Text

Forwards Scenario for 1985 Annual Emergency Exercise on 851017.List of NRC Observers Requiring Access Badges Requested.Exercise Schedule Provided
	ML20141F413
Person / Time
Site:	Peach Bottom
Issue date:	09/03/1985
From:	Cooney M; PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Murley T; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
	NUDOCS 8601090321
	Download: ML20141F413 (364)
	v • d • e

{{#Wiki_filter:. - PHILADELPHIA ELECTRIC COMPANY

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( (f P.O. BOX 8699 PHILADELPHIA. PA.19101 (21 s) set-sozo M. J. COONEY a.c, "c"*f.."u '

                            .."o 01".m m ,                        September 3, 1985 Docket Nos. 50-277 50-278 Dr. T. E. Murley, Administrator Region I Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pa. 19406

Subject:

Peach Bottom Atomic Power Station 1985 Emergency Preparedness Exercise m

DearDr. Murley:

L/ Enclosed for your review are two (2) copies of the confidential, detailed scenario for the Peach Bottom Atomic Power Station 1985 annual emergency exercise on October 17, 1985. A schedule for the exercise week is provided below. This schedule includes a pre-exercise briefing at 10:00 a.m., Wednesday, October 16, 1985, at the PBAPS Personnel Processing Center. The post-exercise critique is scheduled for Friday, October 18, 1985, 1:30 p.m., at the PBAPS Personnel Processing Center. l l To ensure access by NRC observers to various plant locations, the observers must be properly badged. Please provide a list of NRC observers which will be used to authorize access to the PBAPS protected area. Please forward the requested list of observers to R. A. Kankus. OV y i gggio,Oa A

                                                                 .3o,o3 p               05000277 PDR -

m. Dr. T. E. Murley- August 3, 1985 Page 2 of 2 O Should you have any comments concerning the scenario or questions concerning the schedule, please contact R. A. Kankus at (215)841-5432 or J. J. Tucker, (717)456-7014, extension 4290. Please mail all written comments on the scenario to R. A. Kankus. Very truly yours,

Enclosures cc: Document Control Desk (w/o attachment) U.S. Nuclear Regulatory Commission Washington, DC 20555 Site Inspector, PBAPS (w/o attachment) l I

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50-278 Dr. Thomas Murley Regional Pdministrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pa. 19406

Subject:

Peach Bottom Atomic Power Station 1985 Emergency Preparedness Exercise

Dear Dr. Murley:

Peach Bottom Atomic Power Station expects to conduct the annual emergency preparedness exercise on October 17, 1985. The objectives related to Philadelphia Electric Company's response are provided for your review. Please contact us if you have any concerns or comments relating to these objectives. Very truly yo es,

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i 3 !. August 5, 1985' Page 2 l. j cc t ' D. F. Taylor (PEMA) l T. Gerusky (BRP) ( J. Asher (FEMA) l Document Control Desk U.S. Nuclear Regulatory Commission l Washington, DC 20555 i i

;                                   -Site Inspector, PDAPS                                                                            ,

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4 U PHILADELPHIA ELECTRIC COMPANY OBJECTIVES FOR THE 1985 NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION In order to demonstrate the radiological emergency response preparedness of the Peach Bottom Atomic Power Station, the Philadelphia Electric Company (PECO) will conduct an integrated radiological emergency response exercise.

The PECO objectives of the exercise are as follow: A. Accident Assessment

1. Demonstrate the ability of site personnel to recognize an emergency initiating event and properly characterize and classify the emergency according to the pre-established Emergency Action Levels.

2. Demonstrate that PECO personnel can perform offsite dose projections and accident assessment, for both radioactive noble gases and radioiodine, quickly and accurately.

3. Demonstrate that onsite and offsite field monitoring teams can be dispatched and deployed in a timely manner; that field O

communications are adequate; that radiological monitoring equipment is functional; that simulated data are accurately obtained and transmitted to the appropriate location and individuals; that results for area radiation levels and air sampling and analysis for radioiodine and particulates can be effectively used in dete rmining protective action recommendations. B. Activation of Emergency Facilities .

1. Demonstrate the ability of station and corporate personnel to activate and staff the emergency response facilities as appropriate for the existing emergency class and to transfer functional responsibilities to the appropriate operations -

center when escalating or de-escalating to a different emergency class.

2. Demonstrate that adequate security of facilities can be maintained.

3. Demonstrate functional capabilities of equipment in both EOF and TSC.

C. . Notification and Communication

1. Demonstrate that station and offsite notification of PECO staff and officials can be accomplished in a timely manner 2034-1471204-B2

1

          \
  /         j                     and that all initial notification and updating is verified

(,/ and logged.

2. Demonstrate the ability to communicate with in-plant monitoring teams, rescue parties, and other station personnel as needed.

3. Demonstrate that the decision to notify the public officials can be accomplished in an effective and timely manner.

4. Demonstrate that messages are transmitted in an accurate and timely manner; that messages are pecperly logged; that status boards are accurately maintained and updated; that appro-priate briefings are held and incoming EOF personnel are briefed and updated.

5. Demonstrate that public information is coordinated between PECO and offsite officials; that there are accurate and timely press releases and briefings; that designated public information personnel are implementing their procedures.

D. Station Health Physics and Security

1. Demonstrate the ability to account for all personnel within the protected area onsite.

t i 2. Demonstrate the ability to provide adequate radiation

\                                 protection   services    such as     dosimetry and    personnel monitoring (frisking).

3. Demonstrate the ability to perform area surveys under emergency conditions.

4. Demonstrate the ability to enter a highly contaminated area for the purpose of rescuing casualties.

5. Demonstrate the ability to provide first aid and transporta-tion to a suitably prepared medical facility for an injured individual who has been contaminated or has received a high radiation dose.

6. Demonstrate the ability to maintain plant security under ,

emergency conditions.

7. Demonstrate the ability to perform post-accident sampling and analysis of in plant airborne radioactivity and surface contamination levels.

8. Demonstrate the ability to perform personnel and equipment decontamination.

9. Demonstrate the use of post-accident sampling equipment to obtain transport, and analyze samples of reactor coolant v

2034-1471204-B2

           . /.

L l ! and/or containment air samples under conditions involving l fuel damage.

                        .E. Direction and Control' 4

l 1. Demonstrate that local offsite support agencies such as ambulance response and fire companies will provide timely l support.

2. Demonstrate the ability of the directors to direct the emergency organizations in the implementation of the

! ' Emergency Plan and the Emergency Plan Implementing Procedures (EPIPs).

3. Demonstrate the capability to technically evaluate the incident conditions and implement appropriate corrective actions.

l

4. Demonstrate that PECO has 24 he capability. Demonstrate that all agency representatives who are assigned emergency reponsibilities can effectively operate from their planned location inside or outside the EOF. .

(May be done on a limited scale by designating two shifts.) t F. Protective Actions l Demonstrate the ability of the site and the EOF to make recommendations on both starting and canceling protective actions. G. Parallel and Other Actions

1. Demonstrate the ability to call on a designated hospital to treat a hypothetically contaminated injured patient and that the ambulance service can effectively transport hypothet-ically contaminated injured personnel, to the hospital.

Demonstrate that the ambulance and associated equipment can be decontaminated and that contaminated clothing and dispos-able materials are properly discarded.

2. Demonstrate the licensee's capability for self-critique and ability to identify areas needing improvement in order to make future appropriate procedural changes.

D 2014-1471204-B2 L

O NRC OBSERVED EMERGENCY RESPONSE EXERCISE MANUAL i l PEACH BOTTOM ATOMIC POWER STATION , l O OCTOBER 1985 PHILADELPHIA ELECTRIC COMPANY m

October 17, 1985 PEACH BOTTOM ATOMIC POWER STATION NRC OBSERVED EMERGENCY RESPONSE EXERCISE rN OCTOBER 1985 ( # ) TABLE OF CONTENTS Section Page 1.0 EXERCISE WEEK SCHEDULE. . . . . . . . . . . . . . . . 1.0-1 2.0 EXERCISE OBJECTIVES . .. . . . . .. .... . . . . 2.0-1 3.0 EXERCISE GUIDELINES AND SCOPE . . . . . . . . . . . . 3.0-1 3.1 GUIDELINES. . . . . . .. . .. ... . ... . . .. 3.1-1 3.2 SCOPE . . . . . . . . . . . . . . . . . ... . .. . 3.2-1 3.3 PLAYER INSTRUCTIONS . . . . . .. .. . ... . ... 3.3-1 3.4 PARTICIPATING CENTERS . . . .. . . . . .. . . .. . 3.4-1 4.0 CONTROLLER / EVALUATOR INFORMATION. . . . ... . . .. 4.0-1 4.1 ASSIGNMENTS . . . . . . . ... . . . . . .. . ... 4.1-1 4.2 INSTRUCTIONS. . . . . . . ... . . . . .. . . ... 4.2-1 4.3 EVALUATION SHEETS . . . . . ... .. . ... . . .. 4.3-1 5.0 EXERCISE SCENARIO . .. . . ... . . . ... . . .. 5.0-1 5.1 INITIAL CONDITIONS. .. . . ... . . . ... . ... 5.1-1 5.2 SCENARIO ABSTRACT . . . . .... . . . ... . .. . 5.2-1 5.3 DETAILED SCENARIO . . . . . .. .. . . .. . .. .. 5.3-1 7N 5.4 SCENARIO TIME LINE. . . . . . . . . . . . . . . ... 5.4-1 c-) 6.0 SCENARIO DATA . . . . . . . . . . . . . . . . . . . . 6.0-1 6.1 PLANT MESSAGES. . . . . . . .. .. .. .. . . . .. 6.1-1 6.2 IIEADQUARTERS SUPPORT REQUESTS . . .. . ... . . . . 6.2-1 6.3 PLANT AND REACTOR SYSTEM VALUES . . . . . .. . . .. 6.3-1 7.0 RADIOLOGICAL DATA . . . . . . . . . . . . . . . . . . 7.0-1 7.1 PLANT HONITORING DATA . . . . . . . . . . . . . ... 7.1-1 7.2 CllEMISTRY SAMPLE DATA . . . . . . . . . . . . . . . . 7.2-1 7.3 EXIIAUST VENT SAMPLE DATA. . . . . . . . . . . . . . . 7.3-1 7,4 CALCULATED DOSE RATES . . . . . . . . . . . . . . . . 7.4-1 7.5 FIELD MONITORING DATA . . . . . . . . . . . . . . . . 7.5-1 7.6 PLANT RADIATION LEVELS. . . .. . . . . . .. . . .. 7.6-1 7.7 SITE AND FIELD MONITORING MAPS. . . . . . . . . . . . 7.7-1 1.8 NETEOR0 LOGICAL DATA . . . . . . . . . . . . . . . . . 7.8-1

8.0 REFERENCES

. . . . . . . . . . . . . . . . .. . . . . 8.0-1 8.1 PROCEDURE INDEX . . . . . . . . . . . . . . . . . . 8.1-1 8.2 REFERENCE DOCUMENTS . . . . . .. . . . ... . . . . 8.2-1 (m) m i

October 17, J985

    'm
       )                                      SECTION 1.0 G'

EXERCISE SCHEDULE 1985 NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACll BOTTON ATONIC POWER STATION 1.1 Onsite Controller / Evaluator Briefing Date: Wednesday, October 16, 1985 Time: 10:00 am Location: PBAPS Personnel Processing Center

Purpose:

Pre-Exercise Scenario Briefing Attendees: PECo Controller / Evaluators NRC Observers Exercise Visitors Coordinator: J. J. Tucker 1.2 Exercise Date: Thursday, October 17, 1985 Time: Approximately 8:00 am to 4:00 pm Location: PBAPS

Purpose:

Radiological Emergency Response Attendees: Site Personnel Coordinator: J. J. Tucker

   /S 1.3 Exercise Debriefing
   !x_ !

Date: Friday, October 18, 1985 Time: 9:00 am Location: Emergency Response Facilities

Purpose:

Controller / Evaluator Debriefing Attendecs: PEco Controller / Evaluators Coordinator: J. J. Tucker . 1.4 Exercise Critique l Date: Friday, October 18, 1985 Time: 1:30 pm Location: PBAPS Personnel Processing Center

Purpose:

PEco Exercise Critique Attendees: PEco Controllers / Evaluators PEco Hajor Players NRC Coordinator: J. J. Tucker m O' l.0-1

October 17, 1985 SECTION 2.0 O (d PHILADELPilIA ELECTRIC COMPANY OBJECTIVES FOR THE 1985 NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACll BOTTOM ATOMIC POWER ST/.fl0N In order to demonstrate the radiological emergency response preparedness of the Peach Bottom Atomic Power Station, the Philadelphia Electric Company (PECO) will conduct an integrated radiological emergency response exercise. The PECO objectives of the exercise are as follow: , A. Accident Assessment

1. Demonstrate the ability of site personnel to recognize an emergency initiating event and properly characterize and classify the emergency according to the pre-established Emergency Acti_on Levels _.

2. Demonstrate that PECO personnel can perform offsite dose projections and accident assessment, for both radioactive noble gases and radioiodine, quickly and accurately.

3. Demonstrate that onsite and of fsite field monitor '.ng teams can be dispatched and deployed in a timely manner; t.$at field communications are adequate; that radiological motitoring equipment is functional; that simulated data are ac .urately

[mi V' obtained and transmitted to the appropriate lo ca *.lon and individuals; that results for area radiation level a and air sampling and analysis for radiofodine and particulaces can be effectively used in determining protective action recommendations. B. Activation of Emergency Facilities

1. Demonstrate the ability of station and corporate personnel to activate and staff the emergency response facilities as appropriate for the existing emergency class and to transfcg functional responsibilitics _ to the appropriate operations, center when escalating __or de-escalatin_g to a _dUf7 rent emergency class.

2. Demonstrate that adequate security of facilities can be maintained.

3. Demonstrate functional capabilities of equipment in both EOF i and TSC.

C. Notification and Communication

1. Demonstrate that s ta t ion _a nd o f f s i t e ,_ not i f ica t i on ,o f_I!!iC0 staff andjof flElais can be accompl.ished_in a timely manner I

a 2.0-1 l.

and that all initial notification and updating is verified and tragged.

2. Demonstrate the ability to comm m ica te with in-plant monitoring teams, rescue parties, and other station personnel as needed.

3. Demonstrate that the decision to notify the public officials can be accomplished in an effective and timely manner.

4. Demonstrate that messages are transmitted in an accurate and timely manner; that messages are properly logged; that A atus boards are accurately maintained and updated; that appro-priate br1Frings are held and incoming 'EUlf personnel are briefed and updated.

         +  5. Demonstrate that public information is coordinated between PECO and offsite officials; that there are accurate and timely press releases and briefings; that designated public information personnel are implementing their procedures.

D. Station llealth Physics and Security

1. Demonstrate the ability to account for all personnel within the protected area onsite,

2. Demonstrate the ability to provide adequate radiation protection services such as dosimetry and personnel monitoring (frisking).

3. Demonstrate the ability to perform area surveys under emergency conditions.

4. Demonstrate the ability to enter a highly contaminated area for the purpose of rescuing casualties.

5. Demonstrate the ability to provide first aid and transporta-tion to a suitably prepared medical facility for an injured individual who has been contaminated or has received a high radiation dose.

6. Demonstrate the ability to maintain plant security under emergency conditions.

7. Demonstrate the ability to perform post-accident _nampling and analysis of~in pE6it 7 Iitiorne raTHT>a c t iv i ty and surface

contamination levels.

8. Demonstrate the ability to perform personnel and equipment decontamination.

9. Demonstrate the use of post-accident sampling equipment to obtain transport, and analyze samples of reactor coolant O

2.0-2

and/or containment air samples under conditions involving

 ,c y              fuel damage.

I i O E. Direction and Control

1. Demonstrate that local offsite support agencies such as ambulance response and fire companies will provide timely support.

          --h 2. Demonstrate the 4.bility of the directors to direct the emergency organizations      in   the implementation of the Emergency Plan and the Emergency Plan Implementing Procedures (EPIPs).

S 3. Demonstrate the capability .to technically evaluate the incident conditions _and_impl went appropriate corrective ^ actions._

        -y    4. Demonstrate that PECO has 24 hr capability. Demonstrate that all   agency representatives who are assigned emergency responsibilities can effectively operate from their planned location inside or outside the EOF.        (May be done on a limited scale by designating two shifts.)

F. Protective Actions Demonstrate the ability of the site and the EOF to make recommendations on both starting and canceling protective actions. ( r]/ G. Parallel and Other Actions

1. Demonstrate the ability to call on a designated hospital to treat a hypothetically contaminated injured patient and that the ambulance service can effectively transport hypothet-ically contaminated injured personnel to the hospital.

Demonstrate that the ambulance and associated equipment can be decontaminated and that contaminated clothing and dispos-able materials are properly discarded.

2. Demonstrate the licensee's capability for self-critique and ability to identify areas needing improvement in order to make future appropriate procedural changes.

v 2.0-3

PBAPS EXERCISE CONTROLLER / EVALUATOR ASSIGNMENTS h5 arf

     ^                                    October 17, 1985                         6d       -d,'/;

LOCATION: Control Room (Head Controller, ext 4464) Head Controller =7 R. Vanasse (SWEC) Controller J. Tucker (PBAPS) LOCATION: In Plant Operations b,cd. 6e f b3 6,~D~ OSC Lead Controller - ext. 4690 Aux. OSC Lead Controller - ext. 4446 Lead Controller - OSC A. Pesarchik (PBAPS) Controller - Damage Repairs J. G. Casey (PBAPS) Controller - Damage Repairs H. R. Abendroth (PBAPS) Controller - Damage Repairs J. McElwain (PBAPS-QC) Controller - Damage Repairs E. E. Wallace III (PBAPS) Controller - Fire Event V. Affafato (LGS) Controller - Chemistry In Plant J. McMenamin (PECo) Controller - Chemistry PASS D. Chase (PBAPS) Controller ' Chemistry In Plant D. Musslemann (LCS) Controller - Contaminated Injury K. Mandl (PECo) Lead Controller - Aux. OSC J. J. McElwain (PECo) _ Controller - In Plant HP R. M. Moore (PBAPS)

 ,/       's   Controller   - In Plant ilP                          S. Taylor (LGS)

Controller - In Plant HP P. Dunn (PBAPS) Controller - in Plant HP R. Spencer Controller - Security Events G Bailey (SWEC) Evaluator - Security Events P. Supplee (LGS) Evaluator - Security Events S. Spencer (Burns - PB4PS) LOCATION: Technical Support Center ( Lead Controller ext 4630) Lead Controller - TSC R. Gerson (SWEC) Evaluator - TSC D. Leonard (SWEC) Evaluator - TSC E. Michael (SWEC) LOCATION: Emergency Operations Facility (Lead Controller ext 4662) Lead Controller R. A. Kankus (PECo) Controller - Dose Assessment C. Mazzola (SWEC) Evaluator - Dose Aasessment W. Lorenz (PECo) Evaluator - EOF KMSchlecker(PEco) Controller - Field Monitoring M. Christinziano (LCS) Controller - Field Monitoring C. Smith (LGS) Controller - Field Monitoring L. Wells (LCS) Controller - Field Monitoring J. Scone (LGS) C,d 3 #(, u. /

October 17, 1985 SECTION 3.0 ! EXERCISE GUIDELINES AND OBJECTIVES O 1985 NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTON ATOMIC POWER STATION Section Page 3.1 GUIDELINES . .. .. . .. .. .. .. . . 3.1-1 3.2 SCOPE .. . ... . . . .. . .. .. . . 3.2-1 3.3 PLAYER INSTRUCTIONS . . . . . . ... . . 3.3-1 3.4 PARTICIPATING CENTERS . . .. . ... . . . 3.4-1 O O 3.0-1

October 17, 1985 SECTION 3.1

 /"N                                  GUIDELINES FOR CONDUCT k  )                     1985 NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION I. PURPOSE This document provides guidance for conducting the October 17,1985 Peach Bottom   Atomic     Power    Station     1985   NRC     Observed  Emergency   Response Exercise.      It    provides    methods    for demonstrating emergency response capability, conducting the exercise, and evaluating results.

II. CONCEPT OF OPERATIONS AND CONTROL OF THE EXERCISES Philadelphia Electric Company (PECo) and Stone & Webster Engineering Corporation (SWEC) will supply official controllers and/or evaluators for each location where an emergency response is being demonstrated. Prior to the exercise, the centro 11ers and evaluators will be provided with the appropriate locations, maps, time periods, guidelines, and an evaluator evaluation checklist corresponding to their assignments. Controllers will hand out messages and cue cards and will make judgment decisions. If crisis situations arise, they will contact the Lead Controller in their assigned Emergency Response Facility (ERF) for advice or resolution of the problem. Lead Controllers are designated for the Technical Support Center (TSC), Operational Support Center (OGC), and h O' Emergency Operations Facility (E0F) to keep these ERFs on track. required, they will contact the Head Controller to force play of some If events. The llead Controller, stationed in the Control Room, will be in overall charge of conducting the exercise. All requests for modifications or holding periods must be cleared through the Head Controller. The exercise initiating events will be controlled by Lead Controllers. Hypothesized initiating events will consist of three types of information: (1) plant information and data provided to Control Room and TSC personnel; (2) release rates; (3) hypothesized environmental radiation levels. The Head Controller in conjunction with the Lead State Controller has the authority to determine the time sequence of these initiating events to ensure an orderly flow of exercise events. All other actions during the exercise will occur through a free play response as the plant and corporate participants respond to the initiating events. As the initiating events are provided to the plant staff, they will determine the nature of the emergency and the implementation of the appropriate emergency response procedures. These procedures are expected to include a determination of the emergency classification in accordance with NUREG-0654, FEMA-REP-1, Revision 1. Players should notify the Lead Controller of the appropriate ERF prior to the formal escalation or de-escalation of emergency classificition. If the proposed change is within 15 minutes of the scenario time line, the controllers will allow players to proceed. Notifications will be made to the appropriate federal, rtate, and county authorities. d 3.1-1

The hypothesized emergency will continue to develop based on data and information provided to the Control Room and TSC personnel. As the situation develops, information will be forwarded to appropriate plant and corporate personnel for the determination of actions to be taken in response to the hypothesi mi emergency. Where information would normally be confirmed via an independent source (such as National Weather Service for weather data), the confirmatioa data will be simulated. If a conflict exicts between the hypothesized data and the actual data, the hypothesized data will be utilized. Certain inconsiatencica (such as plume width, release duration, technical reason for the simulated release, etc.) may be intentional and required to provide an exercise basis which tests the plant and corporate capabilities to the maximum extent feasible in a limited time frame. If an inconsistency is known or determined to be intentional, then the emergency response personnel will note the inconsistency and ignore it. The lead controllers will have the authority to resolve or explain any inconsistencies or problems that may occur during the exercise. With the exception of the aircady cited and potential inconsistencies, the internal operations of the emergency response facilities will be identical with their intended operation in a real emergency. III. GENERAL GUIDANCE FOR THE CONDUCT OF Tile EXERCISE

1. Simulating Emergency Actions Since exercises are intended to demonstrate actual capabilities as realistically as possibla, participants should act as they would during a real emergency. Wherever possible, actions should be carried out. Only when it is not feasible to perform an action should it be simulated. Any orders given that for any reason cannot or should not actually be performed should begin with the word " Simulate." For example, the order to put out a fire that is being hypothesized would state: " Simulate discharging the fire extinguisher." Where such actions are being taken, it is suggested that participants inform any observers in the area of what action really would be taken had the emergency been real.

Radiation Work Permits (RWPs) have not been issued for the conduct of the Emergency Response Exercise. If scenario events direct players to areas that are actually RWP controlled due to high radiation, surface contamination, or airborne radioactivity, players will simulate the activities they would have performed without actually entering the RWP controlled area even if they are authorized on the RWP for some other duty.

2. Avoiding Violation of Laws Intentional violation of laws is not justifiable during any exercise. To implement this guideline, the following actions must be taken:

O 3.1-2

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

a. All evaluators and potential exercise participants must be specifically informed of the need to avoid intentional violation of all federal, state, and local laws, regulations, ordinances, I statutes, and other legal restrictions. The orders of all police, sheriffs, or other authorities should be followed as would i normally be the case.

i

b. Exercise participants will not direct illegal actions being taken by other exercise participants or members of the general public,

c. Exercise participants will not intentionally take illegal actions when being called out to participate in an exercise.

Specifically, local traffic laws such as speed laws will be observed.

3. Avoidina Personnel and Property Endangerment Participants and evaluators will be instructed to avoid endangering property (public or private), other personnel responding to the exercise, members of the general public, animals, and the environment. [

4. Actions to Minimize Public Inconvenience i It is not the intent, nor is it desirable or feasible, to effectively train

! or test the public response during the conduct of radiological emergency exercises. Public inconvenience is to be minimized. [ l The actions of federal, state, and county agencies and nuclear power plant l operators receive continuous public notice and scrutiny; therefore, the conduct of an exercise could arouse public concern that an actual emergency , is occurring. It is important that conversations that can be monitored by the public (radio, loudspeakers, etc) be prefaced and conclude with the l words, "This is a drill; this is a drill." t

5. Maintainina Emergency Readiness During the performance of an exercise the ability to recognize a real -
emergency, terminate the exercise, and respond to the new situation must be

! maintained. Therefore, the exercise scenario and actions of participants - l will not include any actions which seriously degrade the condition of systems, equipment or supplies, or affect the detection, assessment, or l response capability to radiological or other emergeacies. Actions taken by the participants will also avoid actually reducing plant or i public safety. The potential for creating real radiological or other emergencies will be specifically avoided. l l If a real emergency occurs during the exercise, requiring the actions of l plant and corporate personnel, then the exercise will be terminated. All ' messages about real events will be cicarly identified as such. For example, precede a real message with: "This is NOT, repeat, NOT an exercise message." 3.1-3 l t I

e IV. EMERGENCY RESPONSE IMPLEMENTATION AND OPERATIONS

1. Initial Notification Initial notification will be made in accordance with the appropriate Emergency Plan Implementing Procedures (EPIPs).

2. Plant Operations It should be emphasized that the exercise will in no way interrupt normal plant operations, production, and safety. The responses of Control Room personnel and plant operators will be simulated when taking action to combat the emergency. Instead, a controller will narrate the initiating events and the postulated plant response directly to the Shift Supervisor and other Control Room personnel who will then employ the appropriate emergency procedures.

3. Environmental Monitoring Teams PECo will dispatch field environmental monitoring teams. The controllers will provide hypothesized field data which will be used to determine radiation readings at preselected locations. However, these teams will be equipped with the necessary equipment to enable them to determine actual area gamma dose rates and airborne radioiodine concentrations. The monitoring teams will not be suited up in anticontamination clothing, but will have such equipment at their disposal.

4. Public Notification Actual emergency message transmissions via the Emergency Broadcast System will not occur.

5. Public Information Press releases to the general public and news media will be simulated. The simulated press releases will contain all necessary information on the current status of the exercise but will not be transmitted.

6. Communications Communications between the exercise participants will occur in accordance with the appropriate EPIPs. Should any primary communication path become inoperative or prove inadequate, backup means of communication will be utilized as appropriate.

V. CLOSEOUT OF THE EXERCISE The exercise will be terminated by PECo and SWEC lead controllers, at their discretion, when the scenario is completed. This will occur after the plant has entered the recovery T hase. O 3.1-4

October 17,' 1985 ir) ; SECTION 3.2

 ,v SCOPE 1985 NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION Identification of Actual and Simulated Events Actual      Simulation

1. Emergency Detection

The ability to properly recognize and characterize the simulated event X

2. Emergency Assessment

The ability to utilize post accident sampling data, radiation and effluent monitor data, and containment radiation monitoring data to provide initial and -

continuing accident assessment ()f

The ability to predict on-site and r)'j l,'

off-site exposure for various meteorological conditions based on - effluent nonitor readings X

The ability to perform field monitoring within the plume exposure Emergency Planning Zone X
The ability to activate, equip, deploy, and communicate with off-site monitoring teams X
The determination of integrated dose from projected and field monitored dose rates and comparison of these estimates with protective action guides X

3. Emergency Classification

The ability of site personnel to properly classify the emergency according to Emergency Action Levels and include escalation and decscalation of the classification X v

3.2-1

Actual Simulation

4. Emergency Notification and Communication

Notification of state and local response organizations based on the emergency classification X
To demonstrate the effectiveness of notification messages and verification of these messages X
The ability to alert, notify, and mobilize emergency response personnel X
The provision of timely and accurate protective action recommendations to the state X

5. Emergency Communications

Operation of the public alerting system X
To confirm the adequacy of communications with state / local governments during the exercise X
Communications with federal emergency response organizations including the NRC Regional Office Emergency Opera-tions Centers X
To verify the adequacy of communications between the PECo emergency facilities and radiological monitoring teams X
Communications with fire-fighting support facilities X

6. Emergency Response Support Resources

The ability to request assictance from Federal resources X
The ability to support Federal resources X
The ability to obtain assistance from nuclear and other facilities, organiza-tions or individuals identified in the PEco Emergency Plan X
The ability of PEco corporate personnel to provide support X O

3.2-2

Actual Simulation ;

g 7. Public Education and Information

Facilities used for dissemination of information to news media X
The ability of the PECo spokesperson to access and disseminate necessary information X
The ability for timely exchange of information among designated spokespersons X
The ability to deal with rumors X

8. Emergency Facilities Activation

To establish the adequacy of the physical layout and operation of the following emergency centers: Technical Support Center; Emergency Operations Facility; Operations Support Center; Emergency News Center; Headquarters Emergency Support Center X
The timely activation and staffing of all emergency facilities X

b

The ability to maintain plant security under emergency conditions X
To confirm the ability of ERF personnel X
The ability to provide adequate supplies -

and equipment for use by onsite teams X

To accommodate state and local staff' at the EOF X
To demonstrate the assumption of responsibilities by reporting personnel from interim personnel X

9. Assignment of Responsibility

To establish that escrgency personnel understand and can impicment their responsibilities X
To demonstrate the initial response of emergency personnel X

3.2-3 C___

Actual Simulation

10. Emergency Organization

The response of the on-shift emergency organization X
The timely augmentation of the on-shift emergency organization X
Sufficient qualified personnel are available to respcnd to the postulated events X
The timely augmentation of the plant staff emergency organization by corporate support personnel X
The ability to procure assistance from outside contractors and private organizations X
The ability to handle personnel and equipment contamination X

11. Radiological Assessment

To receive and analyze field monitoring data and coordinate sample media at the Emergency Operation Facility X
To effectively use the Post Accident Sampling Station X
To estimate total population exposure X
The ability for radiological monitoring of people evacuated from the site X

   **    The ability to provide evacuation routes and transportation for onsite personnel to some suitable offsite location                        X

The ability to provide respirator" protection and protective clothing to persontel onsite during the exerciac when required X

12. Protective Action Radiological Exposure Control

The application of onsite exposure guide-liner consistent with Station Protective Actions Guides and Procedures X O

3.2-4

Actual Simulation

To demonstrate the procedures for permitting onsite workers to exceed doses in excess of 10CFR20 limits X
To provide and monitor dosimeters for emergency workers X
To evaluate the need for and provide means for personnel decontamination X
To provide contamination control measures such as areas access control X

13. Protective Actions

To warn or advise personnel onsite of emergency conditions X

                 **    The ability to evacuate nonessential personnel from the site                                   X

To assess and recommend protective actions to state and local authorities X

             *A preselected group of on-site personnel will participate in this activity.
 '~ 's       14. Corrective Actions s
       ~

To verify the ability to determine the cause of the emergency condition, terminate the condition with considera-tion of appropriate engineering safe-guards, and place the plant in a safe condition X

15. Emergency Fire Fighting Support

To confirm the ability of PECo personnel to respond to and terminate a fire X

16. Medical Assistance

To provide first aid and transport for an injured individual who has been contaminated or has receised high radiation dose X

17. Parallel and Other Actions

Self-critique of all aspects of the exercise to identify areas of the plan

 .-s
 ,                     and procedures that need improvement          X

( - 3.2-5

F October 17, 1985 SECTION 3.3

      )                               INSTRUCTIONS FOR PLAYERS
 'd 1985 NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACil BOTTOM ATOMIC POWER STATION

1. You may ask the controller / evaluator for information such as:

a. Initial conditions of the plant and systems including:

operating history of the core
initial coolant activity
meteorology data such as wind speed, direction, and stability
availability of systems according to the scenario

b. Area radiation data at the location of emergency teams.

c. Airborne data at the location of the plant and field survey teams af ter a sample has been appropriately taken.

d. Ef ficiency 'of all counting equipment.

(]

e. Activity from nese-swabs or skin contamination surveys.

2. You may not ask the following from the controllers / evaluators:

a. Information contained in procedures, drawings or instructions.

b. Judgements as to which procedures should be used.

c. Data which will be made available later in the day.

d. What the controller / evaluator would do if he were a player.

c. llelp in performing actions in this drill.

f. llelp in carrying out calculations.

3. Remember that two clocks may be used by controllers, the scenario time and the actual clock time. Scenario time will be important if the exercise becomen delayed for any reason.

4. Know the overall controllers' organization and the specific controller assigned to your activity. At the graded exercise, NRC evaluators and visitors will be present. All controllers, evalcators, and visitors will be wearing PEco supplied identification.

 -m 3.3-1

5. Identify yourself by name and function to the Controllers / Evaluators and the NRC Evaluators. Always wear your identification badge.

6. Play out all actions, as much as possible, in accordance with your Emergency Plan and procedures as if it were a real emergency. Unless authorized by the Controller, you should not simulate your actions. If authorized to simulate an action, tell the Controller how and when you would actually perform the action.

7. Periodically, speak out loud, identifying your key actions and deci-sions to the Controller and evaluators. This may seem artificial but it will assist in the evaluation process and is to your benefit.

8. If you are in doubt about data, ask your Controller for clarification.

The Controller will not prompt or coach you.

9. The Controller will periodically issue messages or instructions de-signed to initiate response actions. You must accept these messages immediately. They are essential to your successful perfornance.

10. If the Controller intervenes with your play, it is for good reason.

Obey your Controller's directions at all times. Thi? is essential to the overall success of the exercise.

11. If you disagree with your Controller, you may ask him to reconsider or consult with the Lead Controller as time permits. You must, however, accept his/her word as final and proceed.

12. Respond to the Controller's questions.

13. You must not accept any messages / instructions from the Federal Evalua-tors. If they want to initiate actions, test your abilities, or give you a " surprise," they must work through your Controller. This is essential to the overall success of the exercise.

14. You must play as if radiation levels are actually present, in accor-dance with the information you have received. This will require that you wear radiation dosimeter, anti-c'n, observe good radiation protec-tion practices, and be aware of and minimize your radiation exposure.

Identify the individuals in your emergency response organization who are responsible for informing you of these items. Follow their instructions.

15. The Controllers and Federal Evaluators will not act as if simulated radiation levels from the emergency exercise are present. 'ihey a re exempt. Do not let this confuse you or cause you to act unwisely.

16. If you are entering normal nuclear station radiation areas, observe all rules and procedures. No one (even the Controller and Federal Evalua-tors) is exempt from normal station radiological practices and procedures.

O

                                        .l.3-2

NOTE: DO NOT ENTER HIGli RADIATION AREAS IN TIIE PLANT. FOLLOW ALARA [ } PRINCIPLES. v

17. Demonstrate knowledge of your emergency plan, emergency operations and procedures.

18. Use status boards, log books, 3 part communication forms, etc, as much as possible to document and record your actions, instructions, and reports to your co-players. This is very important. Remember, "Put it in writing". Remember to write, "This is a drill".

19. Do not enter into conversations with the Visitors.

20. You may answer questions directed at you by Federal Evaluators. If the question is misdirected to you and you do not know the answer, refer g them to your lead player or the Controller.

21. Keep a list of items which you believe will improve your plans and procedures. Provide this to your lead player or controller. Lead players will ensure these are considered. If necessary, they will identify it to the Controller. Remember one of the main purposes of the exercise is for you, the player, to assure yourself that you are adequately prepared. Areas for improvement or lessons learned when identified will improve your overall emergency planning and preparedness.

,q

,       22. A critique of the exercise will occur after the exercise is terminated.

(,) Provide your input to your Icad player or the Controller. This will help in the overall evaluation which the Controller will present to the Lead Controller.

23. Make sure all communications begin and end with "TilIS IS & DRILI." and repeat at frequent intervals.

o , 3.3-3

October 17, 1985 c i

,a

' kj} - SECTION 3.4 PARTICIPATING CENTERS 1985 NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION MARYLAND Accident Assessment Center, Baltimore State of Maryland Emergency Operations Center, Pikesville Cecil County Emergency Operations Center, Elkton Harford County Emergency Operations Center, Hickory PENNSYLVANIA Bureau of' Radiation Protection Headquarters Assessment Center, Harrisburg

    h State of Pennsylvania Emergency Operations Center, Harrisburg
~ [d Chester County Emergency Operations Center, West Chester York County Emergency Operations Center, York Lancaster County Emergency Operations Center, Lancaster PHILADELPHIA ELECTRIC COMPANY Headquarters Emergency, Support Center, Philadelphia, _ Pennsylvania Peach    Bottom Atomic            Power    Station   Emergency   Operations   Facility, Peach Bottom, Pennsylvania Peach Bottom Atomic Power Station Technical Support Center, Peach Bottom, Pennsylvania               ,

Muddy Run Recreation Park Emergency News Center, Holtwood, Pennsylvania s C ' E' ' ( i 4- ' 3.4-1 L

O llARRISBURG O O PEfNSYLVANIA BRP FEADalARTERS/ ASSES 9ENT CENTER STATE EOC M

                                  -_        f 31                      LANCASTER ColNTY EOC 3

IANCASTER FillLADELrlilA E DESTER C0tNTY EOC YWK C0tHTY EOC YORK HI j 3 3 M W ( RtN NEWS CENTER 3 PEAuf BOTTOM ATOMIC

                                                                                                        /,e%

PENNSYLVANIA , , j _ _

~ ~ I M HAP.YI.AND

                                   }l                                                                \

imRFORD EOC si leicKoRY CECIL COLNTY EOC I I I 1 1 35 g FIKESVII.LE E g 5 t,g is fMRYLAfN STATE EOC o sc3,,g _ gitgs I i e ACCIDENT ASSESSENT CENTER Hap of Participating Emergency centers ll BAI.TDn)RE l 1 l 3.4-2 I

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

] .)

1

i 1 ,

r [- SECTION 4.0 October 17, 1985 1 4 F CONTROLLER / EVALUATION INFORMATION

!-                                                                                     1985 NRC OBSERVED EMERGENCY RESPONSE EXERCISE                                                                                                         ,

> PEACH BOTTOM ATOMIC PO'wr.R STATION 1 j~ Section Page 4'.1 ASSIGNMENTS. . . . . . . . .. . .. . . . ..... 4.1-1 4.2 INSTRUCTIONS . . .. . . . .... . . . .. .. . . 4.2-1 4 4.3 EVALUATION INSTRUCTIONS. . .. . . . .. . . . . . . 4.3-1 a f ' i l i . t

4 f

j i +

i f

1 l i: 1 4 I i 1 - 1 i f i 9 4.0-1 i- '

    . . - . , . - - .        v.--    L-  ._.__._----_.,-.-.m_.._-_..                                                                  - - - . _ - . . - - , - - _ - _ , . - - - - - . ~ . . _ _ _ _ . . . . - - _ , , ~ .

b I . PBAPS EXERCISE CONTROLLER / EVALUATOR ASSIGNMENTS q Uctober 17, 1985 U z [ LOCATION: Control Room (Heed Controller, ext 4464) Head Controller Bb , R. Vanasse (SWEC) Controller i J. Tucker (PBAPS)

LOCATION: In Plant Operations l ', , OSC Lead Controller - ext. 4690

, Aux. OSC Lead Controller - ext. 4446 Lead Controller - OSC A. Pesarchik (PBAPS) Controller - Damage Repairs M. J.LG. Casey (PBAPS) )- Controller - Damage Repairs g b H. R. Abendroth (PBAPS)-

e. Controller - Damage Repairs jd J. McElwain (PBAPS-QC)

Controller - Damage Repairs E. E. Wallace III (PBAPS) Controller - Fire Event V. Affafato MLGS) Controller - Chemistry In Plant J. McMraamIn (PECo) t t ' Controller - Chemistry PASS D. Chase (PBAPS) . Controller Chemistry In Plant D. Musslemann (LGS) L - Controller - Contaminated Injury gM A K.' Mardi (PECo) Lead Controller - Aux. OSC d J. J.' M:Elwain (PECo) Controller - In Plant HP MvA R. M. Mcore (PBAPS)

.[

4~ Controller Controller In In Plant HP Plant.HP S.. Taylor (LGS) P. Dunn (?BAPS) Controller - In Plant HP R. Spencer

           ' Controller - Security Events                          G. P. Bailey (SWEC)

Evaluator - Security Events P. Supplee (LGS) Evaluator - Security Events S. Spencer (Burns - PBAPS) LOCATION: Technical Support Center ( Lead Controller ext 4630) Lead Controller - TSC. R. Gerson (SWEC) Evaluator - TSC .D. Leonard (SWEC) Evaluator - TSC E. Michael (SWEC)

            . LOCATION: Emergency Operations Facility (Lead Controller ext 4662)

Lead Controller R. A. Kankus (PECo) Controller - Dose Assessment .C. Mazzola (SWEC) ; Evaluator - Dose Assessment W. Lorenz (PECo)

           . Evaluator - EOF                                       K. Schlecker (PECo)

Controller - Field Monitoring M. Christinziano (LGS) Controller - Field Monitoring C. Smith (LGS)

           -Controller    -  Field  Monitoring                     L. Wells (LGS)

Controller - Field Monitoring J. Scone (LGS) ,

PBAPS EXERCISE CONTROLLER / EVALUATORS LISTING (Cont'd)

                                                                             , October 17, 1985 ss        LOCATION: Muddy Run News Center Controller ext 4667.

I Evaluator - MRNC Functions R. H. Geiger (LGS) LOCATION: Headquarters, Emergency Support Center, ext 81-5028 Evaluator - HESC Functions T. Payne (PECo) Evaluator - HESC Functions J. Jankauskas (PECo) Evaluator - HESC Functions P. Schaumberg (PECo)

October 17, 1985 SECTION 4.1 {]/ 3 s_, ASSIGNMENTS 1985 NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION Location: Control Room (Head Controller Ext. 4464) Heed Controller R. Vanasse (SWEC) Controller J. J. Tucker (PBAPS) Location: In Plant Operations OSC Controller Ext Aux. OSC Controller Ext. 4446 Lead Controller - OSC A. Pesarchik (PBAPS) Lead Controller - Aux OSC J. J. McElwain (PECo) Controller - In Plant HP R. M. Moore (PBAPS) Controller - In Plant HP S. Spencer (PBAPS) Controller - Chemistry in Plant J. McHenamin (PEco) Evaluator - Chemistry in Plant J. Effinger (LGS) Controller - Damage / Repairs Event J. G. Casey (PBAPS-QA) Controller - Damage / Repairs Event H. R. Abendroth (PBAPS) Controller - In Plant Activitiew V. Affatato (LCS) Controller - Contaminated / Injury K. Mandl (PEco) Evaluator - Chemistry in Plant D. Chase (RDS-PBAPS) Controller - Security Events C. Bailey (SWEC) P. Supplee (LGS) (s} Evaluator - Security Functions Location: Technical Support Center (Ext 4630) Lead Controller R. Gerson (SWEC) Controller E. Michael (SWEC) Evaluator D. Chase (RDS-PBAPS) Location: Emergency Operations Facility (Ext 4662) Lead Controller R. A. Kankus (PECo) Controller - Dose Assessment C. Mazzola (SWEC) Evaluator - Field Monitoring Group D. Leonard (SWEC) Controller Field Monitoring Group M. Christinziano (LGS) Controller Field Monitoring Group R. Leddy (LGS) Controller Field Monitoring Group S. Taylor (LGS) Controller Field Monitoring Group L. Wells (LGS) Evaluator - EOF Functions K. Schlecker (PECo) Location: Muddy Run News Center Evaluator - News Center Functions L. Eckman (Plymouth) Location: Headquarters, Emergency Support Center Evaluator - HESC T. Payne (PECo) k'"')s Evaluator - HESC P. Schamberg (PEco) Evaluator - HESC J. Jankauskas (PEco) . 4.1-1

4 + October 17, 1985 SECTION 4.2 INSTRUCTIONS FOR CONTROLLERS AND EVALUATORS

1985 NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION

1. Personnel are assigned as controllers or evaluators at all key function areas to monitor and control the exercise. In addition, they will accompany radiological monitoring teams, plant health physics personnel, and maintenance repair / rescue teams.

2. The inplant . controllers will be coordinated by the Head Controller located at the Control Room (ext. 4464). He/she will be responsible l 1

for the overall conduct of the exercise scenario. If unable to reach j' the Control Room, contact the Lead Controller in the TSC (ext. 4630). l

.               Field controllers should contact the Lead Controller in the EOF
!               (ext. 4662) regarding coordination problems or questions.                                          The Lead l

l Controller at the EOF will be responsible for contacting the Lead State i Controller to maintain schedules. i j 3. Message forms and simulated Control Room data will be used to initiate, modify, and complete the events comprising the overall scenario. l Selected controllers will use the message forms to place the scenario , events in effect and to trigger responses from the involved emergency

response' organizations. Each controller will have copies of the messages controlling the portion of the exercise scenario for which he/she is responsible.

   '%)          Two kinds of messages will be used:

Controlling Messages used as a primary means of implementing scenario events by announcing or placing an event in effect by hypothesizing conditions resulting from previous actions. Continaency Messages used at the discretion of the controllers with the i approval of the Head Controller in the Control Room in order to maintain the scenario plan continuity or schedule. 4 Controlling messages will be presented to the designated exercise participant at th;e time specified in the event schedule. The controller should f.ollow up with an explanation of the message and answer questions lo ensure that the participant ' understands the message. Controllers will not initially provide information to the participants regarding scenario development or resolution of problem areas encountered. The participants are expected to obtain information

through their own organization and exercise their own judgment in i determining response actions and resolving problems. In the event of

   %/           incorrect or incomplete responses, or if the participant indicates lack i

4- !. 4.2-1

of knowledge of how to proceed, the controller will prompt the participant with necessary instructions or contingency cards and will so note on his/her critique sheets.

4. Note that the scenario events are hypothetical. Any portions of the scenario depicting plant system operational transients are simulated events. No Control Room actions, or reactions involving operation of plant systems or affecting generation capability, will be initiated.

All exercise scenario messages will be prefixed and suffixed with the words "THIS IS A DRILL." Controllers stationed at areas vital to maintaining generating capability should be especially aware and take extra precautions in issuing messages or giving instructions regarding the scenario events.

5. Required controllers will have the time-related plant and radiological parameters of the exercise scenario. This information should be issued upon request to the appropriate exercise participants by either the Control Room controller or controllers accompanying the radiological monitoring field teams. ,

6 Some exercise participants may insist that certain parts of the scenario are unrealistic. The controllers and evaluators have the authority, with the approval from the Lead controllers, to clarify any que stions regarding scenario content. In some cases, it may be ne essary to exercise " controller's prerogative" and say, "This is due

   . exercise requirements" to preserve the continuity and objectives of the exercise.

7. Prior to commencement, all telecommunications should be tested to ensure satisfactory communications between the lead controllers and all other controllers.

8. All controllers and evaluators will synchronize their watches to ensure that messages are delivered at the proper time.

9. Controllers will commence their assignments at assembly locations for players that they are to observe or as directed by the Lead Controllers. (See Section 4.1, Controller Assignment.)

10. Scenario equipment problems not covered in the Exercise Events section of this manual will be handled by the controllers in the Control Room.

11. Players are not allowed to project free play items into the exercise or its scenario.

12. Be sure to return all exercise books to the Lead Controller.

13. Lunches will be provided by PECo; however, there are no such lunch breaks in the exercise. Players and controllers shall be relieved for lunch as situation permits. Emergency team leaders should decide when team members may take a lunch break.

14. Be sure to have a hard hat with you when entering the plant.

4.2-2

G CONTROLLER'S AND EVALUATOR'S RULES D0s

1. Know the overall Controller's Organization (Section 4.1).

2. Remember that there may be two time designations: a scenario time and a clock time.

3. Identify the players by name and function.

4. Identify yourself at all times to all players. Wear T-shirts or tags as provided by PECo.

5. Identify the phone (or radio for field teams) you will use to maintain communications with lead controllers.

6. Position yourself to maximize your effectiveness in issuing messages and observing the players.

7. Be sure you understand the player's scenario script and the master scenario.

8. Keep the play on schedule by checking your script. ;

      }-   -9. Issue the message on time. Make sure the players understand it.
   %J

10. Remember to call the Lead Controller or Head Controller to report on status of players' actions if off schedule or if in doubt about what to do. Call for advice if players depart significantly from the scenario script which will create a major delay. If necessary, intervene with player action and put players back on scenario track.

11. Allow the players reasonable flexibility to perform their functions and demonstrate their skill, knowledge, and initiative.

12. Identify the federal evaluator (s). Make sure they are reasonably aware of all your actions and those of the players.

13. Make notes on good and bad points of players' actions, the strengths and weaknesses, and areas for improvements. Use the Evaluators' Critique Sheets.

14. Attend the post-exercise critique session to provide your comments and recommendations to the Chief Controller on what happened.

15. Identify the players' leaders. Work with them as appropriate.

16. If a real emergency occurs and this affects the players, call off your portion of the exercise, and notify the Head Controller immediately.

