ML20062J221

1993 Evaluated Exercise Scenario Manual

ML20062J221
Person / Time
Site:	Cooper
Issue date:	06/17/1993
From:	NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML19342B865	List: ML20062J217 ML20062J221
References
NUDOCS 9306220228
Download: ML20062J221 (200)

Text

. _ - . -

l 1

k I

i i

COOPER NUCLEAR STATION  ;

1993 EVALUATED EXERCISE SCENARIO MANUAL ,

f f

.l '

.\ ,

= )

+

Ntsarsxx Punuc Powtn Dsrarcr  :

66220,2 f

,_ , 1 f

304990e96 SF e

+ - -- v_me - ,_ _ _ ,,p._, _ j

n TABLE OF CONTENTS Pne PART A GENERAL INFORMATION

1. INTRODUCTION 1-1

2. SCOPE AND OBJECTIVES 2-1 2.1 Scope 2-1 2.2 Objectives 2-2

3. EXERCISE INFORMATION 3-1 3.1 Exercise Participants 3-1 3.2 Exercise Organization 3-1 3.3 Conduct of the Exercise 3-3 3.4 Precautions and Limitations 3-4 3.5 Abbreviations 3-6 3.6 Definitions 3-10 3.7 References 3-14

4. CONTROLLER / EVALUATOR INFORMATION 4-1 4.1 General Information 4-1 4.2 Controller Instructions 4-1 4.3 Evaluator Instructions 4-2 4.4 Personnel Assignments 4-2 4.5 Simulator Instructions 4-2

5. PLAYER INFORMATION 5-1 ;

5.1 General Information 5-1 5.2 Player Guidelines 5-1

6. SCIIEDULE OF EVENTS 6-1 l 6.1 Times and Places 6-1 6.2 Travel Information 6-1 !

l i

Table of Contents -I- G:\6660WANUALISECT14.WP3 i

i Page PART B CONFIDENTIAL SCENARIO INFORMATION

7. EXERCISE SCENARIO MATERIAL 7-1 7.1 Scenario Summary 7-1 7.2 Initial Conditions 7-5 l 7.3 Sequence of Events 7-7 7.4 Master Events Summary 7-11 ,

7.5 Supplemental Scenarios 7-28

8. STATION OPERATIONS MATERIAL 8-1 8.1 Station Messages 8-2 8.2 Control Room Alarms 8-30 8.3 Operations Data 8-39 1 8.4 PMIS Data 8-48 1

9. RADIOCIIEMISTRY AND IN-PLANT RADIATION MATERIAL 9-1 9.1 Radiochemistry Data 9-2 9.2 Radiation Monitor Summary and Data Sheets 9-10 9.3 In-Plant Radiological Data and Maps 9-16

10. METEOROLOGICAL AND RADIOLOGICAL RELEASE MATERIAL 10-1 10.1 Radiological Release Information 10-2 10.2 Meteorological Summary and Data Sheets 10-4 i 10.3 Onsite Field Data and Map 10-8 l 10.4 Offsite Field Data and Maps 10-23 ,

11. PUBLIC INFORMATION MATERIAL 11-1 i 11.1 Corporate Messages 11-1  !

11.2 Public Assistance Messages 11-16  !

11.3 Telephone Controller Messages 11-30

-l i

k r

r Table of Contents - il - G:us660w&UAurECD.6.WP3

vT

. . - - a a , , - ~

Section 1 INTRODUCTION i

l l

i l

1 i

1. INTRODUCTION The Cooper Nuclear Station (CNS), owned and operated by the Nebraska Public Power District (NPPD), annually conducts an Emergency Preparedness Exercise for the purpose of demonstrating that the NPPD emergency response organization can effectively meet its responsibilities in protecting the health and safety of the residents of the Plume Exposure Pathway Emergency Planning Zone in the event of a radiological incident at the plant.

The NPPD response organization and facilities that have been developed to respond to such an emergency are described in the CNS Emergency Plan. The Plan also discusses the support that is available from Federal, State and local government agencies, as well as from private organizations. It provides for a program of continuous preparedness, one element of which is ,

the conduct and evaluation of this annual Exercise.

