2.6 2.6 4.3 4.5 60. 61. 0.6 < 0.1 4AE-11 99 0 0 1.5CL 6.3 6.3 11. 1t 61. 270 1.6 0.2 1.2E-10 99 0 0 1.5a 2.6 2.6 4.3 4.5 60. 61, 0.6 < 0.1 4.4E-11 99 0 0 1.5b 2.0 2.0 3.3 3.5 60. 61 0.5 < 0.1 3.4E-11 0 0

,1.5c 1.0 1.0 1.7 1.8 60. 60. 0.3 <01 1.8E-11 0 0 1.5d . 0.3 0.3 0.6 0.6 60. 60, c 0.1 cD1 5 9E-12 0 0 1.5e < 0.1 < 0.1 0.1 0.2 60. 60. c 0.1 < 0.1 1AE-12 0 0 2F 01 0.1 0.2 0.3 60. 68. c 0.1 < 0.1 3.1E-'12 0 0 2E 0.4 OA 0.7 0.8 60. 81 0,1 c 0.1 9.1E-12 99 0 0

) ~ft. )>> ,;1 ~1 ~, 1.1;; 1.9, ~ .1.9 60. 110. 03 c 0.1 2.3E-11 99 0 0 2C 2.3 2.3 3.9 4.1 60. 160. 0.6 c 0.1 4.9E-11 99 0 0 28 3.5 3.5 5.9 6.2 61. 190. 0.9 0.1 7.2E-11 99 D 0 2A 4.2 4.2 ~ .; 7.1 7.3 61. 210. 1.0 0.1 8AE-11 99 0 0 2CL 4.5 4.5 7.6 7+8 61. 210. 1 1 0.1 8.9E 11 99 0 0 CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. m OFFSITE SURVEY AND SAMPLING DATA (T = 07:00) ( 10:00)

(continued)

HONITOR READINGS AIR SAHPLES 15-Isin RAD DATA iCONTROLLER INFO (10 CF)

FIELD CLOSED illNDOM OPEN llINDOM bare fliter- change contam I 131 SRD percent HONITOR mist ground uafst ground absorb absorb in SRD cpa/ conc+ dose contrib POINT (eR/hr) (sR/hr) (sSI/hr) (eN/hr) CPH CPH aR 100cm2 uCI/cc PIIs Plt Grd Air Sasple Background is 60 CPH 2a 4.2 4.2 7.1 7.3 61. 210. 1.0 0.1 8.4E-11 99 0 0 2b 3.5 3.5 5.9 6.2 61 190. 0.9 0.1 7.2E.11 99 0 0 2c 2.3 2.3 3.9 4.1 60. 160. 0.6 < 0.1 4.9E.11 99 0 0 2d 1.1 1.1 1+9 1.9 60. 110. 0.3 < 0,1 2.3E-11 99 0 0 2e 0.4 0.4 0.7 0.8 60. 81. 0.1 c 0.1 9.1E-12 99 0 0 2f 0.1 0.1 0.2 0.3 60. 68. c 0.1 c 0.1 3.1E-12 99 0 0 2.5F < 0.1 < 0.1 0.1 0.2 60. 68. < 0.1 < 0.1 2AE 12 99 0 0 2.5E 0.3 0.3 0.5 0.5 60. 84. c 0.1 c 0.1 7.6E-12 0 0 2.5D 0.7 0.7 1.2 1.3 60. 120. 0.2 < 0.1 1.9E-11 99 0 0 2.5C '1.7 1.7 2.8 3.0 60. 180+ OA < 0.1 4.2E-11 99 0 0 2.5B 2.6 2.6 4.4 4,7 61. 230. 0.7 0.1 6.4E-11 99 0 0 2.5A 3.2 3.2 5A 5.6 61. 260. 0.8 0.2 7.7E-11 99 0 0 2.5CL 3A 3A 5 7 6.0 61. ~

260. 0.8 0.2 8.2E-11 99 0 0 2.5a 3.2 3.2 5A 5.6 61. 260. 0.8 0.2 7.7E-11 99 0 0 2.5b 2.6 . 2.6 4A 4.7 61. 230. 0.7 0.1 6AE-11 99 0 0 2.5c 1.7 1.7 2.8 3.0 60. OA < 0.1 4.2E-'ll 99 0 0 180'20.

2.5d 0.7 0.7 1.2 1.3 60. 0.2 < 0.1 1 9E-11 99 0 0 2.5e 0.3 0.3 0.5 0.5 60. 84. < 0.1 < 0.1 7.6E-12 99 0 0 2.5f < 0.1 < 0.1 0.1 0.2 60. '8. < 0.1 < 0.1 2.4E-12 99 0 0 3F 0.1 0.1 0.2 0.2 60. 76. < 0.1 < 0.1 3.5E.12 99 0 0 3E OA OA 0.7 0.7 60. 110. 0.1 c 0.1 1.1E-11 99 0 0 3D 11 1.1 1i9 2.0 60. 200. 0.3 0.1 3.0E-11 99 0 0 3C 2.5 2.5 4.2 4.4 61. 360. 0.6 0.2 6.4E-11 99 0 0 38 4.0 4.0 6.8 7.0 61. 510. 1.0 OA 1 OE-10 99 0 0 3A 4.7 4.7 8.0 8.2 61. 570. 1.2 OA 1.2E-10 99 0 3CL 5.2 5.2 8.8 9.1 61. 610. '1.3 0.5 1.3E-10 99 0 3a 4.7 4.7 8.0 8.2 61. 570. 1.2 0.4 1 2E-10 99 0 3b 4.0 4.0 6.8 7.0 61. 510. 1.0 0.4 1.0E-10 99 0 3c 2.5 4.2 4.4 0.6 0.2 6.4E-11

'.5 61 36D. 99 0 3d 1.1 1.1 1.9 2.0 60. 200. 0.3 0.1 3.0E-11 99 0 0 CONTINUED ON NEXT PAGE

NNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. m I OFFSITE SURVEY AND SAMPLING DATA (T = 07:00) ( 10:00)

(continued)

HONITOR READINGS AIR SAHPLES 15-min RAD DATA <<CONTROLLER INFIP (10 CF)

FIELD Cl.OSED MINDOM OPEN MINDOM bare f f I ter- change contaa 1-131 SRD percent HONITOR uaist ground moist ground absorb absorb in SRD cpm/ cence dose cont rib POINT (mR/hr) (mR/hr) (mR/hr) (mR/hr) CPH CPH mR 100cm2 uCi/cc Pla Plt Grd Air Sample Background is 60 CPH 3e 0.4 OA 0 7 0,7 60. 110. 0.1 c 0,1 1.1E-11 99 0 0 3f 0.1 0.1 0.2 0.2 60. 76. c 0.1 < 0.1 3.5E-12 99 0 0 4F c 0.1 <<0.1 < O.t < 0.1 60. 67. c 0.1 c 0.1 1.6E-12 99 0 0 4E 0.1 0.1 0.2 0.2 60. 87. <<0.1 c 0.1 5.8E-12 99 0 0 40 0.4 0.4 0.6 0.6 60. 140. c 0.1 c 0.1 1.6E-11 99 0 0 4C O.S O.S 1.4 1.5 60. 240. 0.2 0.1 3.7E-11 99 0 0 48 1.3 1.3 2.3 2A 61. 360. 0.3 0.2 6.1E-11 99 0 0 4A 1.6 1.6 2.S 2+9 61. 420. 0.4 0.3 7.5E-11 99 0 0 4CL 1.8 1.8 3.0 3.1 61 450. 0.4 0.3 S.OE-11 99 0 0 4a 1.6 1.6 2.8 2.9 61. 420~ 0.4 0.3 7.5E-11 99 0 0 4b 1.3 1.3 2.3 2.4 61. 360. 0.3 0.2 6.1E-11 99 0 0 4c 0.8 0.8 1A 1.5 60. 240. 0.2 0.1 3.?E-11 99 0 0 4d OA 0.4 0.6 0.6 60'e 140. 0.1 c 0.1 1.6E-11 99 0 0 0.1 0.1 0.2 0.2 60. 8? c 0.1 c 0.1 5 BE-12 99 0 0 4f < 0.1 c 0.1 c Oot <<01 60. 67. c 0.1 c 0.1 1.6E-'12 99 0 0 4.5F < 0.1 c 0.1 < 0.1 < 0.1 60. 66. c O.t c 0.1 1.5E-12 99 0 0 4.5E c 0.1 c 0.1 0.2 0.2 60. 84. c 0.1 < 0.1 5.8E-12 99 0 0 4.5D 0.3 0.3 0.5 0.5 60. 130. < 0.1 <<0.1 1.8E-11 0 0 4.5C 0.7 0.7 t.1 1.2 60. 220. 0.2 0.1 4.0E-11 99 0 0 4.58 1.2 1.2 2.0 2.1 61. 360. 0.3 0.2 6.9E-11 99 0 0 4.5A 1.5 1.5 2.5 2.6 61. 420. 0.4 0.3 8,7E-11 99 0 0 4.5CL 1.5 1,5 ,2.6 2.7 61. 450. OA 0.3 9.1E-11 99 0 0 4.5a 1.5 1.5 2.5 2.6 61. 420. 0.4 0.3 8.?E-11 99 0 0 4.5b 1.2 1.2 2.0 2.1 61. 360. 0.3 0.2 6.9E-11 99 0 '

4.5c 0.7 0.7 1 1 1.2 60. 220. 0.2 0.1 4.0E 11 99 0 0 4.5d 0.3 0.3 0.5 0.5 60. 130. < 0 1 c 0.1 1.8E-11 99 0 0 4.5e c 0.1 c 0.1 0.2 0.2 60. 84. <<O.t < 0.1 5.8E-12 99 0 0 4.5f c 0.1 0.1 <.0,1 c 0.1 60. 66. <<0.1 c 0.1 1.5E-12 99 0 0 5F c 0.1 c 01 <0,1 < 0.1 60 66. < 0.1 < 0.1 1.5E-12 99 0 0 5E c 0,1 c 0.1 0,1 0.1 60. 82. c 0.1 < 0.1 5.9E-12 99 0 0

. CONTINUED ON NEXT PAGE

MNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unih 2 REV 0 TABLE E2. m OFFSITE SURVEY AND SAMPLING DATA (T = 07:00) ( 10:00)

(continued)

HONI TOR READINGS AIR SANPLES 15-mfn RAD DATA *CONTROLLER INFO (10 CF)

F IfLD CLOSED MIND(BI OPEN illNDOM bare fi(ter- change contam I-131 SRD percent HONITOR waist ground uatst ground absorb absorb in SRD cpm/ cone+ dose contrib POINT (mR/hr) (mR/hr) (mR/hr) (mR/hr) CPH CPH mR 100 om2 uCi/oo Plm Plt Grd Air Sample Background is 60 CPH 5D 0.2 0.2 0.4 0.4 &O. 130. c 0.1 c 0.1 1.8E-t 1 99 0 0 5C 0,6 0.6 0.9 1.0 60. 220+ 0+1 0.1 4.3E.11 99 0 0 5B 1,0 1.0 1.7 1.8 61. 360. 0.3 0.2 7.9E 11 99 0 0 SA 1.3 1.3 2.1 2.2 61. 450. 0 3 0.3 9.9E-11 99 0 0 5Cl. 1.4 1.4 2.3 2.4 61. 480. 0.3 0.3 1.1E-10 99 0 0 Sa 1,3 1.3 2.1 2.2 61. 450. 0.3 0.3 9.9E-11 99 0 0 Sb 1.0 1.0 1.7 1.8 61. 360. 0.3 0.2 7.9E-t 1 99 0 0 5c 0.6 0.6 0.9 1.0 60. 220. 0.1 0.1 4.3E-11 99 0 0 5d 0.2 0.2 0.4 0.4 60. 130. < 0.1 < 0.1 1.8E-11 99 0 0 5e < 0.1 c 0.1 0.1 0.'I 82. < 0.1 <<01 5.9E-12 99 0 0 5f <<0.1 c 0.1 < 0.1 < 0.1 66, <01 < 0.1 1.5E-12 99 0 0 6F c 0.1 < 0.1 < 0.1 < 0.1 64. < 0.1 < 0.1 1.2E-12 99 0 0 6E <<01 c 0,1 c 0.1 c 0.1 78 0 c 0.1 c 0.1 5.3E-12 99 0 0

&0 0.1 0.1 0.2 0.2 120. < 0.1 < 0.1 1.8E-11 99 0 0 0 0 6C 0.3 0.4 0.6 0.6 &0. 210. < 0.1 0 1 4.5E-11 99 0 0 68 0.7 0.7 1 1 1.1 61. 360. 0.2 0.2 8.7E-11 99 0 0 0.9 0.9 1.4 1.5 61. 45D. 0.2 0.3 1 1E-10 99 0 0 6CL 0.9 0.9 1.6 1.6 61. 480. 0+2 0.3 1.2E-10 99 0 0 6a 0.9 0.9 1 4 1.5 61. 450. 0.2 0.3 titE-10 99 0 0 6b 0.7 0.7 1.1 1.1 61. 360. 0.2 0.2 8.7E-11 99 0 0

&c 0.3 0.4 0.6 0.6 60. 210. < 0.1 0.1 4.5E-11 99 0 0 6d 0.1 01 0.2 0.2 60. 120. < 0.1 < 0.1 1.8E-11 99 0 0

&e c 0.1 c 0.1 c,D.1 c 0.1 60. 78. < 0.1 < 0.1 5.3E-12 99 0 0 6f < 0.1 < 0.1 c 0.1 <<0.1 60. 64. c 0.1 < 0.1 1.2E.12 99 0 0 1CL 4.7 4.7 7.9 8.1 61. 62. 1.2 c 0 1 B.OE-11 99 0 0 1b 2.8 2.8 4.7 4.9 60. 61. 0.7 < 0.1 4.7E-11 99 0 0 tc 1.0 1.0 1.6 1.8 60. 60. 0,2 < 0 1 1,6E-11 99 0 0 1d 0.2 0.2 0.4 0.4 60. 60. c 0.1 < 0.1 3.7E-12 99 0 0 1e c O.t <<0.1 c D.t .<<0.1 . 60. 60. c 0.1 < 0.1 5.8E-13 97 0 2 1.2E < 0.1 < O.t 0.1 0.2 60. 60. < O.t < 0.1 1.5E-12 99 0 0 CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 OFFSITE SURVEY AND SAMPLING DATA TABLE E2. m (continued)

(T = 07:00) ( 10:00) 0 HONITOR READINGS AIR SANPLES 15-min RAD DATA ~CONTROLLER INFO (10 CF)

F IELD CLOSED IJINDOM OPEN QINDON bare f I lter- change cont aa l-131 SRD percent HONITOR MaiSt ground Nafst ground absorb absorb fn SRD cpa/ cence dose contr ib POIN'I (eR/hr) (aR/hr) (aR/hr) (aR/hr) CPH CPH eR 100 aa2 uCf/cc Pfa Plt Grd Air Saeple Background is 60 CPff 1.2D 0.4 0.4 0 7 0.8 60. 60. 0.1 < 0.1 7.1E-12 99 0 0 1.2C 1.3 1.4 2.3 2A 60. 61. 0.3 < 0.1 2.3E-11 99,0 0 1.28 2.7 2.7 4.6 4.7 60 61, 0.7 < 0.1 4.6E-11 99 0 0 1.2A 3.4 3.4 5.8 6.0 61 62. 0.9 < 0.1 5.9E-11 99 0 0 1 2CL 3.7 3.7 6.3 6.5 61 62, 0.9 < 0.1 6.4E-11 99 0 0 1.2a 3A 3.4 5.S 6.0 61. 62. 0.9 < 0.1 5.9E-11 99 0 0 1.2b 2.7 2.7 4.6 4.7 60. 61. 0.7 < 0.1 4.6E-11 99 0 0 1.2c 1.3 1.4 2.3 2A 60. 61. 0.3 < 0.1 2.3E-11 99 0 0 1.2d 0.4 0.4 0 7 O.S 60. 60. 0.1 < 0.1 7.1E-12 99 0 0

'I.2e < 0.1 0.1 O.f 0.2 60. 60. < 0.1 < 0.1 1.5E-12 99 D 0 OTHERS < 0.1 < 0.1 < 0.1 < 0 1 60. 60. < 0,1 < 0.'I O.OE+00 0 0 0

• FOR CONTROLLER/OBSERVER USE ONLY*

(Not to be Provided to Players):

Current Stability Class E Primary Release Pt: PS Flow: 2.1E+0 m3/sec Release Concentration-GIP (uCi/cc): 1.2E-01 4.9E-06 9.0E-06 (Flow & Release Integrated & Averaged over previous 15 minutes)

Whole Body Dose Projection: 3.6 mRem/hr Thyroid Dose Projection: 0.2 mRem/hr at a distance of: 1.20 miles downwind Maximums and Projections do not'include plant shine or ground shine Maximum Plume Whole-Body Dose Rate: 3.6 mRem/hr at a distance of: 1.20 miles downwind Maximum Thyroid Dose Commitment: 0.2 mRem/hr at a distance of: 4.47 miles downwind

NNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. n OFFSITE SURVEY AND SAMPLING DATA (T = 07:30) ( 10:30)

HONITOR READINGS AIR SAHPLES 15-ain RAD DATA ~CONTROLLER INFO (10 CF)

FIELD CLOSED QINDOM OPEN llINDON bare f I lter- change contcaa I-131 SRD percent HONI TOR waist ground Ma i st grcMld absorb absorb in SRD claa/ cence dose contrib POINT (aN/hr) (aR/hr) (aN/hr) (aN/hr) CPH CPH aSI 100caLZ uCI/cc Pie Plt Grd Air Saapte Background is 60 CPH

.5F 0.7 0.7 1.3 1.3 60. 61. 0.2 < 0.1 3.7E-11 99 0 0

.SE O.S 0.8 1.4 1A 60. 61. 0.2 < 0.1 4.0E-11 99 0 0

.5D 0,9 0.9 1.4 1.5 60. 61 0.2 c 0.1 4.2E-11 99 0 0

.SC 0,9 0.9 1.5 1.5 60. 6'I. 0.2 c 0.1 4.4E-11 99 0 0

.5$ 0.9 0.9 1.6 1.6 60. 61. 0.2 c 0.1 4.6E-11 99 0 0

.5A 0,9 0.9 1.6 1.6 60. 61. 0.2 < 0.1 4.6E- II 99 0 0

.SCL 0.9 0.9 1.6 1.6 60. 61. 0.2 c 0.1 4.7E.11 99 0 0

.Sa 0.9 0.9 1.6 1.6 60. 61. 0.2 < 0.1 4.6E-11 99 0 0

.5b 0,9 0.9 1.6 1.6 60. 6'I 0.2 < O.I 4.6E-11 99 0 0

.Sc 0.9 0.9 1.5 1.5 60. 61. 0.2 c 0.1 4.4E-11 99 0 0

.Sd 0.9 0.9 1A 1.5 60. 61. 0.2 c 0.1 4.2E-11 99 0 0

.Se 0.8 O.S 1A 1.4 60. 61. 0.2 < 0.1 4.0E-11 99 0 0

.5 f 0.7 0.7 1.3 1.3 60. 61. 0.2 < 0.1 3.7E-11 99 0 0 1F 0.2 0.2 0.3 0.3 60. 60. c 0.1 < 0 1 9.5E-12 99 0 0 1E 0.2 0.2 OA OA 60. 60. c 0.1 < 0.1 1.0E-11 99 0 0 1D 0.2 0.2 0.4 0.4 60. < 0.1 < 0.1 1.1E-11 99 0 0 60'.2 1C 0.2 OA OA 60. 60. c 0.1 < 0.1 1.2E-11 99 0 0 18 0.2 0.2 OA 0.4 60, 60. <01 < 0.1 1.2E-11 99 0 0 1A 0.2 0.3 0.4 OA 60. 60. c 0.1 c 0.1 1.2E-11 99 0 0 la 0.2 0.3 0.4 0.4 60. 60. c 0.1 <01 1.2E-11 99 0 0 1.5F < 0.1 < 0.1 0.1 0.1 60. c 0.1 c 0.1 4.2E-'I2 99 0 1.5E < 0.1 < 0.1 0.2 0.2 c 0.1 c 0.1 4.6E-12 99 0 1.5D 0.1 0,1 0.2 0.2 60. c 0.1 < 0.1 4.9E-12 99 0 1.5C 0.1 0.1 0.2 0.2 60. < 0.1 < 0.1 5.2E-12 98 0 1.5B 0.1 0.1 0.2 0.3 60. 60. < 0.1 <01 5.4E-12 98 0 1.5A 0.1 0;1 '.2 0.3 60. <01 < 0.1 '5.6E-12 98 0 1 1.5CL 0.1 0.1 "0.2 OA 60, < 0.1 c 0.1 5.6E-12 96 0 3 1.5a 0.1 0.1 "0.2 0.3 60. <01 c 0.1 5.6E-12 98 0 1 1.5b 0.1 0.1 0.2 0.3 60. <01 c 0.1 5.4E-12 98 0 1.5c 0.1 0,1 0.2 0.2 60. c 0,1 c 0.1 5.2E-12 98 0 1 1.5d 0.1 0.1 0.2 0.2 60. 60. c 0.1 c 0.1 4.9E-12 99 D 0 CONTXNUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. n OFFSITE SURVEY AND SAMPLING DATA (T = 07:30) ( 10:30)

(continued)

HOIITOR READINGS AIR SAHPLES 15-sin RAD DATA *CONTROLLER INF&

(10 CF)

FIELD CLOSED llINDOM OPEN MINDOM bare fliter- change contaa I-131 SRD percent HONITOR us i st ground us i st ground absorb absorb in SRD cpa/ cence dose contrib POINT (aR/hr) (eR/hr) (eR/hr) (aN/hr) CPH CPH ak 1 00cm2 uCi/cc Pie PIt Grd Air Saeple Background is 60 CPH 1.5e c 0.1 < 0.1 0.2 0+2 60. 60. < 0.1 < 0.1 4.6E-12 0 0 1.5f < 0.1 < 0.'I 0.1 0.1 60. 60. c 0.1 < 0.1 4.2E-12 0 0 2F c 0.1 c 0.1 <0 ~ 1 <0.1 60. 60. < O.t < 0.1 2.3E-12 0 0 2E c 0.1 c 0.1 < 0.1 0.1 60. 60. <<0.1 < 0,1 2.6E-12 0 0 2D < 0.1 <01 <01 0.1 60. 60. c 0.1 <01 2.8E-12 0 1 2C c 0.1 c 0.1 0.1 0.2 60. 60. c 0.1 < 0.1 2.9E-12 0 3 28 < 0.1 < 0-1 0.1 0.2 60. 60. < 0.1 c 0.1 3.1E-12 0 3 2A < 0.1 <<0.1 0.1 0.3 60. 60. c 0.1 c 0~1 3.2E-12 0 4 2CL c D.1 c 0.1 D 1 0.3 60. 60. <01 < 0.1 3.2E-12 0 4 2a <'0.1 c 0.1 0.1 0.3 60. 60. c D.t c 0.1 3.2E-12 D 4 2b <<0.1 <<01 0.1 0.2 60. 60. c 0.1 c 0.1 3.1E-12 0 3 2c c 0.1 c 0.1 0.1 0.2 60. 60. c 0.1 < O.t 2.9E.12 0 3 2d < 0.1 c 0 1 < 0.1 0.1 60. 60. <<0.1 c 0.1 2.8E-12 0 1 2e c 0.1 <01 < 0.1 0.1 60. 60. c 0.1 c 0.1 2.6E-12 0 0 2f c 0.1 c 0.1 <<0.1 0.1 60. <01 c 0.1 2.3E-12 99 0 0 2.5E c 0.1 <01 c 0.1 c 0.1 60. 60. < 0.1 c 0.1 1.6E-12 98 0 1 2.5D < 0.1 <01 < 0.1 0.1 ~

60. &0. < 0.1 < 0.1 1.88-12 97 0 2 2.5C c 0.1 <01 c 0.1 0.2 60. 60. c 0.1 c 0.1 1.9E-12 95 0 4 2.5B c 0.1 < 0-1 c 0.1 0.2 60. . 60. c 0.1 c 0.1 2.0E-12 93 0 6 2.5A c 0.1 <01 c 0.1 0.3 60. 60. c 0.1 c 0.1 2.0E-12 92 0 7 2.5CL c 0.1 << O.t c 0.1 0.3 60. 60. < O.t c 0.1 2.1E-12 92 0  ?

2.5a c 0.1 c 0.1 < 0.1 0.3 60. 60. c 0.1 c 0.1 2.0E;12 92 0  ?