17. Be at your post at least 20 minutes prior to any player action commencement. Set yourself up.

l 4.2-3 , 1 1

18. The federal evaluators will not issue " surprise" messages or direct

     " surprise" actions at the players.         They must work through the controller. This is essential for the success of the exercise.

19. Controllers and federal evaluators do not have to follow the radiation exposure control practices for the simulated radiation levels from the emergency exercise scenario appropriate for the simulated radiation levels. However, the players must follow the radiation protection rules. Controllers and evaluators will be exempt from accountability and have access to all areas.

DON'Ts

1. Don't leave your post at key times.

2. Don'tprompttMeplayerstotakeaction.

3. Don't coach the olayers.

4. Don't criticize the players' actions during the play.

5. Don't forget to call the lead controllers to seek advice or help as necessary.

6. Don't allow the media /other external influences to distract the players. No interviews with players are allowed.

7. Don't allow free play to be interj ected into the exercise scenario.

8. Don't allow simulation when equipment and facilities are available except for causing flow discharge of fire extinguishers, etc.

NOTE:

All participants will comply with the radiation exposare control practices existing at the station at the time of the exercise.

O 4.2-4

[gx) t OBSERVER CHECKLIST V OBSERVER LOCATION / GROUP OBSERVED: CONTROL ROOM DATE Directions Write the number in the Rating Scale column that corresponds to the evaluation made by the observer. The Rating Scale is defined as follows: 0 -l Not Observed " S- Satisfactory U Unsatisfactory . M Marginal EVENT / CRITERIA RATING SCALE COMMENTS I. ACTIVATION AND RESPONSE IO Control room personnel rapidly

      'd              and correctly interpreted the problem.

Control room personnel knew when to refer to the Emergency Operating Procedures and Emergency Plan, and which Emergency Implementing Procedures to use. Plant process information was available when required. CR personnel obtained timely meteorological data. CR personnel got timely release information from radiological < and effluent monitor systems. CR personnel responded quickly to personal injury incident. CR personnel responded quickly to fire alarm. {0 0866-1471204-B2 4.3-1 i' r ----y.-a +w--e-- ,e.- - __,m- -__-_m .m__% -7 ,m.-.. --7.-,,, ,,ya, , , - - ..,wy- -- e ,-.m--- -% n- ,,,ei

t EVENT / CRITERIA RATING SCAI.E COMMENTS CR operators responded properly to simulated operational events. HP assistance was requested as needed. Event classifications were timely, accurate and clear.

      'The (I)E. Director took action to determine what other condi-tions might exist which would verify    the accuracy        of     the initial indication.

Control room personnel took appropriate actions to mitigate the effects of the accident. Technical advice was requested and/or received from the proper people. (t(' The emergency was upgraded or downgraded when appropriate. The (I)E.D. made the correct response to implement on-site and off-site assessment and-protective measures. II. COMMUNICATIONS / DISSEMINATION - 0F INFORMATION Notifications were timely and properly completed. , Communication networks were operational and utilized efficiently. Communication flow was adequate to ensure that information was timely, effective, and efficient. Phone listings were available,

s. complete, and up-to-date.

0866-1471204-B2 4.3-2

(O EVENT / CRITERIA RATING SCALE C0tefENTS

%)

General status announcements were made and updated periodically throughout the drill. Proper data flow was maintained between TSC and control room. Logs were maintained. The ambient noise level in the control room was not a problem. Transfer of information within the control room was clearly and completely understood. II

I. PROCEDURE

S Emergency Operating Procedures and Emergency Plan Implementing Procedures were clearly marked and readily available in control room. 1 (~~} V Procedures used were current and controlled. IV. DIRECTION AND CONTROL The (I)E.D. promptly assumed control and authority. Action was taken to initiate activation of the Emergency Facilities when plant conditions and procedures indicated ,they would be activated. The proper management chain of command in the control room was followed when making decisions. Emergency control and authority was properly transferred to the designated Emergency Director located in the Technical Support Center. (U rh 0866-1471204-B2 4.3-3

EVENT / CRITERIA RATING SCALE COMMENTS []J The transfer of control and authority was announced and logged. V. MATERIAL AND EQUIPMENT Plant Monitoring System functioned correctly. Radiation meteorological moni-toring system functioned ' correctly. Public Address System functioned correctly. Paging /Callout System functioned correctly. , Message recorders functioned correctly. PABX and dedicated Hotlines -( ( s functioned correctly. Station Alarm / Fire Alarm System functioned correctly Radios functioned correctly. VI. PROTECTIVE MEASURES Personnel in the control room adequately protected from radiological and . chemical hazards. . Supplies such as respirators, protective clothing and KI for control room personnel were available. HP personnel were available as needed. VII. ACCESS CONTROL Access to control room was 2(. limited to personnel assigned to the control room or 0866-1471204-B2 4.3-4

,. - - - - . - _ - - - . - - . - - -. . - - ~ _ - - . _ l ' i-EVENT / CRITERIA RATING SCALE COMMENTS l-participating in the drill - exercise.- 1 I t l 1 ; - Not Observed S ',- Satisfactory U - Unsatisfactory . M. - Marginal EVENT / CRITERIA RATING SCALE COMMENTS I. ACTIVATION AND RESPONSE The TSC was activated and manned ([s l

\~s/
in a timely manner at the Alert Action Level. Command and control authority was transferred from the control room according to procedure. The transfer of command and
control was formal, was an-nounced, and was logged.
Follow-on activities to aanage injured persons. . Follow-on activities to manage fire. Field survey group dispatched, if appropriate. II. COMMUNICATIONS / DISSEMINATION OF INFORMATION Plant status and/or radiation ({ parameters needed to determine the existing conditions were l 0866-1471204-B2 4.3- 6
EVENT / CRITERIA RATING SCALE COMMENTS available in the TSC including portable radiological monitor-ing, chemistry and meteorologi-cal data. Communication . with State, County, and NRC officials was quickly established. Initial (if appropriate) and Follow-up Notifications were - made in timely (usually 15 minutes) fashion. Major changes in plant or radiation release status were made known to all parties quickly. Off-site protective action recommendations were made quickly and clearly. ,I r"N
! All responsible persons in the TSC kept abreast of current conditions.
Communications between TSC and CR, EOF, OSC and HESC were established and used. Communication with field survey group was adequate. Discussions were held concerning trends, prognosis, courses of action. II
I. PROCEDURE
S Current and controlled copies of the Emergency Plan and Imple-menting Procedures were available. Persennel using procedures were trained and familiar with them. CN ( Q) 0866-1471204-B2 4.3-7 i y y = -s ='m r
=
EVENT / CRITERIA RATING SCALE COMMENTS [b'
\
Communication with off-site groups was made in accordance with procedures. IV. DIRECTION AND CONTROL Transfer of command from control room was clear and understood by all persons in TSC. , Transfer of command from TSC to EOF was clear and understood by all persons in TSC. Appropriate TSC personnel made prompt recosunendations. Logs were kept. Recommendations were passed on to Emergency Director for decisions. ! {,/^) Proper classification upgrading and downgrading was done. V. MATERIAL AND EQUIPMENT Blueprints, as-built drawings, maps, etc, were available. PABX, sound powered, and dedicated Hotlines functioned correctly. . Public Address System functi,oned correctly. Radios functioned correctly. Facsimile machine functioned correctly. Status boards in place and used. VI. PROTECTIVE MEASURES HP coverage available in TSC k, b (air sampling, dose rate V instruments). 0866-1471204-B2 4.3- 8
EVENT / CRITERIA RATING SCALE C0t9fENTS Protective equipment and supplies for TSC personnel. Plant evacuation decisions logical and clear. Plant evacuation directives included travel routes, special precautions, etc. , Continuing accountability , information given to Security. In-plant radiological monitoring reported to TSC. VII. ACCESS CONTROL i Only those people with assigned responsibilities were in TSC. Sign-in system was employed.
", O 4
lo 0866-1471204-B2 4.3-9
OBSERVEL CHECKLIST ( OBSERVER LOCATION / GROUP OBSERVED: PERSONNET, SAFEIl IEAM DATE Directions Write the number in the Rating Scale cclumn that corresponds to the evaluation made by the observer. The
; Rating Scale is defined as follows:
Oj - Not Observed S - Satisfactory U ,- Unsatisfactory i , , Mj - Marginal EVENT / CRITERIA RATING SCALE COMMENTS Adequate trained personnel were available to furnish HP coverage for the emergency situation and -( f % d First Aid teams, Chemistry, Search and Rescue teams, Fire teams, Repair teams, EOF, CSC, and evacuees. Onsite monitoring equipment was easily accessible and properly distributed. Equipment was checked for proper operability prior to its use. Standard HP practices .were employed for entry into actual or potential radiation areas. Proper survey records, dosimetry, stay time, etc. were maintained during entry. Survey results were reported to the appropriate personnel. Follow-up actions were taken on survey results. (-(p) 8.J 0866-1471204-B2 4.3- 10
O RATING SCALE C0t2fENTS EVENT / CRITERIA JJ
\
Pocket dosimeters were frequently checked and properly logged. The TSC, OSC, and CR habitability was frequented monitored.
. Team members had adequate ,
understanding of proper utiliza-tion of equipment (survey) instruments, radios, SCBAs, etc.). Inplant Survey results were systematically collected by the Plant Survey Group Leader. The correct procedure was used to establish emergency dose limits if needed. I Authorization to exceed 10CFR20 _, Exposure limits was documented. Debriefing conducted, records and logs collected. Il. 0866-1471204-B2 4.3 '11
4 \ OBSERVER CHECKLIST [ OBSERVER
~
LOCATION / CROUP OBSERVED: SEARCH AND RESCUE GF[0UP- DATE Directions Write the number in the Rating Scale column that corresponds.to the evaluation made by the observer. The Rating Scale is defined as follows: 0 - Not Observed S .- Satisfactory
i U - Unsatisfactory M - Marginal 4
l EVENT / CRITERIA RATING SCALE COMMENTS OSC Supervisor selected three or more volunteers to serve as I w team, i If radiological hazards are involved, one team member is an HP Technician.
! Team members have current first aid training.
Team members briefed in accord-ance with procedure. At least o n.- team member has required formal access permi.t to area being entered. Radio check perforred. Safety and first aid equipment available as needed. Communi<ations maintained with OSC during search and rescue. Log of setivities kept. J i + Personal dosimetry used, if needed. i 0866-1471204-B2 4.3-12
t. i - l i
t. :.
.' s: 1.. EVENT / CRITERIA RATING SCALE COMMENTS i a j- ' TSC informed' of results of i search and rescue. 1 l;; ;f - l f f i 3-a 4.- 1 = 4 l 4-p i - 4 ! 1 . !- -l-i~ 4-f. A l' i {- ). l' ( ' - I.@ 4 !. 3 s.
i 4 i
?- r i i i I i i l I i- ! i l' ( 1 > ? i- l t, l
- t l- l i
L i 1 0866-1471204-B2 4.3- 13 l 1
OBSERVER CHECKLIST {' ..,i V OBSERVER
~. -
LOCATION / GROUP OBSERVED: FIELD SURVEY GROUP DATE Directions Write the number in the Rating Scale column that corresponds to the evaluation made by the observer. The Rating Scale is defined as follows: 0:- Not Observed S - Satisfactory S!- Unsatisfactory _ M'- Marginal EVENT / CRITERIA RATING SCALE COMMENTS Initial team briefings were held. Team assembled with field kits, vehicles, and communications equipment in a timely manner. Field Monitoring kits were checked for contents before leaving site. Instruments checked for proper operability and current calibration. Teams received explicit instruc-tions of where to go and whit to sample. Procedures for conducting offsite monitoring were consulted and followed. Vehicles were readily available. Vehicle checked for contamina-tion after mission completed. ( Sampling locations were readily located. 0866-1471204-B2 4.3-14
N 4 1 EVENT / CRITERIA RATING SCALE COMMENTS Samples were properly packaged, identified, and labeled. 1
- Pocket dosimeters were period-ically checked.
Pocket dosimeter readings were logged in upon return to LGS. Communications were maintained with the TSC and/or EOF through-out sampling activity. l. ( v i t' h i l J d i 0866-1471204-B2 4.3-15
-...---,-...,,_.--w-- c, , , , ,--.w., , , , , , _ - - - - - - - . --~,-.-,y.,-,,_,,-,-..,,,m.y--------, , ,,vry--
OBSERVER CHECKLIST (O V OBSERVER _ -2 LOCATION / GROUP OBSERVED: FIRE FIGHTING GROUP DATE Directions Write the number in the Rating Scale column that corresponds to the evaluation made by the observer. The Rating Scale is defined as follows: 0 - Not Observed S Satisfactory U - Unsatisfactory . M - Marginal EVENT / CRITERIA RATING SCALE C0'.9fENTS Reaction time between fire alarm and fire team activation is i o timely. Fire fighting personnel response time to the scene of the fire was timely. Fire team members report to scene of fire with appropriate fire fighting gear and equipment. , Initial assessment of fire situation is adequately performed. , When it is apparent team cannot control the fire, offsite support is requested and obtained in a timely manner. Communications are maintained between the fire team leader and the CR (Control Room). Adequate information is provided by the fire team to the control ( room for their assessment. 0866-1471204-B2 4.3 16
i 7 EVENT / CRITERIA RATING SCALE COMMENTS ! Smooth transition and coordina- : tion is made between plant fire team and local fire department. Arrival of local fire department to fire scene is timely. l l l i f I 1 6 l l 1 I
?
( 0866-14712b4-82 4.3- 17
OBSERVER CHECKLIST ( OBSERVER . i _==== _ - ___ LOCATION / GROUP OBSERVED:' FIRST AIDEROUP '/ DATE
Directions Write the number in the Rating Scale column that corresponds to the evaluation made by the observer. The Rating Scale is defined as follows:
0 - Not Observed S,- Satisfactory U . - Unsatisfactory
MI - Marginal l
l EVENT / CRITERIA RATING SCALE COMMENTS i l' First Aid Team assembly was ' l timely following notification. First Aid Team assembled with I the proper first aid equipment. l l Accident / injury assessment made l- by the First Aid Team. ! First Aid assistance was rendered in a timely manner, l , Appropriate decontamination measures were taken. Maintained communications linkage with Control Room. l The HP escort reacted properly to the simulated event. I j The request for and notification
l. of ambulance was in accordance i to procedures.
\ l Patient was made ready for j transport by the First Aid Team. f\ Dosimeter patient. was left with the 0866-1471204-B2 4.3- 18 [-
I ' EVENT / CRITERIA RATING SCALE C0tefENTS Adequate HPs coverage was provided at the hospital. -s Patient's radiation doses are monitored by HP personnel. HP performed radiation survey of i ambulance at hospital before , vehicle vas released. Consideration / measures were , taken to prevent - spread of ! contamination. 7 Periodic status reports are- , i
- provided to the Shift Supervisor as to the injured individual's status.
l l ,
'e ,
t 5 , x 4 N
.s F~ , s -
0866-1471204-B2 4.3- 19, . 4,
OBSERVER CHECKLIST j{ OBSERVER LOCATION / GROUP OBSERVED:. OPERATIONS ' SUPPORT CENTER DATE Directions Write the number in the Rating Scale column that corresponds to the evaluation made by the observer. The Rating Scale is defined as follows: O'- Not Observed S - Satisfactory U,- Unsatisfactory . M:- Marginal
' EVENT / CRITERIA RATING SCALE COMMENTS k
I. ACTIVATION AND RESPONSE i n The OSC was activated in a () timely fashion.
' All support personnel listed in the Emergency Plan were avail-able in the OSC.
The personnel stationed in the OSC understood their emergency response functions. There were enough specialists available to fill all demands for HP, Fire Brigades, Search and Rescue teams, Repair teams, and Field Monitoring teams. II. COMMUNICATIONS / DISSEMINATION OF INFORMATION Communications with the control room and TSC were adequate. Communication with HP was adequate. 'Q . V
; Communications with specialty teams were adequate.
l 0866-1471204-B2 4.3-20 l 1 I i
(.-
EVENT / CRITERIA RATING SCALE COMMENTS v . There was adequate information flow from the TSC concerning plant conditions and hazardous areas. There was adequate information flow from the OSC to specialty teams. II
I. PROCEDURE
S The Emergency Plan and Implementing Procedures were available in current and controlled copies. Appropriate procedures were available, as needed, for the specialty teams. IV. DIRECTION AND CONTROL The OSC was supervised (coordinated) adequately. A chain of command was established. Team formation and briefings were completed quickly and accurately. Information for continuing accountability was supplied to Security. V. MATERIAL AND EQUIPMENT-The office and communication equipment necessary to activate the OSC were available. Specialized tools were obtainable. VI. PROTECTIVE MEASURES ., Protective equipment, clothing, ( p)N and decontamination facilities were available. 0866-1471204-B2 4.3-21 4
. . - . . . _ - . = . _ . . _ . . _ . . - - - .
I' EVENT / CRITERIA RATING SCALE C0tefENTS (O The OSC was monitored for
. radiation.
VII. ACCESS CONTROL
.Only OSC-assigned personnel were 'in the prescribed areas.
I. O e 'O 0866-1471204-B2 4.3 22
4 OBSERVER CHECKLIST .l( ~ OBSERVER CriEdISTRY SadPLING & LOCATION / GROUP OBSERVED: ANAYLSIS TEAM :DATE Directions Write the number in the Rating Scale column that corresponds to the evaluation made by the observer. The Rating Scale is defined as follows: 0 - Not Observed S - Satisfactory I
' U - Unsatisfactory _
M - Marginal ,
~ EVENT / CRITERIA RATING SCALE . COMMENTS -I. ACTIVATION AND RESPONSE A The Chemistry Sampling and d Analysis Team Leader reported promptly to the Technical Assessment area of the TSC.
I The Chemistry Sampling and Analysis Group Leader reported promptly to the Chemistry Field Office. An adequate number of tech-nicians were available or were called in. Analytical results were a' vail-able within the specified times. II. COMMUNICATIONS / DISSEMINATION OF INFORMATION-Communications with the control room and/or TSC were adequate. Directions given to technicians were clear. , j l KO ' 0866-1471204-B2 4.3-23
-: (- m EVENT / CRITERIA RATING SCALE COMMENTS Plant status information was available. to laboratory
.personneU II
I. PROCEDURE
S The appropriate procedures were available and followed. IV. DIRECTION AND CONTROL Samples were collected and analyzed as requested by control room or TSC. Chemistry Supervisor (or alternate) was clearly in command. Analytical results were verified. I Logs of actions were kept. (_s V. MATERIAL AND EQUIPMENT Analytical equipment functioned properly. Sample points were accessible and open (valves correctly aligned by control room and/or technicians). VI. PROTECTIVE MEASURES Health Physics coverage was requested as needed. Protective equipment was available to lab personnel. VII. ACCESS CONTROL Only personnel with emergency responsibilities were present during exercise.
( Access to PASS, etc. was made according to procedure.
0866-1471204-B2 4.3- 24
_, . = - - - .-._ . OBSERVER CHECKLIST l[ OBSERVER LOCATION / GROUP OBSERVED: EMERGENCY OPERATIONS FACILITY DATE Directions Write the number in the Rating Scale column that corresponds to the evaluation made by the observer. The Rating Scale is defined as follows: 0- Not Observed S - Satisfactory U - Unsatisfactory I M- Marginal EVENT / CRITERIA RATING SCALE COMMENTS I. ACTIVATION AND RESPONSE 7 EOF was activated and manned O [V within a reasonable time after declaration of Site Emergency or at the discretion of the Site Emergency Coordinator or Emergency Director. Site Emergency Coordinator received briefing from Emergency Director prior to assuming command and control. EOF personnel ' informed of assumption of specific responsibilities. Sign-in system used to assure full staffing. k 0866-1471204-B2 4.3 25
; EVENT / CRITERIA RATING SCAI.E COMMENTS v l l
II. COMMUNICATIONS / DISSEMINATION ): OF INFORMATION Communications were checked and established with control room, TSC, HESC, and required offsite Federal, State, County, and local agencies. Technical Support Center notified of assumption of command and control of EOF designated responsibilities. Needed data was available from TSC and CR. EOF received prompt information on radiological status, both on and offsite. Pertinent information quickly (15 minutes) transmitted to offsite groups. Up-to-date meteorological data was available. Plant status information was promptly available. Communication with offsite monitoring teams was adequate. General status announcements and updates were made to . EOF personnel throughout exercise. EOF coordinated the supply of information to Headquarters ESC Public Information Services. Status boards used and kept current. II
I. PROCEDURE
S Emergency Plan and Implementing Procedures were available in (V current and controlled copies. 0866-1471204-B2 4.3-26 i
O V EVENT / CRITERIA RATING SCALE COMMENTS EOF participants were familiar with procedures. Correct procedures were used. IV. DIRECTION AND CONTROL The organizational structure and chain of command in EOF was - clear. Appropriate people made prompt decisions and reco:anendatiocs . EOF Staff took appropriate follow-up actions to care for injured personnel, if any. Status boards kept current. Plume pathway tracked and visible. Emergency classifications and action' level notifications transmitted to proper authorities as required. Protective action reconsnenda-tions were made clearly and in timely fashion. Continuing accountability ' data forwarded to Security. V. MATERIAL AND EQUIPMENT , Facsimile machine functioned. Status boards available. Reference materials, procedures, prints, etc., available. VI. ACCESS CONTROL Only assigned EOF people were present. ktx Security Control established. 0866-1471204-B2 4.3-27
OBSERVER CHECKLIST ( OBSERVER J LOCATION / GROUP OBSERVED: DOSE ASSESSMENT DATE Directions Write the number in the Rating Scale column that corresponds to the evaluation made by the observer. The Rating Scale is defined as follows: 0 - Not Observed S '- Satisfactory U = Unsatisfactory M - Marginal EVENT / CRITERIA RATING SCALE CCT!ENTS Initial and subsequent dose calculations were performed in a timely manner. Computer aids were properly utilized. Plume was defined and tracked. Teams were contacted, briefed, and dispatched expeditiously. Communications were maintained with all teams. Personnel was efficiently utilized. Dose Assessment Team Leader will initiate and provide periodic updates to the Site Emergency Coordinator on PAGs. Status' was maintained on team exposure levels. Offsite monitoring data were T coordinated with State.
%J 0866-1471204-B2 4.3-28
t l (U EVENT / CRITERIA RATING SCALE C0mfENTS T Comparisons were made between projected doses and actual field measurements. i^ Field Survey Group provided with adequate information to perform duties. i t i I I i 4 d f 4 9 [ J i l i .f 4 ! 0866-1471204-B2 4.3-29 i 4
,',---,----.~~,g ,w- ,.,,-,,w,-,,r-,,, a,n._,_,_,,,_.w,_,,_,- ,e,we, . , ,,_,w-,,,,,_--w , , , , - - - , ,.,,n-.-n.,,--
OBSERVER CHECKLIST (. OBSERVER (g LOCATION / GROUP OBSERVED: HEADQUARTERS EMERGENCY DATE SUPPORT CENTER Directions Write the number in the Rating Scale column that corresponds to the evaluation made by the observer. The Rating Scale is defined as follows: 0 - Not Observed S - Satisfactory U - Unsatisfactory M, - Marginal . EVENT / CRITERIA RATING SCALE COMMENTS I. ACTIVATION AND RESPONSE The Hqtra Emergency Support U Center was fully staffed in a timely fashion. The Emergency Support Officer was clearly in command. Information was received quickly from the EOF and/or TSC. II. COMMUNICATIONS / DISSEMINATION OF INFORMATION Emergency News Releases "were coordinated prior to release as required by EP-C Corporate Emergency Procedures. Emergency News Releases were made in accordance with pre-
j. scribed' procedure.
l Spokespersons were clearly j identified. Ik Rumor control methods were used. v f 0866-1471204-B2 4.3 30
( EVENT / CRITERIA RATING SCALE COMMENTS II
I. PROCEDURE
S Controlled and current copies of the Emergency Plan and Implementing Procedures were available. IV. DIRECTION AND CONTROL Emergency Support Officer was clearly in control of the ESC.- . Major decisions were made by Emergency Support Officer in consultation with his staff. News releases were reviewed and issued smoothly and quickly. Logistical Support and manpower requests were acted on in an - expeditious manner by staff. ( p) Liaison law (V enforcement with was offsite provided, as appropriate. Spokespersons were knowledgeable about technical aspects of plant problems. V. MATERIAL AND EQUIPMENT Space for staff was adequate. Space for news media represent- ~ atives was adequate. Adequate telephones to handle traffic were available. Facsimile machine operable. VI. PROTECTIVE MEASURES (Not applicable) v 0866-1471204-B2 4.3-31
4 i ! 4 1 i i ( EVENT / CRITERIA RATING SCALE COMMENTS l VII. ACCESS CONTROL i C-Only persons with assigned emergency responsibilities were t present. 1 i i i e er i f 1 4 i t i i i .i r i i I ! t 4 i 1 i l 3 p 5 1 t. I t i l , i
-\
( 1 0866-1471204-B2 4.3- 32
N-l OBSERVER CHECKLIST ! (
^
OBSERVER l 1 ~
. LOCATION / GROUP OBSERVED: DAMAGE CROUP DATE t
^ Directions Nrite the number in the Rating Scale column that
corresponds to the evaluation made by the observer. The i , Rating Scale is defined as follows

0- Not Observed S. - Satisfactory 4 . l 3 I U- Unsatisfactory . ,
' r- !
j M_- Marginal ' s
EVENT / CRITERIA RATING SCALE COMMENTS 7
OSC Supervisor selected three or
,more -volunteers to serve as ,
j( team. If radiological hazards are ] 1 involved, one team member is au j HP Technician. Team members briefed in [ accordance with procedure. At least one team member has - required formal access permit to area being entered. ! Safety and first aid equipment available as needed. - Radio check performed. Communications maintained with i OSC during repair activities. .! Log of activities kept. t Debriefing conducted, records l and log collected. d Personal dosimetry used, if
'\ needed, i
j , 0866-1471204-B2 4.3-33
---_ - --- , , ._,. ,... ,-- -.- _ _, _ -..~-,...,-_.,,,,,-,-__---.,,,_--,,--,.._,_m.--.
I r ( EVENT / CRITERIA RATING SCALE COMMENTS TSC informed of results. . J i ( l 1 k i 0866-1471204-B2 4.3-34
k OBSERVER CHECKLIST [
OBSERVER DATE ,
LOCATION / GROUP OBSERVED: EVACUATION / ASSEMBLY AREA Directions Write the number in the Rating Scale column that corresponds to the evaluation made by the observer. The Rating Scale is defined as follows: 0- Not Observed . S - Satisfactory
, U- Unsatisfactory M- Marginal i
RATING SCALE COMMENTS EVENT / CRITERIA I.- ACTIVATION AND RESPONSE ( Announcement to evacuate is clearly understandable and is heard by all personnel. Announcement was preceded by station alarm. Evacuees quickly assembled in correct area. . Person in charge was clearly identifiable. i II. CONNUNICATION/ DISSEMINATION OF INFORMATION Adequate instructions were given to evacuees. Evacuation supervisor estab-lished and maintained communi-cation with TSC. TSC notified when all persons were accounted for at off-site assembly area. (O 0866-1471204-B2 4.3 35
s EVENT / CRITERIA RATING SCALE COMMENTS II
I. PROCEDURE
S Evacuees passed through - proper control points. Personal . badges and TLDs wqre left at the primary access point. All supervisors and instructors completed muster sheets, as requested. IV. DIRECTIONS AND CONTROL The evacuation supervisor was easily identified and clearly in charge. Evacuation was performed in smooth and controlled manner. Accountability (muster sheets) (h V were used correctly at off-site assembly area. Evacuees followed directions given over PA System and given by evacuation supervisor. V ., MATERIAL AND EQUIPMENT Evacuation Supervisor was equipped with voice amplifier. Adequate number of vehicles were available. Adequate radiation instrumenta-tion and decontamination equip-ment was available. Radios functioned correctly. VI. PROTECTIVE MEASURES Portal Monitors were effectively used to monitor evacuees. 0866-1471204-B2 4.3- 36
EVENT / CRITERIA RATING SCALE COMMENTS First aid equipment was avail-able or obtainable. Decontamination equipment was available or obtainable. Health Physics coverage was available at on-site assembly area. VII.' ACCESS CONTROL Off-site assembly area was fully accessible. There were no major problems in moving evacuees through control points or the principal access point. 'O tO 0866-1471204-B2 4.3-37
,,,-m, - - ,.. , . , - - .
OBSERVER CHECKLIST (?% h OBSERVER LOCATION / GROUP OBSERVED: ACCOUNTABILITY DATE Directions Write the number in the Rating Scale column that corresponds to the evaluation made by the observer. The Rating Scale is defined as follows: 0- Not Observed S - Satisfactory U- Unsatisfactory M- Marginal EVENT / CRITERIA RATING SCALE COMMENTS I. ACTIVATION AND RESPONSE I ,. Security personnel were in place quickly following evacuation announcement. Established means for performing rapid initial accountability for persons leaving protected areas were employed. Established means for quickly finding location of personnel remaining in protected areas were employed. II. COMMUNICATION / DISSEMINATION OF INFORMATION - Initial notification to Securi-ty were clear and complete. Communications internal to the Security organization were adequate. Status reports from Security l( i 'G O Supervisor to the Emergency l l l 0866-1471204-B2 4.3 38
. ~ __ _ . - __ . _ . . _ - - _ _ ___
l EVENT / CRITERIA RATING SCALE C0tefENTS Director were timely and complete. Continuing accountability , reports were quickly furnished to Security by Control Room, TSC, OSC, AND EOF. II
I. PROCEDURE
S . Appropriate Security procedures were readily available. Controlled and current copies of the Emergency Plan and Imple-menting Procedures were readily available. Appropriate procedures were used during exercise. IV. DIRECTION AND CONTROL Accountability of all personnel was achieved within thirty minutes. ! Accountability of people enter-ing or leaving assembly areas was accomplished. Security personnel were trained and familiar with their responsibilities. Security personnel requeste,d or required by procedure were promptly dispatched.
! V. MATERIALS AND EQUIPMENT Security computer in place and i operable.
VI. PROTECTIVE MEASURES Health Physics coverage avail-able as requested. 0866-1471204-D2 4.3- 39 4 i
~ . - . .-- - . . , - _ . - ,- __ - - - ,_- . - ___ - . -, _ , . - . - - - , , _ - - - , - ,
EVENT / CRITERIA RATING SCALE C019fENTS Security personnel kept advise'd of plant status. VII. ACCESS CONTROL Facility access controlled during exercise. Special access controls, if any, put in place as requested. 'O 0866-1471204-B2 4.3-40
CONTROLLER / EVALUATOR CRITIQUE SHEET ! NTROLLER/ EVALUATOR'S NAME:- DRILL / EXERCISE NO: DATE: EVALUATION ASSIGNMENT: EVALUATION AREAS S AT/M ARGIN AL/UNS AT/NOT OBSERVED ACTIVATION & RESPONSE DISSEMINATION OF INFORMATION PROCEDURE IMPLEMENTATION DIRECTION AND CONTROL PROTECTIVE ACTIONS MATERIAL AND EQUIPMENT ACCESS CONTROL l IMPROVEMENT AREAS: O
'v TRAINING:
2. P R OCED U RE S:

3. EQUIPMENT & MATERIALS:
~
4. SCENARIO:

5. OTHER:
O 4.3-41
..._m..__...._,_ _ _ . _ . - . . _ _ _ _ . - - -
t 4 i . SAMPLE CRITIQUE REPORT FORMAT 1 1 IO i 1 r
\'
J-CONTROL ROOM i i t - ! i 4 l 1 l I L STRENGTHS ; 4
1. .,
l 2. i t t' r i I ! l 3' f l i r I f
s i
P i 4 ! I e i !- i i- ; 4 r t I i !
i AREAS FOR IMPROVEMENT !
i , I
l.
c i
i i [ 2.
j. .
}; O - 4.3-42
s U EMERGENCY PREPAREDNESS ACTION ITEM TRACKING SYSTEM Brief Title of Action Item: Identified By: Telephone Number: Date Reported: Action Log Number: COMPLETE DESCRIPTION OF ACTION ITEM (If Additional Space is. Required, Use Additional Blank Sheets) RESOLUTION OF ACTION ITEM Resolution Submitted by: Telephone Number: Resolution Accepted / Declined Site Emergency Preparedness Coordinator ~Date GRADING SYSTEM 0866-1471204-B2 4.3-43
,-~s October 17, 1985 V) ! SECTION 4.3 EVALUATION SHEETS NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION Location / Group Observed Page CONTROL ROOM . . . . . . . . . . . . . . . . . . . . . . . . . 4.3-1 DOSE ASSESSMENT - CONTROL ROOM . . . . . . . . . . . . . . . . 4.3-6 TECHNICAL SUPPORT CENTER . . . . . . . . . . . . . . . . . . . 4.3-7 HEALTH PHYSICS . . . . . . . . . . . . . . . . . . . . . . . . 4.3-11 SEARCH AND RESCUE TEAM . . . . . . . . . ....... .. . . 4.3-13 DOSE ASSESSMENT - TECHNICAL SUPPORT CENTER . . . . . . . . . . 4.3-15 0FFSITE MONITORING TEAMS . . . . . . . . ....... . . . . 4.3-17 FIRE TEAM. . . . . . . . . . . . . . . . . . . . . . . . . . . 4.3-19 FIRST AID TEAM . . . . . . . . . . . . . . . . . . . . . . . . 4.3-21
(} OPERATIONAL SUPPORT CENTER . . . . . . . . . . . . . . . . . . 4.3-23 EMERGENCY CHEMISTRY. . . . . . . . . . . . . . . . . . . . . . 4.3-26 EMERGENCY OPERATIONS FACILITY. . . . . . . . . . . . . . . . . 4.3-28 DOSE ASSESSMENT - EMERGENCY OPERATIONS FACILITY. . . . . . . . 4.3-31 HEADQUARTERS EMERGENCY SUPPORT CENTER. . . . . . . . . . . . . 4.3-33 REPAIR TEAM. . . . . . . . . . . . . . . . . . . . . . . . . . 4.3-36 EVACUATION / ASSEMBLY AREA . . . . . . . . . . . . . . . . . . . 4.3-38 ACCOUNTABILITY . . . . . . . . . . . . . . . . . . . . . . . . 4.3-41 CONTROLLER EVALUATOR CRITIQUE SHEET . . . . . ... . . . . . 4.3-44 EMERGENCY PREPAREDNESS ACTION ITEM TRACKING SYSTEM . . . . . . 4.3-45
\
4.3-0
i aOSSERVER CHECKLIST
/O Q OBSERVER ----------- ===========---- -- -.z==========_;____;;===== =================
C LOCATION / GROUP OBSERVED: CONTROL ROOM DATE Directions Write the number in the Rating Scale column that corresponds to the evaluation made by the observer. The Rating Scale is defined as follows: sf / 0 - Not Observed 3 - Satisfactory
'c 1 - Unsatisfactory 4 - Exceeds Normal Expectations l % 2 - Marginal 5 - Excellent . i l
EVENT / CRITERIA RATING SCALE COMMENTS
1. ACTIVATION AND Resp 0NSE
\
Control room personnel rtpidly
- [(]j and correctly interprbted the problem. #'
Control room personnel knew when : ( to refer to the Emergency ' Operating Procedures and l Emergency Plan,' and which Emergency Implementing Procedures to use. l Plant process information was i available when required. CR personnel .obtained timely I meteorological data. i CR personne)" got timely release ! information 'from radiological and. effluent monitor systems. CW " personnel responded quickly l to personal inj ury incident. ,
CR personnel responded quickly '
l to fire alarm. a 4.3-1
, t ,f f r [g
r EVENT / CRITERIA RATING SCALE Cottr!ENTS LR operators responded properly to simulated operational events. IIP assistance was requested as needed. Event classifications were timely, acenrate and clear. The (I)E. Director took action to determine what other condi-tions might exist which would verify the accuracy of the initial indication. Control room personnel took appropriate actions to mitigate the effects of the accident. Technical advice was requested and/or received f rom the proper people. The emergency was upgraded or downgraded when appropriate. The (I)E.D. made the correct response to implement on-site and off-site assessment and protective measures. II. COMF!UNICATIONS/ DISSEMINATION OF INFORMATION NotificaLions were timely and properly completed. Communication networks were operational and utilized efficiently. Communication flow was adequate to ensure that information was timely, effective, and efficient. Phone listings were available, complete, and up-to-date. O 4.3-2
s n RATING SCALE COMMENTS fm EVENT / CRITERIA f ) (/ General status announcements
were made and updated periodically throughout, the drill. Proper data flow was maintained between TSC and control room.
Logs were maintained. The ambient noise level in the control room was not a problem. Transfer of information within the control room was cle3rly and completely understood. 1 II
I. PROCEDURE
S , l Emergency Operating Procedures and Emergency Plan Implementing Procedures were clearly marked and readily available in control TOom. f'h, ,
! Procedures used were current and controlled.
IV. DIRECTION AND CONTROL The (I)E.D. promptly assumed i control and authority. Action tas taken to initiate activation ,of the Emergency , Facilitiec when plant conditions ') < i and procedures indicated they would be activated. The proper management chain of command in the control room was s followed when making decisions. Emergency control and authority was properly transferred to the designated Emergency Director located in the Technical Support Center. l f% I k
\._)
l 4.3-3 i
.s
EVENT / CRITERIA RATING SCALE COMMENTS The transfer of control and authority was announced and logged. V. MATERIAL AND EQUIPMENT Plant Monitoring System functioned correctly. Radiation meteorological moni-toring system functioned correctly. Public Address System functioned correctly. Paging /Callout System functioned correctly. Message recorders functioned correctly. PABX and dedicated Hotlines functioned correctly. Station Alarm / Fire Alarm System functioned correctly Radios functioned correctly. VI. PROTECTIVE MEASURES Personnel in the control room adequately protected from radiological and chemical hazards. Supplies such as respirators, protective clothing and K1 for control room personnel were available. i l HP personnel were available as j needed. ! VII. ACCESS CONTROL Access to control room was limited to personnel assigned to the control room or 4.3-4
i l i ! l ! 1 1 l i ! 2 EVENT / CRITERIA RATING SCALE COMMENTS I participating in the drill exercise. , j- l I i i 4 s i ' t ) I I 1 I i, i. E t l ! i 4 k i
-1 l 4 1 i
i
4
!O 4 3 ? i 4 T 1 f l
l i
f 4 I I I r 'l i iO I 4.3-5 k 4 l l___.......-.._. _ ____ _ , _ _ _ . . . . . . - _ . . _ _ _ . , _ _ - _ . . -
OBSERVER CHECKLIST OBSERVER =====_========-- _= - - - - - LOCATION / GROUP OBSERVED: DOSE ASSESSMENT - CONTROL ROOM DATE Directions Write the number in the Rating Scale column that corresponds to the evaluation made by the observer. The Rating Scale is defined as follows: 0 - Not Observed 3 - Satisfactory 1 - Unsatisfactory 4 - Exceeds Normal Expectations 2 - Marginal 5 - Excellent EVENT / CRITERIA RATING SCALE COMMENTS The need to perform dose mea-surements was promptly identified. The correct procedures were used for making dose calculations. Shift Technical Advisor (STA) assigned to perform dose calcu-lations was familiar with the procedures. Dose calculations were performed efficiently and accurately. Some means were available to verify that the dose calcula-tions were correct. O 4.3-6
OBSERVER CllECKLIST p ( OBSERVER __ ----------_= =___ ------------- _.. --- 1 LOCATION / GROUP OBSERVED: TECIINICAL SUPPORT CENTER DATE Directions Write the number in the Rating Scale column that corresponds to the evaluation made by the observer. The Rating Scale is defined as follows: 0 - Not Observed 3 - Satisfactory I - Unsatisfactory 4 - Exceeds Normal Expectations 2 - Marginal 5 - Excellent EVENT / CRITERIA RATING SCALE COMMENTS I. ACTIVATION AND RESPONSE The TSC was activated and manned
/ \ in a timely manner at the Alert C Action Level.
Command and control authority was transferred from the control room according to procedure. The t rans fe r of command and control was formal, was an-nounced, and was logged. Follow-on activities to manage injured persons. Follow-on activities to manage fire. Field survey group dispatched, if appropriate. II. COMMUNICATIONS / DISSEMINATION OF INFORMATION Plant status and/or radiation ps., parameters needed to deterinine i the existing conditions were 4.3-7 y - -
EVENT / CRITERIA RATING SCALE COMMENTS available in the TSC including portable radiological monitor-ing, chemistry and meteorologi-cal data. Communication with State, County, and NRC officials was quickly established. Initial (if appropriate) and Follow-up Notifications were made in timely (usually 15 minutes) fashion. Major changes in plant or radiation release status were made known to all parties quickly. Off-site protective action recommendations were made quickly and clearly. All responsible persons in the TSC kept abreast of current conditions. Communications between TSC and CR, EOF, OSC and HESC were established and used. Communication with field survey group was adequate. Discussions were held concerning trends, prognosis, courses of action. II
I. PROCEDURE
S Current and controlled copies of the Emergency Plan and Imple-menting Procedures were available. Personnel using procedures were trained and familiar with them. O 4.3-8
,g EVENT / CRITERIA RATING SCALE COMMENTS ,
' N ,) Communication with off-site groups was made in accordance with procedurec.
.IV. DIRECTION AND CONTROL Transfer of command from control room was clear and understood by all persons.in TSC.
Transfer of command from TSC to EOF was clear and understood by all persons in TSC. Appropriate TSC personnel made prompt recommendations. Logs were kept. Recommendations were passed on to Emergency. Director for decisions. (~'N Proper classification upgrading t s_,/ and downgrading was done. V. MATERIAL AND EQUIPMENT Blueprints, as-built . drawings, maps, .etc, were available. PABX, sound powered, and dedicaten- Hotlines functioned correctly. Public Address System functioned correctly. Radios functioned correctly. Facsimile machine functioned correctly. Status boards in place and used. VI. PROTECTIVE MEASURES HP coverage available in TSC
.( air sampling, dose rate ) instruments).
4.3-9
EVENT / CRITERIA RATING SCALE COBRIENTS Protective equipment and supplies for TSC personnel. Plant evacuation decisions logical and clear. Plant evacuation directives included travel routes, special precautions, etc. Continuing accountability information given to Security. In plant radiological monitoring reported to TSC. VII. ACCESS CONTROL Only those people with assigned responsibilities were in TSC. Sign-in system was employed. O I O 4.3-10
OBSERVER CHECKLIST (su ) OBSERVER LOCATION / GROUP OBSERVED: HEALTH PHYSICS DATE Directions Write the number in the Rating Scale column that corresponds to the evaluation made by the observer. The Rating Scale is defined as follows: 0 - Not Observed 3 - Satisfactory 1 - Unsatisfactory 4 - Exceeds Normal Expectations 2 - Marginal 5 - Excellent EVENT / CRITERIA RATING SCALE COMMENTS Adequate trained personnel were available to furnish HP coverage for _ the emergency situation and g' 's First Aid teams, Chemistry, s ) Search and Rescue teams, Fire teams, Repair teams, EOF, OSC, and evacuees. Onsite monitoring equipment was easily accessible and properly distributed. Equipment was checked for proper operability prior to its use. Standard HP practices were employed for entry into actual or potential radiation areas. Proper survey records, dosimetry, stay time, etc. Were maintained during entry. Survey results were reported to the appropriate personnel. ; Follow-up actions were taken on survey results.
,~.
I \ \ ,Y 4.3-11
EVENT / CRITERIA RATING SCALE COMMENTS Pocket dosimeters were frequently checked and properly logged. The TSC, OSC, and CR habitability was frequented monitored. Team members had adequate understanding of proper utiliza-tion of equipment (survey) instruments, radios, SCBAs, etc.). Inplant Survey results were systematically collected by the Plant Survey Group Leader. The correct procedure was used to establish emergency dose limits if needed. Authorization to exceed 10CFR20 Exposure limits was documented. Debriefing conducted, records and logs collected. O 4.3-12
OBSERVER CHECKLIST
'l T 'j OBSERVER LOCATION / GROUP OBSERVED: SEARCH AND RESCUE TEAM DATE Directions Write the number in the Rating Scale column that corresponds to the evaluation made by the observer. The Rating Scale is defined as follows:
0 - Not Observed 3 - Satisfactory 1 - Unsatisfactory 4 - Exceeds Normal Expectations 2 - Marginal 5 - Excellent EVENT / CRITERIA RATING SCALE COMMENTS OSC Supervisor selected three or more volunteers to serve as fs team.
) \
If radiological hazards are involved, one team member is an HP Technician. Team members have current first aid training. Team members briefed in accord-ance with procedure. At least one team member has required formal access permit to area being entered. Radio cheik performed. Safety and first aid equipment available as needed. Communications maintained with OSC during search and rescue. Log of activities kept. [j Personal dosimetry used, if
\ ,,_,/ needed.
4.3-13 m
1 i l EVENT / CRITERIA RATING SCALE COW 1ENTS TSC informed of results of O search and rescue. O O 4.3-14
r OBSERVER CHECKLIST
~~/ ) OBSERVER LOCATION / GROUP OBSERVED: DOSE ASSESSMENT - DATE TECHNICAL SUPPORT CENTER Directions Write the number in the Rating Scale column that corresponds to the evaluation.made by the observer. The Rating Scale is defined as follows:
0 - Not Observed 3 - Satisfactory 1 - Unsatisfactory 4 - Exceeds Normal Expectations 2 - Marginal 5 - Excellent EVENT / CRITERIA RATING SCALE COMMENTS Initial and subsequent dose calculations were performed in a [N ) timely manner. (, / Computing aids were properly utilized. Plume was defined and tracked. Teams were contacted, briefed, and dispatched expeditiously. Communications were maintained with all teams. Personnel were efficiently utilized. Dose Assessment Team Leader initiated and provided periodic updates to the Emergency Director on Protective Actions. Status was maintained on team exposure levels. Comparisons were made between 7s projected and actual field i f i measurements.
--J ;
1 1 4.3-15 l l 1
EVENT / CRITERIA RATING SCALE COMMENTS O, Field Survey Group was provided with adequate info rma tion to I perform its 6; ties. , 1 4 1 O l l I O 4.3-16
i OBSERVER CHECKLIST [\
- \_,/
OBSERVER
' LOCATION / GROUP OBSERVED: OFFSITE MONITORING TEAMS DATE ~ Directions Write the number in the~ Rating Scale column that corresponds to the evaluation made by the observer. The Rating Scale is defined as follows:
0 - Not Observed 3 - Satisfactory 1 - Unsatisfactory 4 - Exceeds Normal Expectations 2 - Marginal 5 - Excellent EVENT / CRITERIA RATING SCALE COMMENTS Initial team briefings were held. f- ~g - Team assembled with field kits, vehicles, and communications equipment in a timely manner. Field Monitoring kits were checked for. contents before leaving site. Instruments checked for proper operability and current calibration. Teams received explicit instruc-
.tions of where to go and what to sample.
Procedures for conducting offsite _ monitoring- were consulted and followed. Vehicles were readily available. Vehicle. checked for contamina-tion after- mission completed. Sampling locations were readily
/~'N located, b.
4.3-17
EVENT / CRITERIA RATING SCALE COMMENTS Samples were properly packaged, identified, and labeled. Pocket dosimeters were period-ically checked. Pocket dosimeter readings were logged in upon return to LGS. Communications were maintained with the TSC and/or EOF through-out sampling activity. O I l s O 4.3-18 i
OBSERVER CHECKLIST g ( x.j
) OBSERVER LOCATION / GROUP OBSERVED: FIRE TEAM DATE Directions Write the number in the Rating Scale column that corresponds to the evaluation made by the observer. The Rating Scale is defined as follows:
0 - Not Observed 3 - Satisfactory 1 - Unsatisfactory 4 - Exceeds Normal Expectations 2 - Marginal 5 - Excellent EVENT / CRITERIA RATING SCALE COMMENTS Reaction time between fire alarm and fire team activation is timely.
,~
r i (,,,/ Fire fighting personnel response time to the scene of the fire was timely.
' Fire team members report to scene of fire with appropriate fire fighting gear and equipment.
Initial assessment of fire situation is adequately performed. When it is apparent team cannot control the fire, offsite support is requested and obtained in a timely manner. Communications are maintained between the fire team leader and the CR (Control Room). Adequate information is provided by the fire team to the control f-~s room for their assessment. I \ V 4.3-19
EVENT / CRITERIA RATING SCALE COMMENTS Smooth transition and coordina-tion is made between plant fire team ard local fire department. Arrival of local fire department to fire scene is timely. O O 4.3-20 - t
OBSERVER CHECKLIST p. ( . s OBSERVER LOCATION / GROUP OBSERVED: FIRST AID TEAM DATE Directions Write the number in the Rating Scale column that corresponds to the evaluation made by the observer. The Rating Scale is defined as follows: 0.- Not Observed 3 - Satisfactory 1 - Unsatisfactory 4 - Exceeds Normal Expectations 2 - Marginal 5 - Excellent EVENT / CRITERIA RATING SCALE COMMENTS First Aid Team assembly was timely; following notification. -G: f - First. Aid Team assembled with h- the proper first aid equipment. Accident / injury assessment made by the First Aid Team. First ' Aid assistance was rendered in a timely manner. Appropriate decontamination measures were taken. Maintained communications linkage with Control Room. The HP escort reacted properly to the simulated event. The request for and notification of ambulance was in accordance to procedures. Patient was made ready for
. transport by the First Aid Team.
Dosimeter was left with the i patient. v 4.3-21
EVENT / CRITERIA RATING SCALE COMMENTS Adequate !!Ps coverage was provided at the hospital. Patient's radiation doses are monitored by HP personnel. IIP performed radiation survey of ambulance at hospital before vehicle was released. Consideration / measures were taken to prevent spread of contamination. Periodic status reports are provided to the Shift Supervisor as to the injured individual's status. O l l 4.3-22 i
OBSERVER CHECKLIST
/ OBSERVER LOCATION / GROUP OBSERVED: OPERATIONAL SUPPORT CENTER DATE Directions Write the number in the Rating Scale column that corresponds to the evaluation made by the observer. The Rating Scale is defined as follows:
0 - Not Observed 3 - Satisfactory 1 - Unsatisfactory 4 - Exceeds Normal Expectations 2 - Marginal 5 - Excellent EVENT / CRITERIA RATING SCALE COMMENTS I. ACTIVATION AND RESPONSE m The OSC was activated in a l i timely fashion.
%)
All support personnel listed in the Emergency Plan were avail-able in the OSC. The personnel stationed in the OSC understood their emergency response functions. There were enough specialists available to fill all demands for HP, Fire Brigades, Search and Rescue teams, Repair teams, and Field Monitoring teams. II. COMMUNICATIONS / DISSEMINATION OF INFORMATION Communications with the control room and TSC were adequate. Communication with HP was adequate. Communications with specialty (^}/ - (, teams were adequate. 4.3-23 1- ;
EVENT / CRITERIA RATING SCALE COMMENTS There was adequate information flow from the TSC concerning plant conditions and hazardous areas. There was adequate information flow from the OSC to specialty teams. II
I. PROCEDURE
S The Emergency Plan and Implementing Procedures were available in current and controlled copies. Appropriate procedures were ' available, as needed, for the specialty teams. IV. DIRECTION AND CONTROL The OSC was supervised (coordinated) adequately. A chain of command was established. Team formation and briefings were completed quickly and accurately. Information for continuing accountability was supplied to Security. V. MATERIAL AND EQUIPMENT The office and communication equipment necessary to activate the OSC were available. Specialized tools were obtainable. VI. PROTECTIVE MEASURES Protective equipment, clothing, and decontamination facilities were available. 4.3-24
, ~. ._. . -. . _ . . . - . _ . . - _ ._. - - - . - - - - . ._ ..
EVENT / CRITERIA RATING SCALE COMMENTS The OSC was monitored for radiation. VII. ACCESS CONTROL Only OSC-assigned personnel were ' in the prescribed areas. I f i a I 1-e I i r r i 4.3-25 r i'
CBSERVER CHECKLIST OBSERVER LOCATION / GROUP OBSERVED: EMERGENCY CHEMISTRY DATE Directions Write the number in the Rating Scale column that corresponds to the evaluation made by the observer. The Rating Scale is defined as follows: 0 - Not Observed 3 - Satisfactory 1 - Unsatisfactory 4 - Exceeds Normal Expectations 2 - Marginal 5 - Excellent EVENT / CRITERIA RATING SCALE COMMENTS I. ACTIVATION AND RESPONSE The Chemistry Sampling and Analysis Team Leader reported promptly to the Technical Assessment area of the TSC. The Chemistry Sampling and Analysis Group Leader reported promptly to the Chemistry Field Office. An adequate number of tech-nicians were available or were called in. Analytical results were avail-abic within the specified times. II. COMMUNICATIONS / DISSEMINATION OF INFORMATION Communications with the control room and/or TSC were adequate. Directions given to technicians were clear. O 4.3-26
/~Y EVENT / CRITERIA RATING SCALE COMMENTS
, 3 Plant status information was available. to laboratory personnel. III.' PROCEDURES The appropriate procedures were available and followed.
'IV. . DIRECTION AND CONTROL Samples were collected and analyzed as requested by control room or TSC.
Chemistry. Supervisor _ _(or alternate) was- clearly- in command.
' Analytical results were verified.
j . Logs _of actions were kept.
% V.
MATERIAL AND EQUIPMENT Analytical equipment functioned prope rly.' Sample points were accessible and. . open (valves correctly aligned by control room and/or technicians). VI. PROTECTIVE MEASURES Health Physics . coverage was requested as needed. Protective . equipment was available to ' lab personnel. VII. ACCESS CONTROL Only personnel with emergency responsibilities were present during. exercise. Access to PASS, etc. was made according to procedure. 4.3-27
, - - , - , , .,-_,.m.-,- ,. .. , --2, - . -~. . - . - - . ~ , . _ , . .,---mm. ...m m, , ---. -
~ l OBSERVER CHECKLIST OBSERVER
== __
LOCATION / GROUP OBSERVED: EMERGENCY OPERATIONS FACILITY DATE Directions Write the number in the Rating Scale column that corresponds to the evaluation made by the observer. The Rating Scale is defined as follows: 0 - Not Observed 3 - Satisfactory 1 - Unsatisfactory 4 - Exceeds Normal Expectations 2 - Marginal 5 - Excellent EVENT / CRITERIA RATING SCALE COMMENTS I. ACTIVATION AND RESPONSE EOF was activated and manned within a reasonable time after declaration of Site Emergency or at the discretion of the Site Emergency Coordinator or Emergency Director. Site Emergency Coordinator received briefing from Emergency Director prior to assuming command and control. EOF personnel informed of assumption of specific responsibilities. Sign-in system used to assure full staffing. O 4.3-28
, ._. . _ _ . .__ .__..m. _ _ . - - _. _ . . . _ }
f' 3' .D[ ' Q .. EVENT / CRITERIA RATING SCALE COMMENTS I [ .II. . COMMUNICATIONS / DISSEMINATION.
' 0F INFORMATION Communications were checked and established with . control - room, ' TSC, ~ HESC~, and required offsite % Federal, ' State,: County, and *
p. local agencies.
Technical. N Support. Center
notified of , assumption' of 3 command and control of EOF designated respon'sibilities.
J NUded Jata 'was available from TSC and CR.
. EOF received ps:upt information .on radiological status,- both on and offsite. *'
r' Pertinent 'information quickly-1,
%- '(15 minutes) transmitted to I 'offsite groups. :< ~J ~
n Up-to-date ' meteorological ~. data
~
was available.
;. ~
Plant status information was - promptly available.
, Communication wpth -
offsite
' monitoring teams was adequate. . ,
General' status announcements and updates were. made_ to EOF personnel. throughout exe rci'se.
[45 1 EOF coordinated the supply of ' , information to Headquarters ESC ; Public Information. Services. t
, Status / boards used and kept I curreiiti V
II
I. PROCEDURE
S . Emergency Plan and' Implementing Procedures were available- in-
, ' current and controlled copies.
4.3-29
- .:q.
i c':, , , . . , - - . , ..- ,.- . - .. - - - - -
EVENT / CRITERIA RATING SCALE COMMENTS EOF participants were familiar with procedures. Correct procedures were used. I IV. DIRECTION AND CONTROL The organizational structure and chain of command in EOF was clear. Appropriate people made prompt decisions and recommendations. EOF Staff took appropriate follow-up actions to care for injured personnel, if any. Status boards kept current. Plume pathway tracked and visible. Emergency classifications and action level notifications transmitted to proper authorities as required. Protective action ~ recommenda-tions were made clearly and in timely fashion. Continuing accountability data forwarded to Security. V. MATERIAL AND EQUIPMENT Facsimile machine functioned. Status boards available. Reference materials, procedures, prints, etc., available. VI. ACCESS CONTROL Only assigned EOF people were present. Security Control established. 4.3-30
OBSERVER CHECKLIST "b-Q. OBSERVER LOCATION / GROUP OBSERVED: DOSE ASSESSMENT - EMERGENCY DATE OPERATIONS FACILITY Directions Write the number in the Rating Scale column that corresponds to the evaluatica made by the observer. The Rating Scale is defined as follows: 0.- Not Observed 3 - Satisfactory 1 = Unsatisfactory 4 - Exceeds Normal Expectations 2 - Marginal 5 - Excellent t
EVENT / CRITERIA 1 RATING SCALE COMMENTS Initial and. subsequent dose
-calculations were performed in a s/ : ; timely manner.
Computer aids were properly utilized. vi
's Plume was defined. and tracked.
Teams were contacted, briefed, and dispatched expeditiously. 3 Communications were maintained with-all teams, f
; Personnel was efficiently -utilized. ;
Dose Assessment Team Leader will' , Vinitiate and' provide periodic d updates to the Site Emergency Coordina'tor on PAGs. Status - was maintained. on team exposure-levels. 4 Offsite -monitoring data :were t g ,
/T- coordinated with State. , t, U >
t 4.3-31
I l EVENT / CRITERIA RATING SCALE COMMENTS l Comparisons were made between i projected doses and actual field 4 measurements. Field Survey Group provided with adequate information to perform ; duties. l l 9 0 4.3-32
-~
OBSERVER CHECKLIST ( ) ' ,/ OBSERVER LOCATION / GROUP OBSERVED: HEADQUARTERS EMERGENCY DATE SUPPORT CENTER Directions Write the number in the Rating Scale column that corresponds to the evaluation made by the observer. The Rating Scale is defined as follows: 0 - Not Observed 3 - Satisfactory 1 = Unsatisfactory 4 - Exceeds Normal Expectations 2 - Marginal 5 - Excellent EVENT / CRITERIA RATING SCALE COMMENTS I. ACTIVATION AND RESPONSE /o ) The Hqtrs Emergency Support 'x. / Center was fully staffed in a timely fashion. The Emergency Support Officer was clearly in command. Information was received quickly from the EOF and/or TSC. II. COMMUNICATIONS / DISSEMINATION OF INFORMATION Emergency News Releasea were coordinated prior to release as required by EP-C Co rpo ra te Emergency Procedures. Emergency News Releases were made in accordance with pre-scribed procedure. Spokespersons were clearly identified. rs Rumor control methods were used. 'x. / 4.3-33
r EVENT / CRITERIA RATING SCALE COMMENTS II
I. PROCEDURE
S O Controlled and current copies of the Emergency Plan and Implementing Procedures were available. IV. DIRECTION AND CONTROL Emergency Support Officer was clearly in control of the ESC. Major decisions were made by Emergency Support Officer in consultation with his staff. News releases were reviewed and issued smoothly and quickly. Logistical Support and manpower requests were acted on in an expeditious manner by staff. Liaison with offsite law enforcement was provided, as appropriate. Spokespersons were knowledgeable about technical aspects of plant problems. V. MATERIAL AND EQUIPMENT Space for staff was adequate. Space for news media represent-atives was adequate. m Adequate telephones to handle traffic were available. Facsimile machine operable. VI. PROTECTIVE MEASURES (Not applicable) O 4.3-34 I
EVENT / CRITERIA RATING SCALE COMENTb VII. ACCESS CONTROL Only persons with- assigned emergency responsibilities were present. a O l I i 4 4.3-35
OBSERVER CIIECKLIST OBSERVER LOCATION / GROUP OBSERVED: REPAIR TEAM DATE Directions Write the number in the Rating Scale column that corresponds to the evaluation made by the observer. The Rating Scale is defined as follows: 0 - Not Observed 3 - Satisfactory 1 = Unsatisfactory 4 - Exceeds Normal Expectations 2 - Marginal 5 - Excellent EVENT / CRITERIA RATING SCALE COMMENTS OSC Supervisor selected three or more volunteers to serve as team. If radiological hazards are involved, one team member is an IIP Technician. Team members briefed in accordance with procedure. At least one team member has required formal access permit to area being entered. Safety and first aid equipment available as needed. Radio check performed. Communications maintained with OSC during repair activities. Log of activities kept. Debriefing conducted, records and log collected. Personal dosimetry used, if needed. 4.3-36
.._. _. .~ . _ ... .. ....,- . .. _ . .-
I I I EVENT / CRITERIA R/. TING SCALE COMMENTS i TSC informed of results. l l )- i t f i i i i' i i I i i i 3 f 4 i i i i@ 1 4 i i 4 4.3-37 } I l t
OBSERVER CHECKLIST OBSERVER LOCATION / GROUP OBSERVED: EVACUATION / ASSEMBLY AREA DATE Directions Write the number in the Rating Scale column that corresponds to the evaluation made by the observer. The Rating Scale is defined as follows: 0 - Not Observed 3 - Satisfactory 1 = Unsatisfactory 4 - Exceeds Normal Expectations 2 - Marginal 5 - Excellent EVENT / CRITERIA RATING SCALE COMMENTS I. ACTIVATION AND RESPONSE Announcement to evacuate is clearly understandable and is heard by all personnel. Announcement was preceded by station ala rm. Evacuees quickly assembled in correct area. Person in charge was clearly identifiable. II. COMMUNICATION / DISSEMINATION OF INFORMATION Adequate instructions were given to evacuees. Evacuation supervisor estab-lished and maintained communi-cation with TSC. TSC notified when all persons were accounted for at off-site assembly area. O 4.3-38
]
$ w 4 ; 'N / EVENT / CRITERIA RATING SCALE ~ COMMENTS A
v).- < III.~ PROCEDURES Evacuees passed through proper ' 1 control points.
- Personal badges . and ' TLDs ~ were i . left..at the ~ primary access point.
i t-
-All supervisors and instructors completed muster sheets, as - requested. - IV. DIRECTIONS AND CONTROL The ' evacuation supervisor was . easily identified and clearly in charge.
Evacuation was performed . in smooth and controlled manner. 3 Accountability (muster sheets) 4 q' v7j_ were used correctly at off-site assembly' area. 4 Evacuees. followed directions g given over PA System - and given - by evacuation supervisor.
- V. -MATERIAL AND EQUIPMENT 7 - Evacuation Supervisor was - equipped with . voice amplifier.
Adequate number of vehicles were-
, available.
Adequate radiation _ instrumenta-tion and decontamination equip- , ment.was available. Radios functioned correctly. i ..VI. PROTECTIVE MEASURES Portal' Monitors were effectively used to monitor evacuees. i r < V . 4 l 4.3-39
- - ,__ ,_,. . _ - . . . ~ . . .,, , _ _ . , , - . . . . , . . , . . . _ . . . . _ _ - , _ , _ - _ . _ _ _ , . . . , _ _ _ _ , , _ . _ _ _ . . - - _ _ - , - . _ _ . . , - - - .
EVENT / CRITERIA RATING SCALE COMMENTS First aid equipment was avail-able or obtainable. Decontamination equipment was available or obtainable. Health Physics coverage was available at on-site assembly area. VII. ACCESS CONTROL Off-site assembly area was fully accessible. There were no major problems in moving evacuees through control points or the principal access point. O O 4.3-40
f -) 4A 4 --- p 4cm9 A e4 4 k & ai- --e i- AW ~-a
-ae.+ 4'-a- a e OBSERVER CHECKLIST iDI f
9 9_,/ OBSERVER LOCATION / GROUP OBSERVED: ~ ACCOUNTABILITY DATE Directions Write the number in the Rating Scale column.that corresponds to the evaluation made by the observer. The Rating Scale is defined as follows: 0 - Not Observed 3 - Satisfactory 1 = Unsatisfactory 4 - Exceeds Normal Expectations 2 - Marginal 5 - Excellent EVENT / CRITERIA RATING SCALE COMMENTS I. ACTIVATION AND RESPONSE Security personnel were in place [) quickly following evacuation V announcement. Established means for performing rapid initial accountability for persons leaving protected areas were employed. Established means for quickly finding location of personnel l remaining in protected areas
- were employed.
II. COMMUNICATION / DISSEMINATION OF INFORMATION l Initial notification to Securi-ty were clear ~and complete. Communications internal to the Security ' organization were l= adequate. Status reports from Security (}
.-(_/ - Supervisor to the Emergency l
4.3-41 l. E
EVENT / CRITERIA RATING SCALE COMMENTS Director were timely and complete. Continuing accountability
' reports were quickly furnished to Security by Control Room, TSC, OSC, AND EOF.
III. PRCOEDURES App ropria te Security procedures were readily available. Controlled and current copies of the Emergency Plan and Imple-menting Procedures were readily available. Appropriate procedures were used during exercise. IV. DIRECTION AND CONTROL Accountability of all personnel was achieved within thirty minutes. Accountability of people enter-ing or leaving assembly areas was accomplished. Security personnel were trained and familiar with their responsibilities. Security personnel requested or required by procedure were promptly dispatched. V. MATERIALS AND EQUIPMENT Security computer in place and operable. VI. PROTECTIVE MEASURES Ifealth Physics coverage avail-able as requested. O 4.3-42
j.--.,-...-..-.---...---..--~.~..-._....-.._._._-._..-.---.-.._..
* ?
3 i r 1; ! t
!,. -EVENT / CRITERIA RATING SCALE COMMENTS '
1. I j ' Security personnel kept advised ; i of plant status, i i i
! VII. ACCESS CONTROL- !
i 4j< t l 1 Facility- access controlled f
.during exercise.
,i . Special access controls, if any, '
put in place as requested.
2 i-s 1 ,
i i i i t' i, > j. i ! 1: !
.l i
e l I i' \ I i !. i i l 4 i ! l 2 i
i. l 1
t
I 1 i I
i i9 t. l, I i- ! i j i- 4.3-43
t l
1 s
i CONTROLLER / EVALUATOR CRITIQUE SHEET O CONTROLLER / EVALUATOR'S NAME: DRILL /EXERClSE NO: DATE:
EVALUATION ASSIGNMENT