The primary purpose of this Exercise is to evaluate the participating portion of the NPPD CNS emergency response organization in accordance with the CNS Emergency Plan and associated implementing procedures. In keeping with this purpose, only the participating portions of the NPPD CNS emergency organization's will be evaluated in the 1993 Exercise.

The Exercise will be conducted and evaluated by personnel selected by NPPD, and will be observed by representatives from the Nuclear Regulatory Commission (NRC). Upon termination of the Exercise, the NPPD Evaluators will critique the response of the players, assess the effectiveness of their response, and compile a Critique Report for distribution to NPPD management to ensure appropriate actions are taken to resolve any weaknesses that are identified. ,

This Exercise Manual provides all information required to support successful conduct and evaluation of the Exercise. It is to be used by the NPPD Controllers and Evaluators to ensure  ;

that consistent and accurate data is provided to Players during the course of their response to the sequence of events. It is provided to other observers for their information and reference when observing the Exercise.

This manual consists of two sections; Part A, provides information of general interest, instructions to participants, a schedule of associated events, a general description and overview of the Exercise to be conducted, including administrative and logistical information helpful to all participants. Part B, which is subject to a limited, controlled distribution (Controllers, Evaluators and authorized observers) provides the scenario-specific information and supporting data for the sequence of events. Exercise " Players" (see Section 3.2) will not have orior access i lo_or knowledee of any of the scenario that has been developed for this Exercise.

Introduction Page 1-1 G:\6660WANUAl.tSECn_6.WH 7

i i

l l

Section 2 SCOPE AND OBJECTIVES i

l 1

I l

i I

l i

i I

1 4

1 l

i

, ~- ,

2. SCOPE AND OBJECTIVES 2.1 Scope The 1993 CNS Emergency Preparedness Exercise, to be conducted on August 17, 1993, will test and provide the opportunity to evaluate the emergency plans and procedures of NPPD. It will test the ability of participants to assess and respond ,

to emergency conditions and coordinate activities to protect the health and safety  :

of individuals in the plant and in the vicinity of CNS from the consequences of a radiological incident at CNS. The Exercise has been developed to support ,

demonstration of the capabilit.es of the NPPD Emergency Response Organization, and will include full activation and participation of all NPPD emergency facilities.

The Exerche will be used to evaluate the ability of the onsite response personnel  ;

to assess and mitigate the emergency situations at the plant, and to take actions to assist state and local govemment orgamzations in mitigating the radiological consequences to persons in the vicinity of the plant. In addition, the Exercise will provide NPPD with the opportunity to assess the effectiveness of training improvements and modifications made to the CNS Emergency Plan and Procedures since the last Exercise.

Emergency response actions during the Exercise will include:

• prompt recognition and accurate classification of emergency conditions;

• assessment of onsite/offsite radiologica: consequences, and activities to minimize the impact of these consequences;

• notification and mobilization of the emergency response organizations;

• implementation of in-plant corrective actions;

• activation / operation of emergency response facilities and equipment;

• preparation of adequate records to document decisions made and actions taken;

• formulation and recommendation of protective actions fer personnel within the area; and

• termination of the emergency condition. ]

l Specific objectives to be demonstrated by the NPPD CNS Emergency Response )

Organization and Facilities are identified in the following section.  ;

I l

Scope and Objectives Page 2-1 c:w660wANUALtSECD_6.WH i 1

1

2.2 Objectives Exercise objectives are provided under this heading. Objectives provide a basis ,

for scenario development and a means to evaluate responses by the emergency response organization.

The Nebraska Public Power District radiological emergency preparedness exercise objectives for the Cooper Nuclear Station are based on Nuclear Regulatory f Commission (NRC) requirements provided in 10 CFR 50.47, " Emergency Plans",

and 10 CFR 50, Appendix E, " Emergency Planning and Preparedness for Production and Utilization Facilities". Additional guidance provided in NUREG-0654/ FEMA-REP-1, Revision 1, " Criteria for Preparation and Evaluation of .

Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants", was utilized in developing the objectives. l Objectives are grouped according to functional area of emergency response.

Additionally, objectives have been cross referenced to major or parent Emergency Plan Implementing Procedures used in demonstrating the objective, and to any i related open weaknesses from previous years' exercises.

General Objectives:

i t

Accident Assessment, Classfication and Mitigation

1. Demonstrate the ability to assess plant conditions. ,

'NUREG-0654 ref: D.1-2; H.5; I.1 2 Major EPIP ref: 5.7.1

' Weakness ref: none

2. Demonstrate the ability to identify projected trends and potential .

consequences.

'NUREG-0654 ref: D.1-2; H.5; I.1 2

Major EPIP ref: 5.7.7, 5.7.9, 5.7.16 I

' Weakness ref: 298/9112-01

3. Demonstrate the ability to classify emergency events per EPIP 5.7.1.

'NUREG-0654 ref: D.1-2; H.5; I.1 2

Major EPIP ref: 5.7.1  !

' Weakness ref: 298/9214-02.

Scope and Objeaives Page 2-2 G:166WMANUAL1SECTl_6.WPS

i

4. Demonstrate the ability to provide technical support for operations in accident assessment and mitigation. -

'NUREG-0654 ref: B.7.a-b l 2

• Major EPIP ref: 5.7.7

' Weakness ref: 298/9112-01

}

Notification and Mobilization

5. Demonstrate the ability to alert and notify NPPD emergency response personnel in a timely manner. >

'NUREG-0654 ref: A.I.e; B.1,5,7.a; E.2; F.1.e  ;

2 Major EPIP ref: 5.7.6

' Weakness ref: none

6. Demonstrate the ability to mobilize NPPD emergency response personnel  ;

and activate emergency response facilities within the time frames specified l in the Emergency Plan.

i

'NUREG-0654 ref: J.1,4 2

Major EPIP ref: 5.7.7, 5.7.8, 5.7.9

' Weakness ref: none 1

7. Demonstrate the ability of NPPD to notify federal, state and county ,

agencies within the time frames specified in the Emergency Plan.

'NUREG-0654 ref: A.I.e; B.4,7.c; E.1-4; F.1; J.7; N.2.a l 2

Major EPIP ref: 5.7.6  !

' Weakness ref: 298/9214-03  !

8. Demonstrate the ability to alert, advise and direct onsite non-essential personnel.

'NUREG-0654 ref: J.1,4 2

Major EPIP ref: 5.7.3, 5.7.4, 5.7.10, 5.7.11  ;

' Weakness ref: none ,

i Scope and Objectives Page 2-3 G:\6660NANUAUSECD_6.wM

I

)

Emergency Response

9. Demonstrate the ability to direct and coordinate emergency responses.  :

'NUREG-0654 ref: A.1.d; B.2-7.a-b f 2

Major EPIP ref: 5.7.7, 5.7.8, 5.7.9  ;

' Weakness ref: none ,

f

~

10. Demonstrate the ability to transfer emergency direction from the Control '

Room (CR), to the TSC, and finally to the EOF, or from the Control Room directly to the EOF. ,

2NUREG-0654 ref: A.I.d; B.3-5  !

2 Major EPIP ref: 5.7.7, 5.7.8, 5.7.9  :

' Weakness ref: none

11. Demonstrate the ability to provide initial and continuous accountability of l onsite individuals. "

'NUREG-0654 ref: J.5 2

Major EPIP ref: 5.7.10 -

' Weakness ref: none

12. Demonstrate site recovery /re-entry planning.  ;

i 8NUREG-0654 ref: M.1-3 -:

2 Major EPIP ref: 5.7.25

' Weakness ref: none

' Radiological Assessment and Control

13. Demonstrate the ability to provide radiological monitoring and decontamination capabilities for onsite and non-essential personnel.