2.5b c 0.1 < 0.1 c 0.1 0.2 60. 60. c 0.1 < 0.1 2.0E-12 93 0 6 2.5c c 0.1 < 0.1 c 0.1 0.2 60. 60. c 0.1 < 0.1 1.9E-12 95 0 4 2.5d c 0.1 < 0.1 < 0.1 0.1 c 0,1 < 0,1 1.8E-12 97 0 2 2.5e,.~c 0.1 c 0.1 c 0.1 <.,0.1 c 0.1 < 0.1 1.6E-12 98 0 1 3C <01 c D 'I < 0.1 02 c 0.1 < 0.1 1.38-12 93 0 6 38 c 0.1 <<01 c 0.1 0.2 c 0.1 c 0.1 1 4E-12 91 0 9 3A c 0.1 c 0.1 c 0.1 0.2 c 0.1 cD1 1 4E-12 89 0 1D Q' 0 OO 0 3CL c 0,1 c 0.1 < 0.1 0.3 60. 60. c 0.1 c 0.1 1,4E-12 89 0 10

' CONTINUED ON NEXT PAGE

MNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. n OFFSITE SURVEY AND SAMPLING DATA (T = 07:30) ( 10:30)

(continued)

HON(TOR READ(NBS AIR SAHPLES 15.min RAD DATA <<CONTROLLER 1KFO (10 CF)

F(ELD CLOSED MlNDQJ OPEN M1NDM bare f f l ter- change contma '-131 SRD percent HONLTOR mist ground wrist ground absorb absorb in SRD cpm/ conor dose contrib POINT (aH/hr) (sR/hr) (sk/hr) (sk/hr) CPH CPH eR 100 om2 uCi/cc Plm Plt Grd Air Sample Background is 60 CPH 3a < 0.1 c 0.1 < 0.1 0.2 60. 60. c 0.1 < 0.1 1 4E-12 89 0 10 3b < 0.1 < 0.1 < 0.1 0.2 60. 60. c 0.1 c 0.1 1.4E-12 91 0 9 3c < 0.1 c 0.1 < 0.1 0.2 60. 60. c 0.1 < 0.1 1.3E-12 93 0 6 4F < 0.1 < 0.1 0.1 0.1 60. 69. c 0.1 < 0.1 2.1E-12 99 0 0 4E 0.2 0.2 0.3 0.4 60. 90. <<0.1 < 0.1 6.3E-12 99 0 0 40 0.5 0.5 0.9 1.0 60. 150. 0.1 c 0.1 1.6E-11 99 0 0 4C 1.3 1.3 2.1 2.2 60. 250. 0.3 0.2 3o6E-11 99 0 0 48 2.1 2.1 3.6 3.7 61. 370. 0.5 0.3 6.1E-11 99 0 0 4A , 2.5 2.5 4.3 4.5 61. 450. 0.6 0.3 7.3E-11 99 0 0 4CL 2.7 2.7 4.6 4.8 61. 480. 0.7 0.3 7.7E-11 99 0 4a 2.5 2.5 4.3 4.5 61 450. 0.6 0.3 7.3E-11 99 0 4b 2.1 2.1 3.6 3.7 61. 370. 0.5 0.3 6.1E-11 99 0 4c 1.3 1.3 2.1 2.2 60. 250. 0.3 0.2 3.6E-11 99 0 4d 0.5 0.5 0.9 1.0 60. 150. 0.1 < 0.1 1.6E-11 99 0 4e 0.2 0.2 0.3 0.4 60. 90. < 0.1 < 0.1 6.3E-12 99 0 0 4f < 0.1 c 0.1 0.1 0.1 60. N. c 0.1 < 0.1 2.1E-12 99 0 0 4.5F < 0.1 < 0 ' < 0.1 < 0.1 60. 67. c 0.1 c 0 1 1.8E-12 99 0 0 4.5E 0.2 0.2 0.3 0.3 60. 85. c 0.1 < 0 1 5.4E-12 99 0 0 4.50 0.4 0.4 0.7 0.8 60. 130. 0.1 < 0.1 1.5E-11 99 0 0 4.5C 1.0 1.0 1.7 1.8 60. 240. 0.3 0.1 3.3E-11 99 0 0 4.5B 1.8 1.8 3.1 3.2 61. 360. 0.5 0.2 5.9E-11 99 0 0 4.5A 2.2 2.2 3.7 3.9 61. 430. 0.6 0.3 7 4E-11 99 0 D 4.5CL 2 4 2.4 4.1 4.2 61 460. 0.6 0.3 7.9E-11 99 0 0 4.5a 2.2 2.2 3.7 3.9 61. 430. 0.6. 0.3 7.4E-11 99 0 0 4.5b 1.8 1.8 3.1 3.2 61. 360. 0.5 0.2 5.9E-11 99 0 0 4.5c 1.0 1.0 -1.7 '-'1.8 240. 0.3 0.1 3.3E-11 99 0 0 4.5d 0.4 0.7 0.8

'.4

60. 130. 0.1 < 0.1 1.5E-11 99 0 0 4.5e 0.2 0.2 0.3 0.3 60. 85 < 0.1 < 0.1 5 4E-12 99 0 0 4.5f < 0.1 c 0.1 c 0.1 < 0.1 60. 67. c 0.1 c 0.1 1.8E-12 99 0 0 5F c 0.1 c 0.1 c 0.1 c 0.1 60. 66. c 0.1 c 0.1 1.1E-12 99 0 .0 CONTINUED ON NEXT PAGE

NNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. n OFFSETE SURVEY AND SAMPLING DATA (T = 07:30) ( 10:30)

(continueC)

HONITOR READINGS AIR SAHPLES 15-sin RAD DATA ~CONTROLLER INFO (10 CF)

F IELD CLOSED MINDSI OPEN MINDOM bare tilter- change contm I-131 SRD percent NONITOR uafst ground wrist ground absorb absorb in SRD cpa/ conc>> dose contr ib POINT (cR/hr) (aSI/hr) (sk/hr) (sSI/hr) CPN CPN sSI 100 an2 uCi/cc Plo Plt Qrd Air Seaple Background is 60 CPN 5E 0.1 0.1 0.2 0.2 60. 85. c 0.1 < 0.1 4.4E.12 99 0 0 5D 0.4 0.4 0.7 0.7 60. 130. < 0.1 < 0.1 1.4E-11 99 0 0 SC 1.0 1.0 1.7 1.7 60. 240. 0.2 0.1 3.5E-11 99 0 0 58 1.9 1.9 3.2 3.3 61. 390. 0.5 0.3 6.3E-1'I 99 0 0 5A 2.5 2.5 4.2 4.3 61. 490. 0.6 0.4 8.1E 11 99 0 0 SCL 2.6 2.6 4.4 4.5 61. 510. 0.7 0.4 8.7E-11 99 0 '

5e 2.5 2.5 4.2 4.3 61. 490. 0.6 0.4 8.1E-11 99 0 0 Sb 1.9 1.9 3.2 3.3 61. 390. 0.5 0 3 6.3E-11 99 0 0 5c 1.0 1 0 1 7 1.7 60. 240. 0.2 0 1 3 5E 11 99 0 0 5d 0.4 0.4 0.7 0.7 60. 'I30. c 0.1 < 0.1 1.4E-11 99 0 0 Se 0.1 0.1 0.2 0.2 60. 85. c 0.1 < 0.1 4.4E-12 99 0 0 Sf c 0.1 < 0.1 < 0.1 0.1 60. 66. < 0.1 c 0.1 1 'IE '12 99 0 0 6F < 0.1 c 0.1 c0.1 c 0.1 60. 63. c 0.1 < 0.1 8.9E 13 99 0 0 6E c 0.1 < 0.1 <<0.1 c 0.1 60. 75. c 0.1 <<0.1 3.8E 12 99 0 0 6D 0.2 0.2 0.3 0.3 60. 110. < 0.1 < 0.1 1.3E-11 99 0 0 6C 0.5 0.5 0.9 09 60. 190. 0.1 0.1 3.3E-11 99 0 0 68 1.0 1.0 1.7 1.7 61. 300. 0.2 0.2 6AE-11 99 0 0 6A 1.3 1.3 2.2 2.3 61. 390. 0.3 0.3 8AE-11 99 0 0 6CI. 1 4 1.5 2.5 2.5 6'I 420. 0.4 0.3 9.'IE 11 99 0 0 1.3 1.3 2.2 2.3 61. 390. 0.3 0.3 8.4E 11 99 0 0 6b 1.0 1.0 4.7 1.7 61. 300. 0.2 0.2 6.4E-11 99 0 0 0.5 0.5 0.9 0.9 60. 190. 0.1 0.'I 3.3E 11 99 0 0 0.2 0.2 0.3 0.3 60. 110. < 0.1 c 0.1 1.3E.11 99 0 0

<<0.1 <<,0.1 c 0.1 < 0.1 60. 75. c 0.1 c 0.1 3.8E 12 99 0 0 6E <01 < 0.1 <.0'1 < 0.1 63. < 0.1 < 0.1 8.9E 13 99 0 0

'I7F' 0.1 < 0,1 < 0.1 <'0 1 60. 63 < 0.1 < 0.1 7.4E-13 99 0 0 7E c 0.1 <<0.1 c 0,1 < 0.1 . 60. 72. c 0.1 c 0.1 3.5E-12 99 0 0 7D c 0.1 < 0.1 0.2 0.2 60. 100. < 0.1 < 0.1 1.3E-11 99 0 0

. 7C 0.2 0.2 0.4 OA 180 c 0.1 c 0.1 3.3E-11 0 0 78 0.5 . 0.5 0.9 0.9 61 300. 0.1 0.2 6.8E 11 99 0 0

.," CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. n OFFSITE SURVEY AND SAMPLING DATA (T = 07:30) ( l0:30)

(continued)

MONITOR READINGS AIR SAMPLES 15-sin RAD DATA ~CONTROLLER INFO (10 CF)

F IELD CLOSED ill NOON OPEN MINOOM bare f I lter- change contae '-131 SRD percent MONITOR Moist ground uaist ground absorb absorb in SRD cpa/ conc e dose contr lb POINT (aR/hr) (aN/hr) (nN/hr) (sN/hr) CPM CPM aR 100 cm2 uCI/cc Pls Plt Ord Air Seapie Background is 60 CPM 7A 0.7 0.7 1.2 1.2 61. 370. 0.2 0.3 9.1E-11 99 0 0

?CL 0.8 0.8 1.3 1.3 61. 400. 0.2 0.3 9 9E-11 99 0 0

?a 0.7 D.7 1.2 1.2 61. 370. 0.2 0.3 9.1E-11 99 0 0

?b 0.5 0.5 0.9 0.9 61. 300. 0.1 0.2 6.8E-11 99 0 0

?c 0.2 Oo2 0.4 0.4 60. < 0.1 c 0.1 3.3E 11 99 0 0

?d < 0.'I c 0.1 0.2 0.2 100. c 0.1 c 0.1 1.3E-11 99 0 0 7e < 0.1 c D.1 c 0.1 c D.1 72. < 0.1 c 0.1 3.5E-12 99 0 0 7f < 0.1 c 0.1 c 0.1 c 0.1 60. 63. < 0.1 c 0.1 7.4E 13 99 0 0 1CI. 0.3 0.3 0.4 0.6 60. 60. < 0.1 < 0.1 1.2E-11 98 0 1 1b 0.2 0.2 0.4 0.5 60. 60. < 0.1 < 0.1 1.2E 11 98 0 1 lc 0.2 0.2 D.4 0.5 60. 60. <<0.1 c 0.1 1.1E 11 99 0 0 1d 0.2 0.2 0.4 0.4 60. 60. c 0.1 < 0+1 1.1E 11 99 0 0 1e 0.2 0.2 0.3 0.4 60. 60. c 0.1 < 0.1 9.8E-12 99 0 0 1f 0.1 0.1 0.2 0.2 60. 60. <<0.1 c 0.1 7.2E-12 99 0 0 1.2F 0.1 0.1 D.2 0.2 60. c 0.1 < 0.1 6.5E 12 99 0 0 1.2E 0.1 0.1 0.2 0.3 60. <<0.1 c 0.1 7.1E-12 99 0 0 1.20 0.2 0.2 0.3 0.3 60. c 0.1 < 0.1 7.7E-12 99 0 0 1.2c 0.2 0.2 0.3 0.4 60. <<0.1 c 0.1 8.1E-12 98 0 1 1.28 0.2 0.2 0.3 0.4 60. < 0.1 < 0.1 8.4E-12 98 0 1 1.2A 0.2 0.2 0.3 0.4 60. 60. <<0.1 c 0.1 8.6E-12 98 0 1 1.2CL 0.2 0.2 0.3 0 4 60. 60. < 0.1 < 0.1 8.?E- 12 98 0 1 1.2a 0.2 0.2 0.3 0 4 60. 60. < 0.1 c 0.1 8.6E 12 98 0 1

'1.2b 0.2 0.2 0.3 0.4 60. 60. c 0.1 < 0.1 8.4E-12 98 0 1 1.2c 0.2 D.2 0.3 0.4 60. 60. c 0.1 <<0.1 8.1E 12 98 0 1 1.2d 0.2 0.2 0.3 0.3 60. 60. < 0.1 < 0.1 7.?E-12 99 0 0 1.2e 0.1 0.1 0.2 0.3 60. 60. < 0.1 < 0.1 7.1E-12 99 0 0 1.2f 0.1 0.1 0.2 0.2 60. 60. c 0.1 < 0.1 6.5E-12 99 0 0 OTHERS c 0.1 c 0.1 < 0.1 c 0.1 60. 60. c 0.1 < 0.1 O.DE+00 0 0 0 CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. n OFFSITE SURVEY AND SAMPLING DATA (T = 07:30) ( 10:30)

(continued)

• FOR CONTROLLER/OBSERVER USE ONLY*

(Not to be Provided to Players): ~

Current Stability Class B Primary Release. Pt: PS Flow: 2.1E+0 m3/sec Release Concentration-GIP (uCi/cc): 1.2E-01 1.3E-05 1.6E-05 (Flow & Release Integrated & Averaged over previous 15 minutes)

Whole Body Dose Projection: 0.2 mRem/hr Thyroid Dose Projection: < 0.1 mRem/hr at a distance of: 1.20 miles downwind Maximums and Projections do not include plant shine or ground shine Maximum Plume Whole-Body Dose Rate: 1.1 mRem/hr at a distance of: 2.98 miles downwind Maximum Thyroid Dose Commitment: 0.2 mRem/hr at a distance of: 5.53 miles downwind

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. o OFFSITE SURVEY AND SAMPLING DATA (T = 08:00) ( 11:00)

HONI TOR READINGS AIR SAHPLES 15-min RAD DATA <<CONTROLLER INFO (10 CF)

F IELD CLOSED llINDOM OPEN MINDOM bare filter. change contam I-131 SRD percent HONITOR us i st ground mist ground . absorb absorb in SRD cpm/ conc. dose contrib POINT (mR/hr) (mR/hr) (sR/hr) (mR/hr) CPH CPH eR 100cmZ uCI/cc Plm Plt Grd Air Sample. Background is 60 CPH

.5F 0.7 0.7 1.2 1.2, 60. 61.

61.

0.2 0.2

< 0.1 c 0.1 2.2E-11 2.4E-11 99 99 0

0 0

0

.5E 0.7 0.7 1.3 1.3 60.

.5D 0.8 0.8 1.3 1A 60. 61 0.2 c 0.1 2.6E-11 99 0 0

.5C 0.8 0.8 1A 1.4 60. 6'I. 0.2 c 0.1 2.7E-11 99 0 0

.58 0.9 0.9 1.4 1.5 60. 61. 0.2 < 0.1 2.8E.11 99 0 0

.5A 0.9 0.9 1.5 1.5 60. 61. 0.2 < 0.1 2.8E-11 99 0 0

.SCL 0.9 0.9 1.5 1.5 60. 61. 0.2 < 0.1 2.8E-11 99 0 0

.5a 0.9 0.9 1.5 1.5 60. 61. 0.2 < 0.1 2.8E 11 99 0 0

.Sb 0.9 0.9 1A 1.5 60. 61. 0.2 < 0.1 2.8E-11 99 0 0

.5c 0.8 0.8 1.4 1A 60. 61. 0.2 < 0.1 2.7E-11 99 0 0

.5d 0.8 0.8 1.3 1A 60. 61. 0.2 c 0.1 2.6E-11 0 0

.5e 0.7 0.7 1.3 1.3 60. 61. 0.2 c 0.1 2 4E-11 0 0

.5f 1F 1E 0.7 0.2 0.2 0.7 0.2 0.2

'.3 1.2 0.3 1.2 0.3 0.3 60.

60.

60.

61.

60.

60.

0.2 c 0.1

<<0.1

< 0.1 c 0.1 c 0.1 2 2E-11 5.7E-12 6.2E-12 0

0 0

0 0

0 1D 0.2 0.2 0.3 0.4 60. 60. c 0.1 < 0.1 6.7E-12 99 0 1C 0.2 0.2 0.4 OA 60. 60. c 0.1 c 0.1 7.0E-12 99 0 18 0.2 0.2 0.4 OA 60. 60. c 0.1 c 0.1 7.3E 12 99 0 1A 0.2 0.2 0.4 0.4 60. 60. c 0.1 c 0.1 7.5E-12 99 0 1a 0.2 0.2 0.4 0.4 60. 60. c 0.1 <<0.1 7.5E-12 99 0 1.5F < 0.1 < 0.1 0.1 0.1 60. 60. c 0.1 c 0.1 2.5E-12 99 0 0 1.5E < 0.1 < 0.1 0.1 0.2 60. 60. c 0.1 c 0.1 2.8E-12 99 0 0 1.5D c 0.1 c 0.1 0.2 0.2 60. 60. c 0.1 c 0.1 3.0E-12 99 0 0 1.5C <<0.1 c 0.1 0.2 0.2 60. 60. c 0.1 < 0.1 3.2E-12 98 0 1 1.58 0.1 0.1 0.2 0.2 60. 60. c 0.1 c 0.1 3.3E-12 98 0 1 1.5A 1.5CL 1.5a 0.1 0.1 0.1

'.1 0.1 0.1 0.2 0.2 0.2 0.2 0.3 0.2 60.

60.

60.

c 0.1 c 0.1 c 0.1 c 0.1

< 0.1 c 0.1 3.4E-12 3AE-12 3AE-12 98 97 98 0

0 0

1 2

1 1.5b 0.1 0.1 0.2 0.2 60. c 0.1 c 0.1 3.3E-12 98 0 1 1.5c "< 0.1 < 0.1 0.2 0.2 60. < 0.1 c 0.1 3.2E-12 98 0 1 1.5d c 0.1 <<0.1 0.2 0.2 60. 60. < 0.1 c 0,1 3.0E-12 99 0 0 CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. o OFFSZTE SURVEY AND SAMPLING DATA (T ~ 08 00) ( 11:00)

(continued)

HONITOR READINGS AIR SAHPLES 15.min RAD DATA ~CONTROLLER INFO (10 CF)

FIELD CLOSED QI NOON OPEN NINDOM bare fliter . change contm 1-131 SRD percent HONITOR waist ground uaist grand absorb absorb in SRD cpm/ cence dose contrib POINT (mR/hr) (mR/hr) (mR/hr) (mR/hr) CPH CPH mR 1 00cm2 uCI/cc Plm Plt Grd Air Sample Background is 60 CPH 1.5e c 0.1 c 0.1 0.1 0.2 60. 60. < 0.1 < 0.1 2.8E-12 99 0 0

'1.5f < 0.1 c 0.1 0.1 0.1 60. 60. <<0.1 c 0.1 2.5E-12 99 0 0 2F < 0.1 < 0.1 c 0.1 < 0.1 60. < 0.1 <<0.1 1.4E-12 99 0 0 2E c 0.1 c 0.1 <0.1 <01 60. 60. <<0.1 c 0.1 1.5E-12 99 0 0 2D c 0.1 < 0.1 c 0.1 0.1 60. < 0.1 < 0.1 1.7E-12 98 0 1 2C < 0.1 c 0.1 c 0.1 0.2 60 60 < 0.1 <<01 1.8E-12 97 0 2 28 < 0.1 < 0.1 < 0.1 0.2 60. 60. < 0.1 < 0.1 1.9E-12 97 0 2 2A < 0.1 < 0.1 0.1 0.2 60. < 0.1 c 0.1 1.9E-12 97 0 2 2CL c 0.1 < 0.1 0.1 0.2 60. < 0.1 c 0.1 1.9E-12 96 0 3 2a < 0.1 c 0.1 0.1 0.2 60. 60. < 0.1 c 0.1 1.9E-12 97 0 2 2b < 0.1 < 0.1 < 0.1 0.2 60. 60. c 0.1 c 0.1 1.9E-12 97 0 2 2c < 0.1 < 0,1 < 0.1 0.2 60. 60. c 0.1 c 0.1 1.8E-12 97 0 2 2d < 0.1 c 0,1 < 0.1 01 60. 60. < 0.1 c 0.1 1.7E-12 98 0 1 2e c 0.1 c 0.1 < 0.1 << 0.1 60. 60. < 0.1 < 0.1 1.5E-12 99 0 0 2f < 0.1 < 0.1 <<01 < 0,1 60. 60. < 0.1 c 0.1 1.4E-12 99 0 0 2.5D < 0.1 < 0.1 < 0.1 < 0.1 60. 60. < 0.1 < 0.1 1.1E-12 98 0 1 2.5C <<0.1 c 0.1 c 0.1 D.1 60. 60. c D.1 <<0.1 1.1E-12 96 0 3 2 58 < 0.1 < 0.1 < 0.1 0.2 60. 60. < 0.1 c 0.1 1.2E-12 95 0 4 2.5A < 0-1 < 0.1 <<0.1 0.2 60. 60. < 0.1 c 0.1 1.2E-12 94 0 5 2.5CL <01 < 0,1 < 0.1 0.2 60. < 0.1 < 0.1 1.2E-12 94 0 5 2.5a < 0.1 < 0.1 < 0.1 0.2 ~ 60. <<0.1 < 0.1 1.2E-12 94 0 5 2.5b < 0.1 < 0.1 < 0.1 0.2 60. < 0.1 c 0.1 1.2E-12 95 0 4 2.5c < 0.1 < 0.1 < 0.1 0,1 60. c 0.1 <<0.1 1.1E-12 96 0 3 2.5d <<0.1 c 0.1 < 0.1 < 0.1 60. c 0.1 < 0.1 1.1E-12 98 0 1 3C < 0.1 ,<0.1 < 0.1 0.1 60. 60. c 0.1 c 0.1 7.9E-13 95 0 38 <01 c 0.1,f .<01 0,2 60. 60. 0.1 < 0.1 8.3E-13 93 0 6 3A = c 0.1 c 0.1 ic 0.1 0.2 60. 60. << 01 <0.1 8.6E-13 93 0 6 3CL c 0.1 <01 c 0.1 0.2 60. 60. 0.1 < 0.1 8.7E-13 92 0 7 3a "< 0.1 < 0.1 < 0.1 0.2 60. 60. << 0.1 < 0.1 8.6E 13 93 0 6 3b < 0.1 c 0.1 'c 0+1 0,2 60. 60. c 0.1 c 0.1 8.3E 13 93 0 6

\

CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. o OFFSITE SURVEY AND SAMPLING DATA (T = 08:00) ( 11:00)

(continued)

NON I TOR READINGS AIR SAHPLES 15-min RAD DATA ~CONTROLLER IN'10 CF)

FIELD CLOSED llINOON OPEN MIKOOM bare filter- change contam ~ 1-131 SRD percent HONITOR Mal st ground ualst ground absorb absorb In SRD cpa/ conc. dose contr lb POINT (mR/hr) (mR/hr) (mR/hr) (mR/hr) CPH CPH mR 100cm2 uCI/cc P lm Pl t 0rd Alr Sample Background Is 60 CPH 3c c 0.1 c 0.1 < 0.1 0.'I 60. 60. c 0.1 < 0.1 7.9E-13 95 0 4 4D c 0.1 < 0.1 c 0.1 < 0.1 60. 61. c 0.1 < 0.1 5.1E-13 95 0 4 4c < 0.1 c 0.1 < 0.1 0.1 60. 61. c 0.1 c 0.1 5.6E-13 92 0 7 48 c 0.1 < 0.1, < 0.1 0.2 60. 61. c 0.1 < 0.1 5.7E-13 87 0 12 4A c 0.1 c 0.1 < 0.1 0.2 60. 61 o < 0.1 c 0.1 6.1E-13 85 0 14 4CL < 0.1 << 0.1 < 0.1 D.2 60. 61. < 0.1 <01 6.1E-13 85 0 14 4a << 0.1 <<0.1 < 0.1 0.2 60. 61. < 0.1 < 0.1 6.1E-13 85 0 14 4b c 0.1 < 0.1 c 0.1 0.2 60. 61. <<0.1 < 0.1 5.7E-13 87 0 12 4c c 0.1 << 0.1 < 0.1 0.1 60. 61. c 0.1 < 0.1 5.6E-13 92 0 7 4d < 0.1 c D.1 < 0.'I c 0.1 60. 61. c.0.1 < 0.1 5.1E-13 0 4 4.5C < 0.1 <<0.1 c 0.1 c 0.1 60. 61. c 0.1 < 0.1 4AE-13 0 9 4.58 < 0.1 c 0.1 < 0,1 0.2 60. 61. < 0.'I < 0.1 4.6E-13 0 15 4.5A < 0.1 c 0.1 < 0.1 0.2 60. 61. < 0.1 < 0.1 4.7E.13 0 17 4.5CL < 0.1 c 0.1 < 0.1 0.2 60. 61. < 0.1 < 0.1 4.7E-13 0 18 4.5a < 0.1 c 0.1 < 0,1 0.2 60. 61. < 0.1 < 0:1 4.7E-13 82 0 17 4.5b < 0.1 c 0.1 <<0.1 0.2 60. 61. < 0.1 <<0.1 4.6E-13 84 0 15 4.5c < 0.1 c 0.1 < 0.1 < 0.1 60. 61. < 0.1 < 0.1 4 4E 13 90 0 9

< 0.1 c 0.1 c 0.1 'l.1E-12

'0.

SF < 0.1 < 0.1 65. < 0.1 99 0 0 5E 0.1 0.1 0.2 0.2 60. 76. < 0.1 < 0.1 3.2E 12 99 0 0 50 0.3 0.3 0.6 0.6 60. 110. < 0.1 <01 9.1E-12 99 0 5C 0.8 0.8 1.4 1A 60. 180. 0.2 <01 2.0E-11 99 0 58 1.4 1A 2.5 2.6 60. 280. 0.4 0,2 3.9E-11 99 0 5A 1.8 1.8 3.1 3.3 60. 340. 0.5 0.2 4.7E-11 99 0 SCL 2.0 2.0 3.4 3.5 60. 370. '.5 0.3 5.2E-11 99 D Sa Sb 5c

'.4180.8 18 1A 0.8 31 2.5 1.4 3.3 2.6 1.4 60.

60.

60.

340.

280.

180.