EVALUATION AREAS S AT/M ARGIN AL/UNS AT/NOT OBSERVED I ACTIV ATION & RESPONSE , DISSEMINATION OF INFORM ATION 1 PROCEDURE IMPLEMENTATION , DIRECTION AND CONTROL PROTECTIVE ACTIONS MATERIA! AND EQUIPMENT , ACCESS CONTROL 3 1 IMPROVEMENT AREAS: O 1. TRAINING: i j i
2. P ROCED U RE S:
]
3. EQUIPMENT & MATERIALS:

4. SCENARIO:
i
5. OTHER:
i !O,
- 4.3-44
(~h V EMERGENCY PREPAREDNESS ACTION ITEM TRACKING SYSTEM Brief Title of Action Item: Identified By: Telephone Number: Date Reported: Action Log Number: COMPLETE DESCRIPTION OF ACTION ITEM
-~ (If Additional Space is Required, Use Additional Blank Sheets)
'N- / RESOLUTION OF ACTION ITEM Resolution Submitted by: Telephone Number: Resolution Accepted / Declined Site Emergency Preparedness Coordinator Date l' t x_ GRADING SYSTEM 4.3-45
} October 17, 1985 SECTION 5.0
EXERCISE SCENARIO 1985 NRC OBSERVED EMERGENCY RESPONSE EXERCISE
, PEACH BOTTOM ATOMIC POWER STATION i l Section Page r 4 5.1 INITIAL CONDITIONS. . . . . . . . . .. ... . . . . . . . 5.1-1 5.1 SCENARIO ABSTRACT . . . . . . . . .. . ... . . . . . . . 5.2-1 5.3 DETAILED SCENARIO . . . . . . . . . . . ... . . . . . . . 5.3-1 i 5.4 SCENARIO TIME LINE. . . . . . . . . . .... . . . . . . . 5.4-1 4 4 s a ! i 1, i ? f I I l l 1 i, 5.0-1 e t
~ - - . . - , _ _ - , - - _ , - - , - . . - , . _ , , . _ _ , . - . , ~ - - . . -
r-L-
,_s October 17, 1985 4x/ SECTION 5.3 DETAILED SCENARIO '
1985 NRC OBSERVED EMERGENCY RESPONSE EXERCISE , PEACH BOTTOM ATOMIC POWER STATION Time Description '. 0800 Unit 3 is operating at 100 percent power. All power generation equipment is operating satisfactorily. Safety systems are all operable. 0810 Condenser low vacuum alarm occurs. Reactor scram and turbine trip occur.
*** UNUSUAL EVENT should be declared, EP 101-1: ***
Any scram other than planned 0811 Feedwater control limits reactor level increase to below
+45 inches so feedwater pumps do not trip on high level.
Reactor vessel pressure has decreased to 930 psig. (v Condenser hotwell level has fallen to 13 inches. 0813 Control room receives a message that workers near the Unit 3 condenser had accidentally damaged the regulator valve on a high pressure oxygen bottle. The rocketing oxygen bottle punctured the middle condenser at the base (Event No. 1). Condenser hotwell level is 11 inches. 0825 Condenser hotwell level is down to 3 inches. Condensate pump trips. Feedwater pump trips. 0827 Reactor vessel Lo-Lo level alarm annunciates. MSIVs close automatically. HPCI and RCIC start. 0830 Operators limit reactor pressure surge due to MSIV closure to 1090 psig by opening a safety / relief valve. Reactor vessel level has recovered to 0 inches. Torus water level alarm is annunciated (Event No. 2). foFus water, level has fallen to 14.5 feet. (O v> 5.3-1
e _ i Time Description 0845 Reactor vessel water level has recovered to +25 inches. Torus water level has decreased to 13.5 feet. Torus room flood alarm occurs. i
*** ALERT should be declared, EP 101-3: ***
Torus room flood alarm with level decrease in torus. 0900 Drywell pressure and temperature are 1.2 psig and 136 F, respectively. Torus water level and temperature are 12 feet and 76 F, respectively. i l Condensate storage tank level is 16 feet. 0915 Drywell pressure has decreased to 0.7 psig. 7 Torus water level is reduced to 10.5 feet. 1 9q4g 77 0930 Reactor vessel pressure and level are 1060 psig and +25 inches. h Drywell pressure and temperature are 0.4 psig and 140 F. Torus water level is 7.5 feet. IIPCI room flood alarm occurs. RCIC room flood alarm occurs. 0935 IIPCI turbine trips on mechanical overspeed. Torus water level has decreased to 5.5 feet. 0940 RCIC turbine trips on mechanical overspeed. Torus water level is 5.1 feet. 0945 Reactor vessel level has decreased to +20 inches and reactor vessel pressure is 1050 psig. Torus water level is 5.0 feet, g Reactor vessel level and pressure are zero inches and 1045 psig.
//c [ Drywell pressure and temperature are 0.2 psig and 140 F. ,// Y h 9
5.3-2 1
,_s : Time Description e i h }
3- ' 1330 Ground fault alarm for the Division A 125/250 V DC distribution system occurs (Event No. 7). Reactor vessel pressure is down to 150 psig and reactor water level has increased to +20 inches. Torus water level has increased to 5.8 feet and torus water temperature has peaked at 98* F. 1400 Reactor vessel level has stabilized at +25 inches. Torus water level is 7 feet and torus water temperature is down to
.92* F.
Drywell radiation level has decreased to 2P4 R/hr. 1430 Flood alarm occurs for the D core spray pump room (Event No. 8). Drywell radiation level has decreased to 800 R/hr and the main stack high range radiation monitor reading has decreased to SP9 cps. 1500 Reactor vessel level is +25 inches and reactor vessel pressure is l 8 psig.
,O \_-) Main stack normal range monitor reading is down to 3 x 105 cps.
Torus water level has increased to 8.3 feet. Drywell temperature and pressure are 110' F and 1 psig. 1530 Drywell temperature has decreased to 140' F. Mainstack radiation monitor reading is 2 x 104 cps. Reactor vessel pressure and level are stable at 0 psig and
+25 inches. *** DE-ESCALATION TO SITE EMERGENCY or ALERT status ***
can now be considered. 1600 Exercise is terminated. ia l 5.3-5
I
, 1
D)
! Time Description -V.
MMMF Reactor vessel level and pressure are -25 inches and 1020 psig.
-lffI Drywell pressure and temperature are 0.8 psig and 160* F.
Torus water level is 4.8 feet. Smoke detector alarm for the northwest corner of reactor building el. 135 feet actuates (Event No. 3). 1020 Control room annunciator indicates power failure in the ECCS trip units.
*** SITE EMERGENCY should be declared, EP 101-5: ***
Fire which makes an ECCS inop. Main stack radiation mcnitor high ala rm occurs. Reading is 300 cps. Reactor vessel level has decreased to -37 inches and drywell temperature has increased to 170' F. 1028 Main stack radiation monitor high-high alarm occurs, r 1030 Standby liquid control (SLC) pump discharge header pressure starts (_)g varying erratically (Event No. 4). Reactor vessel level is -70 inches and reactor pressure is 1015 psig. Drywell pressure and tempe ra tu re are 1.3 psig ,and 180' F, respectively. Main stack radiation monitor reading is IP4 cps. 1100 Reactor vessel level is down to -145 inches and drywell temperature has leveled off at 190' F. Torus water level is 4.8 feet. Drywell radiation level is 20R/hr and increasing. Main stack radiation monitor reading has increased to 4P4 cps. 1115 Reactor vessel water level is -187 inches. Torus water level and temperature are 4.9 feet and 84* F. 1120 Main stack radiation monitor reads above IP6. Main stack high range radiation monitor is reading 1.7P8 cps. ( 5.3-3 L s
/ Time Description y0 Reactor vessel level and pressure are now -210 inches and 33 990 psig, respectively. 17 Drywell radiation level is 300 R/hr. I Reactor vessel level and pressure are -250 inches and 980 psig, 3' respectively. Drywell pressure and temperature are stable at 1.3 psig and 190* F. Drywell radiation level has increased to SP3 R/hr. Torus water level and temperature are 5.1 feet and 86 F. flain stack high range radiation monitor is reading SP9 cps. 12tfd Reactor vessel level and temperature are -270 inches and 960 psig. 90 l' Drywell radiation level peaks at 7P4 R/hr. Torus water level is 5.2 feet. fla ins ta ck high range radiation monitor reads 7P10 cps, which corresponds to a projected whole body dose rate of 600 mrem /hr at a distance of 3 miles. 1 8 **f GENERAL Et!ERGENCY should be declared * * ' - EP 101-5: Uncontrollable release for more than 20 minutes from the
/ t'1' main stack greater than 2 x 109 cps on RR-7127.
J/I) Control rod drive pumps trip out on. low suction pressure (Event No. 5). Word is received that on llP Technician has been inj ured p f while doing surveys in the reactor building (Event No. 6) Reactor vessel level has stabilized at -285 inches. Reactor vessel pressure is 910 psig.
.15 60 Reactor vessel level and pressure are -285 inches and 860 psig.
Drywell radiation level is constant at 7P4 R/hr. 1 Torus water level is 5.6 feet. 1315 Reactor vessel level and pressure are -210 inches and 400 psig, i respectively. O 5.3-4 L
_ - - , _ - - - _ - ~ _ - - , . -_. - . - October 17, 1985 ,O SECTION 5.1 , l INITIAL CONDITIONS 1985 NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATONIC POWER STATION Units 2 and 3 are operating normally. Power generation equipment is operating satisfactorily and safety systems are fully operable. Unit 3 is , operating at full power and is scheduled to shut down for refueling in l February. Unit 2 is at ninety-five percent power and has been running l continuously since March. Initial plant and reactor system values for Unit i 3 are presented in Tables 5.1-1 and 5.1-2. l l Contractor personnel are engaged in replacement of the rolling steel door t for entrance to the radwaste building at el.135 f t. Other personnel are in the Unit 3 turbine building reinforcing the supports for the condenser compartment coolers. l j An I&E information notice was issued last week reporting that diaphragm cracks had been discovered in target rack safety / relief valves at two other stations. The vigorous low pressure area that brought moderate to heavy rains, which depleted nature's beautiful fall array in our area yesterday, is still influencing our weather. It is centered over Scranton this morning and i moving rapidly toward the Northeast, into Quebec province. The trailing cold front should be through our area in a few hours, bringing rapidly l( l clearing conditions. This morning's blustery NE wind flow should veer to a more westerly heading and reduce in intensity. High temperatures should reach 65-70'F. Tonight's moonlit skies will see temperatures drop to a low l. of 45*F by morning. Fair and seasonable tomorrow; highs in the sixties. The initial meteorological parameters are: l I Wind Direction North northeast (019 degrees) Wind Speed 13 mph Temperature 58*F Delta Temperature -0.4*F l i l [ 5.1-1 l
r TABLE 5.1-1 INITIAL PLANT AND REACTOR SYSTEM VALUES Normal Parameter Units Reading Initial Value Reactor Vessel Water Level inches 15-35 +25 Reactor Pressure. psig <1020 980 Reactor Power-APRM (avg) % full power 0-100 100 Core Plate Diff. Pressure psid 0-20 20 s Total Core Flow lbs/hr x lo 0-102 102 Recire. Loop A Water Temp. 'F 60-535 520 Recire. Loop B Water Temp. *F 60-535 520 Drywell Pressure psig 0.25-0.75 0.6 Drywell Temperature *F 60-135 129 Drywell Radiation R/hr 0-20 2 Containment 02 Concentration % <4 2.2 Containment H2 Concentration % <1 0 Torus Water Level feet 14.6-14.9 14.7 Torus Water Temperature 'F 60-95 70 Reactor Building Pressure inches H 2O .25 - -1.25 -0.5 Refuel Floor Vent Exhaust Rad Mon mR/hr 0.3-5 1.6 Drywell Vent Rad Mon (Gaseous) cpm 100-1000 900 i
\ \ Main Steam Line Flow lbs/hr x lo s 0-13.4 <3P3 13.4 IP3 Main Steam Line Radiation mR/hr Feedwater Flow (total) lbs/hr x 10 8 0-13.4 13.4 Condenser Hotwell Level inches 10 - 25 15 Condenser Vacuum inches Hg >24 29 Condensate Storage Tank level feet 25-39 37 Air Ejector Off-gas Rad Monitor mR/hr <500 40 Main Stack Flow cfm 1.P4-3P4 2P4 Main Stack Hi-Range Rad Monitor cps <1PS <1PS Stack Gas Rad Monitor cps <300 25 Vent Stack Flow cfm 1.25PS-3.5P5 3P5 Vent Stack Exhaust monitor epm (2700 500 Reactor Bldg Vent Exhaust Rad Mon mR/hr 0.3-5 0.5 Radwaste Duct Rad. Monitor epm (2500 300 Standby Gas Treatment System Flow cfm 0 0 /O 4 (J
1 of 1
_ __ .. .. _. . _ . .. . _ _ ._. _. _ __ __ . ... ...____ _ - . _ _. . _ _ _ ~ . - _ . _ _ _ . _ _ _ TABLE 5.1-2 . INITIAL RADIOCHEMISTRY DATA i i Reactor Drywell ^ Coolant Atmosphere Torus i Isotope (pCi/gm) (pCi/cc) (pCi/gm) r Kr-83M 3.9N4 <1N8 -- Kr-85M 1.1N3 2.7N8 -- Kr-85 6.9N6 <1N8 -- , Kr-87 2.1N3 4.9N8 -- l Kr-88 2.9N3 6.8N8 -- Xe-131M 2.2N5 <1N8 -- Xe-133M 1.1N4 <1N8 -- Xe-133 5.9N3 1.4N7 -- Xe-135M 1.6N3 3.6N8 -- Xe-135 1.4N3 3.4N8 -- Xe-138 5.1N3 1.2N7 -- Total NG 3.0N2 7.ON7 -- l I-131 2.9N3 6.8N8 1.7N8 I-133 5.9N3 1.4N7 3.6N8 g Total Iodine 8.8N3 2.1N7 5.3N8 Gross Beta 7.8N2 1.8N6 1.1N7 J 1 1 ! I of 1 4 I
Mm++-wa+re-mee i- er M v wp+%yw.e.wp-.ryw,y- , , - w,--,--wse.g.v-=%y-w.:,.w9-- yey--cse%-,-,p--m-=--wm- -ce y g w y-w- syy m e -g em eg-.y,-m----w-
h_. Octobar 17, 1985-SECTION 5.1
.. -X -.1 INITIAL CONDITIONS 1985 NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION Units- 2 and3 are operating normally. Power generation equipment is . operating satisfactorily and safety systems are fully operable. Unit 3 is operating at full power and is scheduled to shut down for refueling in February. Unit - 2 is a*. ninety-five percent power and has been running . continuously since March. Initial plant and reactor system values for Unit 3 are presented in Tables'5.1-1 and 5.1-2.~ l .; u Contractor personnel are engaged in replacemer.t of the rolling steel door t for entrance to the radwaste building at el.135 f t. Other personnel are in the Unit 3 turbine building reinforcing the supports for the condenser compartment coolers.
I An -I&E information notice was issued last week reporting that diaphragm cracks had been discovered in target rack safety / relief valves at two other stations. The vigorous low pressure area that brought moderate to heavy rains, which F depleted nature's beautiful fall array in our area yesterday, is still influencing our weather. It is centered over Scranton this morning and moving rapidly toward the Northeast, into Quebec province. The trailing cold front should be through our area in a few hours, bringing rapidly v( clearing . conditions. This morning's blustery NE wind flow should veer to a more westerly heading and reduce in intensity. High temperatures should (f' . reach 65-70*F. Tonight's moonlit skies will see temperatures drop to a low of 45'F by morning. Fair and seasonable tomorrow; highs in the sixties. The initial meteorological parameters are: Wind Direction North northeast (019 degrees) Wind Speed 13 mph Temperature 58'F Delta Temperature -0.4*F l ( - 5.1-1
. j , : TABLE 5.1-1
. INITIAL PLANT AND REACTOR SYSTEM VALUES r
Parameter Units -Initial Value , Reactor Vessel Water Level inches +25 l
- Reactor Pressure psig 980 Reactor Power-APRM (avg) % full power 100 Core Plate Diff. Pressure paid 20 ,
Total' Core Flow lbs/hr x 10 8 102 Recire. Loop A Water Temp. *F 520 ;
-Recirc.-Loop B Water Temp. *F 520 Drywell. Pressure psig 0.6 Drywell Temperature *F 129 1Drywell Radiation- R/hr 2 Containment 02 Concentration % 2.2 Containment H2 Concentration % 0 Torus Water Level feet 14.7 Torus Water Temperature *F - 70 Reactor Building Pressure inches H 2O -0.5 ,
Refuel Floor Vent Exhaust had Mon mR/hr 1.6 Drywell Vent Rad Mon (Gaseous) cpm 900 t Main Steam Line Flow lbs/hr x 10s 13.4
/~'s Main Steam Line Radiation. mR/hr IP3 s ~ !, + -
Feedwater Flow (total) lbs/hr x lo 13.4 Condenser Hotwell Level ' inches 15
. Condenser Vacuam .
inches Hg 29 Condensate Storage Tank level feet 37
, Air Ejector Off-gas Rad Monitor mR/hr 40 Main Stack Flow cfm 2P4 Main Stack Hi-Range Rad Monitor cps <1P5 Stack-Gas Rad Monitor cps 25 Vent Stack Flow' cfm 3P5 Vent Stack Exhaust monitor cpm 500 Reactor Bldg Vent Exhaust Rad Mon mR/hr 0.5 Radwaste Duct Rad. Monitor epm 300 Standby Gas Treatment System Flow cfm 0 l
l i I-
d 1 of 1
i %g.. _I3 i TABLE 5.1-2
'u/ INITIAL RADI0 CHEMISTRY DATA Reactor Drywell Coolant Atmosphere Torus Isotope - (pci/sa) (pCi/ce) (pCi/am)
Kr-834 3.9N4 s
<1N8 --
Kr-85M 1.1N3 , 2.7N8 -- Kr-85 - -- 6.9N6 <1N8 --
)
Kr-87 2.1N3 1 4.9N8 --
' ' 2.9N3 6.8N8 Kr@.S --
Xe-131M 2.2N5 <1N8 -- Xe-133M 1.1N4 <1N8 -- Xe-133 5.9N3 1.4N7 -- Xe-135M 1.6N3 3.6N8 --
-Xe-135 1.4N3 3.4N8 --
Xe-138 5.1N3 1.2N7 -- Total NG 3.0N2 7.ON7 -- I-131 2.9N3 6.8N8 1.7N8 I-133 5.9N3 1.4N7 3.6N8 Total Iodine- 8.8N3 + 2.1N7 5.3N8 Gross Beta 7.8N2 1.8N6 1.1N7
'*e' s -
e,
\
s , N
/,. -7 -\;
4 a 1 of 1
s October 17, 1985 m SECTION 5.2 ( ) V SCENARIO ABSTRACT 1985 NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION Units 2 and 3 are operating normally. Power generation equipment is operating satisfactorily and safety systems are fully operable. Unit 3 is operating at full power and is scheduled to shut down for refueling in February. Unit 2 is at ninety-five percent power and has been running continuously since March. While personnel are working in the vicinity of the Unit 3 condenser, the regulator valve on a high pret.sure oxygen bottle is accidentally damaged. The ensuing rocketing of the bottle punctures the condenser at the base of the hot well. Condenser vacuum is lost causing reactor scram at 0810.
*** UNUSUAL EVENT should be declared (Ref. EP.101-1-2) ***
Recovery from the reactor scram is normal but the break in the condenser is causing severe leakage from both sections of the hot well. The drop in hot well level causes the condensate pumps to trip at 0825. The loss of condensate pumps leads directly to feedwater pump trips on low suction pres-sure; SGTS (standby gas treatment system) initiation on low reactor level; main steam isolation valve (MSIV) closure on low-low reactor level; and high pressure coolant injection (HPCI) and reactor core isolation cooling (RCIC)
]g) initiation on low-low reactor level.
G , The closure of the MSIVs causes rapidly increasing reactor pressure, and the operators open a safety / relief valve (SRV) before the lowest automatic pressure relief setpoint of 1105 psig is reached. The discharge of the relief valve into the torus causes excessive strain on the torus wall in the vicinity of an SRV line support pad. At 0830 the torus water level falls to 14.5 feet and a low level alarm is annunciated. By 0845 torus water level has dropped to 13.5 feet and, at this time, a torus room flood alarm occurs.
*** ALERT should be declared (Ref. EP 101-3-2) ***
At 0900 reactor water level is being maintained between 0 and +45 inches by operators and reactor pressure has been stabilized at 1040 psig. Torus level has fallen to 12.0 feet. Drywell pressure is 1.2 psig. Torus level has decreased to 10.5 feet at 0915 and drywell pressure starts decreasing indicating that the downcomers in the torus are becoming uncovered. Torus level starts decreasing faster. Torus level has dropped to 7.5 feet by 0930 and a HPCI and RCIC room flood alarm occurs indicating Icakage from the Torus room to the HPCI and RCIC cubicles. 1 Drywell pressure is 0.4 psig and temperature is stable at 140*F. f 5.2-1 t
At 0935 HPCI trips out due to the flooding condition. Torus level has fallen to 5.5 feet. At 0940 the RCIC trips out. Reactor level starts falling at about one inch per minute. At 1005 drywell temperature increases rapidly indicating reactor coolant system leakage in the drywell. Reactor level starts falling at the rate of 2.5 inches per minute, and at 1020, increases in radioactive releases are detected by the main stack radiation monitors. The loss of reactor coolant is due to a leak in the reactor water cleanup line. Since it is a water leak, the heat loss from the reactor is not as great as it would be for a steam leak and reretor pressure is not reduced rapidly. l A fire in 480 V EMER MCC 30B38 (E334-R-B) causes smoke detector alarms for the north west corner of reactor building el. 135 feet to actuate at 1015. At 1020, control room annunciator indicates power failure for the ECCS TRIP units. When the fire brigade arrives, they determine that offsite assis-tance is required since the motor control center is completely engulfed in flames. N SITE EMERGENCY should be declared (Ref. EP 101-5-1) *** At 1030 reactor water level has fallen to - 70 inches and the main stack monitor reading has increased to 1 x 104 cps. At this time, the standby liquid control pump discharge header pressure is changing erratically. In-vestigation reveals that the relief valve on the discharge of standby liquid control pump has opened and is soaking the motors of both pumps. The operating motor is steaming, encrusted in boric acid crystals, and making a strange noise. At 1115 reactor water levels has fallen to - 187 inches. Torus water level has started rising from a low of 4.8 feet as the torus room is now flooded to the same level as the torus. Radioactive releases are now rising rapidly. Main stack monitor reading was 4 x 104 cps at 1100 but by 1120 it has reached 108 cps. At 1130 the reactor level ia+-210 inches and is dropping more slowly since water level is now approaching the level of the leak.
~ -At 1145, the main stack high range radiation monitor reading is greater than 2x109 eps, and remain above this value for more than twenty minutes. *M GENERAL EMERGENCY should be declared (Ref. EP 101-5-1)
At 1200 radioactive releases reach a level corresponding to a projected whole body dose rate of 600 mR/ hour at a distance of three miles from the reactor.
Reactor water level is now at -270 inches and reactor pressure has been reduced to 960 psig. At 1230 the control rod drive pumps trip out on low suction pressure because of a clogged filter. Station personnel respond and restore control rod drive flow. At this time, an HP team is surveying the radiation levels in 5.2-2
_p the A&C RHR room on ' 91 f t - 6 in, el, of the reactor building. One of them I falls and is cut by protruding metal. Medical assistance is required. t' At 1300 torus level rises above 5.5 feet. The SRV discharge is now covered with water and reactor depressurization is begun using the SRVs By 1330 the reactor has been depressurized to 150 psig and reactor water level has been restored to + 20 inches using available core spray pumps. Torus level is 5.8 feet. An alarm is received indicating that a ground fault has been detected on the common neutral lead of the Division A 125/250 V DC distribution system. Plant staff responds and isolates the grounded circuit. By 1400, torus level has recovered to 7 feet and drywell temperature, 185*F and falling. Radioactive releases have started decreasing. Drywell radiation level, which had peaked at 7x 104 R/hr hac now decreased to 2 x 104 R/hr. A flood alarm for the D core spray pump room is annunciated at 1430. Personnel respond and find that contaminated torus room water is leaking
, around the water tight door into the cubicle. Radioactive releases have now i'
decreased to a level corresponding to 50 mR/ hour at a distance of three miles from the reactor. At 1500, the main stack monitor reading has decreased to 3 x 105 cps and is still falling. Torus. water level has increased to 8.3 feet. Drywell tem-O U perature is down to 160'F. ,. At 1530, the main stack monitor readings drop abruptly from 2 x 10 4cps to normal values indicating that torus room water level now covers the torus break. Reactor pressure is stabilized at 90 psig and reactor water level is being held at + 20 inches. Conditions now support a de-escalation to Site
' Emergency or Alert status.
At 1600, the exercise is terminated.
.g .A%
5.2-3
)
~
_r-u. Oct;ber 17, 1985 SECTION 5.4 SIGNIFICANT EVENTS TIME LINE 1985 NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION Emergency Classification Time Scenario Event Expected Actions None -0800 Initial Conditions Maintain normal operation
Unit 3 at full power

Power generation equipment operating satisfactorily

Safety systems operable None -0810 Condenser punctured by Dispatch personnel to investigate damaged high pressure problem at condenser (Event No. 1) oxygen bottle Declare UNUSUAL EVENT

Reactor scrams on low

Noty offsite agencies condenser vacuum

Perform internal noti-fications

Turbine trips on low Maintain reactor water level condenser vacuum between 0 and +45 inches

Condenser hotwell level begins to decrease UNUSUAL EVENT -0825 Condensate pump trips due to low level in condenser hotwell

Feedwater pumps trip on low suction pressure

Reactor vessel water level decreases rapidly UNUSUAL EVENT -0827 Reactor vessel water level falls Operators open an SRV below -48 inches to prevent overpres-

MSIVs close surization of reactor

HPCI starts in accordance with

RCIC starts procedures.
5.4-1 e
1 Emergency Classification Time Scenario Event Expected Actions _ UNUSUAL EVENT -0830 Torus leak develops Dispatch personnel to locate torus leak
Torus water low Try to restore torus water level level alarm occurs UNUSUAL EVENT -0845 Torus room flood alarm Declare ALERT level occurs

Make offsite notifications

Perform internal notifications

Activate Technical Support Center

Activate Operations Support Center

Activate Emergency Response Teams ALEl< f -0930 HPCI room flood alarm occurs RCIC room flood alarm occurs ALERT -0935 Torus water level Investigate other possible ways to reduced to 5.5 feet depressurize the reactor that do (SRV discharge pipes not involve the torus or the con-are now uncovered denser.
and relief valves can-not be used to de-pressurize reactor) HPCI turbine trips Maintain reactor water level with RCIC ALERT -0940 RCIC turbine trips 5.4-2 O O O .
T= p< J -
/
Emergency Classification. Time Scenario Event- Expected Actions ALERT -1015 , Fire alarm indicates fire _ Fire Fighting Group responds to the' fire on El. 135 ft of the reactor (Event No. 3) building-NW corner They notify control room that MCC 30B38 (E334-R-B) is fully engulfed in flames. l' and request offsite fire fighting assis-tance-Local. fire company responds ALERT -1020 Fire causes power failure Declare SITE EMERGENCY for the ECCS trip units
Notify offsite agencies
.
Perform internal notifications.