8NUREG-0654 ref: J.3-4; K.7 ,

2 '

Major EPIP ref: 5.7.13

' Weakness ref: none Scope and Objectiws Page 2-4 a:16660wANUAL\SECn_6.wN i

t

l l

l

14. Demonstrate the ability to provide onsite contamination controls, and area i access controls. l H

j

'NUREG-0654 ref: K.5,6  ;

2 Major EPIP ref: 5.7.12, 5.7.13 -l

' Weakness ref: 298/9214-01  :

15. Demonstrate the ability to continuously monitor and control emergency worker exposures.

'NUREG-0654 ref: K.1.a-g,2,3.a-b 2

Major EPIP ref: 5.7.12,.5.7.13  ;

' Weakness ref: none I

16. Demonstrate the ability to monitor, assess, and correlate onsite l radiological conditions.

2NUREG-0654 ref: H.5.b,c,9; I.1-3; N.2.d,e.1 ,

2 Major EPIP ref: 5.7.19

' Weakness ref: none  ;

17. Demonstrate the ability to collect, analyze and evaluate simulated -

radiological samples and surveys.

'NUREG-0654 ref: H.5.b,7; N.2.d,e.1 2 Major EPIP ref: 5.7.18, 5.7.19 ,

' Weakness ref: none

18. Demonstrate the ability to assess core damage. ]

'NUREG-0654 ref: I.3; M.1 2  ;

Major EPIP ref: 5.7.17

' Weakness ref: 298/9112-01

19. Demonstrate the ability to make the decision whether to issue emergency  ;

workers radioprotective drugs, KI. i

'NUREG-0654 ref: J.6.c  ;

2 Major EPIP ref: 5.7.14 {

' Weakness ref: none j 1

o swrc aa owcai- ra css c:,assomuuausen_a.G l

l l

l

-3

20. Demonstrate the ability to determine source terms and dose projections, evaluate dose projections against protective action guides and determine  !

appropriate onsite and offsite protective actions.

'NUREG-0654 ref: H.6a,8; I.3-7,9-10; J.10.m 2

Major EPIP ref: 5.7.16, 5.7.17, 5.7.20  ;

' Weakness ref: 298/9214-04

-l

21. Demonstrate the ability to make timely protective action recommendations -

to offsite agencies.  ;

2NUREG-0654 ref: I.5-11, J.7 -

2 Major EPIP ref: 5.7.20 j

' Weakness ref: none  !

Emergency Response Facility-Specific Objectives:

22. Emergency Operations Facility (EOF):

a. Demonstrate the adequacy of the Emergency Plan and Emergency Plan Implementing Procedures both in terms of management control and workability of the procedures for the EOF.

b. Demonstrate the adequacy of communication links between CR, TSC, GOEC, government emergency facilities, field teams and ,

the EOF. ,

c. Demonstrate the effectiveness and availability of appropriate -

1ergency equipment and supplies. ,

i

d. Demonstrate the adequacy of security access control. i

e. Demonstrate activation and staffing of the EOF in a timely fashion.

f. Demonstrate the functional adequacy of the EOF.

3NUREG-0654 ref: B.5; G.3; H.1-3,6-9,12;J.6.a-c,10.a-b, E.2; j F.1,2,3 2

Major EPIP ref: 5.7.9, 5.7.21, 5.7.22

' Weakness ref: none i i

l Scope and Objectin:s Page 2-6 G:\6660 MANUM.tSECn_6.WH \

l

l l

l

23. Technical Support Center (TSC): ) i

a. Demonstrate the adequacy of the Emergency Plan and Emergency l Plan Implementing Procedures both in terms of management  ;

control and workability of the procedures for the TSC. j

b. Demonstrate the adequacy of communication between the TSC, OSC, EOF, inplant response teams, and the Control Room.

)

c. Demonstrate the effectiveness and availability of appropriate '

emergency equipment and supplies.

d. Demonstrate activation and staffing of the TSC in a timely fashion.

e. Demonstrate the functional adequacy of the TSC.

i

f. Demonstrate the ability to perform core damage assessment.

g. Demonstrate the adequacy of TSC habitability surveys.