0.5 0.'4 0.2 <

0.2 4.7E-11 0.2 3.9E-11 0.1 2 DE-11 99 99 99 0

0 0

0 0

0 5ij 0.3 0.3 0.6 0.6 60. 110. < 0.1 < 0.1 9.1E-12 99 0 0 5e 0.1 0.1 0.2 0,2 60. 76. < 0.1 < 0.1 3.2E-12 99 0 0 5f c 0.1 c 0.'1 c 0.1 c 0.1 60. 65. c 0.1 c 0.1 1.18-12 99 0 0 CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. o OFFSITE SURVEY AND SAMPLING DATA (T 08 00) ( 11: 00)

(continued)

HONITOR READINGS AIR sAHPLEs 15-4a5n RAD DATA <<CONTROLLER INFO (10 CF)

FIELD CLOSED MINDOM OPEN MINDOI bere f lter-5 change cont4aa I 131 SRD percent HONITOR 4401st ground waist ground absorb absorb In SRO cp4a/ cence dose contrlb POINT (aN/hr) (aN/hr) (aR/hr) (aR/hr) CPH CPH aSI 100 c4aZ uCI/cc PI4a Plt Grd Alr 84aaple gackground 5s 60 CPH 6F c 0.1 < 0.1 < 0.1 < 0.1 60. 64. c 0.1 c 0.1 9.5E-13 99 0 0 6E < 0.1 c 0.1 01 0.1 60. 74. c 0,1 <<0.1 3.2E-12 99 0 0 6D 0.2 0.2 0.4 OA 60. 110. c 0.1 < 0.1 1.0E-11 99 0 0 6C 0.6 0.6 1.0 1.1 60. 180. 0.2 < 0.1 2.4E-11 99 0 0 68 1.2 1.2 2.0 2.1 60. 280. 0.3 0.2 4.7E-11 99 0 0 6A 1.5 1.5 2.5 2.6 61 340. 0.4 0.2 6.1E-11 99 0 0 6CL 1.6 1.6 2.8 2.9 61. 370. 0.4 0.3 6.6E-11 99 0 0 60 1.5 1.5 2.5 2.6 61. 340. 0.4 0.2 6.1E-11 99 0 0 6b 1.2 1.2 2.0 2.1 60. 280. 0.3 0.2 4.7E-1'I 99 0 0 6c 0.6 0.6 1.0 60. 180. 0.2 < 0.1 2.4E-1'I 99 0 0 6d 0.2 0.2 0.4 OA 60. 110. < 0.1 < 0.1 1.0E-11 99 0 0 6e c 0.1 < 0.1 0.1 0.1 60. 74. < 0.1 < 0.1 3.2E.12 99 0 0 6f < 0.1 < 0.1 < 0.1 c 0.1 60. 64. c 0.1 < 0.1 9.5E-13 99 0 0 7F <<0.1 c 0.1 < 0.1 < 0.1 60. 62. c 0.1 < 0.1 8.4E-13 99 0 0 7E < 0.1 < 0.1 <<0.1 < 0.1 60. 70 0 c 0.1 < 0.1 2.9E-12 99 0 0 7D 0.1 0.1 0.2 0.2 60. 94. < 0.1 < 0.1 9.1E-12 99 0 0 7C 0.3 0.3 0.5 0.5 60 150. <<0,1 <<01 2AE-11 99 0 0 78 0.6 0.6 1.0 1.0 60. 240. 0.1 0.1 4.7E-11 99 0 0 7A 0.7 0.7 1.3 1.3 61. ~ 3DD. 0.2 D.2 6.3E-11 99 0 0 7CL 0.8 0.8 1.4 1.5 61 330 0.2 0.2 6.9E-11 99 0 0 70 0.7 0.7 1.3 1.3 61. 3¹ 0.2 0.2 6.3E-11 99 0 0 7b 0.6 D.b 1.D 1.0 60. 240. 0.1 0.1 4.7E-11 99 0 0 7c 0.3 0.3 0.5 0.5 60. 150. < 0.1 c 0.1 2.4E-11 99 0 0 7d D.1 0.1 0.2 0.2 60 94. < 0.1 c 0.'I 9.1E-12 99 0 0 70 <Dj <01 c 0.1 < 0.1 60. 70. c 0.1 < 0.1 2.9E-12 99 0 0

'7f . c 0.1 < 0.1 c 0.1 4

c 0.1 60. 62. <<0.1 c 0.1 8AE-13 99 0 0 SF c 0.1 < 0.1 0.1 <<0.1 62. c 0.1 < 0.1 5.1E-13 99 0 0 8E c 0.1 < 0.1 c01 <01 60. 69. c 0.1 < 0.1 2.4E-12 99 0 0 SD < 0.1 <<0.1 01 D2 60 94. <<0.1 c 0.1 9.6E-12 99 0 0 8C 0.3 0.3 OA 0.4 60. 160- c 0.1 <<0.1 2.7E-11 99 0 0 CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. o OFFSITE SURVEY AND SAMPLING DATA (T = 08:00) ( 11:00)

(continued)

HONITOR READINGS AIR SAHPLES 15.min RAD DATA ~CONTROLLER INFK (10 CF)

FIELD CLOSED NINDON OPEN MINDOM bare f I lter. change contuse '-131 SRD percent HONITOR waist grand waist ground absorb absorb in SRD cps/ conc. dose contrib POINT (aN/hr) (aN/hr) (aN/hr) (aN/hr) CPH CPH aN 100cm2 uC I/cc P Ia P lt Grd Air Seeple Background is 60 CPII 0.5 0.5 0.9 0.9 60. 270. 0.1 0.2 5.7E-11 99 0 0 0.8 0.8 1.3 1.3 61. 360. 0.2 0.2 7.9E-11 99 0 0 0.9 0.9 1.5 1.5 61. 390. 0.2 0.3 8.8E-11 99 0 0

< 0.1 < 0.1 < 0.1 < 0.1 60. 62. < 0.1 0.1 2.7E-13 100 0 0 9C < 0.1 < 0.1 < 0.1 < 0.1 60. 66. < 0.1 < 0.1 9.1E-13 100 0.1 0.1 0.2 0.2 60. 74. < 0.1 < 0.1 2.2E-12 100 9A 0.2 0.2 0.3 0.3 60. 82. < 0.1 < 0.1 3.5E 12 100 9CL 0.2 0.2 0.4 0.4 60. 85. < 0.1 < 0.1 4.1E-12 100 1CL 0.2 0.2 OA 0.5 60. 60. < 0.1 < 0.1 7.5E-12 99 1b 0.2 0.2 OA 0.5 60. 60. < 0.1 < 0.1 7.1E-12 99 0 0 1c 0.2 0.2 0.4 OA 60. 60. <<0.1 < 0.1 6.8E-12 99 0 0 1d 0.2 0.2 0.3 OA 60. 60. < 0.1 < 0.1 6.4E.12 99 0 0 1e 0.2 0.2 0.3 0.3 60. 60. < 0.1 <<0.1 5.9E-12 99 0 0 1 f 0.1 0.1 0.2 0.2 60 60. <<0.1 < 0.1 4.4E-12 99 0 0 1.2F 0.1 0.'I 0.2 0.2 < 0 ' <<0.1 4.0E-12 99 0 0 1.2E 0.1 0.1 0.2 0.2 < 0.1 < 0.1 4.3E-12 99 0 0 1.2D 0.1 0.1 0.2 0.3 < 0.1 < 0.1 4.6E-12 99 0 0 1.2C 0.2 0.2 0.3 0.3 60. < 0.1 < 0.1 4.9E-12 99 0 0 1.28 0.2 0.2 0.3 0.3 60. '0. < 0.1 <<0.1 5.1E-12 98 0 1.2A 0.2 0.2 0.3 Oo4 60. < 0.1 < 0.1 5.2E-12 98 0 1 1.2CL 0.2 0.2 0.3 OA 60. < 0.1 < 0.1 5.3E-12 98 0 1 1.2a 0.2 0.2 0.3 OA 60. < 0.1 < 0.1 5 2E-12 98 0 1 1.2b 0.2 0.2 0.3 0.3 60. < 0.1 < 0.1 5.1E-12 98 0 1 1.2c 0.2 0.2 0.3 0.3 60. < 0.1 < 0.1 4.9E-12 99 0 0 1.2d 0.1 0.1 0.2 0.3 60. 60. < 0.1 < 0.1 4.6E-12 99 0 0 1 e2e 0.1 0.1 0.2 0.2 60. 60. < 0.1 < 0.1 4.3E-12 99 0 0 1.2f 0.1 0.1 0.2 0.2 60. 60. < 0.1 < 0.1 4.0E-12 99 0 0 OTHERS < 0.1 < 0.1 < 0.1 < 0.1 60. 60. < 0.1 < 0.1 O.DE+00 0 0 0 CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E2. o OFFSITE SURVEY AND SAMPLING DATA (T = 08 00) ( 11:00)

(continued)

• FOR CONTROLLER/OBSERVER USE. ONLY*

(Not to be Provided to Players):

Current Stability Class B Primary Release Pt: PS Flow: 2.1E+0 m3/sec Release Concentration-GIP (uCi/cc): 1.1E-01 7.5E-06 1.3E-05 (Flow & Release Integrated & Averaged over previous 15 minutes)

Whole Body Dose Projection: 0.2 mRem/hr Thyroid Dose Projection: < 0.1 mRem/hr at a distance of: 1.20 miles downwind Maximums and Projections do not include plant shine or ground shine Maximum Plume Whole-Body Dose Rate: 0.7 mRem/hr at a distance of: 3.98 miles downwind Maximum Thyroid Dose Commitment: 0.1 mRem/hr at a distance of: 6.22 miles downwind

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E3. a ENVIRONMENTAL SAMPLING DATA (T = 00: 00) ( 03: 00)

OFFSZTE LEAFY GROUND MONITORING VEGETATION DEPOSITION LOCATION iodine total (pci/kg) (pci/kg) (cpm/100cm2)

ALL SAMPLES LESS THAN MDA

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E3. c ENVIRONMENTAL SAMPLING DATA (T = 03:30) ( 06:30)

OFFSZTE LEAFY GROUND MONITORING VEGETATION DEPOSITION LOCATION iodine total (pCi/kg) (pCi/kg) (cpm/100cm2) 5A 0 1 0' 0.1

.5CL 0.1 0.2 0.1

.5a 0~1 0 2 0.1 1B 0.1 0 2 0.1 1A 0 1 0' 0~1 1a 0.1 0.2 0~1 2.5D 0' 0.3 0.1 2.5C 0.9 0 ' 0.1 2.5B 2 0 2 2 0 1 2 5A 3 3 3 ' 0.1 2 5CL 4' 4.3 0.1 2 'a '.5b 3~3 2.0 3.6 2 '

0.1 0'

2.5c 0' 0.9 0.1 2.5d 0.3 0.3 0.1 3D 0.1 0.1 0.1 3C 0.4 0.4 0 1 3B 0 9 1 0 0.1 3A 1 6 1.8 0.1 3CL 1.9 2 1 0 1 3a 1.6 1 8 0~1 3b 0' 1.0 0.1 3c 0.4 0.4 0.1 3d 0 1 ,.0 1 0.1 1CL 0~1 0' 0.1 1 2A 0.1 0.2 0.1

1. 2CL 0.2 0.1 1 'a 0~1 0 1 0.2 0.1 OTHER SAMPLES LESS THAN MDA

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E3 ~

ENVIRONMENTAL SAMPLING DATA (T = 04:00) ( 07:00)

OFFSITE LEAFY GROUND MONITORING VEGETATION DEPOSITION LOCATION iodine total (pCi/kg) (pCi/kg) (cpm/100cm2)

.5C 0~1 0~1 0.1

.5B 0.1 0' 0.1

.5A 0~1 0' 0.1

.5CL 0 1 0' 0.1

.5a 0 1 0' 0.1

.5b 0 1 0 2 0.1

.Sc 0 1 0.1 0.1 1B < 0.1 0.2 0.1 1A 0~1 0.2 0.1 1a 0.1 0.2 0.1 1.5CL 0.1 0.1 0.1 2CL < 0.1 0.1 0.1 2.5D 0 ' 0.2 0' 2.5C 0.8 0.8 0.1 2.5B 1.8 1.9 0.1 2.5A 3 ' 3.1 0~1 2.5CL 3.6 3 7 0.1 2.5a 3.0 3.1 0.1 2 ~ Sb 1' 1.9 0.1 2.5c 0' 0.8 0 1 2.5d 0' 0.2 0.1 3D 0' 0.2 0.1 3C 0' 0.6 0.1 3B 1.4 1.6 0.1 3A 2.4 2 7 0.1 3CL 2.9 3 ' 0.1 3a 2 4 2.7 0.1 3b 1' 1.6 0' 3c 0.6 0.6 0' 3d 0.2 0.2 0.1 4C 0~1 0.1 0.1 4B 0.2 0.3 0.1 4A 0.4 0.5 0.1 4CL 0 5 0.6 0'. 1 4a 0.4 0.5 0.1 4b 0' 0.3 0.1 4c 0~1 0.1 0~1 1CL 0' 0.2 0~1 1b 0.1 0~2 0.1 1.2B 0.1 0.2 0.1 CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E3. e ENVIRONMENTAL SAMPLING DATA (T = 04 00) ( 07:00)

(continued)

OFFSITE LEAFY GROUND MONITORING VEGETATION ,DEPOSITION LOCATION iodine total (pCi/kg) (pCi/kg) (cpm/100cm2)

1. 2A 0 1 0.2 0 1 1 2CL 0 1 0' 0 1 1 'a 1.2b <

F 1 0.1 0 2 0 2 <

0 1 0.1 OTHER SAMPLES LESS THAN MDA

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E3. e ENVIRONMENTAL SAMPLING DATA (T = 04:30) ( 07: 30)

OFFSITE LEAFY GROUND MONITORING, VEGETATION DEPOSITION LOCATION iodine total (pci/kg) (pci/kg) (cpm/100cm2)

.5F 850. 880 0.1

~ 5E 1700 1800 0.2

~ 5D 3200. '300 0 '

.5C 4500. 4600 0.4

.5B 4800. 4900. 0'

~ 5A 4800. 4900. 0.4

.5CL 4800. 4900 0.4

.5a 4800 4900 0 4

~ Sb 4800. '900.

0.4

.5c 4500. 4600 0.4

~ 5d 3200. 3300 0.3

.5e 1700. '800 0.2 5f 850. 880. 0.1 1F 250 260 0.1 1E 580. 590 ~ 0.1 1D 1200 1200. 0.1 1C 2000 2100 0.2 1B 2200. '300 0.2 1A 2300. '400.

0.2 1a 2300. 2400. 0.2 1 5F 0.1 0.3 0.1 1.5E 0~1 0.7 0.1 1.5D 0 1 1 5 0.1 1.5C 0 1 '2 ~ 8 0.1 1.5B 0~1 3~4 0.1 1 5A 0.1 3.7 0.1 1.5CL < 0.1 0.2 0.1 1.5a < 0.1 3 7 0.1 1.5b 0.1 3.4 0.1 1.5c 0.1 2.8 0.1 1.5d 0~1 1.5 0.1 1.5e 0' 0 ' 0 '

1 Sf 0.1 0.3 0.1 2A < 0.1 0.2 0.1 2CL < 0.1 0.2 0.1 2a 0~1 0.2 0.1 2 'D 0.2 0.2 0.1 2 5C 0.7 0.7 0.1 2 ~ SB 1.6 1.7 0.1 2 SA 2 ' 2 ' 0.1

.. CONTINUED ON NEXT PAGE

NNP-2. Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E3.

ENVIRONMENTAL SAMPLING DATA (T = 04:30) ( 07: 30)

(continued)

OFFSITE LEAFY GROUND MONITORING VEGETATION .DEPOSITION LOCATION iodine total (pCi/kg) (pCi/kg) (cpm/100cm2) 2.5CL 3 2 3.3 0 1 2.5a 2 7 2.8 0 1 2.5b 1 6 1 7 0.1 2 use 0 7 0.7 0 1 2.5d 0 2 0.2 0-1 3D 0 ' 0.2 0.1 3C 0 5 0.6 0~1 3B 1 3 1.4 0~1 3A 2~2 2 ' 0.1 3CL 2 6 2.8 0~1 3a 2 ' 2 ' 0.1 3b 1 3 1.4 0 1 3c 0' 0.6 0.1 3d 0 ' 0.2 0~1 4C 0.3 0.3 0 1 4B 0.7 0.8 0 1 4A 1 2 1-3 0.1 4CL 1.4 1.6 0~1 4a 1~2 1 3 0~1 4b 0.7 0.8 0~1 4c 0.3 0.3 0.1 4.5C 0 ' 0.1 0~1 4 'B 0' 0.2 F 1 4.5A 0 ' 0.4 0 1 4.5CL 0.4 0.5 0~1 4.Sa 0' 0.4 0~1 4 'b 4.5c 0 2

<'0 1 0.2 0.1 0.1 0 1 1CL 0~1 6.0 0 1 lb 0 1 5.2 0~1 1c 0 1 4.1 0~1 1d 0 1 2 1 0' 1e 0 1 1.0 0'. 1 1 2F 0~1 0.4 0~1 1.2E 0 1 1.0 0 1 1.2D 0 1 2 2 0~1 1.2C 0 1 3 ' .0. 1 1.2B 0~1 4 0.1 1 2A 0.1 4' 0.1

1. 2CL 0~1 4.9 0 1 F

CONTINUED ON NEXT PAGE

NNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E3. f ENVIRONMENTAL SAMPLING DATA (T = 04:30) ( 07:30)

(continued)

OFFSITE LEAFY GROUND MONITORING VEGETATION DEPOSITION LOCATION iodine total (pCi/kg) (pCi/kg) (cpm/100cm2) 1.2a < 0.1 4.7 0 1 1.2b < 0.1 4' 0.1 1%2c < 0.1 3 ' 0.1 1.2d < 0.1 2 2 0.1 1 'e 1.2f

< 0.1 0'

1.0 0.4 0.1 0'

OTHER SAMPLES LESS THAN MDA

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E3. g ENVIRONMENTAL SAMPLING DATA (T = 05:30) ( 08:30)

OFFSITE LEAFY GROUND MONITORING VEGETATION DEPOSITION LOCATION iodine total (pCi/kg) (pCi/kg) (cpm/100cm2) 5F 6500. 6600. 0.6 5E 1.3E4 1. 4E4 1.2

.5D 2.4E4 2.5E4 2 2

.SC 3.4E4 3 5E4 3 1

~ 5B 3.5E4 3 ~ 6E4 3 2

.5A 3.6E4 . 3.7E4 3 3

".5CL 3.7E4 3 ~ 8E4 3 3

.Sa 3 'E4 3. 7E4 3 3

~ 5b 3.5E4 3.6E4 3 2

.Sc 3.4E4 3.5E4 F 1

~ 5d 2. 4E4 2 SE4 2 2

.5e 1. 3E4 1.4E4 1 2

~ 5f 6500. 6600. 0 6 1F 2000. 2000. 0 2 1E 4400. 4500. 0 4 1D 9200. 9500. 0.8 1C 1.5E4 1 6E4 1.4 1B 1.7E4 1 7E4 1.5 1A 1.8E4 1.8E4 1.6 1a 1.8E4 1.8E4 1.6 1 5F 690 ~ 5900 0 5 1 5E 1800 '.5E4 1.4 1.5D '900.

3 'E4 3 0 1 5C 7100 6 1E4 5.4 5B '000.

7 5E4 6.7 1.5A 9700. 8 'E4 7 2 1.5CL 7300. 1.0E5 9~1 1.Sa 9700. 8 1E4 7' 1.5b 9000. . 7.5E4 6 7 1.5c 7100. 6. 1E4 5.4 1.5d 3900. 3 4E4 3.0 1.5e 1800. 1. 5E4 1.4 1.5f 690. 5900. 0.5 2F 270 ~ 3700 ~ 0.3 2E 780 1 OE4 0.9 2D 1800. 2 'E4 2 2 2C 3500. 4.7E4 4 2 2B 4700. 6.4E4 5 7 2A 5200. 7 1E4 6 3 2CL 5500. 7 'E4 6.6 CONTINUED ON NEXT PAGE

MNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E3 ~ h ENVIRONMENTAL SAMPLING DATA (T = 05:30) ( 08:30)

(continued)

OFFSITE LEAFY GROUND MONITORING VEGETATION DEPOSITION LOCATION iodine total (pCi/kg) {pCi/kg) (cpm/100cm2) 2a 5200. 7 1E4 6.3 2b 4700. 6 4E4 5.7 2c 3500. 4. 7E4 4' 2d 1800. 2 ~ 4E4 2 2 2e 780. 1 OE4 0.9 2f 270. 3700 0 '

2 2

'F

'E 94.

290. 5100.

'600.

F 1 0'

2.5D 720 1.2E4 1~1 2.5C '500.

2 'E4 2' 2.5B 2100. 3.7E4 3' 2 'A 2400. 4 1E4 3 6 2 5CL 2500. 'E4 3.9

~

2 'a 2.5b 2400

'100.

4 4.1E4 3.7E4 3 6 3 '

2.5c 1500. 2 5E4 2' 2.5d 720 1 2E4 1 1 2.5e 290. 5100. 0.4 2.5f 94 1600. 0 1 3F 17 ~ 320 0 1 3E 55. 1000. 0~1 3D 150. 2600. 0.2 3C 300. 5600. 0' 3B 480. 8500. 0' 3A 550. 1.0E4 0' 3CL 580. 1 1E4 0.9 3a 550. 1.0E4 0 '

3b 480 8500. 0 8 3c 300. 5600. 0.5 3d 150. 2600. 0 2 3e 55. 1000. 0 1 3f 17. 320 ' 0 1 4D 0.1 1 0~1 4C 0.4 0.4 0 1 4B 1' 1~ 1 0~1 4A 1.7 1.9 0 1 4CL 4a '.7' 2 2' 1 9 0 1 0~1 4b 1.0 1.1 0 1 4c 0.4 0 4 0.1 CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E3. h ENVIRONMENTAL SAMPLING DATA (T ~ 06:00) ( 09:00)

OFFSITE LEAFY GROUND MONITORING VEGETATION DEPOSITION LOCATION iodine total (pci/>g) (pci/~g) (cpm/100cm2)

.5F 7100 ~ 7200 0.6

.5E 1. 5E4 1.5E4 1.3

.SD 2. 6E4 2 'E4 2.4

~ 5C 3 7E4 3 'E4 3 '

.5B 3. 9E4 4.0E4 3.5

.5A 3. 9E4 4 'E4 3.6 5CL 4. OE4 4 1E4 3.7

.5a 3 9E4 4 OE4 3.6

.5b 3. 9E4 4.0E4 3.5

.5c 3. 7E4 3.8E4 3.4

.5d 2 ~ 6E4 2.7E4 2.4

.5e 1.5E4 1.5E4 1 3

.5f 7100. 7200. 0' 1F. 2100 2200 0.2 1E 4900. 5000. 0.4 1D 1.0E4 1 OE4 0.9 1C 1 7E4 1.7E4 1.5 1B 1. 8E4 1 9E4 1.7 1A 1.9E4 2 OE4 1' 1a 1.9E4 2.0E4 1.8 1.5F 820 6200. 0.6

1. 5E '100.

1 6E4 1.4 1.5D 4700. 3. 6E4 3 '

1.5C 8500. 6. 5E4 5.8 1 5B 1.1E4 8. OE4 7' 1 5A 1.2E4 8.6E4 7 7 1.5CL 1 OE4 1.3E5 11 1.5a 1.2E4 8.6E4 7 7 1.5b 1.1E4 8 OE4 7.1 1.5c 8500. 6 5E4 5.8 1.5d 4700. 3.6E4 3.2

1. 5e 2100 1.6E4 1.4 1.5f '20 6200 0 6 2F 390. 4600. 0.4 2E 1100. 1.3E4 1.1 2D 2600. 3.0E4 2 7 2C 4900 5.9E4 5.2 2B '600 7 'E4 7 0 2A '400 8 9E4 7~9 2CL 7700 9.1E4 8.1

'ONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 E3. i ENVIRONMENTAL SAMPLING DATA (T = 06:00) ( 09:00)

(continued)

OFFSITE LEAFY GROUND MONITORING VEGETATION -DEPOSITION LOCATION iodine total (pCi/kg) (pci/kg) (cpm/100cm2) 2a 7400 8 9E4 7.9 2b 6600. 7. 9E4 7 '

2c 4900 5. 9E4 5 2 2d '600.

3 ~ OE4 2.7 2e 1100. 1 ~ 3E4 1 1 2f 390. 4600. 0.4 2

2

'F

'E 190

'90.

2900.

8900 0.3 0.8 2 'D 1500. 2 'E4 1.9 2 5C 2900. 4.4E4 4 0 2.5B 4300 6 4E4 5.7 2 5A '800 7 4E4 6.5 2.5CL 5100 7.6E4 6 8 2 'a 2.5b 4800

'300 7 'E4 6.4E4 6.5 5.7 2.5c 2900 4.4E4 4 0 2 Sd 1500. 2.2E4 1 9 2 'f 2.5e 3F 590 190 96.

8900.

2900.

1700.

0 8 0.3 0 1 3E 300 5400 0~5 3D 790. 1.4E4 1.2 3C 1700. 3 'E4 2 '

3B 2600. 4 'E4 4' 3A 3000 5 'E4 4~6 3CL 3200 5 'E4 5-1 3a 3000 5 2E4 4.6 3b '600.

4.5E4 4 '

3c 1700. 3.0E4 2.6 3d 790 1.4E4 1 2 3e 300 5400 0.5 3f '6 1700. 0.1 4F 7.5 150 0.1 4E 28. 550. 0 1 4D 78. 1600 0 1 4C 180 3400 0 3 4B 300. 6100. 0.5 4A '350. 7400 0 7 4CL 380 7600. 0 7 4a '50.