Dispatch field monitoring t.eams

Activate Emergency Opetutions Facility

Activate Muddy Run News Center

Activate Headquarters Emergency Support Center-SITE EMERGENCY -1028 Main stack Hi-Hi radiation alarm SITE EMERGENCY -1030 Standby liquid' control system Damage Repair Group dispatched to pump discharge header is investigate and remedy the problem fluctuating erratically (Event No. 4)
SITE EMERGENCY -1115 Torus water level has started Continue filling torus rising because torus room has filled to the same level as the torus SITE EMERGENCY -1145 Main stack high range radiation monitor reading exceeds 2 x 10 9cps. 5.4-3
Eoergency Classification Time Scenario Event Expected Actions SITE EMERGENCY -1205 Main stack high range radia- Declare GENERAL EMERGENCY tion monitor continues
Notify offsite agencies above 2 x 10 9cps

Perform internal notifications

Develop recommendations on offsite protective action indicated.
GENERAL EMERGENCY -1230
Control rod drive pumps Send Damage Repair Group personnel trip out on low suction to investigate and repair the pressure problem (Event No. 5)

A member of an HP survey Uninjured HP calls for medical group in the reactor assistance (Event No. 6) building falls, resulting

Search and Rescue /First Aid in an injury and radio- Group responds active contamination

Administers emergency first aid

Performs personnel contamination survey

Requests ambulance

Ambulance transports victim to designated hospital

Hospital treats injuries and controls the spread of radioactive contamination GENERAL EMERGENCY -1300 Torus water level rises Depressurize reactor using above 5.5 feet safety / relief valves 5.4-4 O O O .
t e October 17, 1985 i SECTION 6.0 t SCENARIO DATA l i 1985'NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION ; I ~Section Page lt l 6.1 PLANT MESSAGES. . ... .. . . . . . . . . . . . . . . . . . . 6.1-1 i t t 6.2. HEADQUARTERS SUPPORT MESSAGES . . . . . . . . . . . . . . . . . 6.2-1 ' 6.3 PLANT AND REACTOR SYSTEM VALUES . . . . . . . . . . . . . . . . 6.3-1 h. i i
+
1' ? 1 h t ) i- -6 5 1 k h t j 6.0-1 i
- . , , - - . - - - - . - - - . - -- - - . - - - ...--,...-.--,.-,,_.._,n.,,, . . , , - - , , - _ , , . , - - . - - -~ ~ - N
October 17, 1985 c . f ' - SECTION 6.1 s *
'g PLANT MESSAGES 1985 NRC OBSERVED EMERGENCY RESPONSE EXERCISE l l PEACH BOTTOM ATOMIC POWER STATION I .Section Page 4
PLANT EVENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6.1-1 4 ~
1. Condenser Shell Break . . . . . . . . . . . . . . . . . . . . . 6.1-1 i
.2. Torus Leak. . . . . . . . . . . . . . . . . . . . . . . . . . . 6.1-2 4
3. Fire-in MCC for ECCS Valves . . . . . . . . . . . . . . . . . . 6.1-3 I
'4. Standby Liquid Control Pumps. . . . . . . . . . . . . . . . . . 6.1-4
5. Control Rod Drive Pump Repair . . . . . . . . . . . . . . . . . 6.1-5

6. - Contaminated Injury . . . . . . . . . . . . . . . . . . . . . . 6.1-6 4~' 7. Ground'in DC Voltage Distr. System. . . . . . . . . . . . . . . 6.1-7 v- 8. Core Spray Pump Room.D Flood. _
. . . . . . . . . . . . . . . . . 6.1-8 ,
i I CONTROL ROOM MESSAGES'(CONTROLLER COPIES). . . . . . . . . . . . . . 6.1-9A i . CONTROL ROOM MESSAGES (PLAYER COPIES) . . . . . . . . . . . . . . . . 6.1-9B i l l3 N + b } i s e 4 E+ l
\
? i 4
i 6.1-i
+ -k ) EVENT NO. 1 CONDENSER SHELL BREAK Approximate. Time 0815 of Event:
Location: Unit 3 Turbine Building - El. 116 feet Problem: Workmen are preparing to hoist oxygen bottles up to scaffolding near one of the condenser cooling units when a bottle is dropped and the regulator valve breaks. The bottle rocketed into the southeast corner of condenser l shell B and water started flooding out. Both workmen have radioactive condensate soaked into shoes, socks, and lower pant legs and have tracked contaminatica to the phone location. A pool of water now covers the
-floor on the East side of the condenser pit and a 6-8 foot long tear of condenser shell B can be st!M. c damage to the condenser tubing can be seen.
Response: Responding operations personnel should call HP office to obtain assistance in decon of the workmen and the area outside the condenser pit and inform control room supervision of the damage. { Health Physics Department should set up radiological controls and surveys of the area. A safe method of removing the contaminated water should be developed and the condenser pit decontaminated. Then work on repairing the condenser can begin. Controller One on El.116 feet at the 4 uth- entrance to the con-Location: denser area near the generator-cooHug equipment. Q)lns{
-} g3 0 w / '\
s FOR CONTROLLER USE ONLY 6.1-1
EMERGENCY PREPAREDNESS DRILL -/ \-
.k,/ EVENT NO. 1- CUE CARD NO. 1-1 FOR: Workmen TIME: 0815 LOCATION: Unit-3 Turbine Building, El. 116 ft.
A A A ;,;. A A irk
A A A A A A A ;./ t. ;. A A ;. t. :.t A A;, A A A A A ;. A ; ;.;,;. A A A ;,;.;. A A A A A A A ;,;. ;. A*A ;. A ;. A A A A ;;.; A A ;. ;&*
THIS IS A DRILL
-DO NOT initiate actions affecting normal plant operations. **A A A A A ;. A ;. t. t. A ;. A a**A A ; ;. A A A ;. a**fd A ;. t. A A k*A ;. A A A ;, ;. A ;. ;. A A k*****+n k**A A A A ;. ;. ;.1. A A A ;. ;. A MESSAGE: This is a drill. ~
This is (workman's name). We've just had a bad accident in Unit 3 turbine building at 116 ft. elevation. An oxygen tank which we were hoisting up on the scaffolding dropped and broke. It was propelled into - the middle condenser and ripped open. -We've got water gushing out. (Coworker's name) and I are soaked from the knees down, but otherwise we're OK.
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THIS IS A DRILL . ******************************* :. ;. A t. A A A*********n A A ;. A .. h** A A A A A 1. A ,wc**** ****** a v) 6.1 EMERGENCY PREPAREDNESS DRILL
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i, s EVENT NO. 1 CUE CARD NO. 1-2
':x.,i FOR: , Operators responding to phone message TIME: 0815+
LOCATION: Unit 3 Turbine Building, El. 116 ft. [I A A A aaa;, A A A A A A A A aa-A A A A A;, A uc******* ;,; A A A A A ;,; A A A ; A A; A A;,; A A A A A A ;,1ck***** A A A A A A A A* THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
**+k**e+wnwc**************fewet ********1ck*-;, A 1, A A ;, ;, A 1,+*******fcA+a+wek**f+afck . MESSAGE:
Both workmen are soaked with condensate from the knees down. Water is pouring out of a 6-8 ft. tear in the Southeast corner of condenser shell B and a pool now covers the floor of the condenser pit. No visible damage has been incurred to the condenser tubing. The workers have tracked water to
-the phone locations. .s J ' fnwnwc**enwck**********fnwek************fnw+A*f+aa**********-*********** ******
THIS IS A DRILL
***********-k**fc******fnwc******fetektnwek****+* k****+k***f*M-k****f,*k***********
s 6.1-1B
I i i EMERGENCY PREPAREDNESS DRILL
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EVENT NO. 1 CUE CARD NO. 1-3 FOP.: HP. Technicians TIME: 0815+ LOCATION: Unit 3 Turbine Bldg., El. 116 ft.
***-;,;. A A A A; ;,; A ;,;, A ;,;, A A A A A A+/+k*fa;,;, A AA A A;d. A;. A A ;4 ;, A ;,;macA A A;. A A A A A A;,rA-/ctd.k&A+A-#
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
******** A A A A A A A A A A A !, A t, a A+,wwc** ! 1. ,wc*** A A A t A*i+;d A ;, A ;,,,;,; A A ta+kt+1de*,wcA+k-!+1d+k MESSAGE:
Dose Rates General Area of' Workers 1,600 - 3,500 cpm field Pit Area 3,500 - 6,500 cpm Floor Contamination at phone location 10,000 dpm/100 cm 2
. , , Worker #1 'I i' from knees up 1,000 - 5,000 cpm. 'd from waist down- 5,000 - 20,000 cpm Worker #2- g,ys# .from waist up 900 - 4,500 cpm from 6 down 4,500 - 18,000 cpm
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- >wwWl CAM *kNA"*'kSc$ A$ A A A A-A A A A A A A l+A~k'4"SC'ScA+INnwe$ RAW +Wnwr$dnNk'!<'lC'lnwd,WWN$,$dd, A A *- A+k,N A- THIS IS A DRILL ; I ******->nwe,wwci+;ce+k**-+,www+k****** ,w.w,******+ &rca+,wwmd+k*<ci+,wnwwemme<*
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E EMERGENCY PREPAREDNESS DRILL
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! \ 'N f EVENT NO. 1 CUE CARD NO. 1-4 .FOR: .HP Technicians TIME: 0815+
LOCATION: Unit 3 Turbine Bldg., El. 116 ft.
** A ;,; A A A A;ct. A A; A A A; AA;,; A; ;,; A;, A; A A A A A A A A A A a**;cA***xaA A ;,;, k*vcA-!ch***s A A A A ;, x+k**
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
**** A 1, A A A A A A A i, Aa a***fek**-!chewek*** A A A t, t, A 1 t, A**************** A :. . A 1, ; A A ;c*%e+k -MESSAGE:
Dose rates from workers (After clothing change) Worker #1 from knees up 250 - 500 cpm from knees down 650 - 830 cpm
'[ . Worker #2 from knees up 200 - 450 cpm from knees down 500 - 950 cpm ********;cs* wicks ** .wnwc**1cick*1cks****1ck****************ktcirk***A+k*** A t, : A M***-k ' /'N THIS IS A DRILL .i ***** ,wer****( *** tek***fex+,dk*f,+1,+k**fcA*
A A A tek**********************-A*kA+k****
6.1-ID a
-EMERGENCY PREPAREDNESS DRILL
' 5, -EVENT NO. .' 1 CUE CARD NO. 1-5 s._/
'FOR: HP Technicians TIME: '0815+ . LOCATION: Decontamination Area - *** A A ;. A A ;;,; ;, A ;.+k*******i, A ;. A A A A ;,;. A a t. A A A A ;, A ;, A A A A A ;, A A ;,;, A A A ;.a a k**;.;; ;. A A A A A A ;;,; ;ck .
THIS-IS A DRILL DO NOT initiate actions affecting normal plant operations.
******k***fek*A A . A A . A A h******* A . A A 1. A**-k**1ca+A*-;. t. ;, A ka*****1ch***f,+;. A 1. A ;. A a+A+k - MESSI_GE:
Do'se from decontaminated workers Worker #1 30 cpm Worker #2 35 cpm
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n EMERGENCY PREPAREDNESS DRILL
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CUE CARD NO. 1-6 EVENT NO.
?- .1 FOR: HP Technicians TIME: 0815+
LOCATION: Unit ~3 Turbine B16g., El. 116 ft., at condenser pit u A A A A ; A A A A A;. A;,; A A A A A A A A-;ana A+A A A; A;, AA A-** A ;. A A A-;,-fcA A A ;. A A A ;cA A A A; A A; A ;,;,;. A-k*f,+A** THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
****** Mart.1, t, A laa*******fa a aa A A A******-;cA+*******w, ; A A ;, A ;, A ,, a*c A 1 A A t, A A A A+>**1cx<
MESSAGE: Contamination levels in condenser
. pit after water removal: 20,000 - 30,000 dpm/100cm 2
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F 4 e a e I k AA6 (- --k 7 " 4 ^#, a, , , O ,% , O di ~ g THIS IS A DRILL
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EMERGENCY PREPAREDNESS DRILL
, .y ') . EVENT NO. 1 CUE. CARD NO. 1-7 %J FOR: HP Technician TIME: 0815+
LOCATION: Unit 3 Turbine Bldg., El. 116 ft. at condenser pit
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THIS IS A DRILL D0'NOT initiate actions affecting normal plant operations'.
. *****-A* aaaea ;, A A A Ainw, .ckf A A A 1. a***a e a a**ar****** A ; A A A A A +k***feck***w ; ;. A ;. A A A A ;.
MESSAGE: Contam'ination-levels in condenser-pit l after decontamination: 50 - 100 dpm/100cm 2 M b i I
***************,wn.-****f.+;cx***s+r****->***fnw+ea,wwwww+>***+****+wA A A A A ;. ;. t. ;.
THIS IS A DRILL
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4 - , EVENT NO. 2 TORUS LEAK I Approximate. Time 0830 of Event: Location: Unit 3 Reactor Building El. 91 feet-6 inches Problem: Personnel ' investigating torus water low level alarm become . aware while trying to open one of the watertight , doors to the torus room that level is rising rapidly in .. the torus room. fi -I l Response: Inform control room supervision of the situation; verify
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1 that doors from.the torus room are not leaking. l Controller One accompanying personnel- from the control room area. * [ Location:
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EMERGENCY PREPAREDNESS DRILL s ' . [q.
EVENT NO. - 2 CUE CARD NO. 2-1
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FOR: Personnel investigating torus low level alarm TIME: 0830 t LOCATION: Unit 3 Reactor Building, El 91 ft. 6 in. ; A A A;;, A A A A A A A A A A A A A A A A A; A A; A A A A A A A A A A A A A A A A A A A A AI, A A k**t A A A A A A A k**********f, A A A THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- *******fex-*****1cA A A aana******** ; ;, ;, A A-A A A A t, tc/+k****a ;, A A A A Ic******* a-k*****+A+***
MESSAGE: Rushing water is heard inside the torus room. Water tight doors are not found to be leaking. rs ,
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*************f&h********* Aaaa A ;, A A A ;, A Ick**-k*f+k**-;cich*****-k*********fch*****k*** .f 6.I-2A . _ _ . _ . _ - . . _ _ . _ _ _ . . _ - .._.~ ,,.___ _ _ _ . _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ . .
EVENT NO. 3 FIRE IN MCC FOR ECCS VALVES b -3 - Approximate Time 1015 of Event: Location: Northwest corner of Unit 3 Reactor Building El.135 feet Problem: Smoke detector alarms problem in the area. When Fire Brigade arrives, they find. heavy smoke pouring from MCC 30B38 (E334-R-B) and widespread flames breaking out. l Response: They determine that offsite assistance is required and request it. Fire is contained to the affected MCC and associated cabling. Controller One accompanying Fire Brigade team leader. One at the Locations: scene of the fire on El. 135 feet. One at security entrance to accompany local fire fighters. O FOR CONTROLLER USE ONLY s 6.1-3 s
, - . . - ~ . - . . . . - . - _ . . . . ~ .. - - - . . . . . . . -- . ---.. . - .. . . . . -. . .. -. . ~. ~
1 EMERGENCY PREPAREDNESS DRILL
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i; ' EVENT NO . 3 CUE CARD.NO. 3-1 - A ..
- FOR: Fire brigade team leader TIME: 1015+
LOCATION: . Reactor Building Unit 3, El. 135 ft.
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aa ;. A A A A k*****-k************-k******-wk***fewek**fcH+k*******4 A A ;, A A A A A A A ;<**a A A : k THIS IS A DRILL DO NOT in'itiate actions affecting normal plant operations. i
***************fcAth******************f*H", owe *** 4 A A A ;. A A A h****-H-*******1&h****
a MESSAGE: i 4 - Heavy smoke'is_ pouring from MCC30B38 (E334-R-B). Widespread flames are breaking out. !
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re EMERGENCY PREPAREDNESS DRILL
,m . / \ 's } 'swj EVENT NO. 3 CUE CARD NO. 3-2 FOR: Fire brigade team leader TIME: 1015+
LOCATION: Reactor Building-Unit 3,-El. 135 ft. i
** A A A A A A A A A A A A A A A A A A A A Aan A A A A A A AA A A A A A A A+A A A A A A M A A A A A A A A A A A A A A A A A A A A A A M%SM l t
THIS IS A DRILL i DO NOT initiate actions affecting normal plant operations. ! i A A A A A A A A A A A A a-A;, A A,o. A A A A; A A A M A;,;, A A a*** A;. A A A A A x;; A A A A;d ;. A A A A A A A A A A A , I [ MESSAGE: ,
.0ffsite fire fighting team has puti the fire out. MCC30B38 (E334-R-B) is completely destroyed.' \ !
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1 EVENT NO. 4 STANDBY LIQUID CONTROL PUMPS -- Approximate Time 1030
~ of Event:
1
-Location: Unit 3 Reactor Building - El. 195 feet west side Problem: Damage repair personnel find that the discharge side relief valve on SLC pump A is discharging and the discharge is striking the motors for both pumps. The B motor is soaked and will not start. The A motor is smoking and getting very noisy.
Response: Shut the pump down. Repair or replace the relief valve and get the motors dried out. Restore one pump to service. Controller One at El. 195 feet near the pumps. Locations: ( FOR CONTROLLER USE ONLY 6.1-4
.E_MF.RGENCY PREPAREDNESS DRILL 73
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.V, , EVENT NO. 4' ' CUE CARD NO.4-1 -- FOR: Damage repair personnel TIME: 1030+
1 LOCATION: Unit 3 Reactor Bldg, El. 195 Ft., near SLC pump
;, ; .. ;<aa aae r******* ;. ;, ;, A ;, a A 1. A A a******f+k**,w*********a a a a aa a A A A A sa A A aa A a?. ;. A a a A a THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
Aaa A A A a********fd.+;cA A t, A A A A A idow**aaaa ;. I,;. A A A1,+k1ca*fnwa****v,+A*fow*****-a*fdek* MESSAGE: .The discharge relief valve on SLC pump A is spewing liquid on both motors. The pump A motor is smoking and running. The pump. B motor is soaked. The area around the pumps is wet but not flooded. Relief valve discharge is estimated to be 1 or 2 gpm.
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***************at. ;. ; A A a*******< cuss !. :. ;. ; A A a************u+k***1cutna,ucunwass->*
THIS IS A DRILL f r^ *********fd. ,. : t. A a A aaa A ;, aaains A t. A A A A A A aaa A aa Ai.;, A A t. A A+a*fc**vek****f,+a4 t,;, A . A*1,+k
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EMERGENCY PREPAREDNESS DRILL r f EVENT NO. 4- CUE CARD NO.4-2
$ 0R: Damage repair personnel TIME: 1030+
LOCATION: Unit'3 Reactor Bldg, El.195 Ft., near SLC pump
*f. ;. ;. :. A A a**a A A A A A A **1cA+un*<***** A :. A : ;, A A********* A t. A ; ;, A A A A*a eauf.+****f+1, /, i. A i, A !. t.
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
**+h****************a A A A A 1. k******f. t. A A A A A !. A A A A A ;. A a*****f+h*fow+dsc***-1+1cA 1. A 1. A MESSAGE: Attempt to-start pump B does not succeed.
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, :s f l 4 - EMERGENCY PREPAREDNESS DRILL jk EVENT NO.-4 CUE CARD No.4-3 FOR: Damage . repair personnel TIME:ar1120 I,0 CATION: Unit 3 Reactor Bldg, El. 195 Ft., near SLC pump
***f, A A A A A ;, A A A ;,; A t ;,1, A A A 1. A A-k* A ;,;, A A :. A ;, A ;<*f,+A******-A+A-k1ca ;, A A A ;, a A ;, A A A A Atw,,-***er l
THIS IS A DRILL 4 DO NOT initiate actions affecting normal plant operations.
************1,+k****+k*** A i, ;. A A ;<e<*****+k***** A A A A t, A A A A t, h*-; A A 1. A ha i. A i A 1. A a A A 1,1, A A MESSAGE: Repairs completed on one pump and motor, i
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EVENT NO. 5 ; I CONTROL ROD DRIVE PUMP REPAIR 2-f N
h. - Approximate Time 1230 of Event:
4 . i
Location

Unit 3 Turbine Building- El. 115 feet - northwest corner g:
Problem: Control rod drive pumps have tripped out on low suction , pressure. While trying to restart, high differential r j pressure across the inlet filter is noted. 4 i Response: - Replace or bypass filter element. I 1 i a l 4 Controller ' One at El. 116 feet at the pumps. Locations: i i k I t, . ! i 1 l t T
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Q: ,. EMERGENCY PREPAREDNESS DRILL' pA 1 EVENT No. 5 CUE CARD NO. 5-1 s., EFOR:;i. Maintenance personnel TIME: 1230+
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LOCATION: Unit 3 Turbine Bldg., El. 115 ft., northwest corner 46; . y 4
************* A A A A A A k***w *$1ch****+ Hex A A A A A A A k******A+A**-a A A A A A A A A A AA A A a-** ?. S - .THIS IS A DRILL .x DO NOT initiate actions affecting normal plant operations. 'j a.**********1ch**A+********E******feierfch*fd********M+kich******A+******** A A A k** .-_yNESSAGEE ' High dif ferential pressure across inlet filter is observed while . g . attempting to restart ' pumps.
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**fcA+**********c+**1ck*********************** k**1&***********************Vekfch THIS IS A DRILL , ****1ck************-/ch***fd* ***********fele&ch**%+**************************+A*
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- EVENT NO. 6 CONTAMINATED INJURY Time: ,v1300 Location: Unit 3 Reactor Building - 'A' RHR Room 91 ft 6 in Elevation.
Problem: While surveying the 'A' RHR 91 ft 6 in elevation an H.P. Technician slips and falls into the sump pit which has the grating removed. As a result the H.P. Technician receives a serious laceration to the inner right thigh and an abrasion to the forehead. Response: The second H.P. Technician calls for medical help. The First Aid / Search and Rescue Group responds, performs first aid, surveys the injured H.P. , and surveys the general accident area. The injured H.P. is removed from the RHR Room, decon-ned, and transported to Harford Memorial Hospital (HMH), by ambulance.
' Controller One at HMH Locations: One at the RBCCW Rm (to stage the event)
One at guard house (for ambulance entrance and exit) r% Note: The RHR Event will be simulated in the RBCCW Room k' Controllers should observe:
First Aid Team response

First aid techniques and information transfer

Radiological controls at the accident scene and during various transports

Proper decontamination methods

Ambulance arrival at guard house

H.P. Technician interfacing with ambulance and hospital personnel

Radiological posting at the hospital

Ambulance and hospital release surveys

Ambulance and hospital staff release surveys (frisking) 4 p FOR CONTROLLER USE ONLY 6.1-6
. ') ' 'r',A y g i
m . EMERGENCY PREPAREDNESS DRILL
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v l : e EVENT No. 6
CUE CARD NO. 6-1
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FOR: Aux OSC TIME:12:45 To: Plant Survey Group Leader LOCATION: Unit 3 Reactor Building - El. 91 ft 6 in. A RHR Room
**** ,; ;,; A A A ,, A A A ;. ;. ;;.;. A ;, A A ;, A ;. A A ; A ;,;. ;. A A ;,;,;.; ;,;. A A A A ; ;;. A ;.;.;,;.;,1,;.;. A A A A A A A ;. A A ;,;. A A ;, c, A A y ,THIS IS A DRILL o ,
DO NOT initiate actions eaffecting normal plant operations. A A A A A A A A A A A A A A A A A A A A A A A A;; A &*4 A A A A A A A A A AA A A A;. A A A A A A A A A;, A A A A A A A A ; A A A A!. A A A A A A A ( MESSAGE: Send.two (2) H. P. Technicians to survey the Unit 3 A+C ' RHR Room 116' and 91'6" Elevations l
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6.1-6A
EMERGENCY PREPAREDNESS DRILL j EVENT NO. 6 CUE CARD NO. 6-2 v
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FOR: Uninjured H. P. Technician TIME:1300 LOCATION: Unit 3 Reactor Building - El. 91 ft 6 in A RHR Room
*a;. .;;;; ;,;;;;;;;;,; ;.1.;***a A;;;,;. ;;;;;. u !.aaa;;; ;;;aa;. Awaa;;;.z;;;;;;a A A; ;,;;&ae**
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
*;. ; ; ;. aa a**aa aa ; ;;. ;;;. ;;;; ; ;;. ;;;. ; ; ;. ;. ; ; ;; ;; :. ;;, ;. ;,;;; ;; ;; ;; ; ;. ;;;. t. ;; ; ; ;; ; ;;<**c->***
MESSAGE: This is (uninjured Technician's name), I'm calling from the Unit 3 RBCCW Room. I was surveying the A&C RHR Room with (injured H. P. technician's name) and he slipped and fell into the floor sump; he is conscious, dripping wet and has a bad cut on his right thigh, and an abrasion on his forehead. 6
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E rw EMERGENCY PREPAREDNESS DRILL X-) EVENT NO. 6 CUE CARD NO. 6-3
. FOR

First Aid / Search and Rescue Team TIME:1300 LOCATION: Unit 3 Reactor Building - El. 91'6" A

RHR Room
*********1ch**** ******** A A A A A ;, ;, A a*;, A ;, ; ;,+k********** A A A A ;, A ****fe-k*fcA+k**fe,cs*
THIS IS A DRILL DO NOT initiate actions affecting normal plan. operations.
*******1er, A A A A As A A ;,;;, A A A A A A A A k**** A A A 1,-a********fer****1d A ;, ;, ;, A a****+k*A+k*f,+A**
MESSAGE: The H. P. Technician slipped and fell into the floor sump in A RHR Room. He is conscious, wet, and has a severe laceration on the inner right thigh. Blood is pulsing from the wound. His forehead has an abrasion which is seeping blood. ! [] If taken Pulse: 102
-(,,/ Respirations: 24 Skin: Pale, cool Blood pressure: 96/70 Laceration: Right Thigh Abrasion: Forehead 4
Vital signs remain the same until reaching }&DI and they are as read by HMH staff
/ / / /
I .'
\. ~
FOR CONTROLLER USE ONLY
;,1,1,;. AA A A ; A A k**A; A ;,; A A ; A A A ;, A !, A A A A ; A ;,2******* A A A A A A A A A***-;,;,1,; A ;. A ;, A A ;<*v,; A ! A AA h*
THIS IS A DRILL m) g
== = x =Am =AmAm =Am = = = u m m a****m== = m*m -
6.1-6C
-,-n.- ,- , ,----.---..,,w ,-r ,- , - - - - - -
i EMERGENCY PREPAREDNESS DRILL . y.~ b)
+ EVENT NO. 6 FOR: H. P. Technician with First Aid Team CUE CARD NO. 6-3a TIME:1300 LOCATION: . Unit 3 Reactor Building - El. 91 ft 6 in -
A RHR Room vekA-A A A A A A A A A A k***fca+*********1d&fcA********s+A+1.-*** ****fek****s-**s+fch***1& kick THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
*te:&tekks*****kM,ctekk*****s+***A4*******1dda-***ick*s+******?ck+****s-kM&.udet&k*
MESSAGE:
*
General Area Dose Rates 91'6" at Sump - 100-300 mR/hr
*
General' Area Floor Contamination 91'6" - 4K - 40K dpm/100cm2

Injured H. P. (wet coveralls)
Anti.Cs 40 mrad /hr Thigh Wound Area - 20 mrad /hr - p ~s (~ ) Injured H. P. (After coverall removal) head and hair - 20K cpm body - 10K-40K cpm area of thigh wound - 40K cpm nasal smear - 10K dpm with BC-4 10K cpm with RM-14
* *. Supply only, when taken FOR CONTP.0LLER USE ONLY ***metac.W&tek********1dekh*1 dad &tcs***************ia&k*1chidacs******s,be+kkWnWe*
THIS IS A DRILL
*************************ich*1dd.-*******************kwde****tekiddek****tek**ich*
k o 6.1-6D
~ EMERGENCY PREPAREDNESS DRILL
[X .
~/-
T I EVENT NO. 6. CUE CARD NO. 6-4 FOR: lH. P. Technician TIME:1300 LOCATION: RHR Sump Area A A A A;;;;;; A;;;;;;;; A A;;;; A A A;; A A A Aaa aa: A A A;;;; A;&****;;;; A A A;;,;;;;;aaa;;;;;; THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
*waa;;;, A A A A ;,;,;,;,;;cA A ;;;;;,1,; A A ;ch**a A;,;,;,;;cA; A A;,; A A A ;,;,;,;<**A ;,;,;,;;;;,1,;;;,;;; Ax-****
MESSAGE: (Supply if sample is taken) Gel. Scan Results pCi/ml MPC % MPC r~N CO-58 7.014N6 9NS 7.8 !,) _ 1C0-60 8.423N5 3N5 280.8 Zn-65 1.216N3 IN4 1216.0 CS-134 9.210N5 9N6 1023.3 Cs-137 2.213N4 2NS 1106.4 Total pCi/ml = 1.62IN3
' *** ,wekv<***************aa AA A ;, ;, A A A *** A ;, ;, ; ,, ; ;, A A A A ;, ;, ;, ;, ;, ;, ;, ;, ;, ;, ; ,, ;, A A A ;, A A ;, ; ;.1, ; ; ;, A ; ; a THIS IS A DRILL ****A A ; aa : A ;,;,;, a***********f ;;; A A A A ;;;<*** A A ;,;,1,;;, A ;,;<**a A A A ;;,;;,;,1,;; A A ;;,;,;;;, A ;,;,;.
I b V 6.1-6E
EMERGENCY PREPAREDNESS DRILL m, EVENT NO. 6 CUE CARD NO. 6-5 (]
. FOR: H. P. Technician TIME: 1300+
LOCATION: Radwaste Building - El. 135' Decon Area A ;,; AA ; A ;c* A; A A ;, A A A A A A;, A ;,; A ;, A A A A A A ;;,;, A ;,; AindkAA A A A ;,;, A ;,;;;,;,;, A A uf, A ;,;;; A A A;,;. ;;, A ;,;, A THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
***-;. A A A ;,;. A ;;,;cAaaaA A A ;,;,;,;, A Aa ;, A ;, A ;,;,;,;; A A A A A A A A AA A Aa-A ; A A A ;. A A A A A A A A A-x ; A A A A n****
MESSAGE: f Injured H. P. contamination levels af ter the first decon attempt
head and hair - SK cpm

general body areas - 4K - 10K cpm

area of thigh wound - 20K cpm

nasal smear - 2K cpm or dpm
/n\
Supply only if taken FOR CONTROLLER USE ONLY f.ed>******f<*******f+k**** A A A A A A k*f, A A A A Aa****A A A ;. A A A A A A A A A A A A A A A A A A A A A A kk THIS IS A DRILL A A A ;; A A A A A A A***fd. A ;,;, A A ;,;,;, A***********A A A A ;,;, A k******-kaa t ;, A A A A A A A ;. A ;,;, A A A A A****
\s 6.1-6F
____,____,.7-., -
-r -
EMERGENCY PREPAREDNESS DRILL p 9Vh -EVENT NO. 6 CUE CARD NO. 6-6 FOR: .H. P.. Technician TIME:1300+ LOCATION: Radwaste Building - El. 135' Decon Area
*****f, t,;,; A A ;,;;, A A ;,;,;, A ;,; a a* A A ;,;,; A t<**-;d,;. A ;; a A A ; k**-;;. A A ;,;,;,; A A A A k**A A ;,;, A a td&***A-k THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. ****** fad,-*******fand-tc**1,%Wawek**1. A A ;, A A k*********A t. :. A A :. A A A A *1,;,:,;, :<***14 A A A A :,:<
(
' MESSAGE:
Injured H. P. contamination levels after the second decon attempt
head and hair - 2K cpm

general body areas - IK - 4K cpm

area of thigh wound - 20K cpm

nasal smear - IK cpm or dpm
.g O a NsY
Supply only if taken FOR CONTROLLER USE ONLY
*4 A t, A A *inwek***********Vekfdd<********************Ewca A A A A ,, A A 1. A**f,-*fek***-r. ,, ,, A A A ,,
THIS IS A DRILL
***********fenw<**********fde/ddciclek*fd-************fnWdd A A ;, ,, ,, A **1ddnWe*** t A 1, I, A A A V
6.1-6G 1
EMERGENCY PREPAREDNESS DRILL
/m.<
Q ' EVENT NO. 6 CUE CARD NO. 6-7 FOR: H. P. Technician TIME:1300+ LOCATION: Radwaste Building - El. 135' Decon Area 1, A ;, A ;,;. A ;, A A ;,;. A ;,;. t. A A A A ,. ;,; A A A A ;,;,;,;. k*-;, A ;, A A A A A ;, A A ; A A A ; aa ta A A A A A ;. ;,;,;, kf,+A+weseddek* THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. A ;,;, a A A A ;.1, ;, A !, A A ;, ;. ;, A ;,;. ;. ;c**** fetch ******f,+A****-MdcA*;dch*fcA+;ctra . t. A A A a ;d.*k*f,;, t. A A A A a MESSAGE: Injured H. P. contamination levels after the third decon attempt
head and hair - <100 cpm

general body areas - <100 cpm

area of thigh wound - 10K cpm

nasal smear - 300 cpm or dpm
[-) (/ If any more decon attempts are tried, the contamination levels will remain the same as stated above.
*
Supply only if taken FOR CONTROLLER USE ONLY
**;. ;,;. ;,1,;, A t, A !. ;,;,;,;c*****************f. A t,;,;. ;, a A A A ;<*vek**-A A A A A A :. A ;. A A A aaa a A A A A A A A A A A A THIS IS A DRILL
-e 1,;,;. t. A ;. t. ;, A A A A A ;, A ;,-k*****f,;,;. t. A A A h******fa ;. A A ;,;. ;. t. A A A A ;,;. A A A** A ai, A ; A A ;, A A ;. A ;, ;, A A **** v 6.1-6H
EMERGENCY PREPAREDNESS DRILL .p 'i EVENT NO. 6 CUE CARD NO. 6-8 FOR: Ambulance Personnel / Hospital Staff TIME:1300+ LOCATION: Transport / Hospital
*** A A A A A A Mek*fek***fe!&k******1 cake. A !. /. /&******1dc*fe<**1cid&awa t. A A A Ainw+/wid***
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
***1ck** sick +***************ks***t&*******1&**** tad &tainwdnw&:c:&hsiciaidesst&M&
MESSAGE: The patient has a severe laceration on his inner right thigh and an abrasion on his forehead. He is contaminated with the following levels:
10K cpm in the thigh wound area

Supply vital signs from Cue Card 6-3 for Ambulance Transport P
()\ i
Vital-signs at HMH are as read by the staff

Supply only if the H. P. or First Aid Team Leader does not transmit this information to the ambulance /HMH Staff FOR CONTROLLER USE ONLY
**1cta***1dernuc*1a*1&ksick1dc*************1&kidars*******1dcs***1cictddes A A A A n .. .. :ctetsch THIS IS A DRILL *****************1ctdes&*******1ckstanuck*1d&:dc:nuc1&ks*****1cs******1dch**tek******
k 6.1-6I l l l
EMERGENCY PREPAREDNESS DRILL
. im i
s
. EVENT NO. 6 CUE CARD NO. 6-8a -FOR: H. P. Technician TIME:1300+
LOCATION: Harford Memorial Hospital
;,;. A A ;. A;,;,;,;. t. A ;. A A A A A A A ;,1,;. a a** A k******A+k*****v ;,;,;. ;. A-A A ;, A ; ;, A A ;, A A ;, A ;. A A*aa A A A A;. A r*
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
;, ;, A A ;, ;, ;, A ;, ;. A ;. t. ;. A . A 1. A** A A A ; ;. ;. A A A ; A A A a *****fer****fx+h********f,+,a+A+.a+x-r*****
HESSAGE:
'HMH first decon attempt reduces the thigh wound area to SK cpm Second decon attempt to 1K cpm Third decon attempt levels remain the same -, i XJ 5
FOR CONTROLLER USE ONLY
<,;,;, A r. ;, A ;,;, A ;,;,;, A ;. ;,;,;. A Aaea A A A ;,;.*a A 1,;. A A ; A-A A A ***aa t. A ;, A A***1,+*******1<**+k***;. A ;,;,; A p,, = = ;.= = = = = = =t. = A:ss+. - t. = ;...= =
THIS IS A DRILL
;ar,*****+*******+,s,*********
v 6.1-6J
EMERGENCY PREPAREDNESS DRILL i A)
;J 8
EVENT NO. 6 CUE CARD NO. 6-9 FOR: H. P. Technician TIME:1300+ LOCATION: Harford Memorial Hospital
**wk*-;,;,;,;,; A ;,;,;, A A ;. A ;,;,; ;,;,;,; A;, A ;, A ;,;. A A A <**s A ; A ;, A A A ;,;, A ;, A a*;d,;. A A ;,; ;;,;,;, A ;,;,;, A A A****
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. A A ,,,, A ;,;. A A ;,;. A A A A ;,;,; A A A A A ;,; AlcA A A ; A ; 1,;,;,;. A A ; ;; A A A A A ;,;. A A A A ;, A A A A ;,;, A A A A A A A A ; A A A A A !, A MESSAGE: Ambulance stretcher becomes contaminated during the transport to 1500 dpm/100cm2 . After first decon, the stretcher reads <100 dpm/100cm 2
' f% /
FOR CONTROLLER USE ONLY
***** a a a ;, ,, ,, a**** ;, ,, ,, ;. A A ************************************
A A A t, ;, A ;, A A . ;, ;, A ; A t, A THIS IS A DRILL
** A ; A a t A a******fgr******************** A A A A ;, ;, ;, ;, ;. .wr******************* ;. A I, ;,1, ;, A A
( / 6.1-6K
EVENT NO. 7 GROUND IN DC VOLTAGE DISTRIBUTION SYSTEM Approximate Time 1330 'of Event: Location: Control Building El.135 feet Problem: A ground fault has been detected in the neutral lead of the Division 125/250 V DC system. ~ Response: I&C' technicians start diagnostic procedures to find the grounded circuit without disabling safety circuits Controller One at the cable spread room. l Locations: FOR CONTROLLER USE ONLY 6.1-7
ENERGENCY PREPAREDNESS DRILL
,,m . , EVENT NO. CUE CARD NO. 7-1 1.._- 7 FOR: I&C Technician TIKE: 1330+
LOCATION: Cable Spread Room
** A A ;,;.t. A A A A A tek***** A A t, A A A t. ;,;,;, A ld<***$cA**w A A A A A ;. A ;,;,;, A ;,;, A A A*e A A A A 1 h**et***$+t**
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
*****$dnw<******at, A t, AaicA A A t, A t,inw,; A ,, A A t,; A**** ;,;, A t, A t. A A A A A A ,,;ct. ;,,,;, A ;,+;cA**$dde****
MESSAGE: Ground fault is at the common point in Division A 125/250 VDC
' system. ^. .
r 3'g,)
*$$**$4**$f*$fSe**$fSC$fSC$c!C*$4$$n St$,**$nW$$*$4SC*Wi+***$4$OWn4 A A A t, t,is$$8,*$O**$i$nW*$ 1, A A t,S $ A $ a O THIS IS A DRILL t *******************$ cts,****$cta,***$,-> A A A A A A A A A*$,*$,*$, A ;. A A A A &********** A A A A A A A A ;,*
b i 6.1-7A
r l
.p l ' b EMERGENCY PREPAREDNESS DRILL DRILL TYPE EVENT NO. 7 CUE CARD NO. 7-2 -FOR: I 6 C Technician TIME: 1330+
l LOCATION: Cable Spread Room [.
**M. a a a :&Mnwc********************1adc*******t.-***a a a a a a k****snwasa&k*1aaaac*** -
THIS IS A DRILL t DO NOT. initiate. actions affecting normal plant operations, n ************************** .******************* a a a a a a a k********Mowa+kenw<***
, . MESSAGE:.
l l- ! Ground fault is isolated to circuit 30C05A - the control circuit for reactor feed pump A turbine.
~\
l-l t l . ******************1ac*******1anwch***************<<***fch***Maar**************** TilIS IS A DRILL O ******************* *********************fnwac*************** A a a a Aa *********** L 6.1- 7B
- ~ _ . . , - - ~ ~ . _
EVENT NO. 8 CORE SPRAY PUMP ROOM D FLOOD \ Approximate Time 1430 of Event: Location: Core Spray Pump Room D, Unit 3 Reactor Building El. 91 feet-6 inches - northeast corner. Problem: Cubicle is flooded to a depth of about 10 inches and water can be seen leaking in from torus room around door seal. Response: Personnel who respond will have to decide whether to close off the core spray pump D cubicle or attempt to clean up the cubicle and stop the leakage from the torus room. Controller One accompanying personnel from the OSC. Locations: O FOR CONTROLLER USE O!4LY 6.1-8
EMERGENCY PREPAREDNESS DRILL m
-l '
1 EVENT NO. 8' CUE CARD NO. 8-1 FOR: -Operator TIME: 1430+ LOCATION: Core Spray Pump Room D Unit _3 Reactor Building, El. 91.5 ft.
************************************vek*********feuch**f. A A a a a a a A . A 1. A A A A A****1dc THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. *****fr*******fch**************fea A A A A***** A A A a A aa**a 1.1. A a***1d<***************1ck MESSAGE:
Cubicle is flooded to a depth of 10 inches. Water can be seen leaking in from torus room around door seal, k
******kkMckfdde*fdek****kidddddchkk**Me**kfde*********k*************Mr****1ddddde Tl!!S IS A DRILL *fdach**** ******1dadch*******************************1de*************1ek*****fdek 6.1-8A J
Time: 0800 NESSAGE FOR. Control Room SINULATED PLANT CONDITIONS: Normal Operation A A A A A A A A A A A A A A A A A A A A A A A A A A A A;. A A A A AA A A A A A AAA******f. A A A A A A A A A A A A A A A A A A A A A A A A A A THIS IS A DRILL DO NOT initiate actions affecting normai plant operations.
;. A ;. ; ;. ;. A A ;. t. t. t. A A A A A A A A ;. ;. A ;. t. ;. i. ;. ;. t. A ;. A A A ;. A A A A ;. t. ;. A ;. t. ;. ;. ;. t. ;. t. A Air;-&********f.-** A A ;. A A A ;. A NESSAGE: Initial conditions are attached.
\ l r i ACTION EXPECTED: t I l l FOR CONTROLLER USE ONLY , 1 1 6.1-9A l l
=
6 - u m Time: 0800
~
MESSAGE FOR Control Room i t t annnnnnnnnnnnnnnnnnnnnnnnnnnnnnnnnnnnnnnnnannnnnnnnnnnnnnnnnnnnnnnannnnnnnnn THIS IS A DRILL-DO NOT initiate _ actions affecting normal-plant operations. . ,
;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;,;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;a;;;;;;;;;; -i l
l
' NESSAGE: Initial Conditions are attached. r s
F h i 1
.P h
I 4 l L I I
?
i e 6.1-9B
l-l i I .' Time: 0800 1 '.I J MESSAGE FOR Control Room l' V SIMULATED PLANT CONDITIONS: Normal Operation - i i l
. :. :. :. ;. :. :. :. :. : : :. : :. ;. ; ; ; ; :. ;. :. : :. :. ;. :. : ;. ;. ; ;. : :. ;, ;. ; ; ;. : ;. : :. :. : : : aaa;. ;. : :. :. : : : :. : : :,
l THIS IS A DRILL l ( , DO NOT initiate actions affecting normal plant operations.
;. :. ; ;. :. : :. :. :. :. :. : ;. :. ::. :::.:.:. ::. ;;. :.;. :.;. 4 :.;. ;. zaa k*s. ::. :. :::.;;. :. ;.;.:ca-a-:ckk****
MESSAGE: Initial Conditions l- ! Units 2 and 3 are operating normally. Power generation equipment l is operating satisfactorily and safety systems are fully operable. Unit 3 is operating at full power and is scheduled to shut down for refueling in February. Unit 2 is at ninety-five percent power and has been running continuously since March. Initial plant and reactor system values for Unit 3 are presented in Table 1.
. Contractor personnel are engaged in replacement of the rolling g steel door for entrance to the radwaste building at el. 135 ft.
Other personnel are in the Unit 3 turbine building reinforcing the l, supports for the condenser compartment coolers. An I&E information notice was issued last week reporting that diaphragm cracks had been discovered in target rack safety / relief valves at two other stations. The vigorous low pressure area that brought moderate to heavy l' rains, which depleted nature's ' beautiful fall array in our ' area yesterday,'is still influencing our weather. It is centered over [ Scranton this morning and moving rapidly toward the Northeast, j into Quebec province. The trailing cold front should be through our area in a few hours, bringing rapidly clearing conditions. l This morning's blustery NE wind flow should veer to a more l: westerly ~ heading and reduce in intensity. High temperatures' i should reach 65-70*F. Tonight's moonlit skies will see temperatures drop to a low of 45'F by morning. Fair and 1 O 6.1-10A e
.g
.+ ,
Time: 0800
'-s.. LNESSAGE FOR~ Control Room .V); -
4 i THIS IS A DRILL DO'NOT initiate actions.affecting normal plant operations.
;;; ; ;;; ; ;;; ;;;;<**1. ;;, ;;;;;;;. ;; ; ;, ; ;,; ;;; ; ;;; ;. ;;;;;;;,;;;;; ;, ;;;;;;;;,; ;;;;;;. ;;;; ; ;
MESSAGE: Initial Conditions Units 2 and 3 are operating normally. Power generation equipment is' operating satisfactorily and safety systems are fully operable. Unit 3 is operating at full power and is scheduled to shut down for refueling'in February. Unit 2 is at ninety-five percent power and has been running continuously since March. Initial plant and reactor system values for Unit 3 are presented in Table 1.
Contractor personnel are engaged in replacement of the rolling steel . door for entrance to the radwaste building at el. -135 ft.
Other_. personnel are in the Unit 3 turbine building reinforcing the
,G supports for the condenser compartment coolers.
An I&E information notice was issued last week reporting. that
' diaphragm cracks- had been . discovered in target rack safety / relief valves at-two other stations.
The . vigorous . low pressure area that brought moderate to heavy rains, which depleted nature's beautiful fall array in our area yesterday,-is still influencing our weather. It is centered over Scranton . this morning and moving rapidly toward the Northeast', into ' Quebec province. The trailing cold front should be through our area in a few hours, bringing rapidly clearing conditions. This morning's blustery NE wind flow should veer to a more westerly heading and reduce in intensity. High temperatures should reach 65-70 F. Tonight's moonlit skies will see tempe-ratures drop to a -low of 45*F by morning. ' Fair and seasonable v 6.1-10B
1 4 j seasonable ~ tomorrow; highs in the sixties. The initial meteorological parameters are: , L
} Wind Direction North northeast (019 degrees) i Wind Speed 13 mph '
l Temperature 58"F
Delta Temperature -0.4*F >
I ACTION EXPECTED: l l^ j i ! l' i i
1 i I
! i
i i
i ! ! I 1 , i ! ! ? f L I ~[ f t. l I- i L f' i F 4 i 1 1 l L !. i I s i I. 1 l 4 l 1i r i FOR CONTROLLER USE ONLY i ? . l ( i i ; i 6.1-11A t i
_.. _ ._ _ _ _ _ . _ . . . . - - . . _ . . . _ . .._.y_._________._._.____ _ _ - - .
/g m >
5
?"- ' }
i tomorrow; . highs . in ' the sixties. The initial meteorological parameters are. j. i; Wind Direction North northeast (019 degrees) s
}. . Wind Speed 13 mph {
i Temperature 58'F , } .. Delta Temperature -0.4*F ; g
}' .,
t
i. !
1 :- i i 3 4 3 e f j.
$ }
1,- i.- l 4 i .
j. I l' [
1 f' i- p j' f 2 - t 4-
.I I
- i 4 , I I j; ; r; , k
I 1 .
4 I' i . 8 l I' l l-I J, . 4 l r 1- 6.1-11B j .s l o . .
TABLE 1
~ / INITIAL PLANT AND REACTOR SYSTEM VALUES Parameter Units Initial Value Reactor Vessel Water Level inches +25 Reactor Pressure prig 980 Reactor Power-APRM (avg) % full power 100 Core Plate Diff. Pressure psid 20 Total Core Flow lbs/hr x 10 8 102 Recirc. Loop A Water Temp. *F 520 Recire. Loop B Water Temp. 'F 520 .Drywell Pressure psig 0.6 Drywell Temperature 'F 129 Drywell Radiation R/hr 2 Containment 02 Concentration % 2.2 Containment Hz Concentration % 0 Torus Water Level feet 14.7 Torus Water Temperature *F 70 Reactor Building Pressure inches H 2O -0.5 Refuel Floor Vent Exhaust Rad Mon mR/hr 1.6 Drywell Vent Rad Mon (Gaseous)- cpm 900 Main Steam Line Flow lbs/hr x 10s 13.4 Main Steam Line Radiation mR/hr IP3
. ,O Feedwater Flow (total) lbs/hr x 10 8 13.4 b '- Condenser Hotwell Level inches 15 Condenser Vacuum inches Hg 29 Condensate Storage Tank level feet 37 Air Ejector Off gas Rad Monitor mR/hr 40 Main Stack Flow cfm 2P4 Main Stack Hi-Range Rad Monitor cps <1P5 Stack Gas Rad Monitor cps 25 Vent Stack Flow cfm 3P5 Vent Stack Exhaust monitor cpm 500 Reactor Bldg Vent Exhaust Rad Mon mR/hr 0.5 Radweste Duct Rad. Monitor
~
cpm 300 Standby Gas Treatment System Flow cfm 0 0 6.1-12A
I; , l-TABLE-1 f((7 L
~~
Parameter INITIAL PLANT AND REACTOR SYSTEM VALUES Units Initial Value t
. Reactor. Vessel Water Level. inches +25 ,
Reactor' Pressure psig 980= l l' Reactor Power-APRM (avg): % full' power 100 Core Plate Diff. Pressure psid 20 Total Core Flow lbs/hr x 10s 102 Recirc. Loop A Water Temp.
*F 520 ,
Recire. Loop B Water Temp. *F 520 l i DrywellLPressure- psig 0.6 ; Drywell Temperature *F 129 .; Drywell' Radiation-- ,
. R/hr 2 . Containment 02 Concentration % 2.2 ;
Containment H2 Concentration' % 0
.. Torus Water Level feet 14.7 Torus Water Temperature *F- 70 inches H 2O ~
Reactor Building Pressure -0.5 Refuel' Floor Vent Exhaust Rad Mon mR/hr 1.6
.Drywell' Vent Rad Mon (Gaseous) cpm 900 Main' Steam Line Flow lbs/hr x 10 8 13.4 Main Steam Line Radiation- mR/hr IP3. -Feedwater-Flow (total)' lbs/hr x 10 8 13.4 Condenser Hotwell Level inches 15 jJs_ -} ' Condenser Vacuum inches Hg 29 Condensate Storage Tank level feet 37' .
Air Ejector Off gas Rad Monitor mR/hr 40
. Main Stack Flow cfm 2P4 -l Ma: ' Itack Hi-Range Rad Monitor cps <1P5 'Stae6 Jas Rad Monitor- cps 25 Vent Stack flow cfm 3P5 Vent Stack' Exhaust monitor cpm 500 Reactor Bldg Vent Exhaust Rad Mon mR/hr 0.5 Radwaste Duct Red. Monitor = cpm 300 Staadby Gas Treatment Systen. Flow cfm 0 i
s 6.1-12B
i Time: 0810
' r"N l 3,~./ ). NESSAGE FOR Control Room -
l SINULATED j PLANT CONDITIONS: Normal operations i THIS IS A DRILL i DO NOT initiate actions affecting normal plant operations.
;;;;;;;;;;;;;;a;;;;;;;;;;;A;;;;;a;aa;;;;;A;;;;;;;k*****aa;;;;;aa AA;;;;;;;;;
I-f NESSAGE: Low condenser vacuum alarm is annunciated Reactor scrams Turbine trips i lU l l ACTION EXPECTED: Proceed with scram recovery in accordance with established procedures Declare UNUSUAL EVENT FOR CONTROLLER USE ONLY s I I 6.1-13A l l
Time: 0810 p ' MESSAGE FOR . Control Room-9
.\ ;;.t. ;;.;;;. ;;;;;;;;;;;;;;;;;;;;;;;;;. ;;;;;;;;;;;;;;;;;;;;;;;;;;;;4;;;; . ;;;;; . ;; . -THIS IS A.DRILLt -DO NOT initiate actions affecting normal plant operations. . ;;;:::::::::::::aaaa :::::: Kaaaaaa;;;;;;;;; :::::::azaaa;;;;.;;;;;;;;;;aaaaa MESSAGE: Low condenser vacuum alarm is annunciated Reactor scrams Turbine trips 5
6.1-13B
. - ._ . ,.~ . . . . . . - . - . _ ~
1
+
r m-y
.w . .
4
-Time: 0825
[ HESSAGE FOR Control Room ( O. . b,- -SIMULATED PLANT CONDITIONS: Reactor scram, low level in condenser hotwell i.
*f, A A; A A A A A A A A A A A A A A A A A A Al, A A!, A A A!, A A A**fcA A A A A A A A A A A A A A A A A A A A A A A A A-fcA A A A A,, A A A A A A . THIS IS A DRILL
t j DO NOT initiate. actions affecting normal plant operations.
I v
***fcA ;; l A ;,;,;,;, A A A A A A A k****f ;,;. A A A !, A ; A a; ****f, A A ;,1,;,; .. A A A A A A ; A ;, A A A A ; A A ; A A ; A A ; A ;,;,;,
HESSAGE: . Condensate pump trips , ! , . Feedwater pumps trip on low stktion pressure - i I
, s e
s i 4
,v s.m 4
f ACTION EXPECTED: Try to limit transient due to loss of feedwater. 4 I: , 4 i r h l
\ /
L i FOR CONTROLLER USE ONLY i - 1 % . g 6.1-14A > E, 1 L
,e -,.,-e, .,. ,,---.. u.. c.,...,,,.,,-.re,--,.-_m._.. . ,,.e..~.-m m. ,_.-m ..._,.,m-.~.._m., .._.,#,_.._.,--.y, orm -,y ,. . . , - -y. .,
Time: 0825
.s MESSAGE FOR. Control Room-k.
A;;;;AAAAAAAAAAAA;;AAA;;;AAAA;;;AAAAAAAAAAAAAA;;;AAAAAAAAAAAAAAAAAAAAAAAA;;; THIS IS A DRILL lD0 NOT' initiate actions affecting normal plant operations. AAAAAAA;;;AAAAAAAA;AAAAAA;;AAA;;AAAAAA;;AAAAAAAAAAAAAAAAAA;;AAAAAAAAAAAAAAAA IMESSAGE: Condensate pump trips Feedwater pumps trip on low suction pressure t 6.1-14B
j, , r
'h Time: 0830 "~ % -
MESSAGE FOR Control Room -
,s SIMULATED PLANT-CONDITIONS: Reactor scram, feedwater isolat' ed, MSIVs closed .t
. :. a ;. ;. ;. :. :. :. ;, ;. t. a ;. a ;. t. a a ;. ;. a ;. :. ;. a ;. a ;. ;. ;. : :. t. a a k***** ;. a a ; ;. a a a r ;. ;, ;. :. a a a ;. ; ;. a aa a a a a a ;. ;. a ; ;. a k THIS IS A DRILL i
DO NOT initiate actions affecting normal plant operations. l
;. ;. a a ;. ;, a a ;. ;. a a a t. a ;. a a a a a ;. ;. a a a a a k***aa aa a ;. a a a a a *********f, ;. a ;. a a a a a a ***a a a a a a ;. ;. a a a f \
MESSAGE: Torus water high/ low level alarm is annunciated [- n ( , 1 i i .' b
\
l i' l J
?,
s-1 l s t;r ACTION EXPECTED: Send personnel to find cause of torus water loss. I ( t-
,1 i
i FOR CONTROLLER USE ONLY. i i
; - be* s 6.1-15A h-r ,
L-e, r Time: 0830 MESSAGE FOR Control Room
'THIS IS A DRILL -DO NOT initiate. actions affecting normal plant operations. . hAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAksaAAAAAAAAAAAAAAAAAA - MESSAGE: Torus Water high/ low level alarm is annunciated .c I
t I l 4 9 r i
~!
a t I F l P b N ' s 6.1-15B j t i f f b d
.n---,-..,~,,.--.,~,a,-,--- .-. . _ . ._..,_,-._.,,,:
Time: 0845 MESSAGE FOR Control Room SIMULATED PLANT CONDITIONS: Reactor scram, condenser unavailable, torus leaking L
?
I
;. ;,;. A ;. A :. A A :. A .;. ;. A A ;. A : ;, A A ;, A A ;. A A A ;,;. ;,;. t. t. A ;<****** A A A ;, A ;,;+x-A A 1. A A***x-sn*,x+;ca+k*
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
;,;, A A A A A A ; A A ;. ;, A ;. ;. A A A A A A A A A A A A A A A A ;,; 1. A A ***f*********i.+kfch***-a-A A A ;, Aaa ; ;. t. ;. A ;,,. t. A MESSAGE: Torus room flood alarm is annunciated.
O G ACTION EXPECTED: Declare ALERT b FOR CONTROLLER USE ONLY x 6.1-16A
_ _ _ . _ _ . _ _ .. _ . . _ . ~ . _ _ _ - _ . . . _ . _ - __ ._. .___ _ _ _ _ . .___ _. _ __ _ _ _ _ _ . _ . _ _ _ _ _ _ .
. " , ' # t t
, s !
\
i y.- ' '. Time: - 0845~ t 4 ~ .
- MESSAGE FOR- - Control Room 4 ,; - - m _
i e f,
+
i e
. . . . . . . . . . . . . . . . . ., M M M MMMMMMMMMMMMMMF MM+M M M M M M ,., M M M M M M M 5 M ,., M M M M M .MMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMN THIS IS A DRILL '
DO NOT initiate actions.affecting normal plant operations.
,.,M ...MM,.,,.,,., .M,,..M,.,,.,,.,,.,,.,,.,,.,MMMM,..M,..MM,..M,..,M,.,,.,,.,,.,,...,.,,.,,.,,.,M,.....M,......,.,M,.,M,..MM,.,,.,,.. .M . . . , . , ,. . . .
? __ j -MESSAGE: Torus' room flood alarm is annunciated 4 e 1 a . L 4 A g k i 5 4 2 sf 'I , I 4 ) 4 + i x IT 6.1-16B
d Time: 0930 .t I MESSAGE FOR Control Room
- d -SIMULATED PLANT CONDITIONS: ALERT condition, torus and condenser unavailable ;. t. A AA A A A ;,;,;,;,;,;,1,;,;, A A A A A; A ; A A A ; ;,; A A ;,;,; A A A ; A ;,; A A A ;,;,;,; A A ;,;, A ;,;, A A A A***c A A ;;, A ;,;, A ;; A l
THIS IS A DRILL DO NOT-initiate actions affecting normal plant operations. A A A A A aan A A A A A A A A A A A A A A A A A A A A A A A A A A AA*fek**kk****fr/cair!rA A A A A A A A;r*****WA A A A A A A A A MESSAGE: HPCI room flood alarm occurs RCIC room flood alarm occurs m t d ACTION EXPECTED: 4 FOR CONTROLLER USE ONLY
6.I-17A -
4 t Time: 0930.
. s
MESSAGE FORI . Control Room J
a- -...............
-------------- A;;;;;;;;;;;;;;;;;;;;;.;;;;..;....... ...,, ., ,,,,, ,
i i THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. r A4;; A A A A A A A A A;;;;; A A;; A A A A A A A A A A A;*k% A A A A AkA A A k**4 A A A A A A A A A A A A;;;;; A A A A A A***
) . MESSAGE: HPCI room flood alarm-occurs RCIC room flood alarm occurs ,
s 9 - w a 6.1-17B i
l i Time: 0935 '
-r% . . 't. N~ /i MESSAGE FOR Control Room SIMULATED PLANT CONDITIONS: ALERT Condition, torus and condenser unavailable A ;;;; ; ; ; ; ;;;;; ;; ;;;; ;;;;;; ;;;; ; ;;;;; ; ;;;;;;-; ;;; ;; ;a;-*i ; ;;;;;; ;;;;; ;;;; ;; ;; ; a THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. ; ; ; ; ; ; ; ; a; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ;; ,, ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; a MESSAGE: HPCI turbine trip is annunciated \~
ACTION EXPECTED: Maintain reactor water level with RCIC. FOR CONTROLLER USE ONLY (,, 6.1-18A
. . . - - - ~ ,
3 , .~ , t b J f s _ Time: 0935 i t
n . t .
{ r . MESSAGE FOR' Control' Room : f e 1 s-a, . d
,.,-,.,M-------,. . . , . , - . , . ,.- -., . . , , . , , . , , . , , . ,, . , , . , , ... . , . , , . , , . , , . , -. , ..,.,,...,.,,.,,.,,.,,.,,.,,.,,.,,.,,...........,.,,.,--M,,c,.- - - ,.. ,., . . . .M . .. ---M s
D THIS IS A DRILL
- DO NOT initiate actions affecting normal plant operations. ,