'NUREG-0654 ref: B.5; G.3; H.1-3,6-9,12; J.6.a-c,10.a-b, E.2; F.1,2,3 2

Major EPIP ref: 5.7.7, 5.7.17, 5.7.21, 5.7.22

' Weakness ref: 298/9214-01

24. Control Room (CR)

a. Demonstrate the adequacy of the Emergency Plan and Emergency Plan Implementing Procedures both in terms of management control and workability of the procedures for the Control Room. ,

b. Demonstrate the adequacy ofinformation flow between the Control Room, TSC, EOF and inplant operators. ,

c. Demonstrate the effectiveness and availability of appropriate emergency equipment and supplies.

d. Demonstrate the functional adequacy of the Control Room.

"NUREG-0654 ref: B.5; G.3; H.1-3,6-9,12; J.6.a-c,10.a-b, E.2; ,

F.1,2,3 '

2

, Major EPIP ref: 5.7.2, 5.7.3, 5.7.21, 5.7.22

' Weakness ref: none i scope and objecthes Page 2-7 a:tsssowAnususecn_6.wn

25. Operations Support Center (OSC): j

a. Demonstrate the adequacy of the Emergency Plan and Emergency Plan Implementing Procedures both in terms of management control and workability of the procedures for the OSC.

b. Demonstrate the adequacy of communication links between inplant teams, the TSC and the OSC. t

c. Demonstrate the effectiveness and availability of appropriate emergency equipment and supplies, a

d. Demonstrate activation and staffmg of the OSC in a timely ,

fashion. '

e. Demonstrate the functional adequacy of the OSC. l

f. Demonstrate the adequacy of OSC habitability surveys. i

'NUREG-0654 ref: B.5; G.3; H.1-3,6-9,12; J.6.a-c,10.a-b, E.2; F.1,2,3 2

Major EPIP ref: 5.7.8, 5.7.13, 5.7.21, 5.7.22 3

' Weakness ref: 298/9214-01  ;

(

!)

i l

i Scope and Objeaiw:t Page 2-8 c:uss0MMALtmCT1_6.%T5 i

1

26. General Office Emergency Center (GOEC)/ Media Release Center (MRC):

I

a. Demonstrate activation and staffing of the GOEC/MRC within approximately 60 minutes of notification to General Office personnel.

b. Demonstrate the capability to register NPPD, State, Federal, Media and other personnel at the GOEC/MRC.

c. Demonstrate the capability at the GOEC/MRC to obtain current and accurate information pertaining to the emergency at CNS.

d. Demonstrate the capability at the GOEC/MRC to coordinate and assemble emergency information for dissemination to the media and/or public.

e. Demonstrate the capability at the GOEC/MRC to coordinate and >

assemble emergency information for dissemination to other NPPD offices and employees. 1

f. Demonstrate the capability at the GOEC/MRC to provide  !

CNS/NPPD background information to the media.

g. Demonstrate the capability at the GOEC/MRC to respond directly to questions from the media and/or public concerning real and rumored events of an emergency at CNS.  ;

h. Demonstrate the capability at the GOEC/MRC to identify rumors and correct false information concerning an emergency at CNS.

i. Demonstrate the interface and coordination between NPPD and State personnel located at the GOEC/MRC.  !

j. Demonstrate the capability to coordinate and.' plan Recovery operations with CNS ERO personnel.

k. Demonstrate the functional adequacy of the GOEC/MRC.

'NUREG-0654 ref: B.7.d; G.4.a,b; G.4.c 2

Major EPIP ref: 5.7.23

' Weakness ref: none t

Scope and Objectin:s Page 2-9 c:sss60wAhvAturcn_6.wn i 6

7

i e

Scenario

27. Demonstrate the ability to provide an exercise scenario and controller I organization that permits testing a major portion of the emergency plan. j .

l

'NUREG-0654 ref: N.1.a-b ~

2 Major EPIP ref: EPDP 11

' Weakness ref: none Evaluation ,

i

28. Demonstrate the ability to conduct a post-exercise critique to identify weak or deficient areas that need correction.- -

8NUREG-0654 ref: N.4,5 .