7400 0.7

'N CONTINUED NEXT PAGE

HNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E3. i ENVIRONMENTAL SAMPLING DATA (T = 06:00) ( 09:00)

(continued)

OFFSITE LEAFY GROUND MONITORING VEGETATION DEPOSITION LOCATION iodine total (pCi/kg) (pCi/kg) (cpm/100cm2) 4b 300. 6100. 0.5 4c 180. 3400. 0.3 4d 78 1600. 0 1 4e '8 550. 0~1 4f '.5 150. 0.1 4.5E ( 0.1 0.1 0.1 4.5D 0' 0.5 0.1 4 ~ SC 0.3 1' ( 0.1 4.5B 0.8 2' 0.1 4 'A 4.5CL 1.4 1.7 3.4 3.9 0~1 0 1 4.5a 1.4 3.4 ( 0.1 4.5b 0.8 2.4 0.1 4.5c 0.3 1.2 0.1 4.5d 0.1 0.5 0~1 4.5e ~

< 0.1 0.1 0.1 5C 0' 0.3 0 1 5B 0.7 0.8 0.1 5A 1.3 1 4 0.1 5CL 1.5 1 7 0.1 5a 1.3 1.4 ( 0.1 5b 0.7 0' ( O.l 5c 0.3 0.3 0' 6B 0.1 0.2 0' 6A 0.2 0.3 0.1 6CL 0.3 0.3 0.1 6a 0.2 0.3 F 1 6b 0' 0.2 ( 0.1 1CL 1.8E4 1 4E5 12 1b 1.6E4 1 2E5 '1.

1c 1.3E4 9 4E4 8.4 1d 6800. 5. 2E4 4.6 1e 3200. 2 ~ 4E4 2.2 1f 250. 1900. 0.2

1. 2F 1300. 1 OE4 0.9 1.2E 3300. 2.5E4 2' 1 2D 6800 5 2E4 4.6 1.2C 1 2E4 9 1E4 8.1 1 2B 1.4E4 1 OE5 9.2 1 2A 1.5E4 1. 1E5 9' CONTINUED ON NEXT PAGE

HNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E3 ~ i ENVIRONMENTAL SAMPLING DATA (T = 06:00) ( 09:00)

(continued)

OFFSITE LEAFY '"

GROUND

.MONITORING VEGETATION DEPOSITION LOCATION iodine total (pCi/kg) (pCi/kg) (cpm/100cm2)

1. 2CL 1 5E4 1. 1E5 10 1 2a 1.5E4 1. 1E5 9.9 1.2b 1.4E4 1 'E5 9.2 1 2C 1.2E4 9.1E4 8 1

1. 2d 6800. 5 'E4 4.6 1e2e 3300. 2.5E4 2' 1.2f 1300. 1 OE4 0.9 OTHER SAMPLES LESS THAN MDA

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E3. i ENVIRONMENTAL SAMPLING DATA (T = 06:30) ( 09: 30)

OFFSITE LEAFY GROUND MONITORING VEGETATION DEPOSITION LOCATION iodine total (pCi/kg) (pCi/kg) (cpm/100cm2)

~ 5F 7100. 0.6

.5E 1.5E4 1. 5E4 1 3 LSD 2 6E4 2 ~ 7E4 2.4

~ 5C 3 8E4 3. 8E4 3.4 5B 3.9E4 4.0E4 3.5

~ 5A 3.9E4 4.0E4 3.6

.5CL 4 'E4 4.1E4 3 7

.Sa

.5b

.5c 3 9E4 3.9E4 3 'E4

'300.'E4 4.0E4 4

3.8E4 3.6 3.5 3.4

~ 5d 2 'E4 2.7E4 2.4

.5e 1 5E4 1.5E4 1 3

.Sf 7100. 7300. 0.6 1F 2100. 2200. 0.2 1E 4900. 5000. 0.4 1D 1.0E4 1.0E4 0 '

1C 1.7E4 1.7E4 1.5 1B 1 'E4 1 'E4 1.7 1A 2.0E4 2. OE4 1' 1a 2 OE4 2 'E4 1.8 1 5F 900 5700. 0.5 1 5E '300.

1.5E4 1 3

1. 5D 5100. 3.3E4 2.9 1 SC 9200 6.0E4 5' 1 5B 1 2E4 7.4E4 6.6 1.5A 1 3E4 8 'E4 7 1 1.5CL 1. 1E4 1.2E5 11 1.5a 1 3E4 8 'E4 7.1 1.5b 1.2E4 7.4E4 6' 1.5c 9200 6.0E4 5.3 1 5d '100 3.3E4 2.9 1.5e '300.

1.5E4 1 3 1 5f 900. 5700. 0 '

2F 430. 4400. 0.4 2E 1200. 1.2E4 1-1 2D 2800 2 'E4 2.6 2C '400.

5.6E4 5.0

~

2B 7300. 7.6E4 6.8 2A 8200. 8.5E4 7' 2CL 8500 8 'E4 7.8 CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E3. j ENVIRONMENTAL SAMPLING DATA (T = 06:30) ( 09:30)

(continued)

OFFSITE I EAFY GROUND MONITORING VEGETATION - DEPOSITION LOCATION iodine total (PCi/~g) (PCi/kg) (cpm/100cm2) 2a 8200 8.5E4 7.6 2b 7300. 7.6E4 6 8 2c 5400. 5.6E4 5.0 2d 2800 2 'E4 2.6 2e 1200 1.2E4 1~1 2f '30.

4400. 0.4 2 SF 230. 3100. 0'3 2 'E 2 5D 710.

1700.

9400.

2 'E4 0.8 2 '

2 5C 3500. 4 'E4 4.2 2 'B 5100 6.7E4 6.0 2 'A 5800. 7.7E4 6.9 2 5CL 6100. 8.0E4 7' 2 Sa 5800. 7 'E4 F 9 2.5b 5100 6.7E4 6 '

2.5c 3500. 4.7E4 '

2 'd 2.5e 1700.

710.

2.3E4 9400 4

2 0 0.8 2 ~ Sf 230. '100 0.3 3F 130. '100 0.2 3E 430 ~ 6700. 0 '

3D 1100 1.7E4 1.5 3C '400.

3.7E4 3 3 3B 3700. 5 6E4 5.0 3A 4200. 6.5E4 5.8 3CL 4500. 7 'E4 6.2 3a 4200. 6.5E4 5.8 3b 3700 5.6E4 5' 3c 2400. 3.7E4 3.3 3d 1100. 1.7E4 1.5 3e 430. 6700. 0.6 3f 130. 2100. 0.2 4F 41. 800. 0.1 4E 150. 2900 0.3 4D 430. 8500. 0.8 4C 970. 1 9E4 1.6 4B 1600. 3.2E4 2' 4A 2000. 3.9E4 3' 4CL 2100. 4.1E4 F 7 4a 2000 3.9E4 3' F

• K'N CONTINUED NEXT PAGE

MNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E3 ~ j ENVIRONMENTAL SAMPLING DATA (T = 06:30) ( 09:30)

(continued)

OFFSITE LEAFY GROUND MONITORING VEGETATION DEPOSITION LOCATION iodine total (pCi/kg) (pCi/kg) (cpm/100cm2) 4b 1600. 3. 2E4 2.8 4c 970. 1.9E4 1.6 4d 430. 8500. 0 '

4e 150. 2900 0.3 4f 41. '00 F 1 4.5F 18 400 0.1 USE '9

'500 0 1 4 'D '00

'300.

0.4 4.5C 480. 1.0E4 0' 4.5B 830. 1.8E4 1.6 4 'A 1000. 2 'E4 2.0 4.5CL 1100. 2.4E4 2 '

4.Sa 1000. 2 2E4 2.0 4 'b 4.5c 830.

480.

1. 8E4

1. OE4 1 6 0 '

4 ~ Sd 200. 4300 0.4 4.Se 69. 1500 0~1 4 ~ Sf 18. 400 0 1 5F 3 ' 81 ~ 0 1 SE 15 320 0.1 5D 48. 1000 0 1 5C 110. '400.

0-2 SB 200. 4500. 0 '

SA 250 5500. 0.5 5CL '80.

6000. 0.5 sa 250. 5500. 0 5 5b 200. 4500. 0 '

5c 110. 2400. 0.2 5d 48. 1000 0.1 5e 15. 320 0 1 Sf 3 8 '1.

0.1 6C 0 1 0.1 0 1~

6B 0 ' 0.4 0.1 6A 0 6 0 ' 0.1 6CL 0 ' 0 ' 0 1 6a 0~6 0' 0~1 6b 0~3 0.4 0.1 6c 0.1 0.1 0.1 1CL 2. OE4 1. 3E5 11.

1b 1. 8E4 1. 1E5 10.

CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E3 ~

ENVIRONMENTAL SAMPLING DATA (T = 06:30) ( 09:30)

(continued)

OFFSITE LEAFY GROUND MONITORING VEGETATION 'DEPOSZTZON LOCATION iodine total (pCi/kg) (pCi/kg) (cpm/100cm2) 1c 1. 4E4 8.7E4 F 7 1d 7400. 4 'E4 4.2 1e 3500. 2 'E4 2 '

1f 270. 1800. 0.2 1 2F 1400. 9200. 0.8 1.2E 3500. 2.3E4 2 '

1 2D 7400. 4.8E4 4.3 1 ~ 2C 1 'E4 8.3E4 7.4 1.2B 1.5E4 9.5E4 8.5 1.2A 1.6E4 1.0E5 9.1 1.2CL 1 'E4 1 OE5 9.2 1.2a 1.6E4 1 'E5 9 '

1. 2b 1.5E4 9 5E4 8.5 1r 2c 1.3E4 8 'E4 7.4

1. 2d 7400. 4.8E4 4.3 1 ~ 2e 3500. 2 3E4 2.0 1.2f 1400. 9200 0.8 OTHER SAMPLES LESS THAN MDA

.WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E3. j ENVIRONMENTAL SAMPLING DATA (T = 07:00) ( 10:00)

OFFSITE LEAFY GROUND MONITORING VEGETATION DEPOSITION LOCATION iodine total (pCi/kg) (pCi/kg) (cpm/100cm2) 5F 7200. 7300. 0.6 5E 1.5E4 1 5E4 1.3 5D 2.7E4 2.7E4 2 4

.5C 3.8E4 3.9E4 3.4

~ SB 3 9E4 4.0E4 3 '

~ 5A 4. OE4 4 1E4 3 6 5CL 4. 1E4 4.1E4 3 7

.5a 4. OE4 4.1E4 3'

.5b 3. 9E4 4.0E4 3 '

.5c 3. 8E4 3 'E4 3.4

.5d 2. 7E4 2 'E4 2 4

.5e 1 5E4 1.5E4 1.3

~ Sf 7200 7300 0 6 1F 2200. 2200. 0.2 1E 4900. 5000 0.4 1D 1.0E4 1.0E4 0.9 1C 1.7E4 1.7E4 1.5 1B 1.8E4 1.9E4 1 7 1A 2 ~ OE4 2 ~ OE4 1.8 1a 2 'E4 2.0E4 1.8 1.5F 910 3600. 0.3 1

1

'E

'D 2300.

5100 9300.

2 1E4 0 8 1'

1.5C 9300. 3 'E4 3 3 1 ~ 5B 1.2E4 4 6E4 4 1 1.5A 1 3E4 5.0E4 4.5 1.5CL 1. 2E4 1.1E5 9.6 1.5a 1. 3E4 5 'E4 4 '

1.5b '1. 2E4 4.6E4 F 1 1.5c 9300. 3.8E4 3 '

1.5d 5100. 2.1E4 1.8 1 'f 1.5e 2F 2300 910.

460 9300.

3600 3900 0 8 0'

0.3 2E 1300. '.1E4 1.0 2D 3000. 2.6E4 2' 2C 5800. "5 OE4 4 5 2B 7800 6 8E4 6.0 2A 8700 7. 5E4 6.7 2CL 9100. 7.9E4 7 0 CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 E3. k ENVIRONMENTAL SAMPLING DATA (T = o7:oo) ( 10:00)

(continued)

OFFSITE LEAFY GROUND MONITORING VEGETATION .DEPOSITION LOCAT1ON iodine total (pCi/kg) (pci/kg) (cpm/100cm2) 2a 8700. 7. 5E4 6.7 2b 7800 6. 8E4 6.0 2c '800.

5 OE4 4.5 2d 3000 2.6E4 2 '

2e '300.

1.1E4 1~0 2f 460. 3900. 0~3 2.5F 250. 3100. 0.3 2.5E 770 9700. 0.9 2 ~ 5D 2.4E4 2 1

'C

'900.

2 3800. 4.8E4 4~3 2 ~ 5B 5600. 6.9E4 6~1 2 'A 2.5CL 6300.

6700 7.9E4 8 3E4 7.0 7~3 2.5a 6300 7. 9E4 7' 2.5b 5600. 6. 9E4 6.1 2.5c 3800. 4 SE4 4.3 2.5d 1900. 2. 4E4 2 1 2.5e 770. 9700. 0.9 2.5f 250. 3100. 0 3 3F 160. 2200. 0.2 3E 500 7200. 0.6 3D 1300. 1.8E4 1.6 3C 2700. 3.9E4 3 '

3B 4200. 6.0E4 5' 3A 4900. 7 'E4 6' 3CL 5200. 7.4E4 6~6 3a 4900. 7.0E4 6~2 3b 4200. 6.0E4 5.3 3c 2700 3.9E4 3.5 3d '300.

1.8E4 1.6 3e 500. 7100. 0.6 3f 160 2200. 0.2 4F '9.

970. 0' 4E 210. 3600. 0.3 4D 610. 1.0E4 0~9 4C 1400. 2.3E4 2 '

4B 2300. 3.8E4 3.4 4A 2800. 4 7E4 4.2 4CL 3000 5 OE4 4' 4a '800

4. 7E4 4.2 CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E3. k ENVIRONMENTAL SAMPLING DATA (T = 07:00) ( 10:00)

(continued)

OFFSZTE LEAFY GROUND MONITORING VEGETATION DEPOSITION LOCATION iodine total (pci/kg) (pci/kg) (cpm/100cm2) 4b 2300. 3 'E4 3.4 4c 1400. 2 'E4 2' 4d 610 ' 1.0E4 0.9 4e 210 3600 0.3 4f '8.

970 0' 4 ~ SF 37 '80.

0.1 4.5E '40 2600. 0.2 4.5D 410 7400. 0.7

'C

~

4 980. 1.8E4 1.6 4 SB 1700. 3.1E4 2.8 4.5A 2100 3.8E4 3.4 4.5CL 2200. 4.1E4 3 '

4.Sa 2100. 3.8E4 3.4 4 5b 1700. 3.1E4 2 '

4.5c 980. 1.8E4 1.6 4.5d 410. 7400. 0.7 4.5e 140. 2600. 0.2 4.5f 37 680. 0.1 5F 21 ~ 430 0.1 5E 85. '700 0~1 SD 260. 5300. 0.5 5C 620 1 3E4 1.1 5B 1100. 2 ~ 3E4 2.0 5A 1400 2 ~ 9E4 2.6 5CL 1500 3. 1E4 2.8 Sa 1400. 2 9E4 2.6 5b 1100. 2. 3E4 2.0 Sc 620. 1. 3E4 1.1 5d 260 5300. 0.5 5e 85. 1700 0.1 Sf 21. 430. 0.1 6F 2.1 47 0.1 6E 9.3 '10 0.1 6D 30. '80 0.1 6C 78 1800. 0.2 6B '50.

3400 0.3 6A 190. '400 0.4 6CL 210. 4700 0' 6a 190 '400 0.4 6b 150 3400 0' CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E3. k ENVIRONMENTAL SAMPLING DATA {T 07:00) ( 10:00)

(continued)

OFFSITE LEAFY GROUND MONITORING VEGETATION DEPOSITION LOCATION iodine total (pCi/kg) (pCi/kg) (cpm/100cm2)

,6c 78 1800 0.2 6d 30. 680 0.1 6e 9' 210 0.1 6f 2 1

'7 0.1 7B 0~1 '.1 0.1 7A 0.2 0 2 0.1 7CL 0.2 0.3 0.1 7a 0 ' 0 2 0.1 7b ( 0.1 0.1 0.1 1CL 2.0E4 8 0E4 7' 1b 1.8E4 7.0E4 6.3 1c 1.4E4 5.5E4 4 '

1d 7400 3.0E4 2.6 1e '500 1.4E4 1~3 1f '80 1100. 0.1 1.2F 1400. 5800 0.5 1.2E 3600. '.4E4 1 3 1 2D 7500. 3 'E4 2'

1. 2C 1.3E4 5.2E4 4.7 1.2B 1 5E4 6 OE4 5' 1.2A 1. 6E4 6.4E4 5.7 1 2CL 1. 6E4 6.5E4 5.8 1 2a 1. 6E4 6.4E4 5.7 1.2b 1. 5E4 6 OE4 5' 1 ~ 2c 1. 3E4 5.2E4 4.7 1.2d 7500. 3.0E4 2 '

1.2e .3600. 1.4E4 1.3 1 2f 1400. 5800. 0.5 OTHER SAMPLES LESS THAN MDA

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E3 ~ k ENVIRONMMPAL SAMPLING DATA (T = 07:30) ( 10: 30)

OFFSITE LEAFY GROUND MONITORING VEGETATION DEPOSITION LOCATION iodine total (pCi/kg) (pCi/kg) (cpm/100cm2)

.5F 7200. 7300. 0 6

~ 5E 1.4E4 1 4E4 1.3 5D 2.5E4 2 'E4 2 '

5C 3 'E4 3 6E4 3 2

~ 5B 3 'E4 3.9E4 3.4 5A 3 'E4 4.0E4 3.6

.SCL 4 OE4 4 lE4 3.6

.5a 3 9E4 4 OE4 3.6 Sb 3 8E4 3.9E4 3.4

.5c 3.5E4 3.6E4 3 '

.5d 2.5E4 2.6E4 2 '

.5e 1.4E4 1.4E4 1.3

.5f 7200. 7300. 0.6 Main tng 13 14 0 1 1F '100.

'200 0.2 1E 4700. '800.

.0.4 1D 9600. 9700 0.9 1C 1. 6E4 '.6E4 1.5 1B 1. 8E4 1 8E4 1 6 1A 1 9E4 2 OE4 1 7 1a 1. 9E4 2 OE4 1 7 1 5F 900 2600. 0 2

1. 5E 2200. 6600. 0.6

1. 5D 4800. 1.5E4 1' 1.5C 8800. 2.7E4 2'

1. 5B 1.1E4 3.3E4 2.9 1 5A 1.2E4 3.6E4 3 '

1 5CL 1 2E4 8 'E4 7 1 1.5a 1. 2E4 3.6E4 3 2 1.5b 1. 1E4 3.3E4 2.9 1.5c 8800 2.7E4 2.4 1 5d '800.

3.. 5E4 1.3

1. 5e 2200. 6600. 0.6 1.5f 900. 2600. 0.2 2F 480 2900. 0.3 2E 1300. 8100. 0.7 2D 3000 1.9E4 1.7 2C 5700 3 7E4 3 '

2B 7800. 5 OE4 4.4 2A 8700. 5. 6E4 5.0 CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unct 2 REV 0 TABLE E3. l ENVIRONMENTAL SAMPLING DATA (T = 07:30) ( 10:30)

(continued)

OFFSITE LEAFY GROUND MONITORING VEGETATION DEPOSITION LOCATION iodine total (pci/kg) (pci/kg) (cpm/100cm2) 2CL 9100 5 ~ 8E4 5.2 2a '700.

5 6E4 5.0 2b 7800. 5.0E4 4' 2c 5700. 3 'E4 3.3 2d 3000. 1 9E4 1.7 2e 1300 8100 0.7 2f 480. 0.3

'F

'900 2 280. '600 0.2 USE 820. '

'200 0.7 2.SD 2000 OE4 1.8 2 SC 4.0E4 3.6

'B

'000.

2 5900. 5.8E4 5.2 2 'A 2.5CL 6700.

7100 6.7E4 6.9E4 5.9 6.2 2.Sa 6700 6.7E4 5.9 2.5b '900.

5 8E4 5.2 2.Sc 4000. 4.0E4 3.6 2 'd 2.5e 2000.

820.

2 OE4 8200.

1.8 0.7 2.5f 280 2600. 0.2 3F 180 2100. 0.2 3E 560. 6800. 0.6 3D 1400 ~ 1 7E4 1.5 3C 3000. 3 'E4 3~3 3B 4700. 5.7E4 5.0 3A 5400. 6 6E4 5.9 3CL 5800. 7 'E4 6.2 3a 5400 6 'E4 5.9 3b 4700. 5 7E4 5.0 3c 3000. 3.7E4 3.3 3d '1400 .1. 7E4 1.5 3e 560. 6800. 0~6 3f 180 2100 ~ 0.2 4F '9.

1200 0.1 4E 250 4300 0.4 4D 720 1. 3E4 1.1 4C '700

2. 8E4 2.5 4B 2800 4 8E4 4.2 4A ,3400 5 8E4 5.2 4CL E

'600 6.2E4 5.5 1

CO NTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E3. 1 ENVIRONMENTAL SAMPLING DATA (T = 07:30) ( 10:30)

(continued)

OFFSITE LEAFY GROUND MONITORING VEGETATION DEPOSITION LOCATION iodine total (pCi,/~g) (pCi/kg) (cpm/100cm2) 4a 3400. 5. 8E4 5.2 4b 2800 4 ~ 8E4 4.2 4c 1700. 2.8E4 2.5 4d 720. 1.3E4 1.1 4e 250. 4300 0.4 4f 69. 0.1

'F

'200 4 47. 880 0~1 4.5E 180. 3300. 0.3 4 'D 540 9900. 0.9 4 'C '300.

2.4E4 2 '

4.5B 2200. 4 'E4 3 '

4.5A 2800. 5 2E4 4.6 4.5CL 3000. 5.6E4 4.9 4.Sa 2800 'E4 4.6 4 'b 4.5c 1300.

'200.

5 4 2E4 2.4E4 3

2.1 4.5d 540. 9900. 0.9 4.5e 180. 3300. 0.3 4 sf 47. 880 0.1 5F 30 ~ '60.

0.1 5E 120. 2200. 0.2 5D 370 6900 0.6 5C 880. E4 1.4 5B 1600. 3 ~ OE4 2.7 5A 2000. 3 ~ 8E4 3~3 5CL 2200. 4. 1E4 3.6 Sa 2000. 3 8E4 3.3 5b 1600. 3 ~ OE4 2 7 5c 880. 1. 6E4 1.4 sd 370. 6900 ~ 0.6 5e 120. 2200. 0.2 sf 30. 560. 0.1 6F 12. 260 0.1 6E 51. '100 0~1 6D 170. 3700 0.3 6C 430. '

'300 0.8 6B 850 8E4 1.6 6A 1100 2.4E4 2.1 6CL '200.

2 'E4 2 '

-6a 1100.'* 2.4E4 2.1 CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E3 1 ENVIRONMENTAL SAMPLING DATA (T = 07:30) ( 10:30)

(continued)

OFFSITE LEAFY GROUND MONITORING VEGETATION 'EPOSITION LOCATION iodine total (pci/>g) (pCi/>g) (cpm/100cm2) 6b 850. 1.8E4 1.6 6c 430 9300. 0.8 6d 170 ~ 3700. 0 '

6e 51. 1100. 0.1 6f 12 ~ 260. 0.1 7F 1.3 29 0.1 7E 6.0 140. 0.1 7D 21. 500 0.1 7C 58. 1300 0.1 7B 120 2600 0' 7A 150. 3700. 0' 7CL 170 ~ 3900. 0.3 7a 150. 3700 0.3 7b 120. 2600 0' 7c 58. '300 0.1 7d 21 500. 0~1 7e 6.0 140 0.1 7f 1.3 '

'9 0~1 WNP4 8.7 4 0.1 1CL 2 OE4 5 7E4 5.1 1b 7E4 5. OE4 4.5 1c 1 3E4 3 9E4 3.4 1d 7000. 2 1E4 1.9 1e 3400. 1 OE4 0.9 1f 370 910 0.1 1.2F 1400 ~ 4200 ' 0.4 1 2E 3400 OE4 0.9

1. 2D 7100 2 'E4 1.9 1 2C '.2E4 3.7E4 3.3 1 2B 1 4E4 4 'E4 3 '

1 2A 1 6E4 4 6E4 4.1

, 1 2CL 1 6E4 4 7E4 4.1 1 2a 1 6E4 4 ~ 6E4 4.1 1.2b '

1 'c 1 2d 1

1 4E4 2E4 7100.

4 3E4 3 'E4 2 1E4 3

3 1.9 1 ~ 2e 3400. 1 OE4 0' 1 2f I',

1400 4200. 0 '

OTHER SAMPLES LESS THAN

NNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E3. l ENVIRONMENTAL SAMPLING DATA (T = 08:00) ( 11 00)

OFFSITE LEAFY GROUND MONITORING VEGETATION DEPOSITION LOCATION iodine total (pCi/kg) (pCi/kg) (cpm/100cm2)

~ ~ 5F 7400. 7600. 0.7

~ 5E 1.4E4 1.4E4 1 3

~ 5D 2 4E4 2.4E4 2~2

~ 5C 3.4E4 3.4E4 3.0

~ 5B 3.6E4 3.6E4 3'

~ 5A 3.7E4 3.8E4 3.4

.5CL 3 'E4 3.9E4 3.4

.Sa 3.7E4 3.8E4 3'

.5b 3.6E4 3.6E4 302

.Sc 3.4E4 3.4E4 3.0

.5d 2 'E4 2 'E4 2 '

.Se 1.4E4 1.4E4 1.3

~ 5f 7400 7600. 0.7 Main tng '9.

31. 0' 1F 2200. 2200. 0' 1E 4600. 4600. 0.4 1D 9100. 9200. 0.8 1C 1 5E4 "1. 5E4 1.4 1B 1. 7E4 1. 7E4 1.5 1A 1 8E4 1. 8E4 1' 1a 1 8E4 1 ~ 8E4 1.6 1.5F 920. 1900. 0 2 1 ~ 5E 2100. 4800 0.4 1.5D 4600. OE4 0.9 1 'C 8300. 1. 9E4 1' 1.5B 1 OE4 2. 4E4 2.1 1 5A 1 1E4 2. 6E4 2' 1 5CL 1 2E4 5. 2E4 4.6 1.5a 1. 1E4 2.6E4 2' 1.5b 1 OE4 2.4E4 2' 1.5c 8300 ~ . 1.9E4 1.7 1 5d 4600. 1. OE4 0.9

1. 5e 2100. 4800. 0 '

1.5f 920 1900 0'2 2F 490. '000.