4. , ,
. , . , , . , , . , - - , . , - , .6M,.,,..M6 . - .. . -M. .4MM . 4MM . . , . .5 M. M7E . .M- . . . . .... .
MMMMMMMM ,., - , .t g-
~M. --M .-,.,,.,,.,--MMD.,.,--...
L:. t a J
- MESSAGE: ' HPCI turbine trip is annunciated 3
- A 4 f e. k I' i I 1 T A r> !
^
L r . 3- $.*, V i*
1. _
f.' t-t , e 1' a. , i 1: 1; a 1: ! E I a. s 1 i I e k e > i i 4-L9 l'
- 6.1-18B ,
4-N.
1. -
j- i c' _ , - .
.5 ,na,-,,----...,.-- ?.+.w,.+wn,n-,,m.a.-,--
ew ~ , , r u e +-- a m- ,, .--,,n 4.n,---. . - - . . , + , . .. -,-~~a---+.,-+,----,----
Time: 0940 O t
\ .
MESSAGE FOR Control Room
' SIMULATED PLANT CONDITIONS: ALERT condition, torus and condenser unavailable, HPCI tripped . A ;. A A A ;. A A A A A !. A A A*A-k*A A A A A A aa A A A A A A !. A A A44*A*kM-*********A4*H A A 1. A A A A A k********
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
****** A A A A A a A
A*a a a a i. A A A A A A ***-l. A 1. A A A A A ak***************-inht************4s,nwrA-k MESSAGE: RCIC turbine-trip is annunciated m
.{ ACTION EXPECTED: Use all alternate injection systems to maintain reactor water level TOR CONTROLLER USE ONLY w 6.1-19A
..,c M ^' '
4 a.. % w, f- : 4-
, g Time: 0940 e .
!.< c MESSAGE FOR' ' Control Room E u 4 9 . 1 s v {; . .#3 et . . at. .at. .n ..............................
#3 at et an #3 s, et at neat n et#3a at at #3at etn atatn et at at #3 e, at an et at at etatn at atatatse#3etn#3n atetatetogn at et,.a. .n. 85 . . . n. .n. .n. n . . at. . .n. A . . at. . .n. at . . .at at 4 ,\
1 1' t T. e THIS IS A DRILL ; DO NOT' initiate actions ~affecting normal plant operations. i ( nr. 1.a.- -
.,......,..,..,....,.,.,.,,...,.,.,.,.k*.,..,.,.,.,.,,.,.A,...,.,.,.....,.,..,.,...,.,,.,.,.,..,..,..,..,.,.,.,.,.,...k***. ,
ennnnn en 53 s .3 n n e e 3 .t .t t t t e 55 e t o 4 5 en 5 e e .4 .t .3 3 e tn e enn 5 6 6 t .3 5n 6m 5n t 5 t t e t n .e ,l ' , 5:- ,
, >NESSAGE: RCIC turbine trip is-annunciated. :
4 + 4 > 4 o T r - 4 o 7. 4-
.) .
I 1 1 1 4 'l A
? .m 1 .,
i i 4 4e D 1" f 1 u 6.1-19B d i .ir > h
. i h '
a i l .! s ge ~ > 4 [
~ . i -~r , , , w- + <.,r - -
mn,,-,e,- ---., u _ .-.-~-,-, ~ ,,. _ ,, n , - ~ ,-,-- .n. - - . . - - - - , - - , - . - - , - , , - - . , . ~ . . '
.. _.. . .__ _ _ . _ . _ . . _ . _ . - _ . - _ , . _ . . _ . . _ . ~ . _ _m -.____. _ ._.
l Time: 1015 7,s
v. >
MESSAGE FOR Control Room SIMULATED PLANT CONDITIONS: ALERT condition, torus and condenser unavailable, HPCI and RCIC tripped. a a ;,;,;,;,;, A A A A A A A ;, ;, ; A ;, ;,;,;,;, ;, A ; A A A A ;, A ; A ;, A A A A ;, ;, ;,;,;, ;,;. A r*** A ;, A A a ; A A A a*fc;ck**e,-A A ;;, A A ;,;. . THIS IS A DRILL
DO NOT initiate actions affecting normal plant operations.
J.
,,;,;. A Ai, A ; A ; As a t, A A A A k*A a a aa ;; A ; A A ; A A A ;, A A A A A ;,;cr***fcA-r**-A-A ga ;, A A A ;,-aa ; A A 4 3;A_,*fcufc3 ' MESSAGE: Smoke detector alarm for the northwest corner of reactor building, El. 135 feet i
s 1
1. -
f a 4 ACTION EXPECTED: Fire Brigade responds to fire i i f 4 f FOR CONTROLLER USE ONLY 6.1-20A
)
, ,, . ...- -. . -. -.. ... - .- . - - - . . - . - ~ . . - - - . - - - . - _ . - _ . . . . - - . . ~ . _ . - - - - . .
l
-- Time

1015 e
i k ' MESSAGE FOR Control Room ,e i m f' i' I - ; ;; ; ; A A A ;.; ;.;. A ;. A A A ;, A ;. A ;,;.;. ;.;, A A A ; A ; A A A ;.t. A ;,;.;. A A ;. A A A A A ; A A A ;. A A A A A ; A A ;. A A A A A A ;. A A ;. A A ;. [ j . f .- L I +-
.THIS IS A DRILL
,t . . '.,, ;DO NOT initiate actions affecting normal plant operations, i i I A A A A A A A A A A A A A ;. A A A A A ;.;;. A A ;. A A ;.;.;,;, A ;.;.t A A A ;. ;,; A*** A ;.1. A A A A A A ;. A A A***********A A A ;. ; ;<* i
)
i-MESSAGE: -Smoke -detector alarm for the northwest corner of the Reactor ; li Building ^, El. 135 feet i. . . 1 ff i j. i' . t
^
1 I. i h i I: .i k . I 1
-j i y 6
I s i ', r 0 - i k i
: i 4 ,
i h j j- i . i
1. t i
4. h lj . i': l i l
1. !
d 6.1-20B !, 1 % 5 I i 6 4 i i ). o. ee - > 3 s i
4. y
- ,.-.--,..cn-~--.,,,v.,,-,,.,--,,,_n..._,.+,,,,,._,, ___ _.n__,-..--,_n,_ . --_nn......,_..--.. -n,n
Time: 1020 -[m \ MESSAGE FOR Control Room SIMULATED PLANT CONDITIONS: ALERT condition, major fire in progress
*1+McMddacMd&k*1dcMekidcMedekidekidanckt+ -kidekkiscMdadad&kend&kinkida.-:-A-Mwamek THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. **ica-sidencM&Mc:dde:cks*te:dd&Mcks***1de:d&:chica-***te:d+:ckh*1c:+Mac:dekicudek****s+:+k MESSAGE: ECCS trip units power failure is annunciated Main stack radiation monitor high alarm occurs -
N {'J x_- ACTION EXPECTED: Declare SITE EMERGENCY
-~ FOR CONTROLLER USE ONLY \
6.1-21A
- - - . , . _ _ _ _ _ , . -- - _. _ ,_ =. .- -
n n
/ >' ,
4 ~ ' Time: .1020 I. ,
) '
i'. Ng. MESSAGE FOR Control Room - "
J t A A A A A A A A A A A A A A A A A A A A A A A ;. A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A k* THIS IS A DRILL
. DO NOT' initiate actions.affecting normal plant operations. . A A A ;. A A A A A A A ;. A;. A A A A ;;;;. A A A A A A A A A A A kk**f.+A+A A A A A A AA A A A A A A;. A;. A A A A A A A A+>k**+k**
MESSAGE: ECCS trip units _ power _ failure.is_ annunciated Main stack radiation monitor high alarm occurs t i 9
's i '[
( I i.
$ )
I 5 4 i 6.1-21B l
.... - - - ..=. .
i l J
.' I i
Time: 1028 1 i MESSAGE FOR Control Room , - SIMULATED PLANT CONDITIONS: SITE EMERGENCY 1
l I
aa;, A;, A;, A A A; ;,; aa t, A A A ; A A A A A ;; A aakf+k**aa A A ; A*****1ct+;+Af*k****** ; A A A A k**a t A; A;. i I t i I THIS IS A DRILL l
f. .DO NOT initiate actions affecting normal plant operations.

- ****** a a-A e a a a A A ;, ; k************1+A*********************************f*********
t 1 4 4 ( i MESSAGE: Main stack radiation monitor high-high alarm occurs I l ! 1 i, i i t b 4 ]. r 4 4 i i- ACTION EXPECTED: i: .: u i i r t ) FOR CONTROLLER USE ONLY , P t
!~ 6.1-22A
l 1
Y, e f i: .
.. - . . = . . - - - . . , - - - - - ,
Time: 1028
, ; MESSAGE FOR- : Control' Room - AAAAA;;;AAAAAAA;;AAAAAAAAAAA;;AAAAAAAAAAAAAAAAA;;;AAAAAAAAAAAAAAAAAAAAAAAAAA ~
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. A A ;. A A A ;. ; ; ;;. ;.;, A ;;;.;. A tekt. A A ;.;;.;. A ;. A A A A A A A A A A ; ; ;. A ; .;. A ;;;. A A ;. A A A ;. A ;. A A ; ;.;; A ; ;. t A A ;. A A MESSAGE: Main stack radiation monitor high/high alarm occurs
~
1 E i -A f- : s 6.1-D r b ;
nm a a w- - - w- -- - - m--,--
-+m- . s.e a s 10 m3 --+u s u -A w & ,
Time: 1030 7~ (s MESSAGE FOR Control Room SIMULATED
+
PLANT CONDITIONS: SITE EMERGENCY, significant radioactive releases in . progress AAAAAAAAAAAAAAAAAAAAAAAAAAAAAA M M M *k***AAAAAAA MAAAAAAAAAAAAAick*aAAAAAAA 2 .. i l THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. A A A A A ;. Aa**Aaaa A A A A A A A A A k**a A A A A A A AA A A A A A A A A A A;, A A A A A k*********Aews-****+k** p. MESSAGE: SLC pump discharge pressure is. behaving erratically
~
i
.i
.-c-f
.s i.
4 ACTION EXPECTED: Send someone to check problem i i t . FOR CONTROLLER USE ONLY 6.1-23A
~--w-= - , -- w -,e ,, , , -- , ,w- , ,
2 Time: 1030 , t MESSAGE FOR . Control Room ,i
, AA AA AA A A A AA A A A AA A AAAAAA A AA A A A AA A AA A A A A A AA A AAAAAAA A A A A A AAA AAA AAA AAA AA AAAA A A A A THIS IS A DRILL .DO NOT initiate actions affecting normal plant operations. -AAAAAAAA;;;AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA MESSAGE: SLC pump discharge pressure is behaving erratically r -f G
l E' b 6.1-23B , I I i l l
-,,,a, ..-n-e,-,,-n,-,,,-r-- , , , ,
Time: - 1230 x Control Room V) MESSAGE'FOR SINULATED PLANT CONDITIONS: GENERAL EMERGENCY, major radioactive releases A;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;; THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ;-* ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; a ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ;-*
MESSAGE: Control drive pumps both trip out on low suction pressure d
\v/
e ACTION EXPECTED: Send personnel to investigate 4 2 FOR CONTROLLER USE ONLY v 6.1-24A i
, -r- -
f I
.i Time: 1230 i i
1 MESSAGE FOR~ . Control Room 1,;,;.;,;,;. A ;. A A A A A-;<*;,;,;, A ;. ;.;,;,;,; ;;,; :.;,; A ;.;. A ;.t. A ;, A A ;.;. A A ; A A ;.;. A A A AA A A ;. A kaAA A A A A A A A A ;. .wir*
.THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. .A ;. A A ;. ;. ; ;. ;. A ;. A A A ;. ;, A A A ;. ; ;, A A A A ;, A ;, ;. ;. A A ; ;. A *A ;. A A ; ;. I. ;. A ;. A A A ;. A ;. A ;. AaA ;. A ;. t. /. A A A A ; I. A,W.****
MESSAGE: ~ Control rod drive .. pumps both trip out on low suction pressure 4 e f a ' w r-9 s + 6.1-24B
Time: 1330 g.
\' NESSAGE FOR Control Room cd.
SINULATED PLANT CONDITIONS: GENERAL ENERGENCY, major radioactive releases A;; A A;. A;;;;;; A A A A A A A A A A A A A A A A;. A A A;c*a A A A; A A A A A A A A A A A A A A A A A!c***a A A A A A A A A A A A A A A THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. A A A A Aa- A A ;. A A A A A ;.;cA A A A A ; A A A A ; A A A A A A A A A A A A A ;. A A k****aa t, A A A A A A A Aa tc*****aea A A A A ;, a i l NESSAGE: Division A 125/250 V DC distribution system ground fault indica-tion activates n (V' ACTION EXPECTED: Send I&C technicians to clear the problem FOR CONTROLLER USE ONLY
'\.
6.1-25A
e. ,
2 l Time: 1330 .i i
. MESSAGE FOR. : Control Room \ l i
1
+;;. ; ; ;;;;;;;;. ; ; ; ; ;;. ;;; ;;;;; ;;;;;; ; ; ; ; ;;; ; ;;;; ;. ;;; ; ;;;; ;, ; ; ;;;;; ; ; ;;;;; ;;;;;;;
I THIS IS-A DRILL
,DO-NOT : initiate actions -af fecting normal plant operations. , ;;;;;;;;;.;;;;;;;;;;;;;aa;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;
1 l i
MESSAGE: Division A 125/250 V DC distribution system ground fault indication activates.
J
/
6.1-25B
Time: 1430 MESSAGE FOR Control Room
-y- )
g SIMULATED PLANT CONDITIONS: GENERAL EMERGENCY, radioactive releases decreasing G A ;,;. A A A ;, A A A A A A ;. A A A A ;, A A A A A A A A A ; 1.1. A ; ; A A A A ;c******** A ;; A ;,;, a A A ;,;c******v-a**a ; A A A A THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. A A A A ;, a a aa A ;,; A A ;,**********aa a aa;, A A aea a A cc************-A A ;, A A 1,;,;<*-A-A a A-a c ;, A Aa a a awa-a MESSAGE: D Core Spray Pump Room Flood alarm is annunciated j.m (w ACTION EXPECTED: Send Damage Repair personnel to correct the flooding condition FOR CONTROLLER USE ONLY
\
6.I-26A
r s .. . . . _ . . . _ . _ _ . . ~ . _ _ _ . _ _ _ _ _ . _ _ _ . _ _ _ . . . - _ . .. . _ _ _ _ _ _ _ _ _ .
+' ,. . , !?i _
j'- O
~
s -: - 1
* <t 2
2;
. Time: 1430.
2- ' MESSAGE'FOR~ Control ~ Room 4; j. i=
.$ a.n. ,.. n ,. . ..... . n n ,....n.n .a .n .n .n .n .n .a .n .n .n .e .n .n .,.no. . .n .nnnnnn . . n. n. ..n.n.n.n.nnnnnn ,. . . . . . . . n n n. n ,.. n n n n n a n n a n n n n o n n n n ,..nn.
L . THIS IS A DRILL { n j;.
~DO NOT initiate. actions affecting normal plant operations.
p n .n. . ***,.,,...,.....,....,.h*^,.-F,c,,.,,.,,...............,....,.......,...,.......,...,..,.........,.
.n .nnn .nnn . . n n oo. n . . n oo. n . .n .nnn .
d* i c MESSAGE: D Core Spray Pump Room Flood Alarm is annunciated 'h 1 kr 4 1 1 i~ ) y f - f t {', N f &s ~ 9J . a t i i ~.
i. :
i Y k l' 1 r- ?' h5 i.
.I
) f f . 6.1-26B
~ HEADQUARTERS SUPPORT MESSAGE DATE: 10/17/85 Time: 1030
. /m . $,)g MESSAGE FOR: MUDDY RUN NEWS CENTER
** A A ;. aa a t. A A A ;. A A A ;, A ;. ;. ;. A A A ;+A A A A A A ;;. ;. A !&A-k**i A A ;. A ;. l. A A A A A A A A ;. . A A ;.*A A A A A A A A A A A k THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
A A 1. A ;. A t. ; ;. A !. ;. A A A A A A ;. ;*A**e-*******+A+A*******-;dd.+A ;. A A 1. k********** A A A A A :. ;. A A A A CONTINGENCY MESSAGE MESSAGE:
- From NBC-TV news:
Please comment on reports that Peach Bottom Plant conditions are such that a core melt down is likely within the next 12 hours. ACTION EXPECTED: Submit request to Site Emergency Coordinator. FOR CONTROLLER USE ONLY v 6.2-1A
t HEADQUARTERS SUPPORT MESSAGE DATE: 10/17/85 Time: 1045
l p
( , MESSAGE FOR: EMERGENCY DIRECTOR
************v, A A A A A A A A A ;,;,1, A A A;, A ;;;,;, A A A;,;, A A A A A A A A;, A ;<*f, A A; A A!ck*A A A A A A A A A A A A A A+
THIS IS A DRILL l DO NOT initiate actions affecting normal plant operations. , **-;ch**A t,1, A A A;c;ca A A A A A A ;,;<*****fe,wch*-A A; A A4A A A,w, A A A;, A A A A A A A A A A A a-;c,w-A---A A A A A;, A-;ctrk .; CONTINGENCY MESSAGE MESSAGE: The Lieutenant Governor is requesting a visit to the TSC and a briefing of I plant status. State House press representatives will accompany him. A PECo i- . representative should be assigned to contact him. I 3 V ACTION EXPECTED: Submit request to Site Emergency Coordinator. a 1 FOR CONTROLLER USE ONLY , 6.2-2A 4 l 4
- - , - -m.- y y ,c _ _ ,, - - - . -,-c- - - - . m--., , , - , , , , , - , . , . , . .-,-,-.--,-,----.e --y- - - . - - - . - , . -
W-g .. 3
f d HEADQUARTERS SUPPORT MESSAGE. DATE: 10/17/85 Time: 1 0 t
.(.%) ) ' MESSAGE FOR: EMERGENCY DIRECTOR ** A A A A A A weA t A A A A A;cuck******A A A A A A A AicicA***kt-A*****+*****fcA-k***-1,-wek*-A A A A A A AA-k THIS IS A DRILL + , DO NOT initiat,e actions affecting t.ormal plant operations. . . . . . .. \ ********************* t. A A A A A A+************p ****************1ch****A !, A A A A **M*
CONTINGENCY MESSAGE 4-4 MESSAGE: J' A call has been received from a panicked nearby resident requesting help. A family member who was outside when the public alert sirens came on has started vomiting and there is fear of higit radiation dose exposure. Her name is Mrs. J. Litsko. Telephone 301-365-2954. , T
. (m - ~ '4 _'
2
\ >
w , y N ACTION EXPECTED: Submit request to Site Emergency Coordinator.
',; ~ '
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\
FOR CONTROLLER USE ONLY
~
I 6.2-3A . : t
, ,- ,g.,--eg-- n- , . ,w w,-,-- -,,- -, ,-,, - -n-,,.h-~0,- n-,--,-n-, - ,-.,,,--,..,,,,-w. , , , , , . - , , - . . - - , - - - - - , - , , - - -
HEADQUARTERS SUPPORT MESSAGE DATE: 10/17/85 Time: 1125 MESSAGE FOR: EMERGENCY DIRECTOR A;. A A A A A A A;; A A A A A A A A; A A A A A A A A A A A A A A A A;;;;;; A A A A;; A;;;;; A A;;, A A A A A A A A A A A k***** THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. A;. A A AaaaAAAAA A A A A A A A A A A AA A A A A A A A A A A A A AaaA A A A A A A A A A A A A A A A A;, A A A A A A A A A A AA A A A A A CONTINGENCY MESSAGE MESSAGE: Ten additional HP technicians are required to assist site personnel. O) t v ACTION EXPECTED: Submit request to Site Emergency Coordinator. FOR CONTROLLER USE ONLY O 6.2-4A _2
, :/ 'i HEADQUARTERS SUPPORT MESSAGE DATE: 10/17/85 Time: 1130 (O
V MESSAGE FOR: HEADQUARTERS EMERGENCY SUPPORT CENTER
****v,; A A A A A Ai, A;,;. A aaa a A; A AA A A ; A A A A A ; ;; A t<***-A A A A;, A;;,; A A A A cac******,we ;;. A ; ea;dc***
s THIS IS A DRILL DO NOT irIitiate actions affecting normal plant operations. A
******vcA ;, A aaA 1,,,; A A A+k****aaA A A A tek******aa A A A A aaaA+;<**** A A Aaa A-;ck*',dek*fecF,c**
CONTINGENCY MESSAGE MESSAGE: A phone call has been received from a hysterical resident who has heard that there is a fire consuming the fuel and there is going to be a large release like they-had in England. l k}t l' > i l l ' A i l(%a) . 1 y a
's ACTION EXPECTED:
Submit request to Site Emergency Coordinator.
.a-p FOR CONTROLLER USE ONLY .V -s 6;2-5A % v 4
. . HEADQUARTERS SUPPORT NESSAGE DATE: 10/17/85 Time: 1230 7 s, ! b- %_/ ^
HESSAGE FOR: EMERGENCY DIRECTOR
; ;, ;, ;; ; ;, ;, ; ; ; ;, ; ;, ;, ; ;, ; ; ; ;, ; ;a ; ; ; ;, ;, ; ; ; ; ; ; ; ;, ; ;, ; ; ; ; ; ;, ;, ; ; ;, ;, ; ;, ; aa ; ; ;ww,wcufg, ; ;, ;, ; ; ; ;-sch 'THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. *******a a a; ; ; ;dek*****fekt. ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ;a ; k***f, ; ; ; ; ; ; ; ; ; ; ; ; ; a* ; ; ; ; ; ; ; a a ; ;
CONTINGENCY MESSAGE MESSAGE: T'here is an immediate need for 15 RM-14 Friskers at PBAPS. Units should be purchased or borrowed from supporting organizations. Please obtain 20 additional Scott air packs. [ .'\, _. ACTION EXPECTED: Submit request to Site Emergency Coordinator.
/"'% FOR CONTROLLER USE ONLY 'l%)4 6.2-6A
i i O
-( HEADQUARTERS SUPPORT MESSAGE DATE: 10/17/85 Time: 1245 -MESSAGE FOR: HEADQUARTERS EMERGENCY SUPPORT CENTER . aAA A A A A A A A A A A A A;;;; A A A A A A A A A A A A A A A A A A A A A A A A;; A A A A A r. A A A A A A A A A A A A A A A A A A A A AA A A THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
A A A A A A A A A A A A-A- ,<*****!ca+/cA-A A A A A A A A A A A A AA A A A A A A AAA A A A A A;. A A A AA A A A A A A ;c CONTINGENCY MESSAGE MESSAGE: A call has been received from an angered local resident who claims her valuable race horse was injured by a barbed wire fence when spooked by PECO's sirens. She has threatened to sue the company.
-Her name is Ms. Peabot Atpowst.
Telephone: 301-679-9700
-r O \
t s ACTION EXPECTEDi FOR CONTROLLER USE ONLY J- ' .Is 1 6.2-7A E-. w . , _ . -- -t-r ~ --e -* - , - - - - - -- . ---r - - - - -+ + - -- -e *<=-
, .. . . ... - - - . . _ . _ __.. _. . m . _ . _ , . _ _ _ _ _
[. s
- HEADQUARTERS SUPPORT MESSAGE DATE: 10/17/85 Time: 1300 c NESSAGE FOR: EMERGENCY DIRECTOR 4
1
********************fetow&k*1drk*er ; ; ; ; ; ; ; ; ; ; a; ; ; ;;; ; ; ; ; ; ; ; ; ; ; ; ; ; ; a ; ; ; a ; ; ; ; a w -
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
*fdd&k****1dc****th********; ;; A ; ; ; ; ; ; ; ; ; ; k*-A-k***-k**fd&; a a a ; ; ; ; !&k*f&k*** ,hhM l' CONTINGENCY MESSAGE HESSAGE:
A call has been received from a Lieutenant of the Pennsylvania State Police. lie would like to coordinate road blocking status with a PECo representative in Philadelphia. In particular, can PECo direct all its traffic to and from PBAPS area through a' single checkpoint? i-i t.
\
4 ACTION EXPECTED: 1 Submit request to Site Emergency Coordinator. 1 i r' 1 i' , 4 t 1-I 1. FOR CONTROLLER USE ONLY s
, 6.2-8A 'T T-FF'-1 %T4wy1 47=# ww a-&-ar*w?---+-m-r'+'-t-M-- ?+P-- "" *d+-*w_e--e --r--* ~w& ----^'-*-wmM ?v T*T'v-----MTP**e^+ e
i l I l HEADQUARTERS SUPPORT MESSAGE DATE: 10/17/85 Time: 1320 ,
/~'s _ l ! 1 L. l MESSAGE FOR: EMERGENCY DIRECTOR *** A;; A A A A A A A A A A A A A A AA A A A A A A AA A A A A A A A A A A A;;; A A ;, AAA A A A ;.; k** A A A A A aa******+*A-k THIS IS A DRILL TO NOT- initiate actions affecting normal plant operations. , A A A A A A k*****1HrA-A-A-A- A A A A A A*** t****M h A A A A A A A a***A-A-k*******1dnibWrkfA A A A k*A-k*****
CONTINGENCY MESSAGE
. MESSAGE:
Headquarters engineering support is needed to devise supplementary radwaste processing methods. Temporary system and storage tanks should be sent to PBAPS as soon as possible. There are at least a million gallons of con-taminated water that will have to be pumped out of the Unit 3 reactor building. i Ia%./ Q)-. 3 ACTION EXPECTED: Submit request to Site Emergency Coordinator.
;/ FOR CONTROLLER USE ONLY Y])
6.2-9A
HEADQUARTERS SUPPORT HESSAGE DATE: 10/17/85 Time: 1340 MESSAGE FOR: EMERGENCY DIRECTOR
~.s AAAAAAAAAAAAAONAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAlk*kkkkk THIS IS A DRILL DO NOT . initiate actions affecting normal plant operations.
A A A A A A A A A A A-a A A A A A A Aaaaa a;;. AA A A A A A k********t A A A A A A A AA A A A a r**A A A A A A A A A A A A A* CONTINGENCY MESSAGE HESSAGE: Headquarters support is needed to expedite the following purchasing requirements: 3,500 anticontamintion suits and hoods 7,500 pairs of rubber gloves 1,000 rolls of 2-in. masking tape v
)
ACTION EXPECTED: Submit request-to Site Emergency Coordinator. FOR CONTROLLER USE ONLY t
\
6.2-10A
HEADQUARTERS SUPPORT' MESSAGE DATE: 10/17/85 Time: 1430 (p.).- - MESSAGE FOR: EMERGENCY DIRECTOR
%J ***** A A A A A A A A A ;.-**** A 1. A ;. ;. ;. A A A ;. ;. A A A A;<**f. .1.1. A A t. A A 1. ;. t. A 1. A A A A A A k*****A+A*A+A-;c****
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
****-h***A A ;. Aa A AA A A k************f. A A A*atr** ;. A ;. Au e ;. t. ;;; a A*A A A A A A A A A A A A A ; ;;. A A+**
CONTINGENCY MESSAGE MESSAGE: Construction _ personnel are required to erect a temporary wooden storage building, with 150,000 cu ft storage capdeity. Building will be used to store emergency equipment . enroute to PBAPS and is to be erected near the North Substation. f~~) . I J-
%d ACTION EXPECTED:
Submit request to Site Emergency Coordinator. FOR. CONTROLLER USE ONLY .f' ss 6.2-11A
HEADQUARTERS SUPPORT MESSAGE DATE: 10/17/85 Time: 1500 . ym I i MESSAGE FOR: EMERGENCY DIRECTOR t /- ' %J
;. ;, ;. A A ;. A ;, A ;, ;. t. ;. A A ;. ;, ;, ;. A ;, A A A A A A A A ;. ;, ;. A !. A A ;, ; A A ; ;. . ;, A A A ,. A A A A A A A ;. ;, ;. A A ;. A ;. A ;, ;. t. ;, A ;. A A-*f,-r THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
A A ; ;. A ;. t. ;. ;,;. A A A A A A AA A A A A ;. ;. A ;ck*as t a aaa A ;,;,;, A AA ;, A ;. A ;. A ;. A ;. A A ; ;. A A ; A A A A A A A ;<****f,+k** CONTINGENCY MESSAGE MESSAGE:
-A robot is needed that can negotiate through the water tight doors. The unit must be operable by remote control with no trailing cables. \s ACTION EXPECTED:
Submit request to Site Emergency Coordinator. FOR CONTROLLER USE ONLY
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6.2-12A
HEADQUARTERS SUPPORT NESSAGE DATE: 10/17/85 Time: 1515
A.
( . MESSAGE FOR: EMERGENCY DIRECTOR aa;;AAAAA;;aAA;;;;;;;;;;;;;;;;;;;A;;;;;;;;;A;;;;;;;;;;;;;;;;;;;;;A;;;;;;;AA THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
f. A Aa A A A A A A A A A A trf.; A;; A A A A A;;;; A;;;;ca-ara-Maa A A A;; AtrA A A A A A: A;;;;rA-kH;;;!.;;
CONTINGENCY MESSAGE NESSAGE: Headquarters QA/QC support is needed to inspect emergency repair methods for the torus and approve welding in progress on the condenser. ACTION EXPECTED: Submit request to Site Emergency Coordinator. FOR CONTROLLER USE ONLY 'U 6.2-13A
,, . . . . . . . .- .. . - . _. - . - - . , . . - ~ _ . . .
T
. j~i HEADQUARTERS SUPPORT MESSAGE. DATE: 10/17/85 Time: 1030 i - P, MESSAGE FOR: MUDDY'RUN NEWS CENTER . ;;;;;;;;;;;;;;;;;;;;;;;;;;;;*;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;aa;;;;;;;;;
THIS IS A DRILL i DO NOT initiate actions affecting normal plant operations.
- ;,1,1, ; ; ; ; ; ****** A+A-a a ; ;, ; ; ; ;, ;, ;, ; ;, ; ; ; ; ; ; ;, ; ;, ; ; ;, ; ;, ; ;, ;, ;, ;, ; ;, ;, ;, ; ;, ;, ; ; ;, ;, ;, ; ;, ; ; ;, ;, ; ; ; ; ; ; ; ; ;
MESSAGE: [ From NBC-TV News. Please comment on reports that Peach. Bottom plant conditions are such that a core melt down is=likely within the next 12 hours. ) '. p
, a N
me> 6.2-1B
HEADQUARTERS ~ SUPPORT MESSAGE DATE: 10/17/85 Time: 1045 l s ,a . II MESSAGE FOR: EMERGENCY DIRECTOR
--\v)
AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA THIS IS A DRILL
.D0 NOT initiate actions affecting normal plant operations.
AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA;;AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA
. MESSAGE:
The Lieutenant ' Governor is requesting a visit to - the TSC and a briefing of i
! plant status. State House press representatives will accompany him. A PECo representative should be assigned to contact him. i i
t s v J t. l t v 6.2-2B i r , , ,, -,,mw. ., , --w . - - - m -+c-,,,m-. ,,,, -- ---.r--. . - - - -
--~-i- e- 7
i HEADQUARTERS SUPPORT MESSAGE DATE: 10/17/85 Time: 1120
.,;~.I // MESSAGE FORi : EMERGENCY DIRECTOR
N,_J .
;EANES$$;ANS$$$ESA;EEENASAA;;EEEAA$5S$$;AESSEAAAAAddd$$$d;E$A;$$$Ad$;;EEEAS THIS IS A DRILL .'DO NOT_ initiate actions'affecting normal plant operations. ;;;;;;;;A;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;A;;;;;;;;;;;A;;;;;A; MESSAGE: .A call'has been received'from a panicked nearby resident requesting help. A' family member who was outside when the public alert sirens came on has started vomiting and there is fear of high radiation dose exposure.
Her name is Mrs. J. Litsko. Telephone: 301-365-2954
' O; ;s j . \J '
bt 6.2-3B
, , . - . . ~ .. _ . + HEADQUARTERS SUPPORT MESSAGE- DATE: - 10/17/85 Time: 1125 MESSAGE FOR: EMERGENCY DIRECTOR .(b .
i l THIS IS A DRILL ' DO NOT -initiate. actions affecting normal plant operations.
**-;. ;. :. :. ;. ; ;. ; ;. ;. :. ;. ;. :. ; ;. ; ;. :. :. :. ; ; ;. :. :. : :. :. ;. :. ; ;. : :. ;. ;,1 ;. :. ;. : :. ;. :. :. ;. ;. ;. ;. ;. : : ;. ;. ;. ; ; ;. ;.
MESSAGE: Ten additional HP. technicians are required to assist site personnel.
/
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l' i l' r I: oo o 6.2-4B 1 i e ,,.-,..,._,-,-,--r,--m,,.-,m,---,.-- ..-e.-,--,,_--,-,-.,. _m_ . . -,,m.m_m,,..%- ,,,,,-,,_~,-,...---,.w---
_ :;.sc,5. 1 4a., &' , ) o
'M :! - A- HEADQUARTERS SUPPORT MESSAGE DATE: 10/17/85 Time: 1130 .f y. - (v i l MESSAGE'FOR: - HEADQUARTERS EMERGENCY SUPPORT CENTER i
I ); THIS IS A DRILL.
'DO NOT. initiate actions affecting normal plant operations. ;. ; ;. ; ; ;. :. ;. :. :. ; ;. ; : ;. ;. :. :. ; ;. :. ; ; ;. ;. ; ;. ; ;. ; ; ;. ; ; ; ;. ; ; ;. ; ; ;. ; ;. ;. ; ;-kt. ;. ;. ;. ; ;. ;, ;. ; ; ;. ;. ;. ; ; ; a a a ; ; ;. ; ;. ;. ;. ; ' MESSAGE:
A phone call has been received from a hysterical resident who has heard that there is a fire consuming the fuel and there is going to be a large release like they had in England. y b. L l' a b' 1
..l b
6.2-5B
. . - _ _ - , _ . . - _ . _ . _ . _ . _ _ - - _ _ _ _ _ . . _ _ ~ _ _ _ ._.. , _ _..__ _ , . _ .. _
HEADQUARTERS SUPPORT MESSAGE- DATE: 10/17/85 Time: 1230
\.v _J .
MESSAGE FOR: EMERGENCY DIRECTOR THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: There -is an immediate need for 15 RM-14 Friskers at PBAPS. Units should be
, purchased or borrowed from supporting organizations.
Please obtain 20' additional-Scott air packs. 's ~-
)
O 9
^ . /
6.2-6B
]
e W. l \ HEADQUARTERS SUPPORT MESSAGE DATE: 10/17/85 Time: 12:45
.% f A/ _
MESSAGE FOR: HEADQUARTERS EMERGENCY SUPPORT CENTER THIS IS A DRILL-DO NOT ' initiate actions affecting normal plant operations.
;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;a;;;;;;;;;;;;;;;;;;;;;;;;;;
HESSAGE: A call has been received 'from an angered ' loc al resident who claims her valuable race horse was injured -by a barbed wire fence when spooked by PECO's sirens. -She has' threatened to sue the company.
.Her name is Ms. Peabot Atpowst.
Telephone: 301-679-9700 xs [. L t
.\
6.2-7B 9
9 A. . HEADQUARTERS SUPPORT MESSAGE DATE: 10/17/85 Time: 1300 i
( '
/ . s,/ ~ . MESSAGE FOR: EMERGENCY DIRECTOR ;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;u*****
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: A call has been received'from a Lieutenant of the Pennsylvania State Police. He would like to coordinate road blocking status with a PECo representative (in Philadelphia. In particular, can PECo direct all its traffic to and from PBAPS area'through a singel checkpoint? O V - 6.2-8B
- HEADQUARTERS SUPPORT MESSAGE DATE: 10/17/85 Time: 1320 -a MESSAGE FOR: -EMERGENCY DIRECTOR A;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;
THIS IS A DRILL DO NOT- initiate actions affecting normal plant operations.
, *;;;;.;;;;;;;;;;;;;;;;;;;;.;;;;.;;;;;;;;;;;;;;;;;;;;;.;.;;.t.;;;;;;;;;;.;;;;;;;;;;;
MESSAGE: Headquarters. engineering support is need to devise . supplementary radwaste processing. methods. Temporary system and storage tanks should be sent to PBAPS as soon as possible. There are a t. least a million gallons of contaminated water that will have to be pumped out of the Unit 3 reactor-
-building. ./ -J t
I i , i ( 6.2-9B L_ .
b -- l-
'5 L-p 10/17/85- Time: 1340 HEADQUARTERS SUPPORT MESSAGE- DATE:
V!m.
' -(,/ \'
r> p -MESSAGE FOR: EMERGENCY DIRECTOR r-A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A ; A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A--Aa THIS IS A DRILL
'DO NOT initiate' actions affecting normal plant operations.
AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA;;;AAAAAAAAAAA
' MESSAGE:
Headquarters support is needed to expedite the following purchasing requirements: 3,500 anticontamination suits and hoods 7,500 pairs of rubber gloves , 1,000 rolls of 2-in. masking tape ! i b t e O 4 t 6.2-10B
r
.M.
W, et.v-:
n
, -HEADQUARTERS SUPPORT MESSAGE DATE: 10/17/85 Time: 1430 -( m).
33 .
. MESSAGE FOR: EMERGENCY DIRECTOR AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAkAAAAAAAAAAAAAAAAAAAAAAAAAAAA THIS IS A DRILL' DO NOT initiate actions affecting normal plant operations.
y - M ; A A A;,;. A A;;;. A A A A A A A A A;. A A A A A A A ;,;, A;,;. A A A;; ;,; A A A A A A A A A ;. A A ;, A ;; A A A A A A;,;,;,;;, A A A A; 1, MESSAGE: Construction personne1' are required to - erect a temporary wooden storage building, with 150,000 cu ft storage capacity. Building will be used to store emergency equipment enroute to PBAPS and is to be erected near the North' Substation.
.o J
6.2-11B
g _ '
. - HEADQUARTERS SUPPORT MESSAGE DATE: 10/17/85 Time: 1500 (w
NESSAGE FOR: EMERGENCY' DIRECTOR AA;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;; THIS IS A DRILL DO NOT. initiate actions affecting normal pittat operations. MESSAGE: A robot is 'needed that can negotiate through the water tight. doors. The unit must be operable by remote control with no trailing cables. nv t t L t , i I i ,O
\
6.2-12B i l i r l
[E
(
, HEADQUARTERS SUPPORT MESSAGE DATE: 10/17/85 Time: 1515 ' i,s) ~N MESSAGE FOR: EMERGENCY DIRECTOR THIS IS A DRILL DO NOT -initiate actions affecting normal plant operations.
MESSAGE: Headquarters QA/QC support is needed to inspect emergency repair methods for the torus and approve welding in progress on the condenser. 0-G V 6.2-13B
INDEX FOR PLANT AND REACTOR SYSTEM PARAMETERS VS TIME GRAPHS (OCTOBER 17, 1985) Parameter Units Graph Number N- -Reactor Vessel Water Level inches IB, 2 Reactor Pressure _ psig 1R Reactor Power-APRM (avg)
~ % full power 3 Core Plate Diff. Pressure psid 4R Total Core-Flow lbs/hr x lo s- 4B - Recire. Loop A Water Temp. 'F SR Recirc. ' Loop B _ Water Temp. *F 5B-Drywell Pressure psig 6, 7B Drywell Temperature "F 7R Drywell Radiation R/hr 8 Containment 02 Concentration % 9 Containment Hz Concentration % 10 Torus Water Level feet 11G Torus Water Temperature 'F 11R Reactor Building Pressure inches H 2O 12 Refuel Floor Vent Exhaust Rad Mon mR/hr 13 Drywell Vent Rad Mon (Gas) cpm
Main Steam Line Flow lbs/hr x lo s 14R Main Steam Line Radiation mR/hr 15 Feedwater Flow (total) lbs/hr x 10 8 14B Condenser Hotwell Level inches' 16 Condenser Vacuum inches Hg 17 n Condensate Storage Tank Level feet 18 Air Ejector Off-gas Rad Monitor mR/hr 19 (ss)
Main Stack Flow cfm 20 Main Stack Hi-Range Rad cps 21 Stack Gas Rad. Monitor cps 22 Vent Stack Flow cfm 23 Vent Stack Exhaust Mon mR/hr 24 Reactor Bldg Vent Exhaust. Rad Mon mR/hr 25 Radwaste Duct Rad. Monitor cpm 26 Standby Gas Treatment System Flow cfm 27
'* Graph not provided 6.3-1
f [~ 3 7 i ) ! ! ! / w/ V V PLANT AND REACTOR SYSTEM VALUES VS TIME (OCTOBER 17, 1985) l Parameter Units 0800 0810 0810 + 0811 0813 0815 Rrector Vessel Water Level inches +25 +25 +35 +45 +45 +40 Resctor Pressure psig 980 980 940 930 925 920 Recctor Power-APRM (avg) % full power 100 100 0 0 0 0-Core Plate Diff. Pressure psid 20 20 20 20 20 20 Total Core Flow Ibs/hr x 10 6 102 102 60 20 5 5 Recire. Loop A Water Temp. 'F 520 520 520 520 520 520 Recire. Loop B Water Temp. *F 520 520 520 520 520 520 Drywell Pressure psig 0.6 0.6 0.6 0.6 0.6 0.6 Drywell Temperature *F 129 129 130 130 130 130 Drywell Radiation R/hr 2 2 1 1 1 1 Containment 02 Concentration % 2.2 2.2 2.2 2.2 2.2 2.2 Containment H2 Concentration % 0 0 0 0 0 0 Torus Water Level feet 14.7 14.7 14.7 14.7 14.7 14.7 Torus Water Temperature *F 70 70 70 70 70 70 Re=ctor Building Pressure inches H 2 O -0.5 -0.5 -0.5 -0.5 -0.5 -0.5 Refuel Floor Vent Exhaust Rad Mon mR/hr 1.6 1.6 1.6 1.6 1.6 1.6 Drywell Vent Rad Mon (Gas) cpm 900 900 900 900 900 900 Main Steam Line Flow lbs/hr x 10 6 13.4 13.4 3.5 2.7 1.2 1.1 Main Steam Line Radiation mR/hr IP3 IP3 100 50 25 20 8 Ferdwater Flow (total) Ibs/hr x 10 13.4 13.4 3.5 2.7 1.2 1.1 Condenser Hotwell Level inches 15 15 14 13 11 9 Condenser Vacuum inches Hg 29 29 0 0 0 0 Condensate Storage Tank Level feet 37 37 37 37 36 36 l Air Ejector Off gas Rad Monitor mR/hr 40 40 30 10 10 10 Main Stack Flow cfm 2P4 2P4 2P4 2P4 2P4 2P4 Main Stack Hi-Range Rad cps <1P5 <1P5 <1P5 <1PS <1P5 <1P5 Stack Gas Rad. Monitor cps 25 25 25 25 25 25 Vent Stack Flow cfm 3P5 3P5 3P5 3P5 3P5 3P5 Vent Stack Exhaust Monitor cpm 500 500 500 500 500 500 Resctor Bldg Vent Exhaust Rad Mon mR/hr 0.5 0.5 0.5 0.5 0.5 0.5 Radwaste Duct Rad. Monitor epm 300 300 300 300 300 300 Standby Gas Treatment System Flow cfm 0 0 0 0 0 0 6.3-2 1
(- p ( j\
\
l Q ,]
\ ,Y PLANT AND REACTOR SYSTEM VALUES VS TIME (OCTOBER 17, 1985)
Parameter Units 0825 0825+ 0827 0830 0845 0900 Reactor Vessel Water Level inches +25 +8 -48 0 +25 +25 Reactor Pressure psig 920 920 920 1090 950 1040 Reactor Power-APRM (avg) % full power 0 0 0 0 0 0 Core Plate Diff. Pressure psid 20 20 20 5 2 2 Total Core Flow lbs/hr x 10 6 4 2 0 5 4 4 Recirc. Loop A Water Temp. *F 520 520 520 520 510 500 Recire. Loop B Water Temp. *F 520 520 520 520 510 500 Drywell Pressure psig 0.6 0.6 0.6 0.7 1.0 1.2 Drywell Temperature *F 130 130 130 132 134 136 Drywell Radiation R/hr 1 1 1 1 1 1 Containment 0 2 Concentration % 2.2 2.2 2.2 2.2 2.2 2.2 Containment H2 Concentration % 0 0 0 0 0 0 Torus Water Level feet 14.7 14.7 14.6 14.5 13.5 12 Torus Water Temperature *F 70 70 70 70 73 76 Reactor Building Pressure inches H 2 O -0.5 -0.5 -0.5 -0.5 -0.5 -0.5 Refuel Floor Vent Exhaust Rad Mon mR/hr 1.6 1.6 1.6 1.6 1.6 1.6 Drywell Vent Rad Mon (Gaseous) cpm 900 900 900 900 500 200 Main Steam Line Flow lbs/hr x 10 6 0.9 0.9 0.8 0 0 0 Main Steam Line Radiation mR/hr 20 20 20 20 20 20 Feedwater Flow (total) Ibs/hr x 10 8 0.9 0 0 0 0 0 Condenser Hotwell Level inches 3 3 3 3 3 3 Condenser Vacuum it.ches Hg 0 0 0 0 0 0 Condensate Storage Tank Level feet 31 29 29 28 22 16 l Air Ejector Off gas Rad Monitor mR/hr 10 10 10 10 10 10 Main Stack Flow cfm 2P4 2P4 2.8P4 2.8P4 2.8P4 2.8P4 Main Stack Hi-Range Rad cps <1PS <1P5 <1P5 <1P5 <1P5 <1P5 Stack Gas Rad. Monitor cps 25 25 25 25 25 25 Vent Stack Flow cfm 3P5 3P5 2.2P5 2.2P5 2.2P5 2.2P5 Vent Stack Exhaust Mon cpm 500 500 700 700 700 700 Reactor Bldg Vent Exhaust Rad Mon mR/hr 0.5 0.5 0.5 0.5 0.5 0.5 Redwaste Duct Rad. Monitor cpm 300 300 300 300 300 300 Standby Gas Treatment System Flow cfm 0 0 8P3 8P3 8P3 8P3 6.3-3 1
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PLANT AND REACTOR SYSTEM VALUES VS TIME (OCTOBER 17, 1985) Parameter Units 0915 0930 0940 0945 1000 1005 Reactor Vessel Water Level inches +25 +25 +25 +20 +5 0 Reactor Pressure psig 1060 1060 1055 1050 1045 1045 Reactor Power-APRM (avg) % full power 0 0 0 0 0 0 Core Plate Diff. Pressure psid 2 2 0 0 0 0 Total Core Flow 8 lbs/hr x 10 3 3 3 2 0 0 Recire. Loop A Water Temp. *F 490 480 473 47G 460 457 Recirc. Loop B Water Temp. *F 490 480 473 470 460 457. Drywell Pressure psig 0.7 0.4 0.3 0.2 0.2 0.2 Drywell Temperature F 138 140 140 140 140 140 Drywell Radiation R/hr 1 1 1 1 1 1 Containment O2 Concentration % 2.2 2.2 2.2 2.2 2.2 2.2 Containment H 2 Concentration % 0 0 0 0 0 0 Torus Water Level feet 10.5 7.5 5.1 5 4.9 4.9 Torus Water Temperature *F 76 76 76 75 74 74 Reactor Building Pressure inches H 2 O -0.5 -0.5 -0.5 -0.5 -0.5 -0.5 Refuel Floor Vent Exhaust Rad Mon mR/hr 1.6 1.6 1.6 1.6 1.6 1.6 Drywell Vent Rad Mon (Gas) cpm 400 200 100 100 100 100 Main Steam Line Flow Ibs/hr x 10 8 0 0 0 0 0 0 Main Steam Line Radiation mR/hr 20 20 20 20 20 20 Feedwater Flow (total) lbs/hr x 10 8 0 0 0 0 0 0 Condenser Hotwell Level inches 3 3 3 3 3 3 Condenser Vacuum inches Hg 0 0 0 0 0 0 Condensate Storage Tank Level feet 13 10 8 7 4 3 Air Ejector Off gas Rad Monitor mR/hr 10 10 10 10 10 10 l Main Stack Flow cfm 2.8P4 2.8P4 2.8P4' 2.8P4 2.8P4 2.8P4 Main Stack Hi-Range Rad eps <1P5 <1PS <1P5 <1P5 <1P5 <1P5 Stack Gas Rad. Monitor cps 25 25 25 25 25 25 Vent Stack Flow cfm 2.2P5 2.2P5 2.2P5 2.2P5 2.2P5 2.2P5 i Vent Stack Exhaust Mon epm 700 700 700 700 700 700 Reactor Bldg Vent Exhaust Rad Mon mR/hr 0.5 0.5 0.5 0.5 0.5 0.5 Radwaste Duct Rad. Monitor cpm 300 300 300 300 300 300 Standby Gas Treatment System Flow cfm 8P3 8P3 8P3 8P3 8P3 8P3 6.3-4 i,
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i 1 PLANT AND REACTOR SYSTEM VALUES VS TIME (OCTOBER 17, 1985)
Parameter Units 1015 1020 1030 1045 1100 1115 Reactor Vessel Water Level inches -25 -37 -70 -112 -145 -187 Reactor Pressure psig 1045 1045 1040 1035 1030 1020 Reactor Power-APRM (avg) ,
% full power 0 0 0- 0 0 0 -
Core Plate Diff. Pressure psid 0 0 0 0 0 0 Total Core Flow lbs/hr,x 10 8 0 Or 0 0 ' O .,, O Recire. Loop A Water Temp. *F 450 447 440 430 420 S'410 Recire. Loop B Water Temp. *F 450 447 440 430 , 420- 420 r Drywell Pressure psig 0.8 1.1 1.3 1.3 1.3 1.3 Drywell Temperature *F 160 170 180 190 190 ,f 190' Drywell Radiation R/hr 2 3 5 10 20 ,30 Containment 02 Concentration _ % 2 1.8 1.6 1.4 1.2 1 Containment H 2 Concentration e r % 0 0 0 0 0 0 Torus Water Level feet 4.8 4.8 4.8 4.8 4.8 4.9 Torus Water Temperature QF 76 78 80 82 83 84 Reactor Building Pressure 16ches H 2O -0.4 -0.4 -0.4 -0.45 -0.5 -0.5 Refuel Floor Vent Exhaust Rad Mon mR/hr '. 1.6 1.6 1.6 1.6 1.6 1.6 Drywell Vent Rad Mon (Gas) cpm 100 100 100 100 100 100 Main Steam Line Flow 8 ~0 0 0 0 0 0 lbs/hr x 10 Main Steam Line Radiation , mR/hr 20 20 20 20 20 20 8 Feedwater Flow (total) Ibs/hr x 10 0 0 0 0 0 0 Condenser Hotwell Level inches 3 3 3 3 3 3 Condenser Vacuum inches Hg 0 0 0 0 0 0 Condensate Storage Tank Level feet 1 0 0 0 0 0 l Air Ejector Off gas Rad Monitor mR/hr 10 10 10 10 10 10 Main Stack Flow cfm 2.8P4 2.8P4 2.8P4 2.8P4 2.8P4 2.8P4 Main Stack Hi-Range Rad cps <1P5 <1P5 1.7P6 3.5P6 7P6 3.5P7 Stack Gas Rad. Monitor cps 25 300 1P4 2P4 4P4 2P5 Vent Stack Flow cfm 2.2P5 2.2P5 2.2P5 2.2P5 2.2P5 2.2P5 Vent Stack Exhaust Hon epm 700 700 700 700 700 700 Reactor Bldg Vent Exhaust Rad Mon mR/hr 0.5 0.5 0.5 0.5 0.5 0.5 Radwaste Duct Rid. Monitor epm 300 300 300 300 300 300 Standby Gas Treatment System Flow cfm 8P3 8P3 8P3 8P3 8P3 8P3 6.3-5
n i 1 8
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PLANT AND REACTOR SYSTEM VALUES VS TIME (OCTOBER 17, 1985) Parameter Units 1120 1130 1145 1200 1215 1230 Reactor Vessel Water Level inches -195 -210 -250 -270 -280 -285 Reactor Pressure psig 1015 1005 985 960 935 910 Reactor Power-APRM (avg) % full power 0 0 0 0 0 0 Core Plate Diff. Pressure psid 0 0 0 0 0 0 Total Core Flow lbs/hr x 10 6 0 0 0 0 0 0 Recire. Loop A Water Temp. *F 407 400 390 380 370 360 Recire. Loop B Water Temp. *F 407 400 390 380 370 360 Drywell Pressure psig 1.3 1.3 1.3 1.3 1.3 1.3 Drywell Temperature 'F 190 190 190 190 190 190 Drywell Radiation R/hr 100 300 SP3 7P4 7P4 7P4 Containment O2 Concentration % 1 1 1 1 1 1 Containment H2 Concentration % 0 0 0.1 0.3 0.7 0.7 Torus Water Level feet 4.9 5 5.1 5.2 5.3 5.4 Torus Water Temperature *F 85 85 86 87 88 89 Reactor Building Pressure inches H 2O -0.5 -0.5 -0.5 -0.5 -0.5 -0.5 Refuel Floor Vent Exhaust Rad Mon mR/hr 1.6 1.6 1.6 1.6 1.6 1.6 Drywell Vent Rad Mon (Gas) cpm 100 100 100 100 100 100 Main Steam Line Flow lbs/hr x 10 6 0 0 0 0 0 0 Main Steam Line Radiation mR/hr 20 20 20 20 20 20 Feedwater Flow (total) lbs/hr x 10 6 0 0 0 0 0 0 Condenser Hotwell Level inches 3 3 3 3 3 3 Condenser Vacuum inches Hg 0 0 0 0 0 0 Condensate Storage Tank Level feet 0 0 0 0 0 0 l Air Ejector Off gas Rad Monitor mR/hr 10 10 10 10 10 10 Main Stack Flow cfm 2.8P4 2.8P4 2.8P4 2.8P4 2.8P4 2.8P4 Main Stack Hi-Range Rad cps 1.7P8 3P8 SP9 7P10 7P10 7P10 Stack Gas Rad. Monitor cps IP6 >1P6 >1P6 >1P6 >1P6 >1P6 Vent Stack Flow 5 cfm 2.2P5 2.2P5 2.2P5 2.2P5 2.2P5 2.2P5 Vent Stack Exhaust Mon epm 700 700 700 700 700 700 Reactor Bldg Vent Exhaust Rad Mon mR/hr 0.5 0.5 0.5 0.5 0.5 0.5 Radwaste Duct Rad. Monitor epm 300 300 300 300 300 300 Standby Gas Treatment System Flow cfm 8P3 8P3 8P3 8P3 8P3 8P3 6.3-6
.y. ,n .( -
(< s a (V-) U i N _ PLANT AND REACTOR SYSTEM VALUES VS TIME (OCTOBER 17, 1985) Parameter Units 1245 1300 1315 1330 1345 1400 Reactor Vessel Water Level inches -285 -285 -210 +20 +25 +25 Reactor Pressure psig 885 860 400 150 120 50
' Reactor Power-APRM (avg) % full power 0 0 0 . 0 0 0 Core Plate Diff. Pressure psid 0 0 0 0 0 0 Total Core Flow .lbs/hr x 10 8 0 0 0 0 0 0 l Recirc. Loop A Water Temp. *F 350 340 330 320 305 290 l Recirc. Loop B Water Temp. *F 350 340 330 320 305 290 ~
Drywell Pressure psig 1.3 1.3 1.3 1.2 1.1 1.1 Drywell Temperature *F 190 190 190 190 190 185 Drywell Radiation R/hr ~ 7P4 7P4. 7P4 7P4 SP4 2P4 Containment 02 Concentration % 1 1 1 1.1 1.2 1.2 Containment H2 Concentration % 0.7 0.7 0.7 0.7 0.7 0.7 Torus Water Level feet 5.5 5.6 5.7 5.8 6.2 7 Torus Water Temperature *F 90 90 91 91 92 92 Reactor Building Pressure inches H 2 O -0.5 -0.5 -0.5 -0.5 -0.5 -0.5 r 1 t Ra M ) Ib0 b b b0 b
., -,w l Main Steam'Line Flow' lbs/hr x 10 8 0 0 0 0 0 0 i Main Steam Line Radiation mR/hr 20 20 20 20 20 20 Feedwater Flow (total) lbs/hr x 10 8 0 0 0 0 0 0 Condenser Hotwell Level inches 3 3 3 3 3 3 Condenser Vacuum inches Hg 0 0 0 0 0 0 Condensate Storage Tank Level feet 0 0 0 0 s - 0 0 l Air Ejector Off gas Rad Monitor mR/hr 10 10 10 10 10 10 Main Stack Flow cfm. 2.8P4 2.8P4 2.8P4 2.8P4 2.8P4 2.8P4 Main Stack Hi-Range Rad cps 7P10 7P10 7P10 7P10 SP10 2P10 Stack Gas Rad. Monitor cps >1P6 >1P6 >1P6 >1P6 >1P6 >1P6 Vent Stack Flow ~ cfm 2.2P5 2.2P5 2.2P5 2.2P5 2.2P5 2.2P5 Vent Stack Exhaust Mon cpm 700 700 700 700 700 700 Reactor Bldg Vent Exhaust Rad Mon mR/hr 0.5 0.5 0.5 0.5 0.5 0.5 Radwaste Duct Rad. Moriitor cpm 300 300 300 300 300 300 Standby Gas Treatment System Flow cfm 8P3 8P3 8P3 8P3 8P3 8P3 6.3-7
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f, ) (x.y ) { w./ w PLANT AND REACTOR SYSTEM VALUES VS TIME (OCTOBER 17, 1985) Parameter Units 1415 1430 1445 1500 1515 1530 Reactor Vessel Water Level inches +25 +25 +25 +25 +25 +25 Reactor Pressure psig 20 15 10 8 5 0 Reactor Power-APRM (avg) % full power 0 0 0 0 0 0 Core Plate Diff. Pressure psid 0 0 0 0 0 0 Total Core Flow lbs/hr x 10 8 0 0 0 0 0 0 Recirc. Loop A Water Temp. F 275 260 245 235 225 215 Recirc. Loop B Water Temp. F 275 260 245 235 225 215 Drywell Pressure psig 1.1 1.1 1 1 1 1 Drywell Temperature *F 180 175 170 160 150 140 Drywell Radiation R/hr 4P3 800 300 100 40 8 Containment 02 Concentration % 1.2 1.2 1.3 1.3 1.3 1.3 Containment H2 Concentration % 0.7 0.7 0.7 0.7 0.7 0.7 Torus Water Level feet 7.5 8.0 8.2 8.3 8.5 9 Torus Water Temperature *F 92 91 90 89 88 87 Reactor Building Pressure inches !!2 0 -0.5 -0.5 -0.5 -0.5 -0.5 -0.5 Refuel Floor Vent Exhaust Rad Mon mR/hr 1.6 1.6 1.6 1.6 1.6 1.6 Drywell Vent Rad Mon (Gas) cpm 100 100 100 100 100 100 Main Steam Line Flow lbs/hr x 10 8 0 0 0 0 0 0 Main Steam Line Radiation mR/hr 20 20 20 20 20 20 Feedwater Flow (total) lbs/hr x 10 8 0 0 0 0 0 0 Condenser llotwell Level inches 3 3 3 3 3 3 Condenser Vacuum inches lig 0 0 0 0 0 0 Condensate Storage Tank Level feet 0 0 0 0 0 0 , Air Ejector Off gas Rad Monitor mR/hr 10 10 10 10 10 10 Main Stack Flow cfm 2.8P4 2.8P4 2.8P4 2.8P4 2.8P4 2.8P4 Main Stack Hi-Range Rad eps 4P9 8P8 1.7P8 SP7 1.3P7 3.5P6 Stack Gas Rad. Monitor cps >1P6 >1P6 IP6 3P5 8P4 2P4 Vent Stack Flow cfm 2.2P5 2.2P5 2.2P5 2.2P5 2.2P5 2.2P5 Vent Stack Exhaust Mon cpm 700 700 700 700 700 700 Reactor Bldg Vent Exhaust Rad Mon mR/hr 0.5 0.5 0.5 0.5 0.5 0.5 Radwaste Duct Rad. Monitor cpm 300 300 300 300 300 300 , Standby Gas Treatment System Flow cfm 8P3 8P3 8P3 8P3 8P3 8P3 6.3-8
. c . . . . - . . .-. _ _ - - , . - - . . .
, PLANT AND REACTOR SYSTEM VALUES VS TIME (OCTOBER 17, 1985) Parameter Units 1545 1600 1615 1630 I Reactor Vessel Water Level inches +25 +25 +25 +25 Reactor Pressure psig 0 0 0 0
-Reactor Power-APRM (avg) % full power 0 0 0 0 Core Plate Diff. Pressure psid 0 0 0 0 Total Core Flow lbs/hr x 10 6 0 0 0 0 Recire. Loop A Water Temp. *F 210 205 200 195 Recire. Loop B Water Temp. *F 210 205 200 195 i
Drywell Pressure psig 0.9 0.9 0.9 0.9
Drywell Temperature *F 135 130 125 125 i Drywell Radiation R/hr 10 20 20 20 j Containment 02 Concentration % 1.3 1.3 1.3 1.3 Containment H2 Concentration % 0.7 0.7 0.7 0.7 ,
Torus Water Level feet 9.5 10 10.5 11 i
Torus Water Temperature *F 86 85 84 83 Reactor Building Pressure inches H 2 O -0.5 -0.5 -0.5 -0.5 1.6 1.6 '
Refuel Floor Vent Exhaust Rad Mon mR/hr 1.6 1.6 Drywell Vent Rad Mon (Gas) cpm 100 100 100 100 ; Main Steam Line Flow lbs/hr x 10 6 0 0 0 0 Main Steam Line Radiation mR/hr 20 20 20 20 Feedwater Flow (total) lbs/hr x 10 6 0 0 0. O Condenser Hotwell Level inches 3 3 3 3 Condenser Vacuum inches Hg 0 0 0 0 Condensate Storage Tank Level feet 0 0 0 0 l i Air Ejector Off gas Rad Monitor mR/hr 10 10 10 10 Main Stack Flow cfm 2.8P4 2.8P4 2.8P4 2.8P4 Main Stack Hi-Range Rad cps <1P5 <1P5 <1P5 <1P5 Stack Gas Rad. Monitor cps 100 70 50 70 Vent Stack Flow cfm 2.2P5 2.2P5 2.2P5 2.2P5 Vent Stack Exhaust Mon mR/hr 700 700 700 700 Reactor Bldg Vent Exhaust Rad Mon mR/hr 0.5 0.5 0.5 0.5 Radwaste Duct Rad. Monitor cpm 300 300 300 300 Standby Gas Treatment System Flow cfm 8P3 8P3 8P3 8P3 6.3-9
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O i GRAPH - 27 EMERGENCY GAS FILTER FLOW FT-20008 (0 - 10,000 CFM)
- . . . . ~ . -- .- -_- . -_ . . -
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? 1 J's / - SECTION 7.0 October 17,.1985 RADIOLOGICAL DATA 1985 NRC OBSERVED EMERGENCY RESPONSE. EXERCISE PEACH BOTTOM ATOMIC POWER STATION Section- Page 7.1 PLANT MONITORING DATA . . . . . . . . . . . . . . . ... 7.1-1 '
1. Reactor Coolant Activity Concentrations
'(pCi/gs)
2. Drywell and Suppression Chamber Air Concentrations (pCi/gs)