2 Major EPIP ref: EPDP 11

' Weakness ref: none FOOTNOTES 3

References related emergency planning objectives provided as guidance in NWG454/ FEMA-REP-1 Rev.1, ' Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" as based on NRC requirements provided in 10 CFR 50, Appendix E,

• Emergency Planning and Preparedness for Production and Utihzation -

Facilities".

2 References major NPPD4NS Emergency Plan Implementing Procedure (s) used in demonstrating the objective. Other procedures may be applicable but will generally be referenced by, or branched -

from, the major procedure, 8

References applicable open weaknesses from the 1992 Exercise as listed in lac docket 50-298/92-14 (see the follovdng for a summary of weaknesses).

o i

Scope and Objectim Page 2-10 G:kS660WANUAUSECTL6.WM i

I 4

court.n nuuttsn asasaun 1993 EVALUATED EXERCISE l

l 1992 NRC Exercise Weakness Summary l

l Technical Support Center 298/9112-01 (repeat weakness) The analysis and technical assessment of plant conditions was ]

determned to be a weakness. Conflicting assessments of fuel damage caused confusion as to actual plant conditions which delayed the declaration of the General Emergency and the recommendation of protective actions. A failure to determine why a main steam isolation valve _

had colsed diverted the operating staffs from diagnosing actual plant conditions having higher  !

priorities. The assessment staff did not prusue and properly analyze or diagnose the condition i of the turbine generator, despite multiple indications. The delays in analyzing and responding to this conditien allowed contaminated primary coolant to flow unchecked into the turbine  :

building, thus aggravating the mdiological conditions. These three incidents accounted for the  !

weakness.

Operations Support Center

{

298/9214-01 Failure to maintain ongoing TSC/OSC habitability during a release was .

determined to be a weakness. Steps not observed relative to habitability included closing the  ;

door to the facility and switching to HEPA filtration. A CAM in the facility was placed far ,

from major circulation areas reducing immediate effectiveness. ,

Emergency Operations Facility i 298/9214-02 The failure to detect and classify a General Emergency based on fission product barrier status was determined to be a weakness. The inability to determine the degree of fuel r clad damage based on plant process monitors delayed the determination until a reactor coolant -

sample had been analyzed. The General Emergency was ultimately declared based on actual ,

radiological conditions at the site boundary.

298/9214-03 The failure to approve the initial General Emergency notification messages to state ,

and local agencies and the failure to complete the notification process in a timely manner was determined to be a weakness. Initial notification to offsite authorities for the General Emergency was completed after 26 minutes an therefore not within the required 15 minute period.

Notification messages were not signed by the Emergency Director.

298/9214-04 The use of two dose assessment programs for decision making purposes without clear guidance on reconciling conflicting results was identified as a weakness. The discrepancy in results from the two models used at CNS delayed declaration of the General Emergency for up to one hour.

l t

Scope and Objenives Page 2-12 August 17,1993

l Section 3 EXERCISE INFORMATION P

i

3. EXERCISE INFORMATION 3.1 Exercise Participants >

3.1.1 The Nebraska Public Power Distdct

a. Control Room Simulator

b. Technical Support Center (TSC)

c. Operations Support Center (OSC), and associated in-plant response teams

d. Emergency Operations Facility (EOF), and appropriate offsite radiation monitoring teams

e. General Office Emergency Center (GOEC)

f. Media Release Center (MRC) 3.1.2 Ofsite Agencies TBD 3.2 Exercise Organization The organization for this Exercise consists of the Exercise Coordinator, the Izad Exercise Controller, Controllers, Evaluators, Observers, Observer / Evaluators and the Players as follows:

3.2.1 The Exercise Coordinator The Exercise Coordinator is responsible for the post-exercise Controller debriefing, the CNS exercise critique and the NRC critique and exit meeting.

Subsequent to the Exercise, he will direct the prepamtion of a consolidated evaluation package and preparation of an itemized list of recommended corrective actions.