0.2 2E 1200 5300 0.5 2D .2800. 2E4'1.

1 1 2C 5300. 2. 4E4 2 1 2B 7200 3.2E4 2' 2A '100.

3.6E4 3 '

CONTINUED ON, NEXT PAGE

MNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit. 2 REV 0 TABLE E3. m ENVIRONMENTAL SAMPLING DATA (T = 08:00) ( 11: 00)

(continued)

OFFSITE LEAFY GROUND MONITORING 'EGETATION - DEPOSITION LOCATION iodine total (pci/kg) (pci/kg) (cpm/100cm2) 2CL 8500. 3 'E4 3.4 2a 8100. 3 'E4 3.2 2b "7200 3 'E4 2.9 2c 5300. 2 4E4 2 '

2d 2800. 1 2E4 1.1 2e 1200 5300. 0.5 2f 490. 2000 0.2 2 'F 2 5E 290.

790. 5200

'700.

0.2 0.5 2 'D 1900. 1 3E4 1.1 2 'C 3800. 2 5E4 2 '

2.5B 5500. 3 'E4 3.3 2 5A 6200 4 'E4 3' 2.5CL '600.

4 'E4 3.9 2.5a 6200. 4 'E4 3' 2.5b 5500 3 7E4 3.3 2.5c 3800 2 5E4 2' 2 Sd 1900. 1.3E4 1.1 2.5e 790. 5200 0.5 2.5f 290. 1700. 0 2 3F 190. 1400. 0.1 3E 540 4300. 0.4 3D '300 1 1E4 1.0 3C 2800 2 'E4 2.0 3B '300.

3.6E4 3.2 3A 5000. 4.1E4 3 '

3CL 5400. 4.4E4 3.9 3a 5000. 4 1E4 3' 3b 4300. 3 6E4 3.2 3c 2800. 2 'E4 2.0 3d .1300 1.1E4 1 0 3e 540. 4300. 0.4 3f '90. " '1400. 0.1 4F 89. 1200 0.1 4E 290. 4000. 0.4 4D 790. '1 1E4 1.0 4C '1800 2 SE4 2.2 4B ,3000. 4 ~ 2E4 3 '

4A ,3600 5 'E4 4.6 4CL 3900. 5 5E4 4.9 CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 1

TABLE E3. m I

ENVIRONMENTAL SAMPLING DATA (T = 08 00) ( 11 00)

(continued)

OFFSITE LEAFY GROUND MONITORING VEGETATION DEPOSITION LOCATION iodine total (pCi/kg) (pCi/kg) (cpm/100cm2) 4a 3600 ~ 5.2E4 4' 4b 3000 ~ 4.2E4 3 8 4c 1800. 2.5E4 2 2 4d 790. 1.1E4 1.0 4e 290 4000. 0.4 4f '9 1200. 0.1 4.5F '6.

1000 0~1 4.5E 220. 3600. 0.3 4.5D 640. 1.0E4 0' 4.5C 1500. 2.4E4 2' 4.5B 2600 4.3E4 3 8 4 'A 4.5CL

'200 5.3E4 5.7E4 4 7

'400 5~1 4.5a '200, 5.3E4 4 7 4.5b 2600 4.3E4 3 8

4. Sc '500 2.4E4 2' 4.5d 640. 1.0E4 0' 4.5e 220 3600. 0 3 4.5f 66. 1000. 0 1 5F 43. 740. 0 1 5E 160. 2800. 0 '

5D 470. 8600. 0 8 5C 1100. 2.1E4 1 8 5B 2100. 3.8E4 3 3 5A 2600 4 'E4 4.3 5CL '800.

5.2E4 4.6 5a 2600 4.8E4 4 '

5b '100 3.8E4 3~3 5c '100.

2.1E4 1.8 5d 470. 8600. 0.8 5e 160. 2800. 0.2 5f 43. 740. 0' 6F 22 420. 0 1 6E '4.

1700. 0 2 6D'C 270. 5500. 0.5 680. 1.4E4 1 2 6B 1300 2.7E4 2.4 6A 1700. 3.5E4 3-1 6CL 1800. 3.9E4 3 '

6a 1700. 3.5E4 3 1 CONTINUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E3. m ENVIRONM1MFAL SAMPLING DATA (T ~ 08:00) ( 11: 00)

(continued)

OFFSITE LEAFY GROUND MONITORING VEGETATION DEPOSITION LOCATION iodine total (pCi/kg) (pCi,/kg) (cpm/100cm2) 6b 1300. 2.7E4 2 4 6c 680. 1 4E4 1' 6d 270. 5500. 0' 6e 84. 1700. 0' 6f 22. 420 0~1 7F 7' 170 0~1 7E 34. 800. 0 1 7D 120 2900. 0 3 7C '40.

7800. 0' 7B 670. 1.6E4 1 4 7A 900. 2.1E4 1.9 7CL 1000. 2.4E4 F 1 7a 900. 2 'E4 1 9 7b 670. 1.6E4 1 4 7c 340. 7800 0' 7d 120. '900.

0.3 7e 34. 800. F 1 7f 7.0 170 0' 8F 0 8 19 0.1 8E 4' 97 0~1 8D 15. 370. 0 1 8C 43. 1000. 0 1 8B 90 2100. 0 2 8A '30 2900. 0 3 8CL 140. 3400 0.3 WNP4 19. 21. 0 1 1CL 1. 8E4 4 1E4 3 '

1b 1. 6E4 3. 6E4 3 '

1c 1.2E4 2 ~ 8E4 2' 1d 6700. 1. 5E4 1 3 1e 3400. 7300 ~ 0' 1f 500 830 0.1 1 2F '500.

3100 0' 1.2E 3300 7400 ' 0.7 1.2D 6700 5E4 1' 1.2C 1.2E4 2 'E4 2 '

1.2B 1.3E4 3 'E4 2 7 1 2A 1.5E4 3 'E4 2 '

1. 2CL 1.5E4 3.3E4 3 '

1. 2a 1.5E4 3.3E4 2 '

CONT INUED ON NEXT PAGE

WNP-2 Nuclear Generating Station Scenario 93e Annual Exercise Unit 2 REV 0 TABLE E3. m ENVIRONMENTAL SAMPLING DATA (T = 08:00) ( 11:00)

(continued)

OFFSITE LEAFY GROUND MONITORING VEGETATION DEPOSITION LOCATION iodine total (pCi/kg) (pCi/kg) (cpm/100cm2) 1.2b 1. 3E4 3 'E4 2.7 1 ~ 2c 1. 2E4 2 'E4 2 '

1.2d 6700. 1. 5E4 1.3 1 'e 1.2f 3300.

1500.

7400.

3100.

0 '

0.3 OTHER SAMPLES LESS THAN MDA

TIIVIE LINE lNORKSHEET EXERCISE 93 CONTROL CELL OPERA TIONS SEC TlON

SUPPLY SYSTEM DRILL & HKRCISE EVALUATIONCRXI'ERIA WORKSHEHT APPLICABLE CENTER(S) L EM&GENCT INFORMATION- MEDIA AND RUMOR CONTROL Demonstrate the capability to coordinate'he development and dissemination of clear, accurate, and timely information to the news media.

10.6 Were staff and equipment available at the media center to deal with telephone inquiries from the media? (Control Cell)

YES NO N/A (a) Did telephone staff provide prompt, accurate, consistent, and responsive information to media representatives?

YES NO N/A Demonstrate the capability to establish and operate rumor control in a coordinated and timely manner.

11.5 Did the rumor control stafF provide prompt, accutate, consistent, and responsive information to callers) (Control Cell)

YES NO N/A 11.6 How many caQs were received by the rumor control staff during the exercise? (Control Ceu)

(a) Based on the number of calls received, record the average number of calls handled per hour during the period rumor control staff were activated.

COXFROL CELL OPERATIONS Exercise 93 A. GENUG: The control cell is made up of controOers, whose function it is to role-play as the various agencies and individuals not activated for the drill, but with whom the players would normally interface. Communications are initiated both ways.

For example, a MUDAC player may need to call the National Weather Service for a weather forecast. Instead he should contact the control cell where a controller, role-playing as a forecaster, would read from a data sheet the "ca'nned" drill weather.

Also, controllers may call one of the emergency centers with a scenario message input. Most of the calls, however, will be initiated by controllers to the centers

'heavily committed to outside interfaces, e.g., JIC phone teams.

B. PARTICIPATING AGENCIES: The control cell should not represent organizations or individuals activated for the drill. Those include:

1. All Plant emergency centers

2. The EOF, with possibly limited personnel from State, counties.

3. The Headquarters/JIC, including State and possibly counties.

C. METHODOLOGY Incoming calls:

ao Try to keep designated lines clear of other traffic.

b. Answer by stating the phone number and "This is an Exercise." Then ask, "To whom do you wish to speak?"

C. Portray the agency/individual being called as realistically as possible.

d. Terminate the conversation with the phrase, "This is an Exercise."

2. Outgoing calls:

a. We are reducing the need for pre-scripted messages. Instead: .

1) Assume an assigned personality from Enclosure I. Do not use names of real people.

2) Formulate a call with questions based on designated rumors, EBS broadcasts, news releases, lead controQer assigned topics and other infoimation provided by players. At the end of each section in Enclosure 1, there are a few practical examples of how you should formulate your questions.

3) Make the call. Start and end each call with the statement, "This is an Exercise."

4) Log the call at Enclosure 2. Include all specifics of any call not evaluated as satisfactory.

5) For public information calls, remember local media will react first. The public will react to what they hear from the media.

Make calls plausible. Switch personalities as appropriate.

k Try to keep phone talkers busy with information search requirements. Request call backs and follow up on open items.

8) The FEMA standard is 5 or 6 phone calls per person (player) per hour, including periodic rumors. Phone team members should be able to o Answer questions by reading from news releases and radio announcements QBS messages) at hand; o Look up information in resource books and read/repeat such information ~;

o Dispel rumors based on emergency calendar, farm brochures, EBS messages and news releases.

The Table of Contents in the resource book has been reione for easier access to information by users.

Phone teams should not speculate or answer 'what if'uestions.

FEMA has indicated to the Supply System that most phone calls would be because they (the callers) didn't hear the EBS message. The phone teams should expect to get a great volume of the same exact question. FEMA has indicated that it would be totally inappropriate to expect phone team members to explain or to discuss any technical information or issues. In addition', information need not be memorized, but team members should be able to look up information and to read directly from the resource book. FEMA has also suggested that if repeat questions occur (more than three calls asking the same question), obviously the public is interested in knowing.

Therefore, steps should be taken to get answers included in press releases, etc.

NEWS CONHHUWCES: Designated controllers will attend JIC news conferences to role play as media. They are to adhere to the criteria above for outgoing calls.

NEWS CLIPPINGS: JIC phone team controllers, be prepared to write news stories on the event for processing by the JIC staff. Use Enclosure 3.

NRC CALLS: Keep players busy researching answers to speciTic questions.

Imagine what it really would be like!

CRITIQUE: Write up critique work sheets for favorable and unfavorable observations, based on phone call and news conference evaluations, and turn them in to the lead controller.

TEL12%ONE NUMBERS:

I. NRC:

o TSC Plant/NRC Liaison 2943 o EOF Licensing Manager 8087

2. JIC:

o Media Response Team 5100 o Public Information Team 5011

CO1%1. ROL CELL OPERATIONS COMPTROLLER PERSONAXZHES Exercise 93

1. Television:

a1 KDTV Channel 88-Tri-Cities. Local TV station. You'e young, ambitious, and want to make a name for yourself. Dan Rather or Connie Chung is your role model. You see the Tri-Cities as a stepping stone to bigger things. You would like to be aggressive but know your employer and audience are sympathetic to Hanford so you have to be careful how you make a splash.

b. KDKT Channel 34. Local TV (see KDTV, above) You'e the same but more aggressive. You'e the kind who would send a crew to location without asking for permission. Ifasked to leave, you'd read them your rights.

"Police can't interfere with normal news gathering in public places. The people have a right to know." Leave only when threatened with arrest by Hanford Patrol or ifseduced with better opportunities by the Public Relations staff. The way you are treated will color your story.

C. KPPR Channel 99. Local TV station. You don't have too much invested in your career. You see you'e not going to go very far in broadcasting. You feel pretty neutral about Hanford. You know it's not anywhere as bad as you sometimes read in west side papers.

d. KTAC Channel 2. Seattle-Tacoma TV. You want television footage but you can't afford to send a crew over. Being broadcast media you don't have much time for detail, you want drama.

e. KSEA Channe14. Seattle. %0%! Thisisagreatstory. Hanford Terror.

You want pictures. You are going to send your camera crew over by helicopter in about two hours. You hear that Supply System Security has an armored car. You want to take pictures of blood and guts, if not that then a look of pure terror in a child's face will do. You understand that TV news is entertainment. You'e not in competition with the newspapers and other news shows, you'e in competition with "The Equalizer," "Miami Vice," and "Tour of Duty."

Practical Examples of TV Personalities o Wanda Wilson, KVEW TV-"We would like to bring a camera crew out to Plant 2. What's the probability of getting some video shots? Where can we shoot film? When our crew gets out there, who would be available to talk to us? How about anyone from the NRC? The Supply System regularly holds news conferences in the Headquarters auditorium, right'? When's the next one'? What's the situation at the Plant right now?"

Sandy Spencer-KNDU TV, TriCities. "Has the NRC involved itself in the situation?... What is it doing?... Do you have the names of those representatives?... Any chance I can talk to one of them2... How about the state of Washington'?... Who is down from the Governor's office?

What's the latest condition at Plant 2'2... Who makes the next decision about what to do next2 - The State or the NRC?... Someone mentioned a group called FEMA... I'm not familiar with that... Who is it and what do its people do2... Are FEMA people there now, too?"

o Joe Johnson-KREM TV, Spokane. "Has the snow dropped off yet?...

What hnd of damage did it do? In connection with the problems at the Plant, what effect did the snow have? What's the current situation there? Where are you headed next'? Who's in charge of the problem'... What is his regular role at the Supply System?... What's his background?... Can you tell me how long he has been with the Supply System'?"

o Vicki Veneer-CBS TV News Network. "I'd like to get more information about Plant 2. What is the present situation? What is being done about it?

Please give me the names of the people making the decisions about the actions to be taken... Give me some background on these decision-makers. Is anyone from the NRC personally monitoring the situation? May I have their names, please? What other federal or state agencies are activated? Are any representatives from Idaho or Oregon present?... Why (or %Ay Not)2" Karen Kanderly-KOMO TV. "We'e hearing the situation has deteriorated to the point that the area agricultural industry could be impacted seriously...

Crops have been buried... deadened soil... Things like that... "

0 KHG TV, Spokane. (Somewhat aggressive) "We'e been trying all day to get an interview with your Plant Manager. WHIST are we going to get some cooperation2... It seems to us that %%OOPS might want to put their best expert forward at a time like this... someone who is really going to know what's going on. Can we go to your plant and look at it for ourselves2...

So, we ain't talk to your Plant Manager and we can't go to your plant...

What are you folks trying to hide?"... (Challenge the qualifications of

anyone they oper as a subsritute spokesperson, e.g. - What is hislher background with nuclear energy?- this person isn't going to know Plant 2 like the Plant Manager does, etc.)

Joan Justy-CBS TV News Network. "Tell me about the airplane engine falling on your plant... Apparently American nuclear power plants are susceptible to falling objects even as small as an airplane engine?... Aren' the airspaces over these plants protected?... Has anyone considered what would happen if a bomb were dropped?... You sound pretty vulnerable...

Has anyone got the footage of the engine falling on the plant?"

Brad Burke-KING TV, Seattle. "I'e received a report that very high radiation dose readings were taken at someplace called the Ashe Substation ..

. I presume the substation is a part of the Bonneville Power Grid System, correct?... Where is it located in relation to your Plant 2?... Who took those readings, what were those readings, and what is the significance of those readings?... How often are dose readings taken? .'.. Tell me a little bit more about your field teams taking the readings... "

Rickie Romanovich-KOMO TV, Seattle. "What role is the NRC playing in this incident?... can you give me the names of any NRC people activated on site?... Has the NRC gone on record with any statement about conditions at Plant 2?... Have they said anything about the future of the American nuclear industry in light of the event at Plant 2? Would you take a moment to describe the Plant to me... It contains a BoiTing Water Reactor, doesn't it?

What else can you tell me about the physical makeup of the plant?"

2. Radio:

WWPZ Radio-Tri Cities. You'e older, mature. You know your radio career will probably never take you beyond the Tri-Cities. That's fine because you like it here. A lot of your friends work at Hanford. You know many of the PR people well and know a lot about Hanford. You know they are good folks. You use your reporting as a means to, as much as possible, build a strong community..

b. KOZY Country Radio-Tri-Cities. You don't have much air time for news.

It's something you stick in between Dolly and Kenny Rogers.

C. KRZY Rock FM-.Tri-Cities. See KOZY (¹b), but substitute Def Lepard and Kiss for Dolly and Kenny.

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d. National Non-Commercial Radio-You are the reporter for intellectuals. You are interested in the social consequences of government activities. Does a news event represent a trend for the future? What were the underlying causes

-of the event'? Is the event ultimately good even though it looks bad now?

Will it teach us something?

3. Priat:

ao Columbia Basin Chronicle-Local newspaper. Your editorial policy is friendly to Hanford. You see yourself as a first class science reporter and expect to one day report for a more prestigious paper. You tend to go for a science angle.

b. Spokane Banner-Northwest Regional Paper. God knows what all is going on down there at Hanford. It seems like every rock you uncover down there has a toxic chemical or radioactive rattlesnake under it. You don't know much about modern warfare, world politics, nuclear energy, or technology and you basically distrust those who do. Hanford is especially worrisome. What are they hiding?

C. Seattle Post-Dispatch-Major Northwest Paper. You need flamboyant headlines. Your paper is not so much in to what is true as it is in what sells.

You want stories about people and what happens to them. You don't want too many details about science. You don't care about reasons for things, you just want to know what happens to people. You want details of injuries, you want to know personalities, you want to know how people FEEL about things. You don't report about the danger that people are in, you report about how in~ger people FEEL. This makes reporting easy. You don't have to get expert opinion. You can ask the man on the street and his opinion is nearly as good as the governor'.

d. Seattle Prestige Journal-Major Northwest Paper. You want controversy. It doesn't much matter where it comes from, just get it. Find somebody who is upset about something, state his reasons and opinion and then go find another opinion. You like important people-opposing politicians, opposing government agencies, big shots are best. As long as one side of the argument is important it's okay. DOE against a nobody is a story because DOE is important.

e. Associated News-Wire Service. Just thefacts. Who did what to who. Who announced what. Ask these questions every time: Who? What? Where2 When? How? and Why2 Remember, your selling your material to other news media. You have to be very professional. They don't give a hoot about your opinion.

United News-Wire Service. See notes on Associated News. The same applies, only you are from the Walla Walla bureau and are pretty well informed on Hanford but don't know too much about Battelle.

g New York Daily Planet-You'e the best. The news is what the New York Daily Planet says is news. All the other papers follow your lead. You know this but are very modest and professional about it. You'e interested in the facts of the issue at hand but want lots of background. What led up to the event2 What are the likely consequences? Will there be legislative action?

What philosophy is guiding the courses of action taken by decision makers?

How did the DOE allow this kind of situation to occur'?

h. Portland Post-Northwest Major Newspaper. You want to be fair. You want to report both sides of every question. You don't know too much about DOE.

American Enquirer-National Tabloid. You don't really want news. You want lurid details. You can make most of them up, but sometimes it's nice to have real photos even if they have to be retouched.

Practical Examples of Newspaper Personalities o Sandra Smith-UPI, Seattle. "I understand the whole problem at Plant 2 began when pump motors caught fire... Well, what started the fire? What about the truck fire earlier'? Any question of sabotage? About 20 minutes later your reactor shutdown, correct?... What was the connection between the fire and the scram2 Who has been contaminated? What is your injury status2 How much fuel damage did you experience? Anything else to add?"

Ronald Reeber-LA Times. "What can you tell me about radiation levels at your plant'? Where has the contamination spread? Have Plant personnel been evacuated? Any injuries? Is the NRC going to step in and take over things2 What have they been saying? What are'he names of the NRC representatives there2 %'ell, things must be pretty serious with the NRC in place. How do things forebode for your nuclear plant in the future2 How about ramifications for the nuclear industry?"

Mary King-UPI Seattle. "TeQ me more about why a Site Area Emergency was declared? What are the conditions that require an emergency of this level? There are several classifications, aren't there'?... Detail them, please.

What has been the progression of these classifications at Plant 2? Where will you go next2

o Mandy Motoya-TriCity Herald. "It's my understanding this whole situation started with a fire in something called a standby service water pumphouse.

What exactly is its function and why is it important to the Plant?... Wasn't a backup safety system in place?... How was the radiation released?... For years you'e been telling the public radiation releases will never occur at an American nuclear power plant, what is Plant 2's position now?"

George Gupper-Time Magazine. "How extensive are the damages to your plant?... Has any other commercial nuclear power plant in America experienced the same sort of problems?... You seem to have had a bad string of luck today, first with the diesel truck fire, then the faulty equipment and now with the plane engine dropping on the reactor building. How do you explain that?... Aren't America's commercial nuclear power plants supposed to withstand all sorts of disasters - earthquakes, fires, things like that?...

How do you think Plant 2 speaks to the record?"

Melissa Meeker-Seattle Times. "When do you expect repairs to Plant 2 to be complete?... What methods of restraint are in place at the Plant now?...

What is being done to reduce the seriousness of the situation? What outside agencies are playing a role in restoration of the site? How extensive are damages now? Has anyone put a dollar amount on the damage?"

Manly McGinnis-Aberdeen Daily World. "Did a plane crash into you plant?

... What happened?... Who's involved in evaluating this new situation? ..

. Injuries?... What about evacuations? - Does that mean the Columbia River could be contaminated to some extent?... I'd like to know the environmental impact should the river be exposed to a radioactive plume?"

Fred Frew-Olympia News. "Let's talk a bit about reparative measures at Plant 2... Do you speculate you'l be bringing in outside expertise from General Electric and Westinghouse?... Who was your construction contractor?... There will be some construction on site, won't there? What' the extent of physical damages to the building? How long do you think it would take the Plant to get back in operation?"

Rene Reis-Everett Herald. "Is it true some fuel was uncovered when the airplane engine landed in your reserve fuel water containment system? ..

h

.How much water was splashed out with the impact?... It is possible quite a bit of water could have been splashed out... How big was the airplane engine?... Do you have cubic measurements or weight? What is happening to the radiation level now... Does that indicate the nature of the exposure?"

o Jim DellaSelva-Grants Pass Guardian. "Where's the radiation headed?...

Any changes in weather conditions expected to affect the situation?... What would happen if a storm occurred? - And if it rained? What are the weather conditions right now? What's the forecast for the next couple of days2 How long wiH you restrain evacuated residents from returning to their homes2...

The weather plays a factor in that decision, too, doesn't it? If the wind stirs up, other areas could be evacuated also, right?... Where would you put them?... What is %POOP's obligation to these residents? Who pays for their food and medicine involved with the evacuation? What about looters?"

o Bob Brown-The ¹w York Times. "Since these sort of catastrophes are not supposed to occur at commercial nuclear power plants, why is it this one has-to this magnitude - at your plant?... What explanation has been given to the American public about this?... It doesn't look too good for your plant management, does it?... Who is your Chief Executive Officer?... May I speak to him, please2... Who, in charge, may I speak to? How long have you been in the nuclear power business?... What's your background?...

Does that make you an authority on commercial nuclear power plants2...

You have quite a responsibility speak'uig for the Plant, considering your background, don't you2"

4. Officials

a. Richland School District

b. Pasco School District

c. Hospital

d. Adjacent counties-Grant, Yakima, Walla Walla

e. Senator Wisenhut's Aide-Generally hostile to Hanford Congressman Gold's Aide-Friendly congressman g NRC-Any personality you have met in this role

h. Others as appropriate

Local Popu1ation

a. Womed Spanish-Speaker-Womed about something; make it sound plausible.

b. Local Nut-Knows how to handle these kinds of situations. Wants to help.

Ex-professor, ex-cop, ex-nurse, ex-psychologist, ex-whatever sounds good for the situation. Happy to help out ifyou want.

c. Local Busybody-Wants to explain personal opinions about issues and what the government/town/people ought to do about it. Tries to hold the attention of whom called for as LONG as possible.

d. Richland day care center operator {outside 10 mile EPZ)

e. Kennewick convalescent home operator (outside 10 mile EPZ)

Potential looter-loohng for tactical information

g. Concerned citizen

h. Employee's spouse

i. Parent of a child on tour of the WNP-2 Visitor center

j. Resident worried about garden

k. Resident womed about cattle and milch cows Residents womed about missing relatives that live in the evacuation/shelter area

m. Residents womed about what they ate from the neighbour's garden today

n. People calling wanting transportation

o. People calling in because they didn't hear the radio message P. Residents who want to know who is covering expenses from losses

q. People who lost the calendar wanting to know what to take with them when they leave Mothers wanting to know where their school children are Someone wants to know what the difference in classifications means Others, as appropriate 8

Practical Example of a Local Populace Personality o Wife of Plant 2 HP-Chemist. "Why isn't my husband back home? I heard on the radio all unnecessary personnel are being sent home. Where is Mark?"

"You can't tell me that you don't know what's going on out there" "Why won't you tell me where Mark is? Is he one of the injured people I heard about?"

"Injuries are the types of things press people should know about. Tell me if Mark is among them!"

"Are you hiding something? You media people know everything!"