3. Suppression Pool Activity Concentrations (pCi/gs)

4. Reactor Building Concentrations (pCi/cc) . . . . . . 7.2-1 4
7.2 CHEMISTRY SAMPLE DATA EXPOSURE RATE FROM SAMPLES (mR/hr). . . . . . . . . ... 7.2-1 7.3 MAIN STACK SAMPLE DATA. . . . . . . . . . . . . . . . . . 7.3-1 O< s
% ./
7.4 RELZASE DATA AND CALCULATED DOSE RATES. . . . . . . ... 7.4-1
1. Anticipated Dose Assessment Group Results 7.5 FIELD MONITORING DATA . . . . ..... . . . . . . . ... 7.5-1

1. Whole Body Dose Rates (mR/hr)

2. Sam II Readings (cpm) i

3. TCS Readings (cpm) l 1
7 7.6 PLANT RADIATION LEVELS. . . . . . . . . . . . . . . ... 7.6-1
1. Area Radiation Levels, Surface Contamination Levels, and Airborne Radioactivity Levels by Region

2. Maps Showing Plant Areas and Regions
-3. Area Radiation Monitoring System Data 7.7 SITE AND FIELD MONITORING MAPS. . . . . . . . . . . ... 7.7-1 .7.8 METEOROLOGICAL DATA . . . . . . . . . . . .. . 7.8-1
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Q (N (g : U d V GETOBER 17,1985 EIEREISE TABLE 7.1-2 M-Ott-85 DRYNELL AND TDRUS AIR EONEENTRATIONS luEi/cc) 800 830 900 1000 1030 1100 1130 1200 1300 1330 1400 1430 1500 1530 1600 IS0 TOPE 830 900. 1000 1030 1100 1130 1200 1300 1330 1400 1430 1500 1530 1600 END Kr-83a 1.3E-08 9.4E-08 5.1E-07 1.6E-04 8.3E-04 2.6E-03 4.3E-01 6.1E400 6.0E+00 4.2E+00 3.3E-01 2.4E 3.0E-03 7.5E-04 1.4E-03 Kr-85s 3.9E-08 2.6E-07 1.3E-06 3.9E-04 2.0E-03 6.3E-03 1.1E+00 1.5E+01 1.6E+01 1.1E+01 8.9E-01 6.7E-02 8.7E-03 2.2E-03 4.2E-03 Kr-E5 NA NA NA 3.3E-06 1.8E-05 6.1E-05 1.1E-02 1.7E-01 2.lE-01 1.6E-01 1.4E-02 1.!E-03 1.6E-04 4.0E-05 9.lE-05 Kr-87 7.!E-08 3.9E-07 1.4E-06 3.3E-04 1.4E-03 3.6E-03 5.0E-01 5.9E+00 4.!E+00 2.4E400 1.6E-01 1.2E-02 1.0E-03 2.6E-M 3.5E-04 Kr-88 9.8E-0B 6.3E-07 2.9E-06 8.4E-04 4.2E-03 1.2E-02 2.0E+00 2.7E+01 2.5E+01 1.7E+01 1.3E+00 9.9E-02 1.2E42 3.0E-03 5.3E-03 Ie-131m NA NA 3.1E48 1.lE-05 5.9E-05 2.0E-04 3.6E-02 5.6E-01 6.7E-01 5.2E-01 4.5E-02 3.3E43 5.lE-04 1.3E-04 2.9E-04 c. Ie-13!s NA 2.BE-08 1.6E-07 5.4E-05 3.0E-04 1.0E-03 1.9E-01 2.9E+00 3.5E+00 2.7E+00 2.3E-01 1.7E-02 2.7E-03 6.7E-04 1.5E-03 le-133 2.0E-07 1.5E-06 8.3E-06 2.8E-03 1.6E-02 5.3E-02 9.7E+00 1.5E+02 1.BE+02 1.4E+02 1.2E+0! 8.9E-01 1.4E-01 3.4E-02 7.8E-02 Ie-135M 5.3E-08 4.6E-07 2.6E-06 8.2E44 4.4E-03 1.4E-02 2.4E+00 3.5E+0! 3.8E+01 2.8E+0! 2.3E+00 1.7E-01 2.4E-02 6.0E-03 1.2E-02 te-135 4.9E-08 4.0E-07 2.7E-06 9.9E-04 5.9E-03 2.1E-02 4.0E+00 6.3E+01 7.9E+01 6.2E+01 5.5E+00 4.1E-01 6.4E-02 1.6E-02 3.7E-02 Ie-138 1.7E-07 2.EE-07 1.4E-07 6.3E-06 0.0E-06 5.7E-06 2.0E-04 NA NA NA NA NA NA NA NA TOTAL NS 7.0E-07 4.0E-06 2.0E-05 6.4E-03 3.5E-02 1.!E-01 2.0E+0! 3.!EU2 3.5E+02 2.7E+02 2.3E+01 1.7E+00 2.5E-01 6.3E-02 1.4E-01 1-131 6.8E-08 3.9E-07 1.9E-06 6.2E-04 3.4E-03 1.!E-02 2.0E+00 3.0E+0! 3.4E+01 ,2.6E+01 2.2E+00 1.7E-01 2.5E-02 6.1E-03 1.6E-02 I-133 1.4E-07 7.9E-07 J.9E-06 1.3E-03 6.9E-03 2.2E-02 4.0E+00 6.0E+01 6.9E+01 5.3E+0! 4.5E+00 3.4E-01 5.0E-02 1.2E-02 2.5E-02 TOTAL 10 DINE 2.1E-07 1.2E-06 5.9E-06 1.9E-03 1.0E-02 3.3E-02 6.0E+00 9.0E+01 1.0E+02 7.9E+01 6.7E+00 5.0E-01 7.4E-02 1.9E-02 4.lE-02 GROSS BETA 1.BE-06 1.0E-05 5.2E-05 1.7E-02 9.0E-02 2.9E-01 5.3E+01 7.9E+02 9.1E+02 6.9E+02 5.9E+01 4.4E+00 6.5E-01 1.E-01 3.6E-01 NA - Value is less than 1.0E-B
r d V ;b/ _ CCTDKR 17,1985 EIERCISE TABLE 7.1-3 04-Oct-85 TORUS ACTIVITY CONCENTRATION (mCilge) BM B30 900 1000 1030 1100 !!30 1200 1300 'T30 1400' 1430 1500 1530 lett ISOTOPE B30 900 1000 1030 1100 !!30 1200. 1300 1330 1400 1430 1500 .. 1530 1600 END
=_= - ________ ____ _ ... -____.
1-131 1.7E-08 1.4E-06 9.9E-06 6.2E-05 3.4E-04 1.1E-03 2.0E-01 3.0E+00 3.4E+00 2.6E+00 2.2E-01 1.7E-02 2.5E-03 1.4E-03 1.6E-03 1-133 3.6E-08 2.BE-06 2.0E-05 1.3E-04 6.9E-04 2.2E-03 4.0E-01 6.0E+00 6.9E+00 5.K+00 4.5E-01 3.4E-02 5.0E-03 2.BE-03 2.5E-03 TOTAL IDDINE 5.3E-08 4.2E-06 3.0E-05 1.9E-04 1.0E-03 3.3E-03 6.0E-01 9.0E+00 1.0E+01 7.BE+00 6.7E-01 5.0E-02 7.5E-03 4.2E-03 4.lE-03 BROSS BETA 1.1E-07 B.4E-06 6.0E-05 3.BE-04 2.0E-03 6.7E-03 1.2E+00 1.BE+01 2.!E+01 1.6E+0! 1.3E+00 1.0E-01 1.5E-02 8.3E-03 8.2E-03 i 1 x 1 I I i 4 Y 1 l t
,m , - -+ .I OCTOBER 17,1955 EIERCISE TABLE 7.1-4 04-Oct-05 REACTBR BUILDING ATMOSPHERE PASS SAMPLE EDNCENTRATIDNS luCi/cc)
B00 830 900 1000 1030 !!00 !!30 i200 1300 1330 1400 1430 1500 1530 1600 ISDTCPE B30 900 1000 1030 !!00 1130 1200 1300 1330 1400 1430 1500 1530 1600 END Kr-B3s NA NA NA NA NA NA NA NA NA NA NA NA NA E M Kr-85s NA NA NA NA NA NA NA NA NA NA KA NA NA NA E Kr-25 NA NA NA NA NA NA NA NA - NA NA NA NA NA NA NA Kr-87 NA NA NA NA NA NA NA NA NA NA NA M NA NA NA tr-BB NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA Ie-131s NA NA NA NA NA NA NA NA NA NA NA NA M NA NA Ie-133s NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA Ie-133 NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA Ie-135M NA NA NA NA NA NA NA NA NA NA NA NA NA NA M Ie-135 NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA Ie-138 NA NA NA NA NA NA NA NA NA NA NA NA NA E NA TOTAL NB NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA 1-131 6.5E-!! 6.5E-!! 6.5E-fl 6.5E-f! 7.4E-10 7.4E-10 7.4E-10 7.4E-10 7.4E-10 7.4E-10 7.4E-10 7.4E-10 7.4E-10 7.4E-10 9.0E-10 - 1-133 1.3E-10 1.?E-10 1.3E-10 1.3E-10 1.5E-09 1.5E-09 1.5E-09 1.5E-09 1.5E-09 1.5E-09 1.5E-09 1.5E-09 1.5E-09 1.5E-09 1.4E-09 TOTAL 10 DINE 2.0E-10 2.0E-10 2.0E-10 2.0E-10 2.359' 2.3E-09 2.3E-09 2.3E-09 2.3E-09 2.3E-09 2.3E-09 2.3E-09 2.3E-09 2.3E-09 2.3E-09 6ROSS BETA 1.7E-09 1.7E-09 1.7E-09 1.7E-09 2.0E-0B 2.0E-08 2.0E-0B 2.0E-0B 2.0E-0B 2.0E-08 2.0E-08 2.0E-0B 2.0E-08 2.0E-0B 2.0E-08 NA - Value is less than 1.0E-B
TABLE 7.1-5 , 1 7- g GENERAL AREA AIR SAMPLE RESULTS-IN PLANT 1 1985 NRC OBSERVED EMERGENCY RESPONSE EXERCISE ! PEACH BOTTOM ATOMIC POWER STATION l l I In-Plant Field Results* Frisker Readings (net epm) R02 Readings Range Color 4) Filter Cartridge (mrad /hr) (net cpm) Green 150 100 N/A 100 to 1,000 Yellow 1,600 1,300 N/A 1,000 to 5,000 Blue 6,000 5,000 1.5 5,000 to 10,000 Red 30,000 20,000 10.0 10,000 to 50,000 White off-scale off-scale 150.0 50,000 and >
NOTES:
1. Assumes that 100 ft3 of air has been sampled.
/"%
s_- 2. Assumes that the frisker has a 10.0 percent efficiency factor.
3. Assumes 1.0 mrad /hr is equal to 3600 cpm on the R02.
,4. These colors correspond to the colors listed in tables of Section 7.6 for Airborne Radioactivity Levels (cpm per 100 ft 3).
O x_ / 1 of 1
TABLE 7.1-6
!(\J GENERAL AREA AIR SAMPLE RESULTS-IN PLANT 1985 NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION Counting Lab Equipment Results GREEN - MPC
SUMMARY
REPORT: Concentration Nuclide (pCi/cc) MPC % MPC
- I-131 6.6N11 9.0N9 0.733 I-133 1.3N10 3.0N8 0.433 Cs-134 1.0N10 1.0N8 1.0 Cs-137 1.0N10 1.0N8 1.0 Total pCi/cc = 4.0N10 Total MPC Fractions (Less Iodines) = 2.0N2
['N ,-) - s Total Iodine MPC Fractions = 1.2N2 Stay Time, 2 MPC hrs, in Mask = 160 hrs MPC Factor (Mask) MPC hrs /hr = 1.25N2
~
Stay Time, 2 MPC hrs, in Air = 62,500 hrs MPC Factor (air) MPC hrs /hr = 1.25N2
Stay Time, 2 MPC hrs No Mask = 62.5 hrs *

MPC Factor (No Mask) MPC hrs /hr = 3.2N2 Gross Beta Analysis For Filter: net cpm = 360 = 2.0N10 pCi/cc O
V 1 of 1
TABLE 7.1-7
' O) .g GENERAL AREA AIR SAMPLE RESULTS-IN PLANT 1985 NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION Counting Lab Equipment Results YELLOW i MPC
SUMMARY
REPORT: Concentration Nuclide (pCi/cc) MPC % MPC
-I-131 7.5N10 9.0N9 10.0 I-133 1.5N9 3.0N8 5.0 Cs-134 1.0N9 1.ONG 10.0.
Cs-137 1.0N9 1.0N8 10.0 Total pCi/cc = 4.25N9 Total MPC Fractions (Less Iodines) = 2.0N1
/ Total Iodine MPC Fractions = 1.5N1 Stay Time, 2 MPC hrs, in Mask = 13.0 hrt.
MPC Factor (Mask) MPC hrs /hr = 1.54N1 Stay Time, 2 MPC hrs, in Air = 5714.0 hrs MPC Factor (Mask) MPC hrs /hr = 3.5N4
Stay Time, 2 MPC hrs No Mask = 5.7 hrs *

MPC Factor (No Mask) MPC hrs /hr = 3.5N1

Gross Beta Analysis For Filter: net epm = 4000 = 2.0N9 pCi/cc 1
i
./
k
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TABLE 7.1-8 ,: A I,
'~# ) GENERAL AREA AIR SAMPLE RESULTS-IN PLANT 1985 NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION Counting Lab Equipment Results BLUE -MPC
SUMMARY
REPORT: Concentration Nuclide (pci/cc) MPC % MPC I-131 2.6N9 9.0N9 28.8
-I-133 5.2N9 3.0N8 17.3 Cs-134 4.0N9 1.0N8 40.0 .Cs-137 4.0N9 1.0N8 40.0 Total pCi/ce'= 1.6N8 Total MPC Fractions (Less Iodines) = 8.0N1 '\_ Total: Iodine MPC Fractions = 4.6N1 Stay Time, 2 MPC hrs, in Mask = 4.2 hrs -MPC Factor (Mask) MPC hrs /hr = 0.476 Stay Time, 2 MPC hrs, in Air = 1600 hrs HPC Factor (Air) MPC hrs /hr = 1.25N3 ***********************t.**************
Stay Time, 2 MPC hrs No Mask = 1.6 hrs *

MPC. Factor (No Mask) MPC hrs /hr = 1.25

Gross Beta Analysis For Filter: net epm = 18,000 = 1.0N8 pCi/cc fi D
1 of 1
TABLE 7.1-9 7- s ('-' GENERAL AREA AIR SAMPLE RESULTS-IN PLANT 1985 NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION Counting Lab Equipment Results RED . MPC
SUMMARY
REPORT: 3 , Concentration l Nuclide (pCi/cc) MPC % MPC I-131 1.2N8 9.0N9 133.0 I-133 2.3N8 3.0N8 76.6 Cs -134 1.75N8 1.0N8 175.0 Cs -137 1.75N8 1.0N8 175.0 Total pCi/cc = 7.0N8 Total MPC Fractions (Less Iodines) = 3.5
/~'% Total Iodine MPC Fractions = 2.1
Stay Time, 2 MPC hrs, in Mask = 0.92 hrs
, MPC Factor (Mask) MPC hrs /hr = 2.17 Stay Time, 2 MPC hrs, in Air = 400 hrs MPC Factor (Air) MPC hrs /hr = 5.0N3
Stay Time, 2 hPC hrs No Mask = .36 hrs *

MPC Factor (No Mask) MPC hrs /hr = 5.6

Gross Beta Analysis For Filter: N/A
~J 1 of 1
TABLE 7.1-10
-jm GENERAL AREA AIR SAMPLE RESULTS-IN PLANT 1985 NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION Counting Lab Equipment Results WHITE MPC
SUMMARY
REPORT: Concentration Nuclide (pCi/cc) MPC % MPC I-131 2.9N7 9.0N9 3.2P3 I-133 5.7N7 3.0N8 1.9P3 Cs-134 2.0N7 1.0N8 2.0P3 Cs-137 2.0N7 1.0N8 2.0P3 Total pCi/cc = 1.3N6 Total MPC Fractions (Less Iodines) = 40.0 Total Iodine MPC Fractions = 51.0 [}
'O Stay Time, 2 MPC hrs, in Mask = 0.04 hrs = 2.4 min MPC Factor (Mask) MPC hrs /hr = 50.0 Stay Time, 2 MPC hrs, in Air = 22.0 hrs MPC Factor (air) MPC hrs /hr = 9.INI
Stay Time, 2 MPC hrs No Mask = 0.02 = 1.2 min

MPC Factor (No Mask) MPC hrs /hr = 100.0 i
Gross Beta Analysis For Filter: N/A t m 1 of 1
/ fA ("
Q} \ \ DCTOBER 17,1985 EIERCISE TA8LE 7.1-11 04-Oct-85 ISOTOPIC ANALYSIS REPDRT - PERCENT TOTAL ACTIVITY 800 830 900 1000 1030 !!00 1130 1200 1300 1330 1400 1430 1500 1530 1600 ISOTOPE 8) 900 1000 1030 1100 1130 1200 1300 1330 1400 1430 1500 1530 1600 END Kr-83e 1.988 2.355 2.530 2.472 2.382 2.268 2.139 2.000 1.715 1.575 1.440 1.440 1.191 1.191 0.972 Kr-85e 5.507 6.440 6.458 6.133 5.854 5.566 5.276 4.988 4.434 4.171 3.919 3.919 3.449 3.449 3.027 Kr-85 0.033 0.042 0.048 0.051 0.053 0.054 0.056 0.057 0.060 0.061 0.M2 0.062 0.063 0.063 0.M5 Kr-87 10.147 9.763 7.084 5.182 4.071 3.185 2.485 1.933 1.164 0.901 0.697 0.697 0.415 0.415 0.247 Kr-88 14.064 15.715 14.624 13.075 11.931 10.845 9.827 8.883 7.217 6.490 5.829 5.829 4.689 4.689 3.760 Ie-131e 0.107 0.136 0.155 0.164 0.169 0.174 0.179 0.183 0.190 0.194 0.197 0.197 0.203 0.203 0.209 Ie-133e 0.545 0.691 0.793 0.839 0.868 0.895 0.919 0.942 0.982 1.001 1.018 1.018 1.051 1.051 1.081 Ie-133 28.707 36.315 41.518 43.826 45.266 46.566 47.757 48.856 50.828 51.721 52.565 52.565 54.129 54.129 55.568 Ie-135M 7.539 11.403 12.827 12.730 12.501 12.215 11.898 !!.559 10.M6 10.482 10.118 10.118 9.400 9.400 8.708 Ie-135 6.959 9.922 13.281 15.430 16.883 18.227 19.465 20.598 22.564 23.404 24.155 24.155 25.409 25.409 26.364 Ie-138 24.503 7.017 0.681 0.098 0.023 0.005 0.001 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 TOTAL N6 (I) 103 100 100 100 100 100 100 100 100 100 100 100 100 100 100 1-131 T3.0 33.0 33.0 33.0 33.0 33.0 33.0 33.0 33.0 33.0 33.0 33.0 33.0 33.0 40.0 1-133 67.0 67.0 67.0 67.0 67.0 67.0 67.0 67.0 67.0 67.0 67.0 67.0 67.0 67.0 60.0 k0ikL100lNEIII 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 TIME AFTER 0.00 0.50 1.33 2.00 2.50 3. 0 3.50 4.00 5.00 5.50 6.00 6.00 7.00 7.00 8.00 SCRAM (HOURS) CTE: The percentages reported is this table are applicable to all chemistry samples (Tables 7.1-1 through 7.1-4) for the time period indicated.
O OCTOKR 17, 1905 EIER:ISE O TAILE 7.2-1 O M-Oct-05 POST ACCIENT SAIFLIM SYSTEN READIMS (eR/hri SAIFLE B00 B30 900 1000 1030 !!00 1130 1200 1300 1330 1400 SYSTE!! SIZE DISTANCE SHIELDING B30 900 1000 1030 !!30 1100 1200- 1300 1330 1400 1430 Reactor 0.1 el 1 in. None M M M M l.4E-02 4.7E-02 8.4E+00 1.3E+02 1.5E+02 1.1E+02 9.4E+00 Coolant I ft. None M M M M M M 5.0E-02 8.BE-01 1.0E+00 7.E-01 6.5E-02 1 in. 2 in. Lead "* M M M M M M 1.4E-01 1.E-01 1.2E-01 1.0E-02 1 ft. 2 in. Lead M M M NA NA M M M M NA M 1 in. 4 in. Lead NA M M M M M M M NA M M
! ft. 4 in. Lead M NA NA M M M M N M M M Reactor 10.0 el 1 in. None 2.!E-01 2.1E-01 2.3E-01 2.7E-01 1.4E+00 4.7E+00 9.4E+02 1.3E+04 1.5E+M 1. lE+M 9.4E+02 Coolant 1 ft. None M NA NA M M 3.2E-02 5.8E+00 8.9E+01 1.0E+02 7.6E+01 6.5E+00 1 in. 2 in. Lead M NA E NA M NA 9.3E-01 1.4E+0! 1.E+0! 1.2E+01 1.0E+00 1 it. 2 in. Lead M M M M M M 4.3E-02 6.5E-01 7.4E-01 5.E-01 4.OE-02 1 in. 4 in. Lead M NA NA M M M NA 5.lE-02 5.OE-02 4.4E-02 M 1 ft. 4 in. Lead M M M M NA NA E N M NA M Eas Stripped 14.4 el 1 in. None 2.5E-01 2.5E-01 2.8E-01 3.2E-01 1.7E+00 5.6E+00 1.0E+03 1.5E+M 1.7E+04 1.3E+04 1.lE*43 Free Reactor 1 ft. Mene M NA NA M 1.2E-02 3.9E-02 6.9E+00 1.0E+02 1.2E+02 9.lE+01 7.7E+00 Ccolant 1 in. 2 in. Lead M NA M M M M 1.lE+00 1.7E+01 1.9E+0! I.5E+01 1.2E+00 1 it. 2 in. Lead M M M M M NA 5.lE-02 7.7E-01 8.9E-01 6.7E-01 5.7E-02 I in. 4 in. Lead M M M M NA M M 6.0E-02 6.9E-02 5.2E-02 M ! ft. 4 in. Lead M NA M NA M M M NA M NA E Drywell and Torus 14.4 s1 1 in. None M NA NA 6.4E-02 3.4E-01 1.!E+00 2.0E+02 3.0E+03 3.5E+03 2.6E+03 2.2E+02 Atacsphere 1 f t. None M NA NA NA E M 1.4E+00 2.lE+01 2.4E+01 1.BE+0! 1.6E+00 1 in. 2 in. Lead NA NA M NA M M 2.2E-01 3.4E+00 3.9E+00 2.9E+00 2.5E-01 I it. 2 in. Lead M M M M M M 1.0E-02 1.5E-01 1.8E-01 1.3E-01 1.1E-02 -
1 in. 4 in. Lead M M M NA B NA M 1.2E-02 1.4E-02 1.lE-02 M I ft. 4 in. Lead M NA NA NA NA NA NA NA M M M Torns Pool 0.1 al 1 in. None M NA M NA NA M 2.4E-02 3.7E-01 4.2E-01 3.2E-01 2.7E-02 Liquid 1 It. None M M NA M M NA M M M M M 1 in. 2 in. Lead M HA NA M M M M M NA NA N
! ft. 2 in. Lead M M M M M M M NA B NA NA 1 in. 4 in. Lead M M M NA M M M M NA M M i it. 4 in. Lead M NA M NA M M NA M NA M M Torus Pool 10.0 el 1 in. None M M M M M 1.4E-02 2.4E+00 3.7E+0! 4.2E+0! 3.2E+0! 2.7E+00 Liquid 1 it. None M M M M NA M 1.7E-02 2.5E-01 2.9E-01 2.2E-01 1.9E-02 I in. 2 in. Lead M MA M M M NA M 4.lE-02 4.7E-02 3.5E-02 M i it. 2 in. Lead M M M M M M NA M M NA M i in. 4 in. Lead M M M M M NA M M M M NA 1 ft. 4 in. Lead M M M M M M NA M M M M Reactor Building 14.4 si ! in. None NA M M NA E M M M M. M NA Atmosphere 1 it. None M M NA M M M M M M M M M - Value is less than 0.01 mR/hr. Use actual meter reading.
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(V 1 ( L l U OCTOBER 17,1985 EIERCISE TABLE 7.3-2 M-Oct-85 MIN STAEK SANPLE BATA B00 900 1000 1030 !!00 1200 1300 1330 1400 1930 1500 1530 1600 Parameter Units 900 1000 1030 1100 1200 1300 1330 1400 1430 1500 1530 1600 END TIME AFTER SCRAR Hours 0.33 1.33 2.00 2.50 3.00 4.00 5.00 5.50 6.00 6.00 7.00 7.00 2.00 SENERAL AREA CIPCSURE RATES At Door (outside) eR/hr 7.BE-02 7.BE-02 1.oE-01 1.0E-01 3.0E+02 7.9E+02 B.2E*02 0.2E+02 B.2E+02 5.9E+00 7.BE-01 4.4E-01 3.3E-01 linside) eR/hr 7.0E-01 7.0E-01 9.0E-01 9.0E-01 2.7E+03 7.lE+03 7.4E+03 7.4E+03 7.4E+03 5.3E+01 7.0E+00 4.0E+00 3.0E+00 10 DINE CARTRID6E SAMPLE IIFORMATION Saaple time ein 10 10 10 10 10 10 10 10 10 10 10 10 10 Flow rate cfs 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 Efficiency I 100 100 100 100 100 100 100 100 100 100 100 100 100 Activity Collected u;i 1-131 1.3E-02 1.4E-02 1.4E42 1.2E+0! 1.!E+03 2.9E+05 3.4E+05 3.5E+05 1.0E+05 3.7E+03 5.2E+01 6.6E-02 4.0E-02 1-133 2.6E-02 2.9E42 2.9E-02 2.5E+01 2.2E+03 5.9E+05 6.BE+05 7.lE+05 2.!E+05 7.6E+03 1.1E+02 1.3E-01 6.0E-02 Total lodine 3.BE-02 [3E-02 4.3E-02 3.7E+01 3.3E+03 8.BE+05 1.0E+05 1.!E+05 3.2E+05 5 1E+04 1.6E+02 2.0E41 1.0E-01 Isotopic Abundance 1 1-131 33.00 33.40 33.00 33.00 33.00 33.00 33.00 33.00 33.00 33.00 33.00 33.00 40.00 1-133 67.00 67.09 67.00 67.00 67.00 67.00 67.00 67.00 67.00 67.00 67.00 67.00 60.00 Tetal lodine 100 100 100 100 100 100 100 100 100 100 100 100 100 Sample Exposure Rates eR/hr (1) 1 inch unshielded 3.4E-04 3.6E44 3.BE-04 3.2E-01 2.9E+01 7.7E+03 B.9E+03 9.4E+03 2.K+03 9.9E+0! 1.4E+00 f.BE-03 8.BE-04 I inch shielded 3.7E-07 4.2E-07 4.2E-07 3.6E-04 3.2E-02 8.bE+00 9.9E+00 1.0E+01 3.!E+00 1.!E-01 1.5E-03 1.9E-06 9.7E-07 I foot unshielded 4.BE-05 5.4E-05 5.4E-05 4.6E-02 4.2E+00 1.lE+03 1.3E+03 1.3E+03 4.0E+02 1.4E+0! 2.0E-01 2.5E-04 1.3E-04 1 foot shielded 5.3E-08 6.0E-08 6.0E-08 5.1E-05 4.6E-03 1.2E+00 1.4E+00 1.5E+00 4.4E-01 1.6E-02 2.2E44 2.BE-07 1.4E-07 3 foot unshielded 5.3E-06 6.0E46 6.0E-06 5.!E-03 4.6E-01 1.2E+02 1.4E+02 1.5E+02 4.4E+0! 1.6E+00 2.2E-02 2.BE-05 1.4E-05 3 fact shielded 5.9E-09 6.7E-09 6.7E-09 5.7E-06 5.2E-04 1.4E41 1.6E-01 1.6E-01 4.9E-02 1.BE-03 2.4E-05 3.!E-08 1.5E4B NOTES:
1. Based upon Radiological Health Handbook rule of thuah: R/hr at I foot = 5.64CE E is conservatively assumed to be 0.5 MeV for iodine and 0.7 MeV for noble Shielded values gas.,
assumewhere a 2 inchClead is the pig isnumber used. of curies and E is the energy I of 2
O OCTMER 17, 1985 EIEK ISE O
j TABLE 7.3-2 M-Oct-55 i MIR STACK SMPLE MTA l l 4 000 900 1000 1030 1100 1200 1300 1330 1400 1430 150 1530 16% j Parameter Units 900 1000 1930 1100 1200 1300 1330 1400 1430 1500 1530 1600 Em ) TIE AFTER SCRM Hours 0.33 1.33 2.00 2.50 3.M 4.M 5.00 5.50 6.00 6.00 7.M 7.00 8.00 i j NOILE SAS SM PLE INFORMATION Sample Votese cc 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 l Activity Collected uti Kr-83e 5.lE-07 6.E-07 6.4E-07 5.2E-04 4.5E-02 1.lE+0! 1.0E+0! 1.0E+0! 2.7E+00 9.DE-02 1.lE43 1.4E-M 5.BE-07 I.E-M Kr-95e 1.7E-M 1.6E-M !.3E-03 1.!E-01 2.6E+0! 2.7E+01 2.7E+0! 7.4E+00 2.7E-01 3.3E-03 4. lE-M 1.OE-M t Kr-85 9.2E-09 1.2E-48 1.3E48 1.2E45 1.lE-03 3.02-01 3.7E41 3.9E41 1.X-01 4.2E-03 6.0E-05 7.6E-00 .3.9E-4B n* Ie-131s M21:52 LI215% 2.9E-4B 4.0E-08 4.3E-08 t#11:#41 i:H21:H2 i:He tit LE215% 3.7E-05 3.5E-03 9.7E-01 1.2E+00 1.2E+00 3.7E-01 1.3E-02 1.9E-04 2.4E-07 kl% - 1.3E-07 ,
le-133e 1.5E-07 2.lE-07 2.2E-07 1.9E-04 1.BE-02 5.0E+00 6.0E+00 6.4E+00 1.9E+00 6.9E-02 1.0E-03 1.3E-M 6.E-07 t