3.2.2 The Lead Exercise Controller The Lead Exercise Controller is responsible for the conduct of a successful exercise and will coordinate exercise preparations including the development of the scenario and messages. The Lead Exercise Controller will ensure the safe conduct of the Exercise and is responsible for resolution of any scenario-related inter-facility questions, and will ensure that the conduct of the Exercise does not adversely impact the operation of the station. The Izad Exercise Controller will also assist with the preparation of a consolidated evaluation package.

Exercise Informazion Page 3-1 ca6660MANUALUECT1).WP3

3.2.3 The Controllers Controllers are qualified personnel selected to perform functions as follows: ,

A Izad Controller is assigned to each emergency response facility. The Lead ,

Controller is responsible for all Controller, Evaluator, and Observer activities for that facility and, as appropriate, its associated teams. Controllers for teams or sub-areas of a facility repon to the Lead Controller of that facility.

Controllers will deliver " Exercise Messages / Data" to designated Players at specified times and places during the Exercise, inject or deliver contingency messages as required to prompt the appropriate Player response and keep the Exercise actions moving according to the scenario, observe the Exercise at other assigned locations, and prepare an evaluation. Controllers will submit written observations to the Lead Controller, who will summanze all comments -

for submittal to the Exercise Coordinator. The Controllers are provided with instruction materials. This information is contained in Section 4.0 of this '  !

manual.

3.2.4 Evaluators i

I Evaluators are personnel who are assigned to judge the effectiveness of participating organizations, personnel, and activities in response to the scenario. They will evaluate performance on the basis of standards or ,

requirements contained in the appropriate Emergency Plan, Implementing  :

Procedures, Exercise messages, and as described herein. Most Controllers will also function to evaluate the facility or function to which they are assigned. They will document their findings on objective based evaluation forms. )

l 3.2.5 Observers l 1

l Observers may be authonzed, on a limited basis, to participate in the Exercise for the purpose of observing exercise activity for personal educations.

3.2.6 Inspectors Inspectors are members of the NRC evaluation team and will have prior knowledge of the Exercise scenario. At their assigned locations they will observe the Exercise and prepare an evaluation to be presented at the exit meeting and critique. ,

l 4

Exercise information Page .1-2 0:\6660NANUALLSECT1_6.%7s ,

I

l 3.2.7 Players l Players include station and cther utility personnel assigned to perform emergency functions as described in the Emergency Plan and Implementing  !

Procedures. Players from offsite organizations and agencies (county, State, i and private industry) are also participants in the Exercise. .j 3.3 Conduct of the Exercise The Exercise will simulate a radiological incident at the Cooper Nuclear Station in order to demonstrate the effectiveness of NPPD CNS emergency i response personnel, facilities, and the appropriate emergency plans and procedures. It will be initiated by abnormal events requiring the Shift Supervisor to implement the Emergency Plan.  !

All notifications to NPPD, State and local responders .will be made in accordance with applicable procedures and policies, with the exception that j notifications to agencies not participating will be made to a control cell. l The 1993 Emergency Preparedness Exercise will include the use of a " live" simulator. The CNS Control Room simulator will be used to duplicate the plant response to actions taken by the on-shift crew of operators. All indications and annunciators which are modelled by the software will be available to indicate to the crew the status of systems and equipment, as the operators respond to the scenario.

The capability exists to provide "real time" data to other emergency response facilities (TSC and EOF) using terminals connected to the simulator. The terminals will provide the Players in these facilities similar information normally available through the Plant Management Information System (PMIS).

The Simulator will be the central point for dissemination of plant data and is the key to ensuring that the Exercise progresses on schedule. In the event of a failure of the Simulator computer, the Lead Exercise Controller shall direct that plant indications, parameters and annunciators will be provided to the Control Room operators using message forms and plant data sheets. Extensive plant information is provided on these data sheets, so that at no time will the messages " prompt" the Players or provide undue assistance in recognition of '

events. To more closely approximate the data that would be available in an actual emergency situation, information available on PMIS will also be provided in the TSC and the EOF where output consoles are located, should the simulator not support a " live" scenario. In this event, less of a potential

, exists for significant disparity between the data available in the Control Room and in the other facilities.