"Don't give me the run-around. Mark's been a loyal employee for three years. Is this how you pay us back?"

CONTROL CELL OPERATIONS COMPROL CELL PHONE LOG

/

EX%%CISE 93 Controller. Page of Pages NOTE: Include all relevant specifics of any response evaluated as unsatisfactory.

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EVALUATIONWORKSHEET INSTRUCTIONS ALL CONTROLLERS 8iI, EVALOATOR$

READ THE FOLLOWING The evaluation section of the drill/exercise package includes a

'custom-tailored'ime-Line V/orksheet and Evaluation Criteria Worksheets prepared for each of the following centers 5/or functions...

-Control Room (CR Simulator) -Operations Support Center

-Technical Support Center -Central Alarm Station (& Site Security)

-Supply System Decision Center -Security Decision Center

-EOF Communications Center -MUDAC

-Technical Data Center -Field Teams

-JIC -Health Physics Center The Time-Line Worksheet for each center is followed by the appropriate Evaluation Criteria Worksheets. The Time-Line Worksheets are for indicating the'time specific actions or events took place in your center. The Evaluation Criteria Worksheets apply to ALL centers or to specific centers as indicated at the top of the form. The evaluation statements, or

'Points of Review', address specific items that the controller/evaluators need to look for. If a specific evaluation criteria is NA, mark it as such. If not, mark whether it was demonstrated or not. Controllers & Evaluators are responsible for filling out the appropriate Evaluation Criteria Worksheets for their appropriate Center &/or Function. It must be understood that the Supply System does not intend to perform evaluation of the performance of Non-Supply System agencies participating in this Drill... for example, Dept Of Health personnel participatingin the TDC and MUDAC.

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THIS PAGE IS:

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T&IE LINE WORKSHEEY XXRRCXSE 93

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EVENT Drill Start Plant PA Announcement completed Unusual Event UE - EAL recognized by PED VE - Declared by PED UE - Crash Call completed UE - Alerting Tone sounded UE - Plant PA Announcement completed UE - PA Announcement of hazards UE - NRC Notification completed Alert ALERT- EAL recognized by PED ALERT- Declared by PED ALERT- Crash Call completed ALERT- Alerting Tone sounded ALERT- Plant PA Announcement completed ALERT- PA Announcement of hazards ALERT- NRC Notification completed Site Area Emergency (ifapplicable)

SAE - EAL recognized by PED SAE - Declared by PED SAE - Crash Call completed SAE - Alerting Tone sounded SAE - Plant PA Announcement completed SAE - PA Announcement of hazards SAE - NRC, Notification completed General Emergency (if applicable)

GE- EAL recognized by PED GE- Declared by PED GE- Crash Call completed GE- Alerting Tone sounded GE- Plant PA Announcement completed GE- PA Announcement of hazards

.. GE- NRC Notification completed

TIME LINE WORKSHEET EXERCISE 93 QAhBZATf N ';~ 'i ~ "";; ';,"' ': "."i',""<'"".". ".~ "P"""~>4

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'VENT Other Items Warranting Input (ifapplicable)

Shift Manager/PED passed control to On-Call PED PED change-over to On-Call PED announcement made in CR Protected Area Evacuation order Plant PA announcement made (specify area and type)

Information Coordinator arrived Control Room communicator arrived Simulator staff secured Exercise f 1 g

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SUPPLY SYSTEM DRILL & EXERCISE EVALUATIONCRH'ERIA WORKSHEET APPLICABLE CEDER(S) R

1. Demonstrate the ability for the Shift Manager and the control room operators to recognize abnormal events, determine plant conditions and bring the plant into a safe shutdown mode (82301-03.02.01b.l.a)

YES NO N/A

2. Demonstrate the ability of the control room operators to correctly implement the immediate actions of the Emergency Plan Implementing Procedures (82301-03.02.0lb.l.b)

YES NO N/A

3. Demonstrate the ability of the control room operators to classify the emergency using the Emergency Action Levels (EALs) and determine the necessary onsite and offsite protective actions without waiting for dose assessment (82301-03.02.0lb.l.c)

YES NO N/A 4, For a Site Area or General Emergency, demonstrate the ability of the control room to evacuate nonessential personnel and initiate protective actions for all personnel remaining on site (82301-03.02.01b.l.e)

YES NO N/A

5. Demonstrate the ability of the control room to promptly notify onsite personnel of emergency events, conditions or actions (82301-03.02.0lb.l.f)

YES NO N/A

6. Demonstrate the ability of the control room to promptly notify offsite officials of emergency events, conditions or actions (82301-03.02.01b.l.g)

YES NO N/A 1

SUPPLY SYSTEM DRILL 8c K&RCISE EVALUATIONCRlTERIA WORKSHEET APPLICABLE CENTER(S) R

7. Demonstrate the ability to make Secondary Alarm Station (SAS) and NRC notifications in a timely manner.

YES NO N/A

8. Demonstrate the timely and systematic transfer of the Plant Emergency Director (PED) duties.

YES NO N/A

TIME LINE WORKSHEET EXERClSE 93 Alert Plant PA Announcement heard OSC Director assumes command OSC Director announces to OSC Staff he has assumed command OSC declared activated Protected Area evacuation Plant PA announcement heard in OSC fspecify area and type)

~ ~ ~

Initial Habitability monitoring conducted

~ ~

First Reentry Team dispatched from OSC to (specify area & taskJ Dispatched Reentry Team to measure rad readings in Protected Area Communications Support personnel arrive from EOF OSC assumes responsiblity for PET direction and control (relieves CRJ Initial accountability declared complete by OSC OSC Staff secure from Exercise

SUPPLY SYSTEM DRILL & KKRCISE EVALUATIONCRH'ERIA WORKSHEET APPLICABLE CENTI'ER(S) L OIQECIIVE 1: MOBILIZATIONOF ElVHHLGENCY PERSONNEL Demonstrate the capability to alert and fully mobilize personnel for both emergency facilities and field operations. Demonstrate the capability to activate and staff emergency hcilities for emergency operations.

1.1 At what times did the center receive notification of emergency classification levels (ECLs)?

N Unusual Event Alert Site Area Emergency General Emergency 1.2 Did all 60 minute responders arrive at the center in the time allotted?

YES NO N/A 1.3 Were all emergency center positions staffed? Ifnot, list those that weren'.

YES NO N/A 1.4 At what times did the activation process for this hcility begin and end.

Begin: End:

1.5 In the implementation of the activities associated with this objective, did the kcility follow its plans and procedures? Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL 4 KCERCISE EVALUATIONCRITERIA WORKSHEET APPLICABLE CENI'ER(S) AL OBJF~VE 2: FACILITIES-EQUIPAQ~22IT, DISPLAYS AND WORK EZAMONMKNT Demonstrate the adequacy of facilities, equipment, displays, and other materials to support emergency operations.

2.1 Was update of the status board(s) done promptly (i.e., within about 10 minutes) following receipt of significant changes in event information at the nuclear power plant? Ifnot, provide comments below YES NO N/A Comments:

2.2 Was acceptable accountability maintained for the center (OSC,TSC,CR)?

YES NO N/A 2.3 In the implementation of the activities associated with this objective, did the facility follow its plans and procedures? Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL' EXERCISE EVALUATIONCRITERIA WORKSHEET APPLICABLE CENTER(S) L OJQECTIVE 3: DIRXXTIONAND CONTROL Demonstrate the capability to direct and control emergency operations.

3.1 Were the following actions performed by the Center Director or designee. indicate YES, NO, N/A, or N/0 in the space provided for each item.)

Issued appropriate instructions to stafF Conducted stafF meetings and briefings, as necessary Resolved jurisdictional or decision-making authority conflicts Provided leadership in decision mahng Involved stafF in decision mahng Dim+ted coordination with other jurisdictions Authorized implementation of protective action recommendations 3.2 Did the Center Director or designee demonstrate the ability to direct the center in performing its essential functions' YES NO N/A 3.3. In the implementation of the activities associated with this objective, did the facility follow its plans and procedures? Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL Bc KCERCISE EVALUATIONCRITERIA WORKSHEET APPLICABLE CENTER(S) AL OBJECHWE 4: COMMUNICATIONS Demonstrate the capability to communicate with all appropriate emergency personnel at facilities and in the field.

4.1 Did the'staff in this facility demonstrate proficiency in the use of the available communications systems2 Ifno, provide comments below.

YES NO N/A Comments:

4.2 Did this facility find alternate ways to communicate with other organizations without undue delay when malfunctions or breakdowns in equipment occurred2 YES'O N/A 4.4 In the implementation of the activities associated with this objective, did the facility follow its plans and pnmxiures2 Ifno, provide comments belev.

YES NO N/A Comments:

SUPPLY SYSTEM DMLL& EXERCISE EVALUATIONCRITERIA WORKSHEET APPLICABLE CENTER(S) A OBJECITVE 5: EMERGENCY WORKERS D<fPOSURE CONTROL Demonstrate the capability to continuously monitor and control radiation exposure to emergency workers.

5.1 Were the direct-reading dosimeters zeroed and/or the initial readings recorded prior to deployment2 YES NO N/A 5.2 . Were emergency workers aware of their maximum authorized mission exposure limit2 YES NO N/A (a) Ifyes, what exposure limit did they indicate' 5.3 Were emergency workers authorized to terminate their mission by their own decisions ifa turn-back value was zeached2 YES NO N/A (a) What turn-back value(s) did they use2 (b) Whom would they contact2 Specify individual by title and organization.

SUPPLY SYSTEM DRILL Sc KCERCISE EVALUATION.CRI'TERIAWORKSHEET APPLICABLE CENTER(S) A OBJECIXVE 8: EMI<&GENCT %ORKI& EXPOSURE CONTROL 5.4 Did emergency workers monitor their own exposure?

YES NO N/A p

(a) Ifyes, were dosimeters read at critical points as dictated by area conditions or the potential for exposure?

YES NO N/A (b) Was personal dosimetry worn in the proper location?

YES NO N/A 5.5 Were emergency workers made aware of the potential need to take potassium iodide (KI) for thyroid blocking?

YES NO N/A 5.6 Were emergency workers, who were assigned special missions, briefed regarding higher dose limits authorized for these assignments'?

YES NO N/A (a) Was any special administrative approval required for these higher dose limits?

YES NO N/A 5.7 In the implementation of the activities associated with this objective, did the facility follow its plans procedures? Ifno, provide comments below.

'nd YES NO N/A Comments:

SUPPLY SYSTIM DRILL 4 KCERCISE EVALUATIONCRITERIA WORKSHEZT APPLICABLE CENTER(S)

1. For Alerts, Site Area and General Emergencies, demonstrate that the OSC can be activated and prepared to perform required functions within about 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after declaration of the emergency.

YES NO N/A

2. Demonstrate the ability of the OSC to effectively communicate with the EOF, 'ISC arid repair teams, and adequately brief, track and debrief teams dispatched from the OSC YES NO N/A

3. Demonstrate the ability to implement emergency exposure guidelines for onsite emergency workers as necessary YES NO N/A

4. Demonstrate the ability to maintain appropriate radiological controls in the Protected Area throughout the course of the event.

YES NO N/A

5. Demonstrate the ability to provide respiratory protection and contamination contxol in the P Area.

YES NO N/A

6. Demonstrate the abiTity to respond to and analyze simulated elevated airborne and direct radiation measurements in the Protected Area environment.

YES NO N/A

7. Demonstrate the ability to monitor OSC habitability.

YES NO N/A

8. Demonstrate the ability to maintain accountability for all on-site personnel for the duration of the emergency event.

YES NO N/A

SUPPLY SYSTEM DRILL & KKRCISE EVALUATIONCRI'IBERIA WORKSHEHl'PPLICABLE CEDER(S)

9. Demonstrate the ability of the OSC Director to command and coordinate OSC activities with the CR and TSC YES NO N/A

10. Demonstrate the ability to communicate technical information to the 'ISC and CR.

YES NO N/A

\R TIME LINE WORKSHEET EXERC(SE 93 EVENT TSC Declared activated On-Call PED assumes control from Shift Manager/PED On Call PED announces his assumption of PED duties from SM over Plant PA Site Area Emergency (ifapplicable)

SAE - EAL recognized by PED SAE - Declared by PED SAE - Crash call completed SAE - Alerting Tone sounded SAE - PA announcement completed SAE - NRC notification completed SAE - direction to commence controlled evacuation given General Emergency fifapplicable)

GE - EAL recognized by PED GE - Declared by PED GE - Crash call completed GE - Alerting Tone sounded GE - PA announcement completed GE - NRC notification completed Other Items Warranting Input (ifapplicable)

PED passed RM duties to on-call EOF RM PA announcement of RM duties now being assumed by on-call EOF RM TSC Director informed of habitability status of TSC PED informed of establishment of road blocks TSC Staff secured from Exercise

SUPPLY SYSTEM DRILL 8c EPKRCISE EVALUATIONCRITERIA WORKSHEET APPLICABLE CENTER(S) L OBJEXTIVE 1: MOBILIZATIONOF EIVQWGENCY PERSONMX, Demonstrate the capability to alert and fully mobiTize personnel for both emergency facilities and field operations. Demonstrate the capability to activate and staff emergency facilities for emergency operations.

1.1 At what times did the center receive notification of emergency classification levels (ECLs).

D Unusual Event Alert Site Area Emergency General Emergency 1.2 Did all 60 minute responders arrive at the center in the time allotted2 YES NO N/A 1.3 Were all emergency center positions staffed? Ifnot, list those that weren'.

YES NO N/A 1.4 At what times did the activation process for this hcility begin and end?

Begin: End:

1.5 In the implementation of the activities associated with this objective, did the facility follow its plans and procedures2 If no, provide comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL & EPKRCISE EVALUATIONCRI'TERIA WORKSHEET APPLICABLE CENTER(S) AL OBJ1KZXVE 2: FACILITIES-EQUIPMENT, DISPLAYS AND WORK ENVIRONMENT Demonstrate the adequacy of facilities, equipment, displays, and other materials to support emergency operations.

2.1 Was update of the status board(s) done promptly (i.e., within about 10 minutes) following receipt of significant changes in event information at the nuclear power plant? If not, provide comments below.

YES NO N/A Comments:

.2.2 Was acceptable accountability maintained for the center (OSC,TSC,CR)?

YES NO N/A 2.3 In the implementation of the activities associated with this objective, did the facility follow its plans and procedures? Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL & KKRCISE EVALUATIONCRITERIA WORKSHEET APPLICABLE CENTER(S)

ORg~~VE 3: DIR%XTION AND CGXIROL Demonstrate the capability to direct and control emergency operations.

3.1 Were the following actions performed by the Center Director or designee. indicate YES, NO, N/A, or N/0 in the space provided for each item.)

Issued appropriate instructions to staff Conducted staff meetings and briefings, as necessary Resolved jurisdictional or decision-making authority confHcts Provided leadership in decision. making Involved staff in decision mahng Directed coordination with other jurisdictions Authorized implementation of protective action recommendations 3.2 Did the Center Director or designee demonstrate the ability to direct the center in performing its essential functions2 YES NO N/A 3.3. In the implementation of the activities associated with this objective, did the facility follow its plans and procedures2 Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL & EXERCISE EVALUATIONCRI'TERIA WORKSHEET APPLICABLE CENTER(S) AL OBJECHVE 4: COMMUNICATIONS Demonstrate the capability to communicate with all appropriate emergency personnel at facilities and in the field.

4.1 Did the stafr in this hcility demonstrate proficiency in the use of the available communications systems? If no, provide comments below.

YES NO N/A Comments':

4.2 Did this facility find alternate ways to communicate with other organizations without undue delay when malfunctions or breakdowns in equipment occurred'l YES NO N/A 4.4 In the implementation of the activities associated with this objective, did the hcility follow its plans and procedures'l If no, provide'comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL & KCERCISE EVALUATIONCRITERIA WORKSHEET APPLICABLE CENTER(S) A OBJECTIVE 5: EMIHLGENCY WORKER 1~&POSURE CONTROL Demonstrate the capability to continuously monitor and control radiation exposure to emergency workers.

P 5.1 Were the direct-reading dosimeters zeroed and/or the initial readings recorded prior to deployment?

YES NO N/A 5.2 Were emergency workers aware of their maximum authorized mission exposure limit.

YES NO N/A (a) Ifyes, what exposure limit did they indicate2 5.3 Were emergency workers authorized to terminate their mission by their own decisions ifa turn-back value was reached?

YES NO N/A (a) What turn-back value(s) did they use?

(b) Whom would they contact2 Specify individual by title and organization.

SUPPLY SKI'EM DRILL & KCERCISE EVALUATIONCRITERIA WORKSEKEI'PPLICABLE CENTER(S)

OBJECTIVE 5: EMHtGENCY WORKER EXPOSURE CONTROL 5.4 Did emergency workers monitor their own exposure?

YES NO N/A (a) Ifyes, were dosimeters read at critical points as dictated by area conditions or the potential for exposure2 YES NO N/A (b) Was personal dosimetry worn in the proper location?

YES NO N/A 5.5 Were emergency workers made aware of the potential need to take potassium iodide (Kl) for thyroid blocking?

YES NO N/A 5.6 Were emergency workers, who were assigned special missions, briefed regarding higher dose limits authorized for these assignments2 YES NO N/A (a) Was any special administrative approval requued for these higher dose limits?

YES NO N/A 5.7 In the implementation of the activities associated with this objective, did the hcility follow its plans and procedures? Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SYZI'EM DRILL Bc KKRCISE EVALUATIONCRI'FERIA WORKSHEET APPLICABLE CENTER(S) 9: PLUME PROTECI'IVE ACTION RECOMMENDATIONS (PARS)

A'BJEXTXVE Demonstrate the capability to make timely and appropriate action recommendations (PARs).

9.1 What PARs were made and when were they madel'pss of plume PARs to be addressed include:

shelter, evacuation, and use of potassium iodide (Kl).

ECL 9.2 Which of the following factors were considered in subsequent PARs'7 (Please indicate YES, HO, N/A, or N/0 in the space provided for.each item.)

Plant conditions and emergency classiQcation level Projected dose based on release estimates and meteorological conditions Projected dose based on plant conditions and emergency action levels Projected dose based on simulated Geld measurements and-meteorological conditions Shelter availability Evacuation time estimates Relative dose savings between evacuation and sheltering Risk fmm evacuation Weather conditions Other (Specify) 9.3 Were appropriate decision makers involved in the PAR process-was the PAD making group effective'ES NO N/A

SUPPLY SYSTEM DRILL Ec KCERCISE EVALUATIONCRITERIA WORKSHEET APPLICABLE CEKKR(S)

For Alerts, Site Area and General Emergencies, demonstrate that the 'ISC can be activated and prepared to perform required functions within about 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after declaration of the emergency (82301-03.02.0 lb.2.a)

YES NO N/A

2. Demonstrate the ability of the TSC to assess plant conditions and determine the proper emergency classification (82301-03.02.01b.2.b)

YES NO N/A

3. Demonstrate the ability of the TSC to assess and direct actions to mitigate the consequences of an emergency (82301-03.02.0lb,2.b)

YES NO N/A

4. Demonstrate the capability of the Duty Plant Emergency Director (PED) to make timely and effective decisions and demonstrate command and control of the TSC and onsite response effort.

YES NO N/A

5. Demonstrate the. ability of the TSC to determine the necessary protective actions for onsite and offsite personnel.

YES NO N/A

6. Demonstrate the ability of the TSC to promptly notif'y onsite personnel of emergency events, classifications and actions (82301-03.02.01b.2.e)

YES NO N/A

7. Demonstrate the ability to conduct and maintain personnel accountability.

YES NO N/A

SUPPLY SYSTEM DRILL Ec EPQDCISE EVALUATIONCRH'ERIA FORESHEET APPLICABLE CENTI'ER(S)

8. Demonstrate the ability of the 'ISC Director to communicate with onsite and offsite emergency response personnel when making decisions and implement corrective actions in an effective and timely manner (82301-03.02.0lb.2.g)

YES NO N/A tl

9. Demonstrate the ability of the ISC to communicate technical information to the CR, OSC, EOF and NRC YES NO N/A

10. Demonstrate the timely and systematic transfer of Recovery Manager duties.

YES NO N/A

TIME LINE WORKSHEET EXERClSE 93

EVALUATORNAMEhiE8 +j~s

-.rjg';;'t,y<,'@Aver>>~A.@gal>ti~" .t~+$ t~yX

f c

't."lUit.~~:~gklui1: fr'ayf't,'fklol/.,Rtf' sitftaIWMie'dl'~,'-'.'QEQTRAiLti T1ME EVENT

. Unusual Event radio announcement completed Alert radio announcement completed Site Area radio announcement completed Road blocks implemented Dosimetry relocated Accountability computer printout sent to OSC CAS staff secured from the Exercise

SUPPLY SYSI'EM DRILL Bc KCERCISE EVALUATIONCRXZERIA WORKSHEEI'PPLICABLE CENTER{S) 089!XTlVE 1: MOBILIZATIONOF IMI~&GENCYPERSONMX Demonstrate the capability to alert and fully mobi1ize personnel for both emergency facilities and field operations. Demonstrate the capability to activate and staff emergency facilities for emergency operations.

1.1 At what times did the center receive notification of emergency classification levels (ECLs)2 Unusual Event Alert Site Area Emergency General Emergency 1.2 Did all 60 minute responders arrive at the center in the time allotted.

YES NO N/A 1.3 Were all emergency center positions stafFed? Ifnot, list those that weren'.

YES NO N/A 1.4 At what times did the activation process for this hcility begin and end2 Begin: End:

1.5 In the implementation of the activities associated with this objective, did the facility follow its plans and procedures2 Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL k, &EXERCISE EVALUATIONCRXI'ERIA WORKSHEET APPLICABLE CENI'ER(S) ALL 08$ 1KTIVE 2: FACILjHIES-EQUIPM~:NT, DISPLAYS AND WORK ENVIRONMI~WT Demonstrate the adequacy of facilities, equipment, displays, and other materials to support emergency operations.

VIEW 2.1 Was update of the status board(s) done promptly (i.e., within about 10 minutes) following receipt of significant changes in event information at the nuclear power plant? If not, provide comments below.

YES NO N/A Comments:

2.2 Was acceptable accountability maintained for the center (OSC,TSC,CR)?

YES NO N/A 2.3 In the implementation of the activities associated with this objective, did the facility foQow its plans and procedures? Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL 8c KKRCISE EVALUATIONCRXI'ERIA WORKSHEEI'PPLICABLE CENTER(S) 089<~IVE 3: DIRF~ON AND CONTROL Demonstrate the capability to direct and control emergency operations.

3.1 Were the following actions performed by the Center Director or designee? indicate YES, NO, N/A, or N/0 in the space pmvided for each item.)

Issued appropriate instructions to stafF Conducted staff meetings and briefings, as necessary Resolved jurisdictional or decision-making authority confiicts Provided leadership in decision making Involved stafF in decision mahng Directed coordination with other jurisdictions Authorized implementation of protective action recommendations 3.2 Did the Center Director or designee demonstrate the ability to direct the center in performing its essential functions?

YES NO N/A 3.3. In the implementation of the activities associated with this objective, did the facility follow its plans and procedures? Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL & HCEKCISE EVALUATIONCRITERIA %ORKSHEET APPLICABLE CENTER(S) L OBJECXIVE 4: COMMUNICATIONS Demonstrate the capability to communicate with all appropriate emergency personnel at facilities and in the field.

4.1 Did the staff in this kcility demonstrate proficiency in the use of the available communications systems? Ifno, provide comments below.

YES NO N/A Comments:

4.2 Did this kcility find alternate ways to communicate with other organizations without undue delay when malfunctions or breakdowns in equipment occurred?

YES NO N/A 4.4 In the implementation of the activities associated with this objective, did the facility follow its plans and pnxedures? Ifno, provide comments below.

YES NO N/A Comments:

I I'

TIME LINE WORKSHEET EXERCl$ E 93

,".,6/mchei~lhloif:Tiun'rhle~r/Isrr~nn&kjkiha8",, QECQRf~p, 'QEQ)$ /Og,,CENg:ER,'r'pe~'>,';,.'...,.....~"'.,-",Q' '.,;";,,

TIME EVENT Security Decision Center declared activated SDC secured from Exercise

k SUPPLY SYSTEM DRILL EXERCISE EVALUATIONCRI'I'ERIA WORKSHEET APPLICABLE CENTER(S)

OBJECIIVE 1: MOBILIZATIONOF EMIHLGENCY PERSON&9 Demonstrate the capability to alert and fully mobilize personnel for both emergency facilities and field operations. Demonstrate the capability to activate and staff emergency facilities for emergency operations.

p F VIEW 1.1 At what times did the center receive notification of emergency classification levels {ECLs)2 N

Unusual Event Alert Site Area Emergency General Emergency 1.2 Did all 60 minute responders arrive at the center in the time allotted?

YES NO N/A 1.3 Were all emergency center positions steed? Ifnot, list those that weren'.

YES NO N/A 1.4 At what times did the activation process for this facility begin and end?

Begin: End:

1.5 In the implementation of the activities associated with this objective, did the facility follow its plans and procedures? Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL & KCERCISE EVALUATIONCRH'ERIA WORKSHEET APPLICABLE CENTER(S) ALL OBJECTIVE 2: FACILITIES-EQUIPMEN'I',DISPLAYS AND WORK EZA~ONMPiT Demonstrate the adequacy of facilities, equipment, displays, and other materials to support emergency operations.

2.1 Was update of the status board(s) done promptly (i.e., within about 10 minutes) following receipt of significant changes in event information at the nuclear power plant? If not, provide comments below.

YES NO N/A Comments:

2.2 %hs acceptable accountability maintained for the center (OSC,'ISC,CR)?

YES NO N/A 2.3 In the implementation of the activities associated with this objective, did the facility follow its plans and procedures? Ifno, provide comments belev.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL & EXERCISE EVALUATIONCRI'IBERIA WORKSHEEI'PPLICABLE CEN'ZER{S)

ORH<AAIVE3: DIRRX.IIONAND CONIROL Demonstrate the capability to direct and control emergency operations.