Ie-133 7.8E-06 1.lE-05 1.lE45 1.0E-02 9.3E-01 2.6E+02 3.lE+02 3.3E+02 1.0E+02 3.6E+00 5.lE-02 6.E45 3.5-45
, Ie-135e 2.4E46 3.3E-06 3.3E46 2.K-03 2.4E-01 6.1E+01 6.K+0! 6.7E+0! 1.9E+01 6.9E41 B.9E-03 1.lE-05 5.X-06 . , Ie-135 2.lE-06 3.5E-06 4.0E-06 3.7E-03 3.6E-01 1.!E+02 1.4E+02 1.5E+02 4.6E+0! 1.E+00 2.4E-02 3.0E-05 1.6E-05 t Ie-138 2.5E-M 1.8E-07 2.5E-08 5.lE-06 1.0E44 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.3E-05 2.6E-05 2.E-05 Grass Total 2.2E-02 2.0E+00 5.3E+02 6.lE+02 6.4E+02 1.9E+02 6.BE+00 9.5E-02 1.2E-04 6.0E-05 i
Isot i 1 bcAbundan

e B3e 2.218 2.530 2.472 2.382 2.268 2.000 1.715 1.575 1.440 1.440 1.191 1.191 0.972 i Kr-85e 6.189 6.458 6.133 5.B54 5. M 4.988 4.434 4.171 3.919 3.919 3.449 3.449 3.027 2 Kr-B5 0.040 0.948 0.051 0.053 0.054 0.057 0.M0 0.061 0.062 0.062 0.M3 0.M3 0.065 Kr-87 10.025 7.004 5.182 4.071 3.185 1.933 1.164 0.901 0.697 0.697 0.415 0.415 0.247 Kr-88 15.336 14.624 13.075 11.931 10.845 8.883 7.217 6.490 5.829 5.029 4.609 4.689 3.760 "
4 te-131e 0.127 0.155 0.164 0.169 0.174 0.183 0.190 0.194 0.197 0.197 0.203 0.203 0.209 l Ie-133e 0.646 0.793 0.B39 0.868 0.895 0.942 0.982 1.001 1.01B 1.010 1.051 1.051 1.001 j Ie-133 33.977 41.518 43.926 45.2M 46.566 48.856 50.828 51.721 52.565 52.565 54.129 54.129 55.560 4 Ie-135e 10.383 12.827 12.730 12.501 12.215 11.559 10.046 10.482 10.118 10.118 9.400 9.400 0.M8 l Ie-135 8.931 13.201 15.430 16.8B3 18.227 20.598 22.564 23.404 24.155 24.155 25.409 25.409 26.364 i Ie-138 10.879 0.681 0.098 0.023 0.005 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 l j Gross Total 100 100 100 100 IN 100 100 100 IM 100 100 100 100 Saaple Espesure Rates mR/hr (11 ! I inch unshielded 2.BE47 3.2E-07 3.2E-07 2.7E-04 2.5-02 6.5E+00 7.5E+00 7.9E+00 2.3E+00 B.4E-02 1.X-03 1.5E-M 7.E-07 j ! inch shielded 3.lE-10 3.E-10 3.5E-10 3.0E-07 2.7E-05 7.2E-03 0. 5 -03 0.7E-03 2.6E43 9.I-95 1.3E-06 1.6E-09 0.2E-10 I 1 foot unshielded 4.0E-08 4.E-08 4 E-00 3.9E-05 3.5E43 9. I -01 1.!E+00 1.lE+00 3.3E-01 1.2E-42 1.7E-04 2.lE-07 1.lE-07 i i foot shielded 4.4E-!! 5.!E-Il 5.lE-11 4.3E-00 3.9E-06 1.0E43 1.2E-03 1.E-03 3.7E-04 1.3E-45 1.9E-07 2.E-10 1.2E-10 1 1 3 foot unshielded 4.4E-09 5.!E-09 5.lE-09 4.5-M 3.9E44 1.0E-01 1.E-01 1.2E-01 3.7E-02 1.3E-03 1.9E-05 2.3E-0B 1.2E-08 ] 3 foot shielded 4.9E-12 5.E-12 5.E-12 4.OE-09 4.3E-07 1.!E-04 1.3E44 1.4E-04 4.lE-05 1.E-M 2.1E-08 2.6E-l! 1.3E-Il I NOTES: i 1. Based upon Radiological Health Hasdhed rule of theeb: R/hr at I foot = 5.64CE ' i E is conservatively assumed to be 0.5 ReV for iodine and 0.7 NeV for noble gas., Shielded ubere values C is athe assume number 2 inch of is lead pig curies used.and E is the energy in MeV. ! 2 of 2 L - -
1 7 7 ( )
+G t V
1 L/ TABLE 7.4-1 October 17,1985 CALCULATED DOSE RATES CALCULATED NHOLE BODY DOSE RATE ALON6 CENTERLINE OF PLUME (eR/Hrl TIME D0uMNIND o 0F RELEASE / DISTANCE-MILES 0.5 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 11.0 1030 ARRIVAL TIME 1032 1035 1039 1044 1048 1053 1058 !!O2 1807 1112 1116 1121 READING 1.7E-01 1.2E-01 3.BE-02 1.9E-02 1.3E-02 B.3E-03 6.!E-03 4.6E-03 3.7E-03 3.ri-03 2.5E-03 2.lE-03
!!00 ARRIVAL TIME 1102 !!05 !!09 1114 1118 1123 1128 1132 1137 1142 1146 1151 READING 1.6E+00 1.tE+00 3.6E-01 1.BE-01 1.2E-01 7.7E-02 5.6E-02 4.3E-02 3.4E-02 2 GE-02 2.3E-02 2.0E-02 1130 ARRIVAL TIME 1132 1135 !!39 1144 !!48 1153 1158 1202 1207 1212 1216 1221 READIN6 6.6E+01 4.4E+01 1.5E+0! 7.3E+00 4.BE+00 3.2E+00 2.3E+00 1.BE+00 1.4E+00 1.d+00 9.5E-01 B.!E-01 1145 MRIVAL TIME 1147 1150 1154 1159 1203 1208 1213 1217 1222 1227 1231 1236 READIN6 2.7E+03 1.8E+03 6.1E+02 3.0E42 2.0E+02 1.3E+02 9.6E+0! 7.3E+0! 5.0E+0! 4.7E+0! 4.0E+0! 3.3E+01 1200 MRIVAL TIME 1204 1209 1217 1226 1234 1243 1251 1300 1309 1317 1326 1334 READING 7.4E+03 4.lE+03 1.4E+03 7.2E+02 4.5E+02 3.lE+02 2.3E+02 1.7E+02 1.4E+02 1.lE+02 9.5E+01 8.3E+01 1215 ARRIVAL T!9E 1219 1224 1232 1241 1249 1258 1306 1315 1324 1332 1341 1349 READING 7.0E+03 3.9E+03 1.4E+03 6.9E+02 4.3E+02 3.0E+02 2.2E+02 1.6E+02 1.3E+02 1.lE+02 9.!E+0! B.0E+01 1230 MRIVAL TIE 1234 1239 1247 1256 1304 1313 1321 1330 1339 1347 1556 1404 READING 7.4E+03 4.tE+03 1.4E+03 7.2E+02 4.5E+02 3.lE+02 2.4E+02 1.7E+02 1.4E+02 1.1E+02 9.6E+01 8.4E+0!
1245 MRIVAL TIME 1249 1254 1302 1311 1319 1328 1336 1345 1354 1402 1411 1419 READING 7.4E+03 4.!E+03 1.4E+03 7.2E+02 4.5E+02 3.lE+02 2.3E+02 1.7E+02 1.4E+02 1.tE+02 9.5E+01 8.3E+0! 1300 ARRIVAL TIME 1304 1309 1317 1326 1334 1343 1351 1400 1409 1417 1426 1434 READIN6 7.4E+03 4.tE+03 1.4E+03 7.2E+02 4.5E+02 3.tE+02 2.3E+02 1.7E+02 1.4E+02 1.1E+02 9.5E+0! B.4E+01 1330 ARRIVAL TIME 1334 1339 1347 1356 1404 1413 1421 1430 1439 1447 1456 1504 READIN6 7.6E+03 4.2E+03 1.5E+03 7.4E+02 4.6E+02 3.2E+02 2.4E+02 1.BE+02 1.4E+02 1.2E+02 9.9E+0! 8.6E+01 1345 MRIVAL TIME 1349 1354 1402 1411 1419 1428 1436 1445 1454 1502 1511 1519 READINE 6.4E+03 3.5E+03 1.2E+03 6.2E+02 3.9E+02 2.7E+02 2.0E+02 1.5E+02 1.2E+02 9.BE+01 B.3E+0! 7.3E+01 L400 ARRIVAL TIME 1404 1409 1417 1426 1434 1443 1451 1500 1509 1517 1526 1534 READIN6 1.5E+03 8.0E+02 2.7E+02 1.4E+02 8.5E+01 5.9E+01 4.3E+01 3.4E+01 2.7E+0! 2.2E+01 1.BE+01 1.5E+0!
~
1430 MRIVAL TIME 1434 1439 1447 1456 1504 1513 1521 1530 1539 1547 1556 1604 READING 5.3E+01 2.9E+0! 9.7E+00 5.0E+00 3.0E+00 2.1E+00 1.5E+00 1.2E+00 9.5E-01 7.BE-01 6.5E-01 5.5E-01 1500 MRIVAL TIME 1504 1509 1517 1526 1534 1543 1551 1600 1609 1617 1626 1634 READING 6.7E-01 3.6E-01 1.2E-01 6.2E-02 3.BE-02 2.6E-02 1.9E-02 1.5E-02 1.2E-02 9.BE-03 B.1E-03 6.9E-03 1530 ARRIVAL TIME 1534 1539 1547 1556 1604 1613 1621 1630 1639 1647 1656 1704 READING 5.6E-04 3.0E-04 1.0E-04 5.2E-05 3.2E-05 2.2E-05 1.6E-05 1.3E-05 1.0E-05 8.3E-06 6.9E-06 5.BE-06 T!!E OF END OF RELEASE 1634 1639 1647 1656 1704 1713 1721 1730 1739 1747 1756 1804 NOTES: Use table values for areas shaded RED Use 0.1 of these values for areas shaded YELLOW Use 0.5 of these values for areas shaded BLUE Use 0.01 of these values for areas shaded GREEN For CLOSED WINDOW readings, use above values. For OPEN WINDOW readings, use 3 TIMES the above values. 1 of 1
V V V TABLE 7.4-2 October 17,1985 CALCULATED DOSE RATES CALCULATED THYR 019 lbHALATION DOSE RATE ALON6 CENTERLINE OF PLUME (eR/Hrl TIME DONNNIND OF RELEASEI DISTMCE-MILES 0.5 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 11.0 1030 MRIVAL TIME 1032 1035 1039 1044 1048 1053 1058 1102 !!07 1112 til6 1121 READIN6 1.3E+00 B.5E-01 2.BE-01 1.4E-01 9.2E-02 6.lE-02 4.5E-02 3.4E-02 2.7E-02 2.2E-02 1.OE-02 1.E-02 1100 MRIVAL TIE 1102 1105 1109 !!!4 1118 !!23 1128 1132 1137 !!42 1146 1151 READING 1.3E+01 B.5E+00 2.K+00 1.4E+00 9.2E-01 6.1E-01 4.5E-01 3.4E-01 2.7E-01 2.2E-01 1.BE-01 1.6E-01 1130 ARRIVAL TIME 1132 1135 1139 1144 1148 1153 1158 1202 1207 1212 1216 1221 READIN6 5.2E+02 3.5E+02 1.2E+02 5.8E+01 3.BE+01 2.5E+01 1.8E+01 1.4E+01 1.1E+01 9.0E+00 7.6E+00 6.4E+00 1145 ARRIVAL TIME 1147 1150 1154 !!59 1203 1208 1213 1217 1222 1227 1231 1236 READINE 2.3E+04 1.6E+04 5.2E+03 2.6E+03 1.7E+03 1.1E+03 B.1E+02 6.2E+02 4.9E+02 4.0E+02 3.4E+02 2.9E+02 1200 ARRIVAL TIME 1204 1209 1217 1226 1234 1243 IMI 1300 1309 1317 1326 1334 READIN6 6.3E+04 3.5E+04 1.2E+04 6.!E+03 3.BE+03 2.6E+03 2.0E+03 1.5E+03 1.2E+03 9.6E+02 B.lE+02 7.tE+02 1215 ARRIVAL TIME 1219 1224 1232 1241 1249 1258 1306 1315 1324 1332 1341 1349 READING 6.4E+04 3.5E+04 1.2E+04 6.2E+03 3.9E+03 2.7E+03 2.0E+03 1.5E+03 1.2E+03 9.7E+02 B.2E+02 7.2E+02 1230 ARRIVAL TIME 1234 1239 1247 1256 1304 1313 1321 1330 1339 1347 1356 1404 READIN6 6.BE+04 3.7E+04 1.3E+04 6.6E+03 4.1E+03 2.BE+03 2.lE+03 1.6E+03 1.3E+03 1.0E+03 8.7E+02 7.6E+02 1245 ARRIVAL TIME 1249 1254 1302 1311 1319 1328 1336 1345 1354 1402 1411 1419 READING 7.!E+04 3.9E+04 1.4E+04 6.9E+03 4.3E+03 3.0E+03 2.2E+03 1.7E+03 1.3E+03 1.lE+03 9.2E+02 8.1E+02 1300 ARRIVAL TIME 1304 1309 1317 1326 1334 1343 1351 1400 1409 1417 1426 1434 READING 7.6E+04 4.2E+04 1.5E+04 7.4E+03 4.6E+03 3.2E+03 2.4E+03 1.8E+03 1.4E+03 1.2E+03 9.BE+02 8.6E+02 1330 ARRIVAL TIME 1334 1339 1347 1356 1404 1413 1421 1430 1439 1447 1456 1504 i READING 7.9E+04 4.3E+04 1.5E+04 7.6E+03 4.BE+03 3.3E+03 2.5E+03 1.BE+03 1.5E+03 1.2E+03 1.0E+03 8.9E+02 1345 ARRIVAL TIME 1349 1354 1402 1411 1419 1428 1436 1445 1454 1502 1511 1519 t READIN6 7.0E+04 3.9E+04 1.3E+04 6.BE+03 4.2E+03 2.9E+03 2.2E+03 1.6E+03 1.3E+03 1.1E+03 9.0E+02 7.9E+02 1400 ARRIVAL TIME 1404 1409 1417 1426 1434 1443 1451 1500 1509 1517 1526 1534 READIN6 1.7E+04 9.2E+03 3.tE+03 1.6E+03 9.BE+02 6.BE+02 5.0E+02 3.9E+02 3.lE+02 2.5E+02 2.tE+02 1.8E+02 1430 ARRIVAL TIME 1434 1439 1447 1456 1504 1513 1521 1530 1539 1547 1556 1604 READING 6.2E+02 3.3E+02 1.1E+02 5.7E+01 3.5E+01 2.4E+01 1.BE+01 1.4E+0! 1.lE+01 9.0E+00 7.5E+00 6.4E+00 1500 ARRIVAL TIME 1504 1509 1517 1526 1534 1543 1551 1600 1609 1617 1626 1634 READING B.6E+00 4.6E+00 1.6E+00 B.0E-01 4.9E-01 3.4E-01 2.5E-01 1.9E-01 1.5E-01 1.3E-01 1.0E-01 8.9E-02 i 1530 ARRIVAL TIME 1534 1539 1547 1556 1604 1613 1621 1630 1639 1647 1656 1704 READING 7.2E-03 3.9E-03 1.3E-03 6.7E-04 4.!E-04 2.BE-04 2.tE-04 1.6E-04 1.3E-04 1.1E-04 B.BE-05 7.5E-05 TIME OF END OF RELEASE 1634 1639 1647 1656 1704 1713 1721 1730 1739 1747 1756 1904 NOTES: Use table values for areas shaded RED Use 0.1 of these values for areas shaded YELLON Use 0.5 of these values for areas shaded BLUE Use 0.01 of these values for areas shaded SREEN 1 of 1
O O O TABLE 7.4-4 October 17, 1985 CALCULATED DOSE RATES CALCULATED ONSITE RADIOLO6! CAL SURVEY DATA (1) From 1100 1145- 1200 1230 1300 1345 1430 1500 To 1145 1200 1230 1300 1345 1430 1500 END Whole Body Dose Rate (nR/hr) Upwind of Line A-A 4.0E+01 1.7E+03 3.3E+03 4.BE+03 4.9E+03 1.3E+03 4.BE+01 5.5E-01 Between A-A and B-B 5.0E+01 -2.1E+03 4.3E+03 5.4E+03 5.5E+03 1.5E+03 5.3E+01 6.1E-01 Downwind of Line B-B 5.4E+01 2.3E+03 4.4E+03 5.4E+03 5.5E+03 1.5E+03 5.3E+01 6.1E-01 Thyroid Inhalation Dose Rate (mR/hr) Upwind of Line A-A 3.2E+02 1.4E+04 3.0E+04 4.7E+04 5.0E+04 1.5E+04 5.5E+02 B.5E+00 Between A-A and B-B 4.1E+02 1.BE+04 3.9E+04' 5.3E+04 5.6E+04 1.7E+04 6.2E+02 9.5E+00 Downwind of Line B-B 4.4E+02 1.9E+04 4.0E+04 5.3E+04 5.6E+04 1.7E+04 6.2E+02 9.5E+00 !adine-131 Concentration (uti/cc) Upwind of Line A-A 2.6E-07 1.1E-05 2.4E-05 3.BE-05 4.0E-05 1.2E-05 4.4E 6.2E-09 Between A-A and B-B 3.3E-07 1.5E-05 3.1E-05 4.2E-05 4.5E-05 1.4E-05 5.0E-07 6.9E-09 Downwind of Line B-B 3.5E-07 1.6E-05 3.2E-05 4.2E-05 4.5E-05 1.4E-05 5.0E-07 6.9E-09 TCS Net Canister w/o Filter Count Rate (cpel Upwind of Line A-A 6.4E+02 2.BE+04 6.1E+04 9.4E+04 1.0E+05 3.1E+04 1.1E+03 1.7E+01 Between A-A and B-B 8.2E+02 3.6E+04 7.7E+04 1.1E+05 1.1E+05 3.4E+04 1.2E+03 1.9E+01 Downwind of Line B-B 8.7E+02 3.9E+04 B.1E+04 1.1E+05 1.1E+05 3.4E+04 1.2E+03 1.9E+01 SAM-2 Count Rate (cpa) Upwind of Line A-A 2.6E+04 1.1E+06 2.4E+06 3.BE+06 4.0E+06 1.2E+06 4.4E+04 6.2E+02 Between A-A and B-B 3.3E+04 1.5E+06 3.1E+06 4.2E+06 4.5E+06 1.4E+06 5.0E+04 6.9E+02 Downwind of Line B-B 3.5E+04 1.6E+06 3.2E+06 4.2E+06 4.5E+06 1.4E+06 5.0E+04 6.9E+02 Notes:
1. Use table values for areas shaded RED; Use 0.5 of these values for areas shaded BLUE; Use 0.1 of these values for areas shaded YELLOW; Use 0.01 of these values for areas shaded GREEN'.
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TABLE 7.4-3 October 17,1985 CALCULATED DOSE RATES CECEATES IDelE-131 CONCENTRATIN EONE CENTERIE OF PLlHE (stilcc) TIE SMWIN OF RELEASE / DISTANCE-NILES 0.5 1.0 2.0 3.0 4.0 5.0 6.0 7.0 B.0 9.0 10.0 !!.0 1(30 ARRIVE TIE 1032 1035 1039 1044 -1048 1853 1950 1102 1107 1112 1116 1121 READINE 5.0E-10 3.39E-10 1.1E-10 5.64E-11 3.67E-11 2.4K-11 1.78E-11 1.35E-11 1.07E-11 0.75E-12 7.34E-12 6.21E-12
!!00 ARRIVE TIE 1102 1105 1109 1114 1110 1123 1128 1132 1837 1142 11 % 1151 READINE 5.00E-09 3.39E-09 1.13E-09 5.64E-10 3.67E-10 2.4X-10 1.78E-10 1.35E-10 1.07E-10 8.75E-11 7.34E-!! 6.21E-11 1130 ARRIVE TIE 1132 1135 1139 1144 1148 1153 1150 1202 1207 1212 1216 1221 REASINE 2.08E-07 1.39E-07 4. E -08 2.31E-08 1.50E-00 , 9.93E-09 7.27E-09 5.54E-09 4.39E-09 3.58E-09 3.00E-09 2.54E-09 1145 ARRIVE TIME 1147 1150 1154 1159 1203 1200 1213 1217 1222 1227 1231 1236 READIN6 9.24E-M 6.16E-M 2.05E-06 1.03E-M 6.67E-07 4.41E-07 3.2K47 2.4E-07 1.95E-07 1.59E-07 1.3X-07 1.13E47 1200 ARRIVE TIME 1204 1209 1217 1226 1234 1243 1251 1300' 1309 1317' 1326 1334 REABINE 2.49E-05 1.37E-05 4.78E46 2.42E-06 1.50E46 1.05E-M 7.85E-07 5.82E-07 4.64E-07 3.79E-07 3.21E-07' 2.81E-07 1215 ARRIVE TIME 1219 1224 1232 1241 1249 1250 13M 1315 1324 1332 1341 1349 READINE 2.53E-05 1.40E-05 4.87E-M 2.47E-M 1.53E-M 1.07E-M I.00E-07 5.94E47 4.74E-07 3.B7E-07 3.27E-07 2.87E47 1230 ARRIVAL TIE 1234 1239 1247 1256 1304 1313 1321 1330 1339 1347 13 % 1404 REABIN6 2.6E-05 1.48E-05 5.15E-M 2.61E-M !.M-M 1.13E-M d.47E-07 6.20E-07 5.01E-07 4.09E-07 3.ME-07 3.03E47 1245 ARRIVE TIME 1249 1254 1302 1311 1319 1328 1336 1345 1354 1402 1411 1419 REAIIN6 2.83E-05 1.%E-05 5.43E46 2.75E-M 1.71E-M 1.19E-06 8.93E-07 6. E -07 5.2EE-07 4.32E-07 3.65E-07 3.2K-07 1300 ARRIVE TIE 1304 1309 1317 1326 1334 1343 1351 1400 1409 1417 1426 1434 READING 3.02E45 1.67E-05 5.81E-06 2.94E-06 1.BK-06 1.27E-M 9.54E47 7.00E-07 5.65E-07 4.6tE-07 3.90E-07 3.42E-07 1330 ARRIVE TIME 1334 1339 1347 13 % 1404 1413 1421 1430 1439 1447 14 % 1504 READilli 3.12E-05 1.72E-05 5.99E-06 3.04E-06 1.09E-06 1.31E-M 9.85E47 7.31E-07 5.03E-07 4.7E-07 4.02E-07 3.51 47 1345 ARRiv E TIME 1349 1354 1402 1411 1419 1428 1436 1445 1454 1502 1511 1519 READINE 2.78E-05 1.54E-05 5.34E-M 2.71E-M 1.68E46 1.17E46 8.77E-07 6.51E-07 5.19E-07 4.24E-07 3.50E47 3.14E-07 1400 ARRIVE TIME 1404 1409 1417 1426 1434 1443 1451 1500 1509 1517 1526 1534 READIN6 6.82E-M 3.6E-M 1.24E-M 6.34E-07 3.90E-07 2.68E-07 1.97E-07 1.54E-07 1.22E-07 9.99E-08 .
8.29E-08 7.07E-40 1430 ARRIVE TIE 1434 1439 1447 14 % 1504 1513 1521 1530 1539 1547 15 % 1604 REABINE 2.44E-07 1.31E-07 4.45E-08 2.27E-08 1.40E48 9.59E-09 7.07E-09 5.50E-09 4.3E-09 3.58E-09 2.97E-09 2.5K-09 1500 ARRIVE TIME 1504 1509 1517 - 1526 1534 1543 1551 1600 1609 1617 1624 1634 REABING 3.41E-09 1.B3E-09 6.21E-10 3.17E-10 1.95E-10 1.34E-10 9.87E-11 7.6EE-11 6.09E-11 5.00E-11 4.14E-11 3.53E-11 1530 ARRIVE TIE 1534 1539 1547 15 % 1604 1613 1621 1630 1639 1647 16 % 1704 REA81NE 2.97E-12 1.54E-12 5.23E-13 2.67E-13 1.64E-13 1.13E-13 B.31E-14 6.4E-14 5.13E-14 4.21E-14 3.49E-14 2.9E-14 TIME OF END OF RELEASE 1634 1639 1647 1656 1704 1713 1721 1730 1739 1747 1756 1904 NOTES: Use table values for areas shaded RED Use 0.1 of these values for areas shaded YELLON Use 0.5 of these values for areas shaded EE Use 0.01 of these values for areas shaded MEEN 1 of I
( (- N TABLE 7.5-1 October 17,1985 l FIELD MONITORING DATA MEASURED WHOLE B00Y DOSE RATE ALONG CENTERLINE OF PLUME (eR/Hr) TIME DOWNute OF EELEASE/ DISTANCE-MILES 0.5 1.0 2.0 3.0 4.0 5.0 6.0 7.0 B.0 9.0 10.0 11.0 1030 ARRIVAL TIE 1032 1035 1039 1044 1048 1053 1058 !!02 1107 1112 1816 1121 READIN6 1.7E-01 1.2E-01 3.BE-02 1.9E-02 1.3E-02 h4 H NA NA NA M MA 1100 ARRIVAL TIME 1102 1105 1109 1114 1118 1123 1128 1D2 !!37 1142 1146 1151 READING 1.6E+00 1.1E+00 3.6E-01 1.BE-01 1.2E-01 7.7E-02 5.6E-02 4.3E-02 3.4E-02 2.BE-02 2.3E-02 2.0E-02
!!30 ARRIVAL TIME 1132 1135 1139 1144 1148 1153 1158 1202 1207 1212 1216 1221 READlh6 6.6E+0! 4.4E+0! 1.5E+01 7.3E+00 4.BE+00 3.2E+00 2.3E+00 1.9E+00 1.4E+00 1.1E+00 9.5E-01 B.1E-01 1145 ARRIVAL TIME 1147 1150 1154 1159 1203 1208 1213 1217 1222 1227 1231 1236 READIN6 2.7E+03 1.BE+03 6.1E+02 3.0E+02 2.0E+02 1.3E+02 9.6E+01 7.3E+01 5.8E+0! 4.7E+01 4.0E+01 3.3E+01 1200 ARRIVAL TIE 1204 1209 1217 1226 1234 1243 1251 1300 1309 1317 1326 1334 READING 7.4E+03 4.1E+03 1.4E+03 7.2E+02 4.5E+02 3.1E+02 2.3E+02 1.7E+02 1.4E+02 1.1E+02 9.5E+01 B.3E+01 1215 ARRIVAL TIME 1219 1224 1232 1241 1249 1258 1306 1315 1324 1332 1341 1349 READING 7.0E+03 3.9E+03 1.4E+03 6.9E+02 4.3E+02 3.0E+02 2.2E+02 1.6E+02 1.3E+02 1.!E+02 9.lE+01 B.0E+01 1230 ARRIVAL TIME 1234 1239 1247 1256 1304 1313 1321 1330 1339 1347 1356 1404 READING 7.4E+03 4.1E+03 1.4E+03 7.2E+02 4.5E+02 3.1E+02 2.4E+02 1.7E+02 1.4E+02 1.!E+02 9.6E+01 8.4E+01 1245 ARRIVAL TIME 1249 1254 1302 1311 1319 1328 1336 1345 1354 1402 1411 1419 READING 7.4E+03 4.1E+03 1.4E+03 7.2E+02 4.5E+02 3.lE+02 2.3E+02 1.7E+02 1.4E+02 1.tE+02 9.5E+01 B.3E+01 1300 ARRIVAL TIME 1304 1309 1317 1326 1334 1343 1351 1400 1409 1417 1426 1434 READING 7.4E+03 4.!E+03 1.4E+03 7.2E+02 4.5E+02 3.1E+02 2.3E+02 1.7E+02 1.4E+02 1.1E+02 9.5E+0! B.4E+01 1330 ARRIVAL TIME 1334 1339 1347 1356 1404 1413 1421 1430 1439 1447 1456 1504 READING 7.6E+03 4.2E+03 1.5E+03 7.4E+02 4.6E+02 3.2E+02 2.4E+02 1.BE+02 1.4E+02 1.2E+02 9.9E+01 8.6E+0!
1345 ARRIVAL TIME 1349 1354 1402 1411 1419 1429 1436 1445 1454 1502 1511 1519 READIN6 6.4E+03 3.5E+03 1.2E+03 6.2E+02 3.9E+02 2.7E+02 2.0E+02 1.5E+02 1.2E+02 9.BE+01 B.3E+0! 7.3E+0! 1400 ARRIVAL TIME 1404 1409 1417 1426 1434 1443 1451 1500 1509 1517 1526 1534 READIN6 1.5E+03 B.0E+02 2.7E+02 1.4E+02 B.5E+01 5.9E+01 4.3E+01 3.4E+0! 2.7E+01 2.2E+01 1.8E+0! 1.5E+01 1430 ARRIVAL TIME 1434 1439 1447 1456 1504 1513 1521 1530 1539 1547 1556 1604 READING 5.3E+01 2.9E+01 9.7E+00 5.0E+00 3.0E+00 2.1E+00 1.5E+00 1.2E+00 9.5E-01 7.BE-01 6.5E-01 5.5E-01 1500 ARRIVAL TIE 1504 1509 1517 1526 1534 1543 1551 1600 1609 1617 1626 1634 READING 6.7E-01 3.6E-01 1.2E-01 6.2E-02 3.BE-02 2.6E-02 1.9E-02 1.5E-02 1.2E-02 NA M M 1530 ARRIVAL TIME 1534 1539 1547 1556 1604 1613 1621 1630 1639 1647 1656 1704 READING M NA NA NA NA NA E NA NA NA M NA TIPE OF END OF RELEASE 1634 1639 1647 1656 1704 1713 172 1730 1739 1747 1756 1904 NOTES: Use table values for areas shaded RED Use 0.1 of these values for areas shaded YELLOM Use 0.5 of these values for areas shaded BLUE Use 0.01 of these values for areas shaded EREEN NA - Less than .01 mRlhr For CLOSEP MINDON readings, use above values. For OPEN WIND 0M readings, use 3 TIMES the above values. 1 of 1
p p f"\ TABLE 7.5-2 October 17,1985 FIELD MONITORING DATA MEASURED TCS CMISTER (NIO FILTERI READINGS ALON6 CENTERLIIE OF PLINIE (CPM AIOVE BACK6ROUNB) i TIE D0uleIIND OF RELEASE / DISTANCE-MILES 0.5 1.0 2.0 3.0 4.0 5.0 6.0 7.0 B.0 9.0 10.0 !!.0 1030 ARRIVAL TIE 1032 1035 1039 1044 1048 1053 1058 1102 1107 1112 1116 1121 READIN6 M M M M NA M M M M M M M 1100 MRIVAL TIME 1102 1105 1109 1114 1118 1123 1128 1132 1137 1142 1146 1151 READING NA NA NA E M M M M M M M M 1130 ARRIVAL TIME 1132 1135 1139 1144 1148 1153 1158 1202 1207 1212 1216 1221 READINE 1.0E+03 7.0E+02 2.3E+02 1.2E+02 M M M M M M M 11 4 1145 ARRIVAL TIME 1147 1150 1154 1159 1203 1208 1213 1217 1222 1227 1231 1236 READIN6 4.7E+04 3.1E+04 1.0E+04 5.2E+03 3.4E+03 2.2E+03 1.6E+03 1.2E+03 9.BE+02 B.0E+02 6.7E+02 5.7E+02 1200 MRIVAL TIME 1204 1209 1217 1226 1234 1243 1251 1300 1309 1317 1326 1334 READING 1.3E+05 6.9E+04 2.4E+04 1.2E+04 7.6E+03 5.3E+03 4.0E+03 2.9E+03 2.3E+03 1.9E+03 1.6E+03 1.4E+03 1215 MRIVAL TIME 1219 1224 1232 1241 1249 1258 1306 1315 1324 1332 1341 1349 READING 1.3E+05 7.1E+04 2.5E+04 1.2E+04 7.7E+03 5.4E+03 4.0E+03 3.0E+03 2.4E+03 1.9E+03 1.6E+03 1.4E+03 1230 ARRIVAL TIME 1234 1239 1247 1256 1304 1313 1321 1330 1339 1347 1356 1404 READING 1.4E+05 7.5E+04 2.6E+04 1.3E+04 B.2E+03 5.7E+03 4.3E+03 3.2E+03 2.5E+03 2.lE+03 1.7E+03 1.5E+03 1245 MRIVAL TIME 1249 1254 1302 1311 1319 1328 1336 1345 1354 1402 1411 1419 READING 1.4E+05 7.9E+04 2.7E+04 1.4E+04 B.6E+03 6.0E+03 4.5E+03 3.3E+03 2.7C+03 2.2E+03 1.9E+03 1.6Dd3 1300 MRIVAL T!!E 1304 1309 1317 1326 1334 1343 1351 1400 1409 1417 1426 1434 READINS 1.5E+05 B.4E+04 2.9E+04 1.5E+04 9.2E+03 6.4E+03 4.BE+03 3.6E+03 2.K+03 2.3E+03 2.0E+03 1.7E+03 1330 ARRIVAL TIME 1334 1339 1347 1356 1404 1413 1921 1430 1439 1447 1456 1504 READIN6 1.6E+05 B.7E+04 3.0E+04 1.5E+04 9.5E+03 6.6E+03 5.0E+03 3.7E+03 2.9E+03 2.4E+03 2.0E+03 1.E+03 1345 MRIVAL TIME 1349 1354 1402 1411 1419 1428 1436 1445 1454 1502 1511 1519 READIN6 1.4E+05 7.7E+04 2.7E+04 1.4E+04 B.5E+03 5.9E+03 4.4E+03 3.3E+03 2.6E+03 2.1E+03 1.K+03 1.6E+03 1400 MRIVAL TIME 1404 1409 1417 1426 1434 1443 1451 1500 1509 1517 1526 1534 READIN6 3.4E+04 f.K+04 6.3E+03 3.2E+03 2.0E+03 1.4E+03 9.9E+02 7.7E+02 6.1E+02 5.0E+02 4.2E+02 3.6E+02
~
1430 ARRIVAL TIME 1434 1439 1447 1456 1504 1513 1521 1530 1539 1547 1556 1604 READING 1.2E+03 6.6E+02 2.2E402 1.1E+02 M M M NA NA IIA IIA NA 1500 ARRIVAL T!!E 1504 1509 1517 1526 1534 1543 1551 1600 1609 1617 1626 1634 READING NA M llA IIA IIA E IIA IIA NA NA IIA M 1530 ARRIVAL TIME 1534 1539 1547 1556 1604 1613 1621 1630 1639 !&47 1656 1704 READIN6 NA IIA NA NA M llA NA IIA NA NA E NA T!!E OF END OF RELEASE 1634 1639 1647 1656 1704 thl3 1721 1730 1739 1747 1756 1904 NOTES: Use table values for areas shaded RED Use 0.1 of these values for areas shaded YELLON Use 0.5 of these values for areas shaded BLUE Use 0.01 of these values for areas shaded EREEN NA - Less than 100 cpa net on cartridae BASED UPON SAMPLE VOLUME OF 25 CUBIC FEET. FILTER CPM A60VE BACK6ROUNO = 0 1 of 1
p ,,- y TABLE 7.5-3 October 17,1995
.- FIELD MONTTORING DATA MEASURED SAM-2 READINGS ALON6 CENTERLINE OF PLipE (CPM ABOVE BACK6ROUM)
TIME DONMIND OF RELEASE / DISTANCE-MILES 0.5 1.0 2.0 3.0 - 4.0 5.0 6.0 7.0 5.0 9.0 10.0 11.0 1030 ARRIVAL TIME 1032 1035 / 1039 1044 1H8 1053 1050 1102 1107 til2 1116 1121 READING 5.lE+0! NA ' NA NA E M NA E M M M J M 1100 ARRIVAL TIE 1102 1105 !!0f ' 1:14 !!!B 1123 1128 1132 !!37 1142 1146 . 1151 READIN6 5.lE+02, 3.4E+02 ' l.!E+02 5.6E+01 M M M M M M M
AA -
1130 ARRIVAL TIME 4 132 1135 1139 1144 1148 ' 1153 1158 1202 1207 1212 1216 122i READIN6 2.1E+04 1.4E+04 4.6E+03 2.3E+03 1.5E+03 9.9E+02 7.3E+02 5.5E+02 4.4E+02 3.6E+02. 3.0E+02 2.5E+02
~ 1145 ARRIVAL TIME _ 1147 rr 1150 $ 115a 1151 1203 1208 1213 1217 1222 1227 1231 1236 s '- I"AMN6 9.2E+05 / 6.2E+05 ' 2.!E+05 1.0E+05 6.7E+04 4.4E+04 3.2E+04 2.5E+H ~l.9E+04 1.6E+04 1.3E+04 1.tE+04 r /1 1200 'ARRIVAt TIME 1204 . .1209 1217 1226 1234 1243 1251 1300 1309 1317 1326 1334
~ ' READIN6 2.5E+06 1.4E+06 4.9E+05 2.4E+05 1.5E+05 1.0E+05 7.9E+04 5.9E+04 4.6E+04 3.8E+04 3.2E+04 2.P.+04 s 1215 APRIVAL TIME I1219 1:24 1232 1241 !!49 1258 1306 1315 1324 1332 1341 1349 READIC ?.5E+06 1.4E+06 4.9E+05 2.5E+05 1.5E+05 1.1E+05 8.0E+04 5.9E+04 4.7E+04 3.9E+H 3.3E+04 2.9E+04 - 1230 ARRIVAL TIME 1234 1239 1247 1256 1304 1313 1321 1330 133? 1347 1356 1404 J READIN6 2.7E+06 1.5E*06 5.2E+05 2.6E+05 1.6EiO5 1.1E+05 8.5E+04 6.3E+04 5.0E+04 4.lE+04 3.5E+04 3.0E+04 4 1245 ARRIVAL TIME 1249 1254 1302 11311 1319 1328 1336 1345 1354 1402 1411 1419 READING 2.9E+06 1.6E+06 5.4E+05 2.8E+05 1.7E+05 1.2E+05 8.9E+H 6.6E+04 5.3E+04 4.3E+H 3.6E+04 3.2E+04 1300 ARRIVAL TIME 1304 1309 1317 1326 1334 1343 1351 1400 1409 1417 1426 1434 READING 3.0E+06 1.7E+06 5.9E+05 2.9E+05 1.SE+05 1.3E+05 9.5E+04 7.1E+04 5.6E+04 4.6E+04 3.9E+04 3.4E+04 1330 ARRIVAL TIME 1334 1339 1347 1356 1404 1413 1421 1430 1439 1447 1456 1504 READINS 3.lE+06 1.7E+06 6.0E+05 3.0E+05 1.9E+05 1.3E+05 9.9E+04 2.3E+04 5.BE+04 4.BE+04 4.0E+04 3.5E+04 1345 ARRIVAL TIME 1349 1354 1402 1411 1419 1428 1436 1445 1454 1502 1511 1519 READIN6 2.BE+06 1.5E+06 5.3E+05 2.7E+05 1.7E+05 1.2E+05 B.8E+04 6.5E+04 5.2E+04 4.2E+04 3.6E+04 3. lE+H 1400 ARRIVAL TIME 1404 1409 1417 1426 1434 1443 1451 1500 1509 1517 1526 1534 READING 6.BE+05 3.7E+05 1.2E+05 6.3E+04 3.9E+04 2.7E+04 2.0E+04 1.5E+H 1.2E+04 1.0E+04 B.3E+03 7.!E+03 1430 ARRIVAL TIE 1434 1439 1447 1456 1504 1513 1521 1530 1539 1547 1556 1604 READING 2.4E+04 1.3E+04 4.4E+03 2.3E+03 1.4E+03 9.6E+02 7.lE+02 5.5E+02 4.4E+02 3.6E+02 3.0E+02 2.5E+02 1500 ARRIVAL TIME 1504 1509 1517 1526 1534 ~ 1543 1551 1600 1609 1617 1626 1634 READING 3.4E+02 1.BE+02 6.2E+0! NA M M hA M M M M M 1530 ARRIVAL TIME 1534 1539 1547 1556 1604 1613 1621 1630 1639 1647 1656 17H READING MA M M hA NA M M M M M M M TIME OF END OF RELEASE 1634 163a 1647 1656 1704 1713 1721 1730 1739 1747 1756 1904 NOTES: Use table values for areas shaded RED Use 0.1 of these values for areas shaded YELLON Use 0.5 of these values for arets shaded BLUE Use 0.01 of these values for areas shaded GREEN NA - Less than 50 cpe above bactoround EASED UPON SAMPLE VOLUME OF 60 CUBIC FEET 11N11 uti/cc PER cpel 1 of 1
Om bS d TABLE 7.5-4 October 17, 1985 FIELD MONITORING DATA MEASURED ONSITE RADIOLOGICAL SURVEY DATA (1) From 1100 1145 1200 1230 1300 1345 1430 1500 To 1145 1200 1230 1300 1345 1430 1500 END Whole Body Dose Rate (aR/hr) Upwind of Line A-A 4.0E+01 1.7E+03 3.3E+03 4.BE+03 4.9E+03 1.3E+03 4.BE+01 5.5E-01 Between A-A and B-B 5.0E+01 2.1E+03 4.3E+03 5.4E+03 5.5E+03 1.5E+03 5.3E+01 6.1E-01 Downwind of Line B-B 5.4E+01 2.3E+03 4.4E+03 5.4E+03 5.5E+03 1.5E+03 5.3E+01 6.1E-01 Thyroid Inhalation Dose Rate (mR/hr) Upwind of Line A-A 3.2E+02 1.4E+04 3.0E+C4 4.7E+04 5.0E+04 1.5E+04 5.5E+02 B.5E+00 Between A A and B-B 4.1E+02 1.BE+04 3.9E+04 5.3E+04 5.6E+04 1.7E+04 6.2E+02 9.5E+00 Downwind of Line B-B 4.4E+02 1.9E+04 4.0E+04 5.3E+04 5.6E+04 1.7E+04 6.2E+02 9.5E+00 lodine-131 Concentr6 tion (uCi/cc) Upwind of Line A-A 2.6E-07 1.1E-05 2.4E-05 3.eE-05 4.0E-05 1.2E-05 4.4E-07 6.2E-09 Between A-A and B-B 3.3E-07 1.5E-05 3.1E-05 4.2E-05 4.5E-05 1.4E-05 5.0E-07 6.9E-09 Downwind of Line B-B 3.5E-07 1.6E-05 3.2E-05 4.2E-05 4.5E-05 1.4E-05 5.0E-07 6.9E-09
~
TCS Net Canister w/o Filter Count Rate (cps) Upwind of Line A-A 6.4E+02 2.BE+04 6.1E+04 9.4E+04 1.0E+05 3.1E+04 1.1E+03 (100 Between A-A and B-B B.2E+02 3.6E+04 7.7E+04 1.1E+05 1.1E+05 3.4E+04 1.2E+03 (100 Downwind of Line B-B B.7E+02 3.9E+04 B.1E+04 1.1E+05 1.1E+05 3.4E+04 1.2E+03 (100 SAM-2 Count Rate (cpe) Upwind of Line A-A 2.6E+04 1.1E+06 2.4E+06 3.BE+06 4.0E+06 1.2E+06 4.4E+04 6.2E+02 Eetween A-A and B-B 3.3E+04 1.5E+06 3.1E+06 4.2E+06 4.5E+06 1.4E+06 5.0E+04 6.9E+02 Downwind of Line B-B 3.5E+04 1.6E+06 3.2E+06 4.2E+06 4.5E+06 1.4E+06 5.0E+04 6.9E+02 Notes:
1. Use table values for areas shaded RED; Use 0.5 of these values for areas shaded BLUE; Use 0.1 of these values for areas shaded YELLOW; Use 0.01 of these values for areas shaded GREEN. 1 og i
y s < t TABLE 7.6-1
' .3 ',
1.l(m
- OCTOBER 17, 1985, NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION .,, 0800 0830 0930 1030 1130 1230 1330 1430 0830 0930 1030 1130 1230 1330 1430 1630
~ Ambient Radiation Level (mR/hr) , IF 20 60 150 500 3P3 2P4 IPS. 2P5 2F , 4 15 30 100 600 4P3 2P4 4P4 3F - - 5 10 40 250 1.5P3 8P3 1.5P4 4F # _ _ 3.5 15 90 500 2.5P3 SP3 7 1G 4 4 15 200 2P3 2P3 600 150 2G 2 2 7 100 1P3 IP3 300 70 General Area Radwaste - - - - - - - 2.5 l Reactor "As read" for the duration of the exercise ARM 1-2 "As read" for the duration of the exercise 1-3 "As read" for the duration of the exercise 1-4 "As read" for the duration.of the exercise
+
1-5 "As read" for the duration of the exercise
'l-6 "As read" for the duration of the exercise CN.. 1-7 1-8 "As read" for the duration of "As read" for the duration of the' exercise the exercise 4-6 20 20 20 20 20 20 20 20 Contamination Survey (dpm/100 cm 2)
General Areas Radwaste 300. 360. 500. 700. 1.P3 1.P3 1.P3 1.5P3 Reactor. "As read" for the duration of the exercise Note: Survey mete'r readings of swipes in cpm are 1/10 of contacination values in dpm per 100 cm2 Airborne Radioactivity Level l General Areas Radwaste green green green green green- yellow yellow green Reactor. "As read" for the duration of the exercise l I l 4 l
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.. i ,*, -
T 6E f~<
= S -W R A '1 O W 9P F
1
. . .1 m: .
D A
,C "O M I
R T 2O
'8 T .* 6.- uuJ fr i. DI 8 A F
2 G
- 2 . NN .M 6 - 2 4 5 l L
I A UL O l
M l
- - - E T R M RG T TO F
3 M R . G I A-M R A R A '6 6.ON 7 E TI B 5 A 8 C D 6'. A - e.: .k L NH / j
,g . !GRUA GEUL I AC A 7
1
/
e jl
.E N ,D"
_ I FRBPP E 0 1
.. g I.I B
CP 3 l.M i. o . C R PU HT C C. RPU
a. ..!e Q : ' - ?. . * , -
.y .
o 4 l
- J[ 0 .
g M R 8
~ )J A - I. ,(\ w I
M #
.\
R A
i
.. i 3 . e..
1
- I. . M R
F.
., A i. %S ;U P
M P Y A j R l. P
-,. 2,',- S . ) . ' E .
P . R Y T O ( C R E i. G N A H C g .- 5 x E T A o -.. . g E .' ~i*. S '. !.
! Ii H
g 7 i 6 a-
?. ' ,* ~
i) . - .. 7 P - .,,/Q
- M Q1 M
U P) RY P e b D g e g R HT A R( i
TABLE 7.6-2' OCTOBER 17, 1985, NRC OBSERVED EMERGENCY RESPONSE EXERCISE
, PEACH BOTTOM ATOMIC POWER STATION N
0800 0830 0930 1030 1130 1230 1330 1430 0830 0930 1030 1130 1230 1330 1430 1630 Ambient Radiation Level (mR/hr) General' Areas Radwaste "As read" for the duration of the exercise l Reactor "As read" for the duration of the exercise ~ ARM 1-10 "As read" for the duration of the exercise 1-11 "As read" for the duration of the exercise 1-12 "As read" for the duration of the exercise 4-7 1 1 1 1 1 1 1 1 l Contamination Survey (dpm/100 cm 2) General Areas Radwaste 200 200 300 300 600 600 900 IP3 Reactor "As read" for the duration of the exercise Note: Survey meter readings of swipes in epm are 1/10 of contamina-tion values in dpm per 100 cm2
;/5) -
Airborne Radioactivity Level General Areas Radwaste green green green green green yellow green green Reactor "As read" for the duration of the exercise I 1 1 of I s
Ii Nc
- N c O . - I ~, T , 4 A T
q S p . ', * ., 1. a
' .h l
E T S R E W I. A O
- W P D "O C E
9, is A2- MI G) i-R '6 O RP UY M7 , T1 T ST . '. R- E . .
DI 1 A A4 NN . E( TK SN OQ [ nT> >
!,I -
2A ULM EO AA - T l iI
^
WT
6. R G TT
[,\ 7ON TI A O B 5 8 C D
/
E L NH 7 1 R 2 zl. h UAI GEUL I ACA / E 01 FRBPP 1 l . g M , O R A g e J
. J. +. ., j' .'il:
c
- b O s a,I.b ~, 1 .N 1
~ 7 1 M 1 R A I.h
.:s 0
I. h - 1 .
) - -
P 1 Y T ( M R R E G N A l, I.h A H * . C -. X E T O
,' c A , - . . , . ' I-E ,.
a_ H _ w - [ 6 g g
O @
\
e @ t
TABLE 7.6-3 /~N \ OCTOBER 17, 1985, NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION 0800 0830 0930 1030 1130 1230 1330 1430 0830 0930 1030 1130 1230 1330 1430 1630
' Ambient Rad' iation Level (mR/hr)
Ceneral Areas Radwaste "As read" for the duration of the exercise l Reactor 'As read" for the duration of the exercise ARM 2-5 "As read" for the duration of the exercise 2-6 "As read" for the duration of the exercise 2-7 "As read" for the duration of the exercise 2-8 "As read" for the duration of the exercise 4-9 10 10 10 10 10 10 10 10 4-10 20 20 20 20 20 20 20 20 4-11 25 25 25 25 25 25 25 25 Contamination Survey (dpm/100 cm2 ) Ceneral Areas Radwaste 200 200 400 600 900 900 IP3 1.5P3 jg Reactor "As read" for the duration of the exercise
]
Note: Survey meter readings of swipes in cpm are 1/10 of contamination values in dpm per 100 cm 2 Airborne Radioactivity Level General Areas Radwaste green green green green green green green green Reactor "As read" for the duration of the exercise I
. .. )
1 f\- J 1 1 I 1 of I l
N
,, '._ .6 IO .. T < A - T 4 S E R T E S W u A O W "O P D - CI A 2 '5 M 4 3,!b R
c :g : DI T3 TO 1 A M0 N NN . R-1 Mi U EO LM A4 R' i 3A g A4 T i? -
*0 n 6RG 7.O N AO TT 5 3
TID B 8/
g 9
- ~
E R C L NH 7 1 U 4 ~ UAI A C IGEULE A0 /
.,I R .
M R A ^ r FRBPP 1 n 6 L
=
i
= " !b ~
j I
> s, , - ; 4 = .,I.
Pb MI ' R' E e- l 1
!E ,'t i
y? y n
,0 e.
8
!E 6 2 2
M R , 7 M R A A{ 4 -
!E L g '
o M5 R,
/._
sh d_
- r!E h \ & @ @ )
i ( k
TABLE 7.6-4 OCTOBER 17, 1985, NRC OBSERVED EMERGENCY RESPONSE EXERCISE , . FEACH BOTTOM ATOMIC POWER STATION 0800 0830 0930 103U 1130 1230 1330 -1430 0830 0930 1030 1130 1230 1330 1430 1630 Ambient Radiation Level (mR/hr) , General Areas. "As read" for the duration of the exercise l
. ARM 4-12 3 3 3 3 3 3 3 3 Contamination Surveys (dpm/100 cm 2)
General Areas 300 300 300 300 300 400 400 400 Note: Survey meter readings of swipes in cpm are 1/10 of conta-mination values in.dpm per 100 cm2 Airborne Radioactivity Level General Areas green green green green green green green green i-Y O 1 of 1
O. 2:== > CN-
=$ @ g p- 9 4,;
2 9 e lM %k G-ARM 4-12 O- ;.,- y aa w O'. s i $ks :sde d . . c,.. , o V e-b i'yic :@.y M
, #g& ?<
h k.W 1% 7[d e e FIGURE 7.6-4 RADWASTE BUILDING-UNIT 2 {' s PL AN AT EL.150'-O" PEACH BOTTOM ATOMIC POWER STATION 10/17/85
TABLE 7.6-5 OCTOBER 17, 1985, NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION U[ 0800 0830 0930 1030 1130 1230 1330 1430 0830 0930 1030 1130 1230 1330 1430 1630 Ambient Radiation Level (mR/hr) General Areas Radwaste "As read" for the duration of the exercise l Reactor "As read" for the duration of the exercise i ARM 2 - 11 "As read" for the duration of the exercise 2 - 12 "As read" for the duration of the exercise Contamination Surveys (dpm/100 cm 2) General Areas Radwaste 200 200 200 200 200 200 200 200 Reactor "As read" for the duration of the exercise Note: Survey meter readings of swipes in epm are 1/10 of contamina-tion values in dpm per 100 cm 2
.f\
() ' Airborne Radioactivity Level General Areas Radwaste green green green green green green green green Reactor "As read" for the duration of the exercise 1 f V. , I of 1
hc c N O 4
- 'a =
IT A T c E S T R
<. S E A W ' O r- W P g , ,e D A "O C - I R 2 '5 M O d DIT6T A 1
NN . 5AU LM
- EO T
6. R G TT
))
7ON A BO 5/8 I L1 lH E R TI C D NH 7 l1 I1
- UAI LAC A /1 H1 1 b GEUL E 0 I
1 FRBPP j e g t e M1 1 R- -
~
J A2
- w (N u e j6 i = \ /
6 u - e 2 1 2 M
~' \
WP ' qn
,e R - ,
A ir g l l u u, 3 i i
}e Lu - -
l r
,S ,e @ g O g g @
TABLE 7.6-6
..- OCTOBER 17, 1985, NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION J
0800 0830 0930 1030 1130 1230 1330 1430 0830 0930 1030 1130 1230 1330 1430 1630 Ambient Radiation Level (mR/hr) General Areas All values are "As Read" for this exercise in Reactor Building-Unit 2-El. 195 ft. and 214 ft. ARM 3-6 5-2 Contamination Survey (dpm per 100 cm 2) General Areas Note: Survey meter readings of swipes in cpm are 1/10 of 2 contamination values in dpm per 100 cm Airborne Radioactivity Level f
-( General Area O
1 of 1 a
w < a>, o O @ @ @ @ @ @ V
& _ .~ . :.g:. g, ,g. ... 3 . 3.
a.: w., t 5 i Oc ...
d? 'YiNY:'h N'hk 4'$ki
.t;:
Yk
?
1iif-bhi- 'f I'3 i 1 g__s lu l
..MMW- ;?.* .'. 4. ,. - c; - . .. y. "Ekhf :[hd.) ItIh hd..
b i, ARM 5-2 4 II 1 -h - a :9.Te a : ..tr
+ W.4. s p *.
s.. ARM 3-6' , p ..a z EEt ,,< p o -- R E h Q Y.. h?. -
2. .%.: :&. R 5 w~ ~4 v .. . .vX ,-s% .
&G 4
h kI I2 E -,-,,:
s. E t h(-d '
PLAN AT E L. 214'- O"
'O h h h 17 FIGURE 7.6-6 REACTOR AND RADWASTE BUILDING-UNIT 2 PL AN AT EL.195'-0" PEACH BOTTOM ATOMIC POWER STATION 10/17/85
TABLE 7.6-7 OCTOBER 17, 1985, NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION 0800 0830 0930 1030 1130 1230 1330 1430 0830 0930 1030 1130 1230 1330 1430 1630 Ambient Radiation Level (mR/hr) [ General Areas All values are "As read" for this exercise in Reactor Building - Unit 2- El. 234 ft. { t ARM 3-7
' 3-8 3-9 3-10 1-l - Contamination Survey (dpm/100 cm 2)
, ' General-Areas ~ Note: ' Survey meter reading of swipes in cpm are 1/10 of contamina-tion values in dpm per 100 cm 2
Airborne Radioactivity Level General' Area
'e v 4 f 4 1 4 O 1 of 1 "w-- ,e , e-e,- y-%-- r -
, .,.-,.-,--7,,. - - --.,,-y-me.--,,.------m_wc,.- -,.------._,,,-,,,..,,.----.--en- v--_---- - - r -'
- N O
O I T A 4 T S E R
~ 0 1
3 9 3 T S A E W O "O P M M W R R D CI A A A 2'4 M y R T2T3O
- r, 8 1
DN .A I
l
" 7 NULM A Eu i , 6 T = 7. R G T O 5 i ONAB 8 l I ETI D RC L NHC / 71 71 UAI GEULE I
A A/ 0 FRBPP 1
. 5 1
8 3 O M R A 3 1
. 2 1
0 1 l i , 7 h 3 M R g A b @ @ g O i
TABLE'7.6-8 OCTOBER 17, 1985, NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION i 0 V 0800 0830 0930 1030 1130 1230 1330 1430 0830 0930 1030 1130 1230 1330 1430 1630 i j Ambient Radiation Level (mR/hr) General Area All values are "as read" for this exercise in Turbine Building - Unit 2 - El 116 ft
., ARM 1-9 i 2-1 l 2-3' i 2-4 Contamination Survey (dpm per 100 cm2)
General Area Note: Survey meter readings of swipes in epm are 1/10 of contamina-tion values in dpm per 100 cm2 Airborne Radioactivity Level General Area O I ' 8 4 I 1 of 1
-,-,~-,-.,,,-.,n, - , , , , - - - , - - - , _ . - , , - - , , - - - - . . , , - , .,, - - , , , , - , , , - - - ~ . . - - .--,-,n. .-r-..w , - - - . , - - ,
I g' J a L , - - U
- N O ] ?
I 76 I
- T ^,
( N
~ . _ , 2 A T
S TI R x s. N E W U O P q6 l 1 4 3 G"OC
=
NMI D '6 O I 1
= .
1 UIL1 .A 4 LM T
- 3 M 8- BE O T h P R A
eI 6. 7NA ETO T8 5 j,', E l B /7
. R BNH 1
n. URA CA /
IE GUL I E 0 1 _'- FTPP gl
.U ,
M 9* L R. f M1 R-A2 T_
c-
'e .
l e i, .
~' . . .T R
E
.. - S N
s J i [8- E D N O C
~( L -
m * . i R
- E S
N h E D N O C i_,, - a . - . _. . l.
>_ r- R E
_ S N
E i
D N
. O i ' C n, :
s T.
b 3 i
+
2 i M R A- i2
d e Q { T. O M
R i A d i cT @ E ,'
)
( . qO
~-
eg-g O 9 O e
TABLE 7.6-9 OCTOBER 17, 1985, NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION 0800 0830 0930 1030 1130 1230 1330 1430 0830 0930 1030 1130 1230 1330 1430 1630 g
,_ Ambient Radiation Level (mR/hr)
General Area All values are "As read" for this exercise in the turbine building - Unit 2 El 135 ft { ARM 2-9. 2-10 Contamination Survey (dpm per 100 cm 2) { _ General Area Note: Survey meter readings of swipes in cpm are 1/10 of contamination values in dpm per 100 cm2 Airborne Radioactivity Level General Area O N J 4 4 % i- 1 of 1 i
. - , - , . . - , - - - - . , , - , . - , - , , _ . - - , - - - -- s
I' .l 'lllIi J
. =' '
N m ._
k. . _
- r N
h O J- T ATb I T
-7 .
r a 2 A T s r
= ,_ . - ,2. T S
I R
. N E g.
U" OW OP Pr n Tb GC I N'5 D M I N H 3O a E C P T IL1 TA OA H U LM . 9B EO 6 T 9 1 n Tb 7 ETT 5 3 NA O I B /8 E
. R URAC /
BNH 7 1 GUL A 0 E
-r e =- .. . - ,y I FTPP 1 a . n Tb 7*
k.
d. .
g
. ~ ]
Th 9
- " 2 .
j M R
\ =* ,.
Tb I A 0 1
'# . 2 I M R
A
<.i, ~ ;. .
Tb
\ ~
e
- f Y -
T cTb 1-s , . p ,
. , . ' . " 3 . ~ -
g@ o h h' @ g i
TABLE 7.6-10 OCTOBER 17, 1985, NRC OBSERVED EHERGENCY RESPONSE EXERCISE O PEACH BOTT(H ATOMIC POWER STATION 0800 0830 0930 1030 1130 1230 1330 1430 0830 0930 1030 1130 1230 1330 1430 1630 R Ambient Radiation Level (mR/hr) General Area All values are "As read" for this exercise in turbine building - Unit 2 - El 165 ft ARM 3-1 3-2 4-3 Contamination Survey (dpm/100 cm 2) General Area . Note: Survey meter readings of swipes in cpm are 1/10 of contamination
. values in dpm per 100 cm 2 Airborne Radioactivity Level General Area O
1 of 1
l T I N U we 3 R O T N A w- OI R gT4 - ' E T
+ 4,. N E A
^\s g
;G E
N I B 2 T T S R I E _ R T U N W O m gT6 U - G- C "OP I 3 H - N '5 M M O O C T A 4 ID6 O T R M M L1 A R I L N A 0ULM O R T E P O '# 1 BEO T N O m nT4 6.E T T 5 C a 7 NA BO 8 I / E R URAC / BNH 7 1 A b GUL E 0 FTPP I
. 1 , k nT5 ' h ,.l nl _..
l. 2-3 M
t r L !4 R d 0 A G FV n U nT4 Id 0 R O T A R
. E N
E
. G r-J LE nT4 . N I =. O R . EU 0 T
U N I A M
]
_ n!4
. J_
1
- s -
n!5 3 , M g11 R A
m. nT4 p'JQ t.
_ ~ r
!4 g& e e @ ' f , ,I! [ !
TABLE 7.6-11 OCTOBER 17, 1985,.NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC ~ POWER STATION 0800 0830 0930 1030 1130 1230 1330 1430 0830 0930 1030 1130 1230 1330 1430 1630
- Ambient Radiation-Level (mR/hr) '1A 5 5 5 30 160 300 400 400 2A 5 5 5 15 80 150 200 200 IB 2 2 2 25 150 750 800 800 2B 2 2 2 10- 60 300 320 320 2F 4 15 30 100 600 4P3 2P4 4P4 3F -
5 10 40 250 1.5P3 8P3 1.5P4 ' ] 4F - 1.5 3.5 15 90 500 2.5P3 SP3 l
.1G: 4 4 15 200 2P3 2P3 600 150 2G 2 2 7 '100 1P3 IP3 300 70 General Area - - - 5 8 10 10 10 l ARM 5-3 15 15 15 90* 800 800 250 50 -- 5-4 10 25 70 130* 600 3P3 3P3 3P3
s. :5-6 6*
.[ 5 2 2 -2 15 10* 80 130 700 800 300 1.5P3 1.5P3 400 60 100 5-10 2 2 2 20 120 600 650 650 Contamination Surveys (dpm/100 cm 2) Inside Horizontally Shaded .400 flooded during remainder of exercise
- Areas Inside Vertically Shaded 400 700 1P3 2P3 3P3 6P3_ IP4 Flooded Areas . General-Areas ~ 400 700 700 800 IP3 IP3 IP3 IP3 Note: Survey meter reading of swipes in cpm are 1/10 of contamination values in dpm per 100 cm 2 ' ' Airborne Radioactivity-Level - Inside Horizontally shaded yellow blue blue red white white white white -Areas- 'Inside Vertically shaded green yellow yellow yellow blue b2ue red white ' Areas /N General Areas. green green yellow yellow yellow blue bica blue 1 of 1
~* "
6 N O
'2 I 9 AT 3 E.T S
T "6- RE I N U '1 O W
- 9 P G" C NOI- M I
D L '8 O T s g e O e 9 1 I U 8A 1 B L.M EO T
6. R T T 5
_ 7O A B /8 O E T i O A R CNH 7 1 UAAC / A R GEL I E 0 1
. ~ - ~ 3" .. [ @ FRPP . A 8 s_
O1A 7
$[ . ,f Q g i
A @ 2 j Y i
. \ A P e ]
X , f, R P Y T
,N 3 / S EP RM L
S @ OU CP
) .
P Y TI R E , 4 G N s - A H C X E T p/- 4 '(k N O l 5 A M k^.. E H R . A 6-
'2B ..
6 5 M l
~
I h ~ . n,[7 R B A- s.N 1h C
- f. .
1. A -
- h ;oo } .k 1 - A .
Q 2, h2G - 5 . xG ,l i1 - G 1 R, G I f 42 .. h FaS 4 1 ' .- 1 g."F2 .
'j , Q
TABLE 7.6-12 OCTOBER 17, 1985, NRC OBSERVED DHERGENCY RESPONSE EXERCISE l '/ \ PEACH BOTTOM ATOMIC POWER STATION , .Y 0800 0830 0930 1030 1130 1230 1330 1430 0830 0930 1030 1130 1230 1330 1430 1630 Ambient Radiation Level (mR/hr) 3A 2 2 2 8 40 80 100 100 4A 2 2 2 4 20 40 50 50 3B 2 2 2 4 25 150 160 160 4B 2 2 2 2 10 60 65 65 IG 4 4 15 200 2P3 2P3 600 150 2G 2 2 7 100 1P3 IP3 300 70
~ General Area - - - -
2 2 3 3 l ARM 5-8 2 2 2 8 40 80 100* 100 5-9 2 2 2 4 20 40 50 50 l 5-12 1 1 1 1.5 4 25* 25 25 6-1 2 2 2 5* 30 190 200 200 6-2 1 1 1 1.5 2 2 3 3
'"' Contamination Surveys (dpm/100 cm2 )
General Area 200 300 400 400 600 600 600 600 Note: Survey meter readings of swipes in cpm are 1/10 of contamination values in dpm per 100 cm 2 t-Airborne Radioactivity Level blue ~ General Area green green green yellow yellow yellow blue L O 1 of 1 _ , ,.m - . , . , _ . , . _ . _.-- _,. _ . . - . - -
' N r'
x s O I T A
. 3 T S
4 T I R N E
- U W O - " P GO C g NMI I'
S D6 O1 R E 7 IL1.A T G N 2U LM A H C 1
- B EO T X @ @ @ g 6. R TT 5 E
7OAO B / 8 4 I f-T A# E HI _ E T RCNH 7 1 UAAC / A 0 GEL I E 1 FRPP Qb# _ - s g ; t M . O 5 R i' A i {i B l4
^
d '
) . \ .
a rO ld l$
. 2 1
5 M , ld R A . G 2 - B i i. e
^ -
A O3 - l5 OR d3 . n [2 A3 ld Q
, .f ~
y N
TABLE.7.6-13 < 's DCTOBER 17, 1985, NRC OBSERVED EHERGENCY RESPONSE EXERCISE PEACH BOTT(M ATOMIC POWER STATION 0800 0830 0930 1030 1130 1230 1330 1430 0830 0930 1030 1130 1230 1330 1430 1630 Ambient Radiation Level (mR/hr) General Area - - - - - 2.5 4 4 l
~ ARM 6-7 1 1 1 1 1.5 2.5 4 4 6-8 2 2 2 2 2 2.5 4 4 6-9 1 1 1 1 1.5 2.5 4 4 6-10 400 400 400 400 400 400 400 400 Contamination Survey (dpm/100 cm2 )
General Area 200 200 300 400 400 500 600 600
. Note: Survey meter readings of swipes in cpm are 1/10 of contamination 2
values in dpm per 100 cm Airborne Radioactivity Level General Area green green green yellow yellow yellow yellow yellow a O 1 of 1
. . l 1 ;! l lllIl' h'
c c N l O
,Y I , T 4 A T
Oc O g g Q 3 T S R
@& e .r I
N U- "O O E W P C I
' .> <* i 2 @ G N '5 M I
3O D1 T L A
. e. I .
3U LM
w.
1
- B EO T M7 6.
7 RTT O 5 _ 0 R- @ ET O AB 87/
.~.. r A6 RCNHC / 1 M8 .
UAA A 0 GELE 1 R-
I FRPP A6 *
,3.
n."j
.. P ..
o
m. @
i 7
\ \ :5 z .6 mt.' .j: ;E'- -.
c d 2
.-..: ..48 e_ ? Uic.
i E ia . , '? :p s
*+ d < . f; g> * ,i ..,,i
v. M0 1 R-
. *\. , A6
w. l M
.* _b M R-9 i @
A6 I r *
.. c o
o : yE i;.?
~ =_
i i g t' i. f-8 l
TABLE 7.6-14 ,
?m OCTOBER 17, 1985, NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION 0800 0830 0930 1030 1130 1230 1330 1430 0830 0930 1030 1130 1230 1330 1430 1630 Ambient Radiation Level (mR/hr) 4 General Area - - - - -
2 3 3 l t ARM 7-1 0.5 0.5 0.5 0.5 1 2 3 3 7-2 0.5 0.5 0.5 0.5 1 2 3 3 Contamination Survey (dpm/100 cm a) General Area 200 200 200 300 300 400 500 500 Note: Survey meter readings of swipes in cpm are 1/10 of contamination i values in dpm per 100 cm 2 Airborne Radioactivity Level General Area green green green green yellow yellow yellow yellow j t 4 u 1 of 1 i 4
....e. ,
X~ N J O ., % > I T A . T
$ 3 S R
T E e I V& - 4 - 4 - N U G0I W O P C
- - - - 5 NM c} ,. i .. 3 I'5 D TO $..l.
IL 6 A 1
,j' 4U .M G '
_t gL & H 1 B LO _ [ N C 6 ET
E T T S- $ .,.; ,i
P 7. O RTO 5 .q- O A t
c, H .. 3' ET AB 8
- ~ -
l . RCN HC 7/ p
.. . UAA G A /1 > ]* ;Gs ~~ . ,..' I ELE 0 M2 FRPP 1 R- . - ~
A7 y< ,. o1
' E* -
8
._w .. ' P :.l.
N ;lf
i. r d-S h'
;. i m. ../ \ !' :
l j , ..a u.
% - 3>
I.
\ i. i :"
c.
/ "
t: 5. T " \
.u p 3 , ~ -
M I : 6 R- ; i , A7 f.
- s e l.
i
,,.i- ;i . ., ;i %. ,
1 et i.
/
~
' 1 n.b rI
TABLE 7.6-15 OCTOBER 17, 1985, NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER CTATION n 0800 0830 0930 1030 1130 1230 1330 1430 0830 0930 1030 1130 1230 1330 1430 1630 Ambient Radiation Level (mR/hr) General Area - - - - - - - 2 l ARM 7-8 0.5 0.5 0.5 0.5 0.5 1 1.5 2 Contamination Survey (dpm/100 cm2) General Area 200 300 300 300 300 400 400 500 Note: Survey meter readings of swipes in cpm are 1/10 of contamination values in dpm per 100 cm 2 Airborne Radioactivity Level General Area green green green green green yellow yellow yellow v l. 9 i . I - k 1 of 1
I:= 4 > cW (D s/ , i i : : , i g
. .2.*..
q_. i r
+; ,*> : - L6l:: . ':4
- ;g l l
.+:e:w: i .. L .; s '.4:. '. .@. . .?.6;.g *'.-
[7 7 1..-
. .] ' ARM 7-8 I{*!.
[ ---@ P- -2 () i~s hm n b i
. i rJ'.-. " " r -rn ,; ......- ,;.. . I _ .g g - - . i e
[ __ g he.5 -C ; . .: . 7 I ! PLAN AT l EL. 214'-O" l m [-fM_._@ l' h h 2e 29 h FIGURE 7.6-15 p REACTOR BUILDING - UNIT 3 sj . PLAN AT EL.195'-O" PEACH BOTTOM ATOMIC POWER STATION 10/17/85
. - - - . _. . .- =. . . , .-
TABLE 7.6-16 OCTOBER 17, 1985, NRC OBSERVED EMERGENCY RESPONSE EXERCISE h PEACH BOTTOM ATOMIC POWER cTATION l[%) 0800 0830 0930 1030 1130 1230 1330 1430 0830 0930 1030 1130 1230 1330 1430 1630 Ambient Radiation Level (mR/hr) General Area "As read" for the duration of the exercise l ARM 7-6 1 1- 1 1 1 1 1 1 4 7-9 10 10 10 10 10 10 10 10
7-10 5 5 5 5 5 5 5 5 7-11 5 5 5 5 5 5 5 5 7-12 5 5 5 5 5 5 5 5 Contamination Survey (dpm/100 cm 2)
General Area 200 200 200 200 200 200 200 200 Note: Survey meter readings of swipes in cpm are 1/10 of contamination values in dpm per 100 cm 2
. Airborne Radioactivity level O
() General Area green green green green green green green green
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I-TABLE 7.6-17 OCTOEER 17, 1985,' NRC OBSERVED' EMERGENCY; RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION p 0800 0830 0930 1030 1130 1230 1330 1430 0830 0930 1030 1130 1230 1330 1430 1630 Ambient Radiation Level (mR/hr) IC 800 15 15 15 10 10 10 10 2C 200 4 4 4 2 '2 2 2 3C. 40 - - - - - - - l General Area - - - - - - - - l ARM 5-11 1 1 1 1 1 1 1 1 6-3 1 1 -1 1 1 1 1 1 6-4 20 20 20 20 20 20 20 20 6-5 800 15 15 15 10 10 10 10 Contamination Surveys (dpm/100 cm 2) Inside Horizontally 400 2P3 SP3 SP3 SP3 SP3 SP3 SP3 Shaded Areas. General Areas "As read" for the duration of the exercise
~ ~,Q Note: Survey meter readings of swipes in cpm are 1/10 of ig_,/ contamination values in dpm per 100 cpm2 Airborne Radioactivity Level Inside Horizodtally blue red red blue blue blue blue blue Shaded Areas
, : General Areas green green green green green green green green e c a 1 of I r .
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TABLE 7.6-18 OCTOBER 17, 1985, NRC' OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION O. 0800 0830 0930 1030 1130 1230 1330 1430 0830 0930 1030 1130 1230 1330 1430 1630 Ambient Radiation Level -(mR/hr) IM 400 10 10 10 5 5- 5 5 2M 80 2 2 2 - - - - 3M 15 _ _ _ _ _ _ _ General Area - _ _ _ _ _ _ _ l ARM 6-11 0.5 0.5 0.5 0.5 0.5 0.5 0.5 0.5 6-12 400 10 10 10 5 5 5 5 , Contamination Survey-(dpm/100 cm 2) General Area 200 200 200 200 200 200 200 -200 Note: Survey meter readings of swipes in cpm are 1/10 of contamination values in dpm per 100 cm 2 Airborne Radioactivity Level General Area green green green green green green green green l l 1 l l
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TABLE 7.6-19 OCTOBER 17, 1985, NRC OBSERVED EMERGENCY RESPONSE EXERCISE
ps PEACH BOTTOM ATOMIC POWER STATION (Gi 0800 0830 0930 1030 1130 1230 1330 1430 0830 0930 1030 1130 1230 1330 1430 1630 Ambient Radiation. Level (mR/hr) .
IT 200 10 5 5 5 5 5 5 2T 20 - - - - - - - l General Area - - - - - - - - l ARM 7-3 0.5 0.5 0.5 0.5 0.5 0.5 0.5 0.5 7-4 0.5 0.5 0.5 0.5 0.5 0.5 0.5 0.5 Contamination Survey (dpm/100 cm 2) General Area 200 200 200 200 200 200 200 200 Note: Survey meter readings of swipes in cpm are 1/10 of contamination values in dpm per 100 cm 2 Airborne Radioactivity Level 5 s General Area green green green green green green green green m/ 1 of 1
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TABLE 7.6-20 OCTOBER 17,.1985, NRC OBSERVED EMERGENCY RESPONSE EXERCISE
-~
PEACH BOTTON ATOMIC POWER STATION AREA RADIATION MONITOR READINGS 0800 0830 0930 1030 1130 1230 1330 1430 UNIT ARM // LOCATION 0830 0930 1030 1130 1230 1330 1430 1630
2- 1-2 Rx. Building - - - - - - -
Sump Area -! El. 88 ft 2 1-3 Torus Compartment- -- - - - - - - - 2 1-4 HPCI Pump Room - - - - - - - -
2 1-5 RCIC Pump Room - - - - - - - -
2 1-6 RHR Pump Room D - - - - - - - - 2 1-7~ .RHR Pump Room A - - - - - - - - 2 1-8 Core Spray Room B - - - - - - - - 2 1-9 Cond. Pump (Pit) - - - - - - - - Area 2 -- 1-10 A&C Core Spray - - - - - - - - l - (s - El. 116 FL 2 l'11 B&D Core Spray - - - - - - -
- l El'. 116 2 1-12 Cooling Water Pump - - - - - - - -
Area Cond. Demin Area 2 . 2-1 - - - - - - - - i
.2 2-3 Control Rod Drive - - - - - - - -
l Pump Area 2 2-4 Moisture Sep. South - - - - - - -
- l El. 116 2 2-5 Rx. Bldg. Eq. - - - - - - - -
Rack and Tip Control-2 2-6 Rx Bldg. - - - - - - - - Personnel Access South 2 .2-7 Rx Bldg. - - - - - - - - (g,) - Personnel Access North I of 5
TABLE 7.6-20 (Cont) OCTOBER 17,1985, NRC OBSERVED EMERGENCY RESPONSE EXERCISE ./N PEACH BOTTOM ATOMIC POWER STATION () - AREA RADIATION MONITOR READINGS g 0800 0830 0930 -1030 1130 1230. 1330 1430 UNIT ARM // LOCATION 0830 0930 1030 1130 1230 1330 1430 1630 2- 2-8 TIP Withdrawal ' - - - - - - - - Area 2 2-9. Turbine aldg. - - - - - - - - Access El. 135 FL 2 2 Moisture Sep - - - - - - - - Area El. 135 Ft l 2- 2-11 Rx. Bldg. Op. - - - - - - - - Area El. 165 Ft Sample Sink 2 2-12 Rx. Bldg. Access - - - - - - - - E1. 165 Ft 2 3-1 Heater and'RFPT - - - - - - - - Areas El. 165 Ft ^ South
2. 3-2 Heater & RFPT - - - - - - - -
Areas El. 165 Ft North 2 3-6 Rx. Bldg. Fan Room - - - - - - - - El. 195 Ft 2 3-7 Steam Separator - - - - - - - - Pool Area 2 3-8 Rx El. 205 Ft - - - - - - -
- l . Refuel Slot Area 2 .3-9 Fuel Pool Area - - - - - - - -
2 3-10 Refueling Bridge - - - - - Com. 4 Turbine Bldg. - - - - - - - - Access' Area El. 135 Ft Com. 4-6 Radwaste Sump 20 20 20 20 20 20 20 20 Area s Com. 4-7 Radwaste Filter 1 1 1 1 1 1 1 1 Fump Area i 2 of 5
._)
TABLE 7.6-20 (Cont) OCTOBER 17, 1985, NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION
\/ AREA RADIATION MONITOR READINGS 0800 0830 0930 1030 1130 1230 1330 1430 UNIT ARM # LOCATION 0830 0930 1030 1130 1230 1330 1430 1630 Com. 4-8 Cond. Phase Sep. 10 10 10 10 10 10 10 10 Rooms Radwaste El. 116 Ft Com. 4-9 Conveyor Op. 10 10 10 10 10 10 10 10 Access Area Com. 4-10 Drum Storage 20 20 20 20 20 20 20 20 Area Com. 4-11 Radwaste Filter 25 25 25 25 25 25 25 25 Hatch Com. 4-12 Waste Sample Tank 3 3 3 3 3 3 3 3 3 5-3 Rx Bldg. Sump Area 15 15 15 90* 800 800 250 50 El 88 Ft. l 3 5-4 Torus Compartment 10 25 70 130* 600 3P3 3P3 3P3 3 5-6 HPCI Pump Room 2 6* 15 80 700 800 300 60 3 5-7 RCIC Pump Room 2 2 10* 130 1.5P3 1.5P3 400 100 l 3 5-8 RHR Pump Room D 2 2 2 8 40 80 100* 100 3 5-9 RHR Pump Room A 2 2 2 4 20 40 50 50 3 5-10 Core Spray Room C 2 2 2 20 120 600 650 650 l 3 5-11 Cond. Pump Area 1 1 1 1 1 1 1 1 3 5-12 A&C Core Spray 1 1 1 1.5 4 25* 25 25 l El. 116 Ft 3 6-1 B&D Core Spray 2 2 2 5* 30 190 200 200 l El. 116 Ft 3 6-2 Cooling Wates 1 1 1 1.5 2 2 3 3 Pump Area 3 6-3 Cond. Demin. Area 1 1 1 1 1 1 1 1 3 6-4 Control Rod Drive 20 20 20 20 20 20 20 20 l Pump Area O
3 of 5
7 TABLE 7.6-20 (Cont) OCTOBER 17, 1985, NRC OBSERVED EMERGENCY RESPONSE EXERCISE
-p PEACH BOTTOM ATOMIC POWER STATION
-( A AREA RADIATION MONITOR READINGS 0800 0830 0930 1030 1130 1230 1330 1430
-UNIT ARM #; LOCATION 0830 0930 1030 1130 1230 1330 1430 1630 3 6-5 H.P. Turb. 800 15- 15 15 10 10 10 10 Moisture'Sep. '3 6-7 R;< Bldg. I 1 1 1 1.5 2.5 4 4 e ' Personnel Access Hatch 3 _6-8 Rx Bldg. 2 2 2 2 2 2.5 4 4 Personnel Access CRD Hatch 3 6-9 Rx Bldg. Equip. 1 1 1 1 1.5 2.5 4 4 Rack & TIP Control 3 '6-10 TIP Withdrawal 400 400 400 400 400 400 400 400 Area 3 6-11 Turbine Bldg. 0.5 0.5 0.5 0.5 0.5 0.5 0.5 0.5 O Access El. 135 Ft 3 6-12 Moisture Sep. 400 10 10 10 5 5 5 5 ' Area El. 135 Ft l 3 7-1 Rx Bldg. SE 0.5 0.5 0.5 0.5 1. 2 3 3 El. 165 Ft at FW Sample Sink 3 7-2 Rx Bldg. 0.5 0.5 0.5 0.5 1. 2 3 3 El. 165 Ft NW Stairwell 3 7-3 Heater and RFPT 0.5 0.5 0.5 0.5 0.5 0.5 0.5 0.5 Areas North .
3 4 Heater and RFPT 0.5 0.5 0.5 0.5 0.5 0.5 0.5 0.5 Areas South
'3 7-6 Rx Refuel Slot 1 1 1 1 1 1 1 1 -Area El. 205 FL 3 7-8 Rx Bldg. Exhaust '0.5 0.5 0.5 0.5 0.5 1 1.5 2 Fans -~ 3 7-9 Equipment Pool 10 10 10 10 10 10 10 10 v
4 of 5
TABLE 7.6-20 (Cont) OCTOBER 17, 1985, NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION AREA RADIATION MONITOR READINGS 0800 0830 0930 -1030 1130 .1230 1330 1430 UNIT ARM # LOCATION 0830 0930 1030 1130 1230 1330 1430 1630 5 5 5 5 5 5 5 3 7-10 West Fuel Storage 5 l Area 3 7-11 Fuel Pool Area 5 5 5 5 5 5 5 5 3 7-12 Refuel Bridge 5 5 5 5 5 5 5 5 Area 7 j.
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OFFS!TE FIELD SURVEY MAP
".h PEACH BOTTOM ATOMIC POWER STATION 10/17/85 1230-Do f
v
,. ( eq October 17, 1985 SECTION 7.8 METEOROLOGICAL DATA 1985 NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION 0900 1000 1030 1100 1130 1200 1230 1300 1330 1400 1430 1500 1530 1000 1030 1100 1130 1200 1230 1300 1330 1400 1430 1500 1530 END Wind Direction (Deg. Az.)
Tower 2 320* 013 013 013 013 013 013 328 328 328 328 328 328 328 Tower 2 75* 015 018 011 009 012 012 322 323 320 318 315 322 320 Tower 1A 90* 017 019 014 012 010 008 321 323 319 314 316 314 320 Hill Pole 33' 014 014 012 010 012 011 326 326 326 325 325 326 326 4 Wind Speed (sph) Tower 2 320* 19.4 18.2 M M M M 14.4 12.9 8.5 7.8 7.4 8.5 9.3 Tower 2 75* 12.2 11.5 12.5 12.4 10.0 9.3 9.9 M M M M 5.9 6.5 I Tower 1A 90* 10.8 10.6 11.2 10.9 9.0 B.3 9.0 B.1 6.0 M M M M Hill Pole 33* 13.8 12.4 13.3 13.5 10.9 10.5 10.8 10.0 6.9 7.6 6.3 7.1 7.8 Temperature Difference (Deg.'F) Tower 2 316-33' -0.4 +0.1 -0.1 +0.2 -0.1 0.0 -0.1 -0.* -0.2 -0.2 -0.3 -0.1 -0.1 Tower 2 150-33' -0.7 -0.3 -0.4 -0.1 -0.4 -0.2 -0.4 -0.3 -0.4 -0.4 -0.5 -0.3 -0.2 Tower 1A 90-33* -0.9 -0.5 -0.6 -0.4 -0.7 -0.4 -0.6 -0.5 -0.7 -0.7 -0.9 -0.5 -0.4 Sigma Theta (Deg. Az.) Tower 2 320' 6.3 7.7 8.8 7.8 8.7 8.6 12.1 10.2 12.7 11.0 11.5 10.8 11.0 Tower 2 75* 8.2 9.3 8.2 7.6 8.2 0.0 15.6 13.0 15.3 15.1 17.1 12.7 15.1 Tower 1A 90* 10.1 11.5 10.1 8.9 10.1 12.0 20.9 18.3 17.1 16.7 19.2 15.9 16.7 4 30* Temp (Deg. F)* 63 64 66 68 68 69 69 70 68 66 64 63 62 30* Dew Point (Deg. F) 60 60 60 60 60 60 60 60 57 55 53 51 49 Precipitation (in.) 0.02 0.04 0.01 T 0.01 i 0.00 S 00 0.00 0.00 0.00 0.00 0.00 ' i M - Missing T - Trace SYNPOSIS: The vigorous low pressure area that brought mod..cate to heavy rain which depleted nature *s beautiful fall array in our area yesterday, is still influencing today*s weather. This morning it is centered over Scranton, moving rapidly to the northeast into Quebec Province. The trailing cold front should be through our area in a few hours, bringing rapidly clearing conditions. This morning's blustery NE wind flow should veer to a more westerly component and reduce in intensity. High temperatures should reach 65-70. Tonight's soonlit skies will see temperatures drop to a low of 45 by morning. Fair and seasonable tomorrow, high in the 60's.
; 7.8-1 1
- -. . . .-_. . . . . . . -. . . . . . . ~ . . _ . . - - . _ . . - _ - . - - .- ._. -. - - . - - . . - . .
4 h ; I~ October 17, 1985 SECTION
8.0 REFERENCES
j_ 1985 NRC OBSERVED EMERGENCY RESPONSE EXERCISE l PEACH BOTTOM ATOMIC POWER STATION t Section Page 4 l 8.1 EMERGENCY PLAN PROCEDURE INDEX . . . . . . . . . . . . . . 8.1-1 1 4 8.2 REFERENCE DOCUMENTS . . . . . . . . . . . . . . . . . . . . 8.2-1 1 i ! i l l i , i' 6 I i k J G l l l 8.0-1 J
October 17, 1985 SECTION 8.1
/ EMERGENCY PLAN PROCEDURES INDEX*
1985 NRC OBSERVED EMERGENCY RESPONSE EXERCISE PEACH BOTTOM ATOMIC POWER STATION Procedure Revision Revision Number Title Number Date EP-101 Classification of Emergencies 14 09/13/85 EP-102 Unusual Event Response 11 09/13/85 EP-103 Alert Response 11 06/26/85 EP-104 Site Emergency Response 12 09/13/85 EP-105 General Emergency Rer,wnse 11 06/14/85 EP-110 Personnel Assembly and Account-ability 1 06/20/83 EP-201 Technical Support Center (TSC) 7 10/12/84 Activation ey EP-202 Operations Support Center 7 01/23/85
) (OCS) Activation u,/
EP-203 Emergency Operations Facility 7 10/12/84 (ECF) Activation EP-203A Alternate Emergency Operations 0 10/12/84 Facility (EOP) Activation EP-205 DELETED 09/12/84 1 EP-205A Chemistry Sampling and 5 09/18/84 Analysis Group . , EP-205A Operation of Post Accident 5 09/20/84
.1 Sampling Station EP-205A Obtaining Drywell Gas Samples 0 05/26/82 .2 from Containment Atmosphere Dilution Cabinets EP-205A Retrieving and Changing Sample 1 04/25/33 .3 Filters and Cartridges from the Drywell Radiation Monitor During Emergencies l
1
'*
Includes changes through Revision 53, dated 09/18/85.
8.1-1
Pr:c; dura R visien R vision Numbar Title Number Date EP-205A Obtaining Drywell Gas Samples 0 05/25/82
.4 from the Drywell Radiation Monitor Sampling Station EP-205 Obtaining Reactor Water Samples 0 05/25/82 .5 from Sample Sinks Following Accident Conditions EP-205A Obtaining Canal Discharge Water 0 05/25/82 .6 Samples Following Radioactive Liquid Releases After Accident Conditions EP-205A Obtaining the Iodine and 2 11/21/83 .7 Particulate Samples from the Main Stack and Roof Vents Following Accident Conditions EP-205A Obtaining Liquid Radwaste 0 05/25/82 .8 Samples from Radwaste Sample Sink Following Accident Conditions EP-025A Obtaining Samples from 0 05/25/82 .9 Condensate Sample Sink Following Accident Conditions EP-205A Obtaining Off-Gas Samples from 0 05/25/82 h .10 the Off-Gas Hydrogen Analyzer Following Accident Conditions EP-205A Sample Preparation and Handling 2 02/29/84 .11 of Highly Radioactive Liquid Samples EP-205A Sample Preparation and Handling 3 01/10/84 .12 of Highly Radioactive Particu-late Filters and Iodine Cartridges EP-205A Sample Preparation and Handling 2 02/29/84 .13 of Highly Radioactive Gas Samples EP-205A Offsite Analysis of High 0 11/23/83 .14 Activity Samples EP-205A Guidelines for the Order of 0 02/29/84 .15 Analysis on Post-Accident Samples EP-205A Storage of Post-accident 0 09/12/85 l Samples g .16 8.1-2
1 l Pr:csdura Ravision Ravision i Numbar Title Numbar Date EP-205B Radiation Survey Groups 5 09/18/84 l \
) EP-205C DELETED 08/07/85 EP-206 DELETED 04/27/83 EP-206A Fire Fighting Group 7 08/26/85 EP-206B Damage Repair Group 3 05/31/83 EP-207 Personnel Safety Team Activa- 6 09/20/84 tion EP-207A Search and Rescue 4 07/31/85 l EP-207B DELETED 04/27/84 EP-207C DELETED 06/26/85 l EP-207D Evacuation Assembly Group 4 09/16/85 l EP-207E
DELETED 08/28/85 l EP-207F DELETED 08/28/85 l
/ i C]- EP-207G Plant Survey Groups 0 09/09/85 I EP-207H Dosimetry, Bioassay, and 0 09/16/85 l
. Respiratory Group EP-208 Security Team 1 05/31/83 EP-209 Telephone List For Emergency 10 06/11/85 l Use EP-209 Inunediate Notification Call 10 09/16/85 l Appendix A List EP-209 DELETED Appendix B 11/04/81 EP-209 Peach Bottom Station Super- 17 09/16/85 Appendix C- vision EP-209 On Site Emergency Team 13 09/14/85 Appendix D-1 Leaders EP-209 Dose Assessment Team 16 05/02/85 .
Appendix D-2 EP-209 Fire and Damage, Team 15 09/14/85 l Appendix D-3 8.1-3
Pr cxdura R vision R;vicion Numbir Titlo Numbar D te EP-209 Personnel Safety Team 18 09/14/85 Appendix D-4 l EP-209 Security Team 13 09/14/85 Appendix D-5 EP-209 Re-entry and Recovery Team 4 04/11/85 Appendix D-6 l EP-209 Technical Support Center 17 09/16/85 Appendix D-7 Group l EP-209 Chemistry Sampling and 03 09/16/85 Appendix D-8 Analysis Team l EP-209 Corporate Emergency Team 14 09/16/85 Appendix E Leaders and Support Personnel EP-209 U.S. Government Agencies 5 06/24/83 Appendix F l EP-209 Emergency Management Agencies 7 09/1 /85 Appendix G l EP-209 Company Consultants 12 09/14/85 Appendix H l EP-209 Field Support Personnel 18 09/14/85 Appendix I-1 l EP-209 Chemistry and Health Physics 17 09/16/85 Appendix I-2 Contractor Call List EP-209 Nearby Public and Industrial 7 05/03/85 Appendix J Users Of Downstream Waters l EP-209 Miscellaneous 7 09/16/83 Appendix K EP-209 Local PECo Phones 6 01/11/85 Appendix L EP-209 DELETED 10/21/84 Appendix M l EP-209 Medical Support Groups 9 06/14/85 Appendix N l EP-209 Staffing Augmentation - 12 06/12/85 appendix P 60 Minute Call Procedure EP-210 Dose Assessment Team 1 09/18/84 8.1-4
Precsdure Ravision . Revision Numbar Title Number Date
. EP-210A Field Survey Groups 0 09/09/85 l - f3 '
3
,\s_/ EP-211 Emergency Radiation-Exposure -0 06/28/85 l .
i Guidelines and Controls EP-212 Technical Support Team 0 09/09/85 l EP-301 Operating the Evacuation 2 09/09/85 l Alarm and Pond Page System EP-303 Partial Plant Evacuation 3 08/30/83 EP-304 DELETED 12/04/81 EP-705 Site Evacuation 5 06/21/83 EP-306 Evacuation of the Information 2 05/25/82 Center EP-307- Reception and Orientation of 2 09/16/85 l Support-Personnel EP-311 Contaminated Injury 4 06/28/85 l EP-312 Radioactive Liquid Release 2 09/20/84 (Emergency Director Functions)
,rs iq_,) EP-313 Control of Thyroid Blocking 2 09/12/85 l (KI) Tablets.
EP-315 Corporate Computer Dose 0 10/12/84 Calculations EP-316 Cumulative Population Dose 7 09/17/85 l Calculations For Airborne Releases-Manual Method EP-316 Worksheets/ Meteorological Cal- 8 09/17/85 Appendix A .culations EP-316 Activity after Reactor Shutdown 7 09/17/85 Appendix B EP-316 Index of X/Q Outputs for Off-Gas 7 09/17/85 Appendix C Stack Releases , EP-316 Relative Dispersion Values for 7 09/17/85 Appendix D Emergency Dose Calculation Procedure EP-316 SGTS Efficiency vs Decontamination 7 09/17/85 Appendix E Factor EP-316 Percent Composition of Isotopic 7 09/17/85 Appendix F Distribution 8.1-5
r Prscadura Revision Revision Number Title Number Date EP-316 Composite Whole Body Dose 7 09/17/85 Appendix G Conversion Factors vs Time Since Reactor Shutdown EP-316 I-131/I-133 Composite Thyroid Dose 7 09/17/85 Appendix H Conversion Factors vs Time Since Reactor Shutdown EP-316 Population Distribution by Compass 0 09/17/85 Appendix I Sector-Summer Day EP-316 I-131/I-133 Percent Abundance vs 0 09/17/85 Appendix J Time Since Reactor Shutdown EP-316 PBAPS Iodine Source Term From 0 09/17/85 Appendix K TSC Field Data EP-316 Index of Plume Shine Outputs 0 09/17/85 Appendix L for Off-Gas Stack Releases EP-316 Plume Shine Value for Emergency 0 09/17/85 Appendix M Dose Calculation Procedure EP-316 Refined Dose Assessment of 0 09/17/85 Appendix N Unmonitored Ground Release EP-316A Reading the Rapid Dose Assess- 1 10/03/84 ment I Program into the TI-59 EP-316B Calculating Rapid Dose Assess- 1 10/03/84 ment on the TI-59 EP-316C Reading the Refine Dose Assess- 0 10/15/84 ment I Program into the TI-59 EP-317 Direct Recommendations to 3 10/12/84 County Emergency Management and Civil Defense Agencies EP-318 Liquid Release Dose Calculation 1 04/13/83 Method for Intake Water at Downstream Facilities EP-319 Liquid Release Dose Calculation 1 04/13/83 Method for Fish EP-320 Procedure for Leaking Chlorine 1 03/12/82 EP-325 Use of the Containment 0 06/09/82 Radiation Monitor to Estimate Release Source Term EP-401 Entry for Emergency Repair and 5 09/15/84 Operations 8.1-6 L
i 4 Procedure Revision Revision ! j_ Number Title Number Date , t EP-500 Review and Revision of Emergency 0 04/01/81 Plan (FSAR Appendix 0) t i 4 A i 1 e 1 i .j i i t 1
- 1 l
i 1 f 1 1 I i { l 1 1 .i 1 1 0859-1471204-B2 8.1-7 !
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ML20141F413

Contents

Text

Subject:

DearDr. Murley:

Subject:

Dear Dr. Murley:

8.0 REFERENCES

Purpose:

Purpose:

Purpose:

Purpose:

I. PROCEDURE

I. PROCEDURE

I. PROCEDURE

I. PROCEDURE

I. PROCEDURE

I. PROCEDURE

I. PROCEDURE

I. PROCEDURE

I. PROCEDURE

I. PROCEDURE

I. PROCEDURE

I. PROCEDURE

I. PROCEDURE

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

8.0 REFERENCES

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