3.1 Were the following actions performed by the Center Director or designee? indicate YES, NO,

. N/A, or N/0 in the space provided for each item.)

Issued appropriate instructions to staff Conducted staff meetings and briefings, as necessary Resolved jurisdictional or decision-mahng authority confiicts Provided leadership in decision mahng Involved staff in decision making Directed coordination with other jurisdictions Authorized implementation of protective" action recommendations 3.2 Did the Center Director or designee demonstrate the ability to direct the center in performing its essential functions?

YES NO N/A 3.3. In the implementation of the activities associated with this objective, did the facility follow its plans and procedures? Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL Ec E3KRCISE EVALUATIONCRITERIA WORKSHEET APPLICABLE CENTER(S) A L OBJECIIVE 4: COMMUNICATIONS the capability to communicate with all appropriate emergency personnel at facilities and in

'emonstrate the field.

4.1 Did the staff in this facility demonstrate proficiency in the use of the available communications systems? Ifno, provide comments below.

YES NO N/A Comments:

4.2 Did this Mlityfind alternate ways to communicate with other organizations without undue delay when malfunctions or breakdowns in equipment occurred?

YES NO N/A 4.4 In the implementation of the activities associated with this objective, did the facility follow its plans and procedures? Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL & KCERCISE EVALUATIONCRH'ERIA WORKSHEET APPLICABLE CENTER(S) D For Site Ama and General Emergencies, demonstrate that the Emergency Operations Facility (EOF) can be activated and prepared to perform required functions within about 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after declaration of the emergency (82301-03.02.01b.3.a)

YES NO N/A Demonstrate the ability of the EOF to set up and maintain a communications channel to offsite authorities and keep them informed of emergency conditions (82301-03.02.01b.3.d)

YES NO N/A Demonstrate the ability to brief offsite representatives at the EOF and keep them informed of emergency conditions (82301-03.02.01b.3.f)

YES NO N/A Demonstrate the ability of the EOF to communicate effectively with corporate headquarters other emergency response personnel and centers and to obtain outside resources in a timely manner; when requested (82301-03.02.01b.3.g)

YES NO N/A

TIME LINE WORKSHEET EXERClSE 93 TIME EVENT Unusual Event UE - EOFCC Crash Calls completed UE - Part IIA responders identified UE - Part IIB responders identified UE - EOF PA announcment completed UE - Part III notifications complete Alert ALERT - EOFCC Crash Calls completed ALERT - Part IIA responders identified ALERT - Part IIB responders identified ALERT - EOF PA announcment completed ALERT - Part lll notifications complete Site Area Emergency SAE - EOFCC Crash Calls completed SAE - Part IIA responders identified SAE - Part IIB responders identified SAE - EOF PA announcment completed SAE - Part,ill notifications complete General Emergency GE EOFCC Crash Calls completed GE - Part IIA responders identified GE - Part IIB responders identified GE - EOF PA announcment completed GE - Part III notifications complete EOFCC Staff secured from Exercise

SUPPLY SYSI'EM DRILL Ec KCERCISE EUALUATIONCRH'ERIA WORKSHEET APPLICABLE CEDER(S) L OBJF~K 1: MOBILIZATIONOF EM9LGENCY PERSONNIK Demonstrate the capability to alert and fully mobilize personnel for both emergency facilities and field operations. Demonstrate the capability to activate and staff emergency facilities for emergency operations.

F 1.1 At what times did the center receive notification of emergency classification levels (ECLs)2 Unusual Event Alert Site Area Emergency General Emergency 1.2 Did all 60 minute responders arrive at the center in the time allotted?

YES NO N/A 1.3 Were all emergency center positions staffed? Ifnot, list those that weren'.

YES NO N/A 1.4 At what times did the activation process for this Rcility begin and end?

Begin: End:

1.5 In the implementation of the activities associated with this objective, did the facility follow its plans and pmcedures? Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL & EPCERCISE EVALUATIONCtuTERIA WORKSEiEET APPLICABLE CENTER(S)

OIQXXTXVE2: FACIXZIKB-KQUIPINKKF,DISPLAYS AND WORK EZA'IRONMENT Demonstrate the adequacy of facilities, equipment, displays, and other materials to support emergency operations.

2.1 Was update of the status board(s) done promptly (i.e., within about 10 minutes) following receipt of significant changes in event information at the nuclear power plant. If not, provide comments below.

YES NO N/A Comments:

2.2 Whs acceptable accountability maintained for the center (OSC,TSC,CR)?

YES NO N/A 2.3 In the implementation of the activities associated with this objective, did the facility follow its plans and procedures? Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL & KKRCISE EVALUATIONCRITERIA WORKSEKEI'PPLICABLE CENTER(S)

OlgECXXVE 3: DlRXX.HONAND COXXROL Demonstrate the capability to direct and control emergency operations.

3.1 Were the following actions performed by the Center Director or designee. indicate YES, NO, N/A, or N/0 in the space provided for each item.)

Issued appropriate instructions to stafF Conducted stafF meetings and briefings, as necessary Resolved jurisdictional or decision-mahng authority confiicts Provided leadership in decision making Involved stafF in decision making Directed coordination with other jurisdictions Authorized implementation of protective action recommendations 3.2 Did the Center Director or designee demonstrate the ability to direct the center in performing its essential functions2.

YES NO N/A 3.3. In the implementation of the activities associated with this objective, did the facility follow its plans and procedures2 If no, provide comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL & KKRCISE EVALUATIONCRXI'ERIA WORKSHEET APPLICABLE CENTFD(S) ALL OBJECHVE 4: COMMUNICATIONS Demonstrate the capability to communicate with all appropriate emergency personnel at hcilities and in the field.

4.1 Did the staff in this facility demonstrate proficiency in the use of the available communications systems? Ifno, provide comments below.

YES NO N/A Comments:

4.2 Did this hcility find alternate ways to communicate with other organizations without undue delay when malfunctions or breakdowns in equipment occurred?

YES NO N/A 4.4 In the implementation of the activities associated with this objective, did the hcility follow its plans and procedures? Ifno, provide comments below.

YES NO N/A Comments:

TIME LINE WORKSHEET EXERClSE 93 gipit fJfer~lkfuiJT~ lhferJ Jsrfnsannif JifvffIvaOj+Ulppgg~s+$ TrpJQ'fop'C}$ )QN f CFNTFR(( g>>,p,~>,, ><!,

TllNE EOF declared activated PA announcement in EOF that EOF is operational On-Call EOF-RM assumes command of RM duties from PEO PA announcement in EOF that EOF-RM has assumed duties PA announcement of hazards o

PA Announcement of Classification Changes (specify fypei PA Announcement of Classification Changes (specify type)

Crash Calls Completed:

Indicate completion time, emergency class, PAD & other major contents SSDC staff secured from Exercise

SUPPLY SYSTEM DRILL &, EXERCISE EVALUATIONCRITERIA WORKSHEZT APPLICABLE CENTER(S)

OHJ1K'HVE I: MOBILIZATIONOF EM<AGENCY PERSONNEL Demonstrate the capability to alert and fuHy mobilize personnel for both emergency facilities and Beld operations. Demonstrate the capability to activate and staff emergency facilities for emergency operations.

1.1 At what times did the center receive notiQcation of emergency classiQcation levels (ECLs)?

Unusual Event Alert Site Area Emergency General Emergency 1.2 Did all 60 minute responders arrive at the center in the time allotted?

YES NO N/A 1.3 Were all emergency center positions stafFed? Ifnot, list those that weren'.

YES NO . N/A 1.4 At what times did the activation process for this facility begin and end?

Begin: End:

1.5 In the implementation of the activities associated with this objective, did the facility follow its plans and procedures? If no, provide comments below.

YES NO N/A Comments:

SUPPLY SYFIEM DRILL & KCERCISE EVALUATIONCRITERIA WORKSHEET APPLICABLE CEDER(S) ALL OBJECHWE 2: FACILI'I'IES-EQUIPMIPFI', DISPLAYS AND WORK ENVIRONMENT Demonstrate the adequacy of facilities, equipment, displays, and other materials to support emergency operations.

2.1 Was update of the status board(s) done promptly (i.e., within about 10 minutes) following receipt of significant changes in event information at the nuclear power plant. Ifnot, provide comments below.

YES NO N/A Comments:

2.2 Was acceptable accountability maintained for the center (OSC,TSC,CR)7 YES NO N/A 2.3 In the implementation of the activities associated with this objective, did the facility follow its plans and procedures) Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SKI'EM DRILL & &KRCISE EVALUATIONCRXI'ERIA ALL WORKSHEEI'PPLICABLE CENTER(S)

OBJECFIVE 3: DXRk&IIONAND COXIROL Demonstrate the capability to direct and control emergency operations.

3.1 Were the following actions performed by the Center Director or designee. indicate YES, NO, N/A, or N/0 in the space provided for each item.)

Issued appropriate instructions to staff Conducted staff meetings and briefings, as necessary Resolved jurisdictional or decision-mahng authority conQicts Pmided leadership in decision making Involved staff in decision making Directed coordination with other jurisdictions Authorized implementation of protective action recommendations 3.2 Did the Center Ducctor or designee demonstrate the ability to direct the center in performing its essential functions2 YES NO N/A 3.3. In the implementation of the activities associated with this objective, did the facility follow its plans and paxedures2 Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL & KKRCISE EVALUATIONCRITERIA WORKSHEET APPLICABLE CENTER(S) L OBJFC'HVE 4: COlVMUNICATIONS Demonstrate the capability to communicate with all appropriate emergency personnel at facilities and in the field.

4.1 Did the*stafi'in this facility demonstrate proficiency in the use of the available communications systems'? If no, pr0vide comments below.

YES NO N/A Comments:

4.2 Did this facility find alternate ways to communicate with other organizations without undue delay when malfunctions or breakdowns in equipment occurred'?

YES NO N/A 4.4 In the implementation of the activities associated with this objective, did the facility follow its plans and procedures'? Ifno, prQvide comments below.

YES NO N/A Comments

SUPPLY SYSTf24 DRILL Sc KCERCISE EVALUATIONCRITERIA CEDER(S)

WORKSHEEI'PPLICABLE For Site Area and General Emergencies, demonstrate that the Emergency Operations Facility (EOF) can be activated and prepared to perform required functions within about 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after declaration of the emergency (82301-03.02.01b.3.a)

YES NO N/A

2. Demonstrate the ability of the Recovery Mmager to make timely and effective decisions and demonstrate command and control of the EOF functions and overall response effort.

YES NO N/A

3. Upon activation, demonstrate the ability of the EOF to make offsite protective action recommendations (82301-03.02.01b.3.c)

YES NO N/A 4, Demonstrate the ability of the EOF to set up and maintain a communications channel to offsi authorities, including NRC and keep them informed of emergency conditions (82301-03.02.01b.3.d)

YES NO N/A

5. Demonstrate the ability to brief offsite representatives at the EOF and keep them informed of emergency conditions (82301-03.02.01b.3.f)

YES NO N/A

6. Demonstrate the ability of the EOF to communicate effectively with corporate headquarters and other emergency response personnel and centers and to obtain outside resources in a timely manner, when requested (82301-03.02.0lb.3.g)

YES NO N/A

TIME LINE WORKSHEET EXERCISE 93

"-"- - ""<<OFF$ KEFAGENCY4COGRDINAT'IGN'::CENTER::::='-"":."'"-'4 EVENT Offsite Agency Coordination Center declared activated Offsite Agency Coordination Center secured from Exercise

SUPPLY SYSTEM DRILL & KKRCISE EVALUATIONCRH'ERIA WORKSHEET APPLICABLE CENTER(S) A OBJECIVfE 1: MOBILIZATIONOF KMHLGENCYPERSONNEL Demonstrate the capability to alert and fully mobilize personnel for both emergency facilities and field operations. Demonstrate the capability to activate and staff emergency hcilities for emergency operations.

1.1 At what times did the center receive notification of emergency classification levels (ECLs)?

Unusual Event Alert Site Area Emergency General Emergency 1.2 Did all 60 minute responders arrive at the center in the time allotted?

YES NO N/A 1.3 Werc all emergency center positions staffed? Ifnot, list those that weren' YES NO N/A 1.4 At what times did the activation process for this facility begin and end?

Begin: End:

1.5 In the implementation of the activities associated with this objective, did the hcility follow its plans and procedures? If no, provide comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL & KKRCISE EVALUATIONCRITERIA WORKSHEET APPLICABLE CENTER(S) LL OBJIKXIVE2: FACILITY-EQUIPMENT,DISPLAYS AND WORK ENVIRONMENT Demonstrate the adequacy of facilities, equipment, displays, and other materials to support emergency operations.

2.1 Was update of the status board(s) done promptly (i.e., within about 10 minutes) following receipt of significant changes in event information at the nuclear power plant? If not, provide comments below.

YES NO N/A Comments:

2.2 Was acceptable accountability maintained for the center (OSC,TSC,CR)?

YES NO N/A 2.3 In the implementation of the activities associated with this objective, did the facility follow its plans and procedures? If no, pmvide comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL & FÃERCISE EVALUATIONCRI'TERIA %ORKSHEET APPLICABLE CENTER(S)

OBJECIEVE 3: DIRRXTION AND COXIROL Demonstrate the capability to direct and contxol emergency operations.

3.1 %ere the following actions performed by the Center Director or designee? {Indicate YES, NO, N/A, or N/0 in the space provided for each item.)

Issued appropriate instructions to stafF Conducted stafF meetings and briefings, as necessary Resolved jurisdictional or decision-mahng authority conflicts Provided leadership in decision mahng Involved stafF in decision making Directed coordination with other jurisdictions Authorized implementation of protective action recommendations 3.2 Did the Center Director or designee demonstrate the ability to direct the center in performing its essential functions2 YES NO N/A 3.3. In the implementation of the activities associated with this objective, did the facility follow its plans and pxocedures2 If no, provide comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL & FZCERCISE EVALUATIONCRITERIA WORKSHEET APPLICABLE CENTER(S) L OEJECIIVE 4: COMMUNICATIONS Demonstrate the capability to communicate with all appropriate emergency personnel at facilities and in the field.

4.1 Did the staff in this facility demonstrate proficiency in the use of the available communications systems2 If no, provide comments below.

YES NO N/A Comments:

4.2 Did this facility find alternate ways to communicate with other organizations without undue delay malfunctions or breakdowns in equipment'occurred? 'hen YES NO N/A 4.4 In the implementation of the activities associated with this objective, did the facility follow its plans and procedures2 Ifno, provide comments below.

YES NO N/A Comments:

P )

TlME LlNE MIORKSHEET EXERCISE 93

,'<ORGANIZATION!,<""<+~": ~g';;:<<5.'.Q:.<'."""<yYi,"<~:.:.Q.."+>: ~:~'<<'g<."!'i'j<A<

, '>;< n'g w5,";xp

'iR 4%t ~(Wharf t'ai i'i'(4'os ~sriifMwcge~+CH NIAL)gDA)PA',;-C<EQTERjj ~,,'c ~,":.;,"j>~~

TlME EVENT Technical Data Center declared activated Technical Data Center secured from Exercise

SUPPLY SYSTEM DRILL k KKRCISE EVALUATIONCRI'FERIA WORKSHEET APPLICABLE CEDER(S) ALL OS':TIVE I: MOBILIZATIONOF EMERGENCY PERSON&%X Demonstrate the capability to alert and fully mobilize personnel for both emergency hcilities and field operations. Demonstrate the capability to activate and staff emergency facilities for emergency operations.

1.1 At what times did the center receive notification of emergency classification levels (ECLs)2 Unusual Event Alert Site Area Emergency General Emergency 1.2 Did all 60 minute responders arrive at the center in the time allotted.

YES NO N/A 1.3 Were all emergency center positions staffed2 Ifnot, list those that weren'.

YES NO N/A 1.4 At what times did the activation process for this facility begin and end'2 Begin: End:

1.5 In the implementation of the activities associated with this objective, 'did the facility follow its plans and procedures2 If no, provide comments belev.

YES NO N/A Comments:

1

SUPPLY SYSTEM DRILL & KKRCISE EVALUATIONCRITERIA A

WORKSHEEI'PPLICABLE CENTER(S)

OEIECI'IVE 2: FACILITIIB-EQUIPMENT,DISPLAYS AND WORK ENVIRONhGKl'emonstrate the adequacy of facilities, equipment, displays, and other materials to support emergency operations.

2.1 Was update of the status board(s) done promptly (i.e., within about 10 minutes) following receipt of significant changes in event information at the nuclear power plant? Ifnot, provide comments below.

YES NO N/A Comments:

2.2 Was acceptable accountability maintained for the center (OSC,'ISC,CR)2 YES NO N/A 2.3 In the implementation of the activities associated with this objective, did the facility follow its plans and procedures2 Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SYSTjEM DRILL 8c KKRCISE EVALUATIONCRI'I1HGA'WORKSHEET APPLICABLE CENTER(S} LL OIQXCXXVE3: DIRECTION AND COXIROL Demonstrate the capability to direct and control emergency operations.

e 3.1 Were the following actions performed by the Center Director or designee. indicate YES, NO, N/A, or N/0 in the space provided for each item.)

Issued appropriate instructions to staff Conducted staff meetings and briefings, as necessary Resolved jurisdictional or decision-mahng authority conQicts Provided leadership in decision making Involved stafF in decision making Directed coordination with other jurisdictions Authorized implementation of protective action recommendations 3.2 Did the Center Director or designee demonstrate the ability to direct the center in performing its essential functions'ES NO N/A 3.3. In the implementation of the activities associated with this objective, did the facility follow its plans and procedures? Ifno, pmvide'omments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL & EXERCISE EVALUATIONCRITERIA WORKSHEET APPLICABLE CENTER(S) A OIQIM.HVE 4: COMMUNICATIONS Demonstrate the capability to communicate with all appropriate emergency personnel at facilities and in the field.

4.1 Did the stafF in this facility demonstrate proficiency in the use of the available communications systems? Ifno, provide comments below.

YES NO N/A Comments:

4.2 Did this facility find alternate ways to communicate with other organizations without undue delay when malfunctions or breakdowns in equipment occurred?

YES NO N/A 4.4 In the implementation of the activities associated with this objective, did the facility follow its plans and procedtues? Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL & EXERCISE EVALUATIONCRITERIA WORKSHEET APPLICABLE CENTER(S) TD For Site Area and General Emergencies, demonstrate'that the Emergency Operations Facility (EOF) can be activated and prepared to perform required functions within about 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after declaration of the emergency (82301-03.02.01h3.a)

YES NO N/A Demonstrate the ability of the EOF to set up and maintain a communications channel to offsite authorities and keep them informed of emergency conditions (82301-03.02.01h3.d)

YES NO N/A Demonstrate the ability to brief offsite zepresentatives at the EOF and keep them informed of emergency conditions (82301-03.02.0lh3.f)

YES NO N/A Demonstrate the ability of the EOF to communicate effectively with corporate headquarters other emergency response personnel and centers and to obtain outside resources in a timely manner, when requested (82301-03.02.01h3.g)

YES NO N/A

TIME LINE WORKSHEET EXERCISE 93 MUDAC activated State MUDAC staff arrive DOE-RL MUDAC Staff arrive First Supply System Field Team dispatched from MUDAC Last Supply System Field Team dispatched from MUDAC Contact with DOE Radiological Assessment Teams First MUDAC dose projection completed Plume definition acheived by MUDAC Staff First dose projection map submitted by MUDAC staff to REM First Field Team status map submitted by MUDAC staff to REM Need for Kl evaluated Kl recommendation ( "YES" / "NO" ) to REM t

Dose Projection PAR's submitted to REIN list PAR number 8 time and attach cc of PAR to this worksheet MUDAC Staff secured from Exercise

TIME LINE WORKSHEET EXERClSE 93 EVENT All Table B.1 Field Team members present in EOF (6 req'd)

First Field Team ready for deployment F/.T no.

Last Field Team ready for deployment. F/T no.

First F/T reports reading above background at (specify grid location of the reading)

River Evacuation F/T at Lestie Groves Park First air sample ordered. F/T no.

First air sample results reported to MUDAC. F/T no.

Contamination boundaries established.

Field Teams secured from the Exercise

SUPPLY SYSTEM DRILL & &KRCISE EVALUATIONCRITERIA WORKSHEET APPLICABLE CEDER(S) LL OIU1K'HVE 1: MOBILIZATIONOF EMERGENCY PERSONM<2 Demonstrate the capability to alert and fully mobilize personnel for both emergency facilities and field operations. Demonstrate the capability to activate and staff emergenby facilities for emergency operations.

F 1.1 At what times did the center receive notification of emergency classification levels (ECLs)?

Unusual Event Alert Site Area Emergency General Emergency 1.2 Did all 60 minute rcsponders arrive at the center in the time allotted2 YES NO N/A 1.3 Were all emergency center positions stafFed? Ifnot, list those that weren'.

YES NO N/A 1.4 At what times did the activation process for this facility begin and end2 Begin: End:

1.5 In the implementation of the activities associated with this objective, did the facility follow its plans and procedures? Ifno, pnwide comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL & KKRCISE EVALUATIONCFZI'ERIA WORKSHEET APPLICABLE CENTER(S) ALL OBJECHVE 2: FACILITHH-EQUIPlVHPK,DISPLAYS AND WORK KNVIRONMEKI'emonstrate the adequacy of facilities, equipment, displays, and other materials to support emergency operations.

P 2.1 Was update of the, status board(s) done promptly (i.e., within about 10 minutes) following receipt of significant changes in event information at the nuclear power plant. Ifnot, provide comments below.

YES NO N/A Comments:

2.2 Was acceptable accountability maintained for the center (OSC,TSC,CR)?

YES NO N/A 2.3 In the implementation of the activities associated with this objective, did the facility follow its plans and ptocedures? Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL & KKRCISE EVALUATIONCRITERIA WORKSHEET APPLICABLE CENTER(S) AL ORJECXIVE 3: DIRECXION AND CORXROL Demonstrate the capability to direct and control emergency operations.

3.1 Were the following actions performed by the Center Director or designee? indicate YES, NO, N/A, or N/0 in the space provided for each item.)

Issued appropriate instructions to stafF Conducted staff meetings and briefings, as necessary Resolved jurisdictional or decision-making authority conflicts Provided leadership in decision making Involved stafF in decision making Directed coordination with other jurisdictions Authorized implementation of protective action recommendations 3.2 Did the Center Director or designee demonstrate the ability to direct the center in performing its essential functions?

YES NO N/A 3.3. In the implementation of the activities associated with this objective, did the facility follow its plans and procedures? Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL Ec KCERCISE EVALUATIONCRITERIA WORKSHEET APPLICABLE CENTER(S) A OBJECHVE 4: CO14&KNICATIONS Demonstrate the capability to communicate with all appropriate emergency personnel at Mlities and in the field.

4.1 Did the staff in this facility demonstrate proficiency in the use of the available communications systems? Ifno, provide comments below.

YES NO N/A Comments:

4.2 Did this Su%ty find alternate ways to communicate with other organizations without undue delay when malfunctions or breakdowns in equipment occurred?

YES NO N/A 4.4 In the implementation of the activities associated with this objective, did the facility follow its plans and procedures? Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL 4 KCERCISE EVALUATIONCRITERIA WORKSHEE7 APPLICABLE CHIRR(S) A OBJECHVE 5: EMERGENCY WORKI~2t IKPOSURE CONTROL Demonstrate the capability to continuously monitor and control radiation exposure to emergency workers.

5.1 Were the direct-reading dosimeters zeroed and/or the initial readings recorded prior to deployment?

YES NO N/A 5.2 Were emergency workers aware of their maximum authorized mission exposure limit?

YES NO N/A (a) Ifyes, what exposure limit did they indicate?

5.3 Were emergency workers authorized to terminate their mission by their own decisions ifa turn-back value was reached?

YES NO N/A (a) What turn-back value(s) did they use?

(b) Whom would they contact? Specify individual by title and organization.

SUPPLY SYSTEM DRILL Ec KCERCISE EVALUATIONCRH'EEUA WORKSHEET APPLICABLE CENTI'ER(S)

OBJECTIVE 8: EMERGENCY WORKIHt EXPOSURE CONTROL 5.4 Did emergency workers monitor their own exposure?

YES NO N/A t

(a) Ifyes, were dosimeters read at critical points as dictated by area conditions or the potential for exposure?

YES NO N/A (b) Was personal dosimetry worn in the proper location?

YES NO N/A 5.5 Were emergency workers made aware of the potential need to take potassium iodide (Kl) for thyroid blocking?

YES NO N/A 5.6 Were emergency workers, who were assigned special missions, briefed regarding higher dose limits authorized for these assignments?

YES NO N/A (a) %hs any special administrative approval required for these higher dose limits?

YES NO N/A 5.7 In the implementation of the activities associated with this objective, did the facility follow its plans and procedures? Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SYFIEM DRILL Bc EXERCISE EVALUATIONCRITFMA WORKSHEET APPLICABLE CENTER(S) A OB,gKXIVE 6: PLUME DOSE RADIATION Demonstrate the capability to develop dose projections and protective action recommendations regarding evacuation and sheltering.

6.1 Were dose projections and PARs accurate and made in a timely manner.

'ES NO N/A (a) At what times were PARs made?

(b) Was the CNF form completed correctly for PAR information?

YES NO N/A (c) Was PAR information transmitted in a timely manner between centers and to offsite agencies?

YES NO N/A E

6.2 Ifa computer was used as the primary means for calculating projected dose, was a backup method demonstrated?

YES NO N/A 6.3 For what exposure pathway(s) were dose projections made? (Check projection(s) made.)

Whole body gamma Iodine inhalation Other (Specify)

SUPPLY SYSTEM DRILL & KKRCISE EVALUATIONCRITERIA WORKSHEET APPLICABLE CENTER(S) A OBJECXIVE 6: PLUME DOSE RADIATION 6.4 Were there any changes to PARs based on dose projections by the facility?

YES NO N/A 4

(a) At what time were these PARs made?

(b) Was the plot(s) of the area(s) for evacuation and sheltering changed on maps or displays to show these revised PARs?

YES NO N/A 6.5 Were monitoring data made available to the dose assessment group regarding the boundaries of the plume?

YES NO '/A (a) Ifyes, when were the first data received by the dose assessment group?

6.6 Was it possible for the dose assessment group to identify the plume location on the basis of field monitoring data?

YES NO N/A (a) Ifyes, was the plume location plotted on a map on the basis of these monitoring data?

YES NO N/A 6.7 Were PARs revised on the basis of field radiation measurements?

YES NO N/A (a) Ifyes, at what time were these revisions transmitted to decision makers.

SUPPLY SYSTEM DRILL 8c EXERCISE EVALUATIONCRH'ERIA WORKSHEET APPLICABLE CEDER(S) A OB,KCI'IVE 6: PLUME DOSE RADIATION 6.8 Was the dose assessment group provided with radiological data regarding maximum gamma exposure rates from plume crossings by field teams' YES NO N/A (a) Were these measurements used as a basis for additional dose projections?

YES NO N/A (b) Ifyes, were earlier PARs changed on the basis of these dose projections'ES NO N/A (c) Ifyes, at what time were these revised PARs transmitted to the decision makers?

PRCEECIIVE ACTION RECOMMENDATION (PAR) 6.9 Were appropriate plume maps and associated information included in the transmissions'l YES NO N/A

SUPPLY SYSTEM DRILL & KKRCISE EVALUATIONCRH'ERIA WORKSHEET APPLICABLE CENIKR(S) A OBJF~~< 6: PLUME DOSE RADIATION

6. 10 Was the dose assessment group provided with monitoring data regarding radioiodine and corresponding gamma exposure rate measurements in the plume?

'ES NO N/A (a) Ifyes, when were these data received by the dose assessment group?

(b) From how many locations was this information received?

(c) Was this information used as a basis for dose projections?

YES NO N/A (d) Ifyes, were earlier PARs changed on the basis of these dose projections?

YES NO N/A (e) Ifyes, at what time were these revised PARs transmitted to the decision makers?

6.11 Did the dose projection group calculate a conversion actor to translate the gamma exposure rate measurements from the plume into corresponding radioiodine concentrations2 YES NO N/A (a) Were additional conversion factors calculated whenever new data became available?

YES NO N/A 6.12 In the implementation of the activities associated with this objective, did the facility follow its plans and procedures?

YES NO N/A 10

SUPPLY SYSTEM DRILL & EXERCISE EVALUATIONCRH'ERIA WORKSHEET APPLICABLE CENTER(S) A OBJECTS.'IVE 7: FIELD RADIOLOGICALMONITORING - AMBIENTRADIATION MOMTORING Demonstrate the appropriate use of equipment and procedures for'etermitung full radiation measurements.

7.1 Did the team check their equipment list prior to deployment to assure that none of it was nllsslIlg?

YES NO N/A (a) Ifequipment was missing, was replacement equipment obtained prior to deployment.

YES NO N/A 7.2 Did the team perform a battery check on all equipment that requires batteries for operation?

YES NO N/A 7.3 Were radio communication checks demonstrated?

YES NO N/A 7.4 'id the team check for proper operational response of each survey instrument with a radioactive check source, where appropriate, or perform an internal operational check of the survey instrument?

YES NO N/A (a) Ifan instrument demonstrated improper operation, was backup equipment provided?

YES NO N/A 7.5 Was each survey instrument labeled with the date of most recent calibration or date that next calibration is due?

YES NO N/A (a) Were the calibration dates, above, within 12 months of the exercise date'?

YES NO N/A 11

SUPPLY SYSTEM DRILL 4 KCERCISE EVALUATIONCRITjERIA WORKSEGKT APPLICABLE CEDER(S)

OBJI~&XXVI~ 7: FIKXBRADIOLOGICALMONHORING - AMBIENTRADIATION NONImRING 7.6 Was the team briefed on the following before deployment?

(a) Plant and meteorological conditions YES NO N/A (b) Exposure control procedures, including use of potassium iodide (Kl)

YES NO N/A (c) Survey procedures to be followed YES NO N/A (d) Starting point for the radiation measurements YES NO N/A (e) Locations that were assigned to be monitored YES NO N/A 7.7 Did the monitoring team arrive at the assigned monitoring location without excessive delay?

YES NO N/A 7.8 List the monitoring locations where radiation measurements were taken and the time when the measurements were taken. (Ifapplicable, attach a list of additional monitoring locations and times.)

MONZIORING LOCATION TIME OF MEASUREMENT 0* ~

12

SUPPLY SYSTEM DRILL & EDKRCISE EVALUATIONCRITERIA WORKSHEET APPLICABLE CENTER(S) LD AM OBJ1KTXVE 7: FGKB RADIOLOGICALMONITORING - AMBIENTRADIATION MONIIORING 7.9 If the plume was found, were the following readings taken at approximately waist level and near the ground (i.e., within two to three inches of the ground)? (Indicate YES, NO, N/A, or N/0 in the space provided for each item).

Waist level closed window Waist level open window Near-ground level open window Near-ground level closed window (a) Ifopen-windav readings were taken, was the open window pointed down for the near-ground-level reading?

YES NO N/A 7.10 Were plume traverse measurements taken to determine peak exposure rates in the downwind direction?

YES NO N/A 13

SUPPLY SYSTEM DRILL Bc EXERCISE EVALUATIONCRITERIA WORKSHEET APPLICABLE CENTER(S) D A OBJFA TIVE 8: FIELD RADIOLOGICALMONHORING - AIRBORNE RADIOIODINE AND PARTICULATE ACTA%IT MONITORING Demonstrate the appropriate use of equipment and procedures for the measurement of airborne radioiodine concentrations as low as 10'0.0000001) microcuries per cubic centimeter in the presence of noble gases and obtain samples of particulate activity in the airborne plume.

8.1 At what times and to what locations were field teams dispatched by the Field Team Coordinator to collect air and particulate samples? (If applicable, attach a list of additional sample locations and times.)

LOCATION 8.2 Did the field team search Sr a location with peak gamma exposure rate to taRe each air sample2 YES NO N/A (a) Were open and closed window exposure rate measurements made to confirm presence of the plume at each sample location2 YES NO N/A 14

SUPPLY SYSTEM DRILL & E3CERCISE EVALUATIONCRXI'ERIA WORKSHEET APPLICABLE CENTER(S) D OBJXXTIVE 8: E'IELD RADIOLOGICALMONITORING - AIRBORNE RADIOIODINE AND PARTICULATE ACI'IVHYMONITORING 8.3 What fiow rates were used in taking the air samples?

(a) How long was the sampling time'l minutes (b) What was the volume of the air sample(s) taken?

cubic feet (c) Were gamma exposure rate measurements made while taking each air sample?

YES NO N/A 8.4 Was the air sample media removed from the plume and taken to a low-background area for measurement2 YES NO N/A (a) %hs the air sample media purged of noble gases?

YES NO N/A (b) Was a field measurement of the gross beta-gamma activity made on the particulate filter?

YES NO N/A (c) Was a field measurement made of the radioactivity on the adsorbent filter cartridge?

YES NO N/A (d) Did field team personnel deviate from established procedures?

YES NO N/A 15

SUPPLY SYSTEM DRILL & KKRCISE EVALUATIONCRH'ERIA WORKSHEET APPLICABLE CENTER{S) M OBJ1iCXIVE 8: HFLB RADIOLOGICALMONIIORING- AIRBORNE RADIOIODINE AND PARTICULATE ACTIVITYMONITORING 8.5 Were gamma radiation exposure rate readings at the sampling locations, iodine and particulate sample count rate data promptly and accurately transmitted' YES NO N/A

{a) Ifthe data were not promptly or adequately transmitted, explain.

8 .6 Were iodine cartridges and particulate filters bagged and labeled with time, date, location taken, sample identification number and the fiel sample count rate data for particulates and IarholodlIles2 YES NO N/A A ~

16

SUPPLY SYSTEM DRILL & KCERCISE EVALUATIONCRITERIA WORKSHEET APPLICABLE CENTER(S) A OBJECTIVE 9: PLUME PROTECHVE ACHON RECOMMENDATIONS (PARS)

Demonstrate the capability to make timely and appropriate action recommendations (PARs).

9.1 What PARs were made and when were they made? aves of plume PARs to be addressed include: shelter, evacuation, and use of potassium iodide (Kl).

~R E PR A TIME ECL 9.2 Which of the Mowing factors were considered in subsequent PARs? (Please indicate YES, NO, N/A, or N/0 in the space pmvided for each item.)

Plant conditions and emergency classification level Projected dose based on release estimates and meteorological conditions Projected dose based on plant conditions and emergency action levels Projected dose based on simulated field measurements and-meteorological conditions Shelter availability Evacuation time estimates Relative dose savings between evacuation and sheltering Risk from evacuation Weather conditions Other (Specify) 9.3 Were appropriate decision makers involved in the PAR process-was the PAD making group effective?

YES NO N/A 17

SUPPLY SYSTEM DRILL & EXERCISE EVALUATIONCRITERIA %ORKSE EET APPLICABLB CENTER(S) A For Site Area and General Emergencies, demonstrate that the Emergency Operations Facility (EOF) can be activated and prepared to perform required functions within about 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after declaration of the emergency (82301-03.02.0lb.3.a)

YES NO N/A Demonstrate the ability of the EOF to deploy environmental sampling teams to appropriate locations, promptly and correctly project direction and maximum dose within the plume EPZ and the distance to which EPA PAGs are projected to be exceeded and perform dose assessment if a release is in progress (8230143.02.01b.3.b)

YES NO N/A Upon activation, demonstrate the ability of the EOF to make offsite protective action recommendations (82301-03.02.0lb.3.c)

YES NO N/A Demonstrate the ability of the EOF to set up and maintain a communications channel to o authorities, including NRC and keep them informed of emergency conditions (82301-03.02.01h3.d)

YES NO N/A Demonstrate the ability to brief offsite representatives at the EOF and keep them informed of emergency conditions (82301-03.02.01b.3.f)

YES NO N/A Demonstrate the ability to periodically assess the habitability of the EOF.

YES NO N/A 18

SUPPLY SYS'EM DRILL'& KCERCISE EVALUATIONCRITERIA WORKSHEET APPLICABLE CENTER(S) A Demonstrate the ability to dispatch offsite monitoring teams in a timely manner and the teams to implement their functions in a timely manner (82301-03.02.01b.6.a)

YES NO N/A Demonstrate proficiency of offsite monitoring teams to use protective measures equipment, locate sampling and monitoring locations, collect, bag and label samples and other duties as required to effectively perform their function (82301-03.02.01b,6.b)

YES NO N/A 19

e TlME LlNE WORKSHEET EXERClSE 93 EVENT Health Physics Center activated Health Physics Center secured from Exercise

SUPPLY SYPI'EM DRILL & KCERCISE EVALUATIONCRI'TERIA WORKSHEET APPLICABLE CENTI'ER(S) L OBJECEWE 1: MOBILIZATIONOF EMERGENCY PERSONNEL Demonstrate the capability to alert and fully mobilize personnel for both emergency facilities and field operations. Demonstrate the capability to activate and staff emergency facilities for emergency operations.

1.1 At what times did the center receive notification of emergency classification levels (ECLs)?

Unusual Event Alert Site Area Emergency General Emergency 1.2 Did all 60 minute responders arrive at the center in the time allotted?

YES NO N/A 1.3 Were all emergency center positions staffed? Ifnot, list those that weren'.

YES NO N/A 1.4 At what times did the activation process for this Rcility begin and end?

Begin: End:

1.5 In the implementation of the activities associated with this objective, did the kcility follow its plans and procedures? Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SYS'ZEN DRILL & EXERCISE EVALUATIONCRH'ERIA WORKSHEET APPLICABLE CENTER(S) L OBHZ'HUE 2: FACILITIIB-EQUIPMI~24T,DISPLAYS AND WORK ENVIRONMRKT Demonstrate the adequacy of facilities, equipment, displays, and other materials to support emergency operations.

2.1 Was update of the status board(s) done promptly (i.e., within about 10 minutes) following receipt of significant changes in event information at the nuclear power plant? If not, provide comments below.

YES NO N/A Comments:

2.2 Was acceptable accountability maintained for the center (OSC,'ISC,CR)?

YES NO N/A 2.3 In the implementation of the activities associated with this objective, did the hcility follow its plans and procedures? Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL 8c EPKRCISE EVALUATIONCRI'FERIA WORKSHEET APPLICABLE CENTER(S)

OBJECHVE 3: DIRI~~ON AND COXIROL Demonstrate the capability to direct and control emergency operations.

3.1 Were the following actions performed by the Center Director or designee. indicate YES, NO, N/A, or N/0 in the space provided for each item.)

Issued appropriate instructions to staff Conducted staff meetings and briefings, as necessary Resolved jurisdictional or decision-mahng authority confiicts Provided leadership in decision making Involved staff'n decision making Directed coordination with other jurisdictions Authorized implementation of protective action recommendations 3.2 Did the Center Director or designee demonstrate the ability to direct the center in performing its essential functions?

YES NO N/A 3.3. In the implementation of the activities associated with this objective, did the facility follow its plans and pmcedures? Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL & KKRCISE EVALUATIONCRI'IBERIA WORKSHEZT APPLICABLE CENTI'ER(S) A OBJECTIVE 4: COMMUNICATIONS Demonstrate the capability to communicate with all appropriate emergency personnel at facilities and in the field.

4.1 Did the staff in this facility demonstrate proficiency in the use of the available communications systems2 If no, provide comments below.

YES NO N/A Comments:

4.2 Did this facility Bnd alternate ways to communicate with other organizations without undue delay when malfunctions or breakdowns in equipment occurred2 YES NO N/A 4.4 In the implementation of the activities associated with this objective, did the facility follow its plans and procedures2 If no, provide comments below.

YES. NO N/A Comments:

SUPPLY SYSTEM DRILL 8c KCERCISE EVALUATIONCRH'ERIA WORKSHEET APPLICABLE CEDER(S)

OBJ1KTIVE 12: LABORAmRY OPERATIONS Demonstrate laboratory operations and procedures for measuring and analyzing samples.

12.1 Did the laboratory stafF record the time of receipt and identity of all samples?

YES NO N/A 12.2 Indicate the time of receipt of the initial sample for analyses for each of the following sample types that were received.

o dine cartridge Air particulate filter Ani'mal feeds Water Grain Forage Food crops Vegetable samples

~ilk Snow (melted)

Meat samples Soil samples Poultry Other (Specify) 12.3 Did the laboratory staff foHow appropriate procedures for avoiding cross-contamination of samples?

YES NO N/A (a) Did the laboratory staff follow appropriate procedures for avoiding contamination of the laboratory?

YES NO N/A 12.4 Did the laboratory staff segregate and store samples that had measurable gamma exposure rates in a location that would avoid build-up of the background radiation level in the laboratory counting area?

YES NO N/A 12.5 Were steps taken to assure preservation of milk samples?

YES NO N/A

SUPPLY SYSTEM DRILL & KKRCISE EVALUATIONCRITERIA WORKSHEET APPLICABLE CENTER(S)

ORKClXVE 12: LABORATORYOPERATIONS 12.6 Did the laboratory have the following analytical capabiTities7 (Check those available.)

Gamma spectrum Lithium drifted germanium [Ge(Li)]

Liquid scintillation Strontium 90 Other (Specify) 12.7 Were fixed (reproducible) geometry(ies) used for counting of samples'ES NO N/A 12.8 Were sample and background counting times adjusted to be commensurate with the required minimum detectable levels for emergency response decisions'ES NO N/A 12.9 Indicate the time that the laboratory stafF provided the results of its initial analyses to the dose assessment group for the following sample types analyzed:

Iodine cartridge Air particulate filter Animal feeds Water Grin Forage Food crops Vegetable samples Milk Snow (melted)

Meat samples Soil samples Poultry Other (Specify) 12.10 In the implementation of the activities associated with this objective, did the facility follow its plans and procedures? Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SYS'ZEM DRILL & KCERCISE EVALUATIONCRITERIA CEDER(S)

WORKSHEEI'PPLICABLE For Site Area and General Emergencies, demonstrate that the Emergency Operations Facility (EOF) can be activated and prepared to perform required functions within about 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after declaration of the emergency (82301%3.02.01h3.a)

YES NO N/A U

Demonstrate the ability to periodically assess the habitability of the EOF.

YES NO N/A

TIME LINE WORKSHEET EXERC!SE 93 EVENT JIC Activation order given JIC declared activated JIC Media telephone team phone lines opened JIC Public Information team phone lines opened First news conference started News Releases List time distribution completed & ~~f list major contents.

Attach copy of News Release to this worksheet JiC Phone teams secured fram Exercise

'" .- Jic staff 4

secured from. Exercise

~ A 0 q ~ E }

SUPPLY SYSTEM DRILL Ec KCERCISE EVALUATIONCRH'ERIA WORKSHEZT APPLICABLE CENTER(S)

OB;jECTIVE I: MOBILIZATIONOF 5~22RGENCY PERSONNEL Demonstrate the capability to alert and fully mobilize personnel for both emergency facilities and field operations. Demonstrate the capability to activate and staff emergency facilities for emergency operations.

1.1 At what times did the center receive notification of emergency classification levels (ECLs)7 Unusual Event Alert Site Area Emergency General Emergency 1.2 Did all 60 minute responders arrive at the center in the time allotted'ES NO N/A 1.3 Were all emergency center positions staffed? Ifnot, list those that weren'.

YES NO N/A 1.4 At what times did the activation process for this facility begin and end?

Begin: End:

1.5 In the implementation of the activities associated with this objective, did the Mlityfollow its plans and procedures'f no, provide comments below.

YES NO N/A Comments:

if <4 g ' lg 1" & I '- ~ 'I 1'

SUPPLY SYSI'EM DRILL 8c. KKRCISE EVALUATIONCRITERIA WORKSHEET APPLICABLE CENTI'ER(S) L OBJECTIVE 2: FACILITIFB-EQUIPMENT,DISPLAYS AND %ORE %26/IRONMENT Demonstrate the adequacy of facilities, equipment, displays, and other materials to support emergency operations.

2.1 Was update of the status board(s) done promptly (i.e., within about 10 minutes) following receipt of significant changes in event information at the nuclear power plant? If not, provide comments below.

YES NO N/A Comments:

2.2 Whs acceptable accountability maintained for the center (OSC,'ISC,CR)?

YES NO N/A 2.3 In the implementation of the activities associated with this objective, did the hcility follow its plans and procedures? Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL & KCERCISE EVALUATIONCRITEIGA WORKSHEZT APPLICABLE CENTI'ER(S)

OBJkXTXVE 3: DIRECIION AND COXIROL Demonstrate the capability to direct and control emergency operations.

3.1 Were the following actions performed by the Center Director or designee. indicate YES, NO, N/A, or N/0 in the space provided for each item.)

Issued appropriate instructions to staff Conducted staff meetings and briefings, as necessary Resolved jurisdictional or decision-making authority confiicts Provided leadership in decision making Involved staff in decision mahng Directed coordination with other jurisdictions Authorized implementation of protective action recommendations 3.2 Did the Center Director or designee demonstrate the ability to direct the center in performing its essential functions'2 YES NO N/A 3.3. In the implementation of the activities associated with this objective, did the facility follow its plans and procedures? Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SYSTEM DRILL & KCERCISE EVALUATIONCRI'FERIA WORKSEiEET APPLICABLE CENTER(S) A OBJECHVE 4: COlVMUNICATIONS Demonstrate the capability to communicate with all appropriate emergency personnel at facilities and in the field.

4.1 Did the statf in this kcility demonstrate proficiency in the use of the available communications systems2 Ifno, provide comments below.

YES NO N/A Comments:

4.2 Did this facility find alternate ways to communicate with other organizations without undue delay when malfunctions or breakdowns in equipment occurred2 YES NO N/A 4.4 In the implementation of the activities associated with this objective, did the facility follow its plans and procedures2 Ifno, provide comments below.

YES =

NO N/A Comments:

SUPPLY SYSTEM DRILL 8'c KKRCISE EVALUATIONCRXI'ERIA EL WORKSEiEEI'PPLICABLE CENTER(S)

OBJ1< CI'D?E 10: EMERGENCY INFORMATION- MEDIA Demonstrate the capability to coordinate the development and dissemination of clear, accurate, and timely information to the news media.

10.1 Did staff provide briefings to the media?

YES NO N/A (a) Ifyes, specif'y the time briefings were initiated.

Briefing ¹1 Briefing ¹2 Briegng ¹3 Briefing ¹4 Briegng ¹3 Briefing ¹g 10.2 Which of the following were provided to the media? (Check those provided.)

Copies of news releases Copies of Emergency Broadcast System (EBS) messages Media kits Other (Specify)

(a) Ifmedia Kits were provided, did staff provide one for each member of the media present at the media center?

YES NO N/A 10.3 Was a log maintained of information provided to the media?

YES NO N/A 10.4 Were copies of news releases retained and accessible to staK?

YES NO N/A 10.5 Were staff members available at the media center to handle inquiries from the media?

YES NO N/A

SUPPLY SYSTEM DRILL k EDKRCISE EVALUATIONCRlTERIA WORKSHEET APPLICABLE CENTER(S) E OBXECIIVE 10: EMERGENCY INFORMATION- MEDIA 10.6 Were stafF and equipment available at the media center to deal with telephone inquiries from the media? (Control Cell)

YES NO N/A (a) Did telephone staff provide prompt, accurate, consistent, and responsive information to media representatives?

YES NO N/A 10.7 Did individuals preparing the briefings have access to copies of EBS messages?

YES NO N/A 10.8 VFere the following subjects addmsed in the briefings? (Indicate YES, NO, N/A or N/0 in the space provided for each item.)

Description of current emergency conditions at the plant with reference to both the potential for or actual release of radioactivity and the current emergency classification level (ECL)

How to maximize protection when sheltering Instructions for transients without shelter What to leave behind and what to take along when evacuating Evacuation routes Location of reception centers Location of congregate care centers Use of potassium iodide (Kl)

Information and instructions for parents of students concerning protective actions for students Infbrmation for transportation-dependent individuals.

Information for special populations Information and instructions on protective actions for ingestion Relocation, re-entry, or return Rumor control telephone numbers Information to address false or misleading rumors Use of public information brochures Other (Specify)

SUPPLY SYSTEM DRILL & KCERCISE EVALUATIONCRXI'ERIA %ORKSHEET APPLICABLE CENTER{S) L OBJlMAIVE 10: KVQHtGENCY 1NFORMATION - MEDIA 10.9 Did the briefings or press releases have the following characteristics2 (Check those characteristics observed.)

Accurate information Clear, understandable language Content consistent with public information brochures Consistency of information and instructions regarding protective action decisions Clear differentiation between previous and current information and instructions Up-to-date information 10.10 In all briefings and releases, were protective action areas described in terms of familiar landmarks and boundaries2 YES NO N/A 10.11 In the implementation of the activities associated with this objective, did the facility foll plans and paxedures? Ifno, provide comments below.

YES NO N/A Comments:

SUPPLY SYSTIM NEWS M<BIASES

%me Information Time Approvals Tine Distribution Xhne Distribution Received Began %am Received Completed

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SUPPLY SYSTEM DRILL Bc KKRCISE EVALUATIONCRH'ERIA WORKSHEET APPLICABLE CEDER(S) JI L OIQIKTIVE11: EMERGENCY INFORMATION- RUMOR CONTROL Demonstrate the capability to establish and operate rumor control in a coordinated and timely manner.

11.1. When was rumor contxol activated?

11.2 How was the rumor control telephone number{s) publicized?

Press briefings Emergency Broadcast System (EBS) messages Public information brochures and postings Other (Specify) 11.3 How many staff demonstrated this operation?

11.4 Did the rumor control staff have access to current and accurate information?

YES NO N/A 11.S Did the rumor contxol staff provide prompt, accurate, consistent, and responsive information to callers? (Control Ceu)

YES NO N/A 11.6 How many calls were received by the rumor control staff during the exercise? {Control Ce19 (a) Based on the number of calls received, record the average number of ca0s handled per hour during the period rumor control staff were activated.

SUPPLY SYSTEM DRILL & KKRCISE EVALUATIONCRH'ERIA WORKSHEET APPLICABLE CENTER(S) L OBJECIIVE 11: IMKRGENCY INFORMATION- RUMOR CONTROL 11.7 Was information on individual calls documented and analyzed in order to identify recurrent or important trends in rumors?

YES NO N/A 11.8 Was information on rumors used in subsequent disseminations of information by public affairs staff?

YES NO N/A (a) 'Ib whom was information on rumors provided? (Check below the recipients of this information.)

Individual caller(s)

Public Affairs Official(s) (PAO)

Other (Specify) 11.9 Did rumor control staff monitor radio and television broadcasts to determine what information was provided by the media to the public and to determine if any of this information was contributing to the spread of hlse or misleading rumors2 YES NO N/A (a) Alternatively, did they seek this information from the PAOs?

YES NO N/A (b) Ifyes, did the PAOs contacted provide the needed information?

YES NO N/A 11.10 In the implementation of the activities associated with this objective, did the Rcility follow its plans and procedures2 YES NO N/A Comments:

SUPPLY SYSTEM DRILL & KCERCISE EVALUATIONCRXI'ERIA WORKSHEHT APPLIC43LE CENTER(S)~

Demonstrate the ability of the Joint Information Center (JIC} to properly coordinate news releases with the NRC and other offsite agencies and disseminate information to the media/press in an accurate and timely manner (82301-03.02.01b.9.a)

YES NO N/A Demonstrate the ability of the JIC to maintain adequate communications for use by the news media (82301-03.02.0lh9.b)

YES NO N/A 10

4 SUPPLY SYSTEM EVALUATORLOG Exercise 93 EVALUATORS NOTB Use as many rows on this sheet as necessary to describe or comment on the item you wish. Use as many sheets as necessary to log all pertinent items.