Exercise infonnation Page 3-3 G:16660thfANUAL1 SECT 1_6.uT3 P

5

Contingency messages (denoted by an 'x' after the message number) are delivered onlv when conditions described in the Controller notes have been mel. Receipt of a contingency message by a Player is NOT necessarily indicative of an error, and should not be construed as such. Some data on these messages, for example, is provided only when specific actions have been taken to access the information or when a particular extent of play activity is required to demonstrate an Exercise objective. Other such messages are provided to Players when specific actions are required to maintain the scenario within acceptable limits of direction and time frames.

Radiological and meteorological data, presented in Sections 9.0 and 10.0, and information included in the supplemental scenarios will be disseminated by Controllers when Players demonstrate the capability to obtain the information from appropriate sources. At no time, unless noted specifically as an exception, will information be provided at a point where it would not be available in a real emergency. Controllers shall deliver all information and messages exactly in the time and manner described on the massage form.

Controllers may interject other information or change a message to ensure that the Exercise progresses as planned, only with the specific concurrence of the Lead Exercise Controller.

Players are expected to " free play" the scenario to the extent permitted by their Controller. Response to each situation should be as realistic as possible, consistent with maintenance of personnel and plant safety.

Notifications of, and contact with supervisors, plant management, and offsite agencies will be made in accordance with applicable procedures and instructions (unless a Controller issues instructions to the contrary). Only those simulations identified by a Controller or specifically identified in >

briefings are permissible. Non-participating organizations can be simulated through the use of a " Control Cell."

3.4 Precautions and Limitations This section provides information for all Exercise participants regarding guidelines to be followed throughout the conduct of this Exercise. Prior to 1 initiation of the Exercise, pre-exercise briefings will be held to review the l entire exercise process with all the Exercise participants.

3.4.1 ActualEmergencies It will be the responsibility of any Exercise Controller or Observer who becomes aware of an actual emergency to suspend exercise response in his/her immediate area and to inform the lead Exercise Controller of the situation. l Exercise infonnation Page 3-4 G:A6660WAMJAUSECn_6.WH l

i

1 Upon notification of an actual emergency, the Lead Exercise Controller will make a determination'whether to continue, temporadly suspend or terminate the Exercise, 3.4.2 Unsafe Conditions Should, at any time during the course of the conduct of this Exercise, an exercise Controller or Observer witness an exercise participant undertake any

~

action which would, in the opinion of the Controller, place either an individual or component in an unsafe condition, the Controller is responsible for intervening in the individual's actions and terminating the unsafe activity immediately.

No response to an exercise situation will be simulated without Controller approval. No action will be taken that reduces the marein of safety in the pjanni.

3.4.3 Operating Equipment All repair activities associated with the scenado will be simulated with extreme caution emphasized around operating equipment. Manipulations of any plant operating systems, valves, breakers, or controls in response to this Exercise ,

are to be simulated. There is to be no alteration of any plant operating equipment, systems, or circuits during the response of this Exercise. No pressurization of fire hoses, discharging of fire extinguishers, or initiation of any fire suppression systems will be allowed inside the plant.

3.4.4 Public Announcements All telephone communications, radio transmissions, and public address announcements related to the Exercise must begin and end with the statement, "This is a drill". Should a Controller witness a drill participant not observing this practice, it is the Controller's responsibility to remind the individual of the need to follow this procedure. i l

Care must be taken to assure that any non-participating individuals who may observe Exercise activities or overhear Exercise communications are not misled into believing that an actual emergency exists. Any Exercise Controller I who is aware of an individual or group ofindividuals in the immediate vicinity . l who may have become alarmed or confused about the situation, should approach that individual or group and explain the nature of the Exercise and its intent.

Exercise information Page 3-5 c:w60wANUAusEcn.,.s.wn l

1

3.4.6 Motor Vehicle Response Any motor vehicle response to this Exercise, whether it be ambulance, fire  !

fighting equipment, police / security vehicles or field monitoring teams, shall observe all normal motor vehicle operating laws, including posted speed limits, stop lights / signs, one way streets, etc. Red lights and sirens will nol be t operated on emergency vehicles for the purposes of the Exercise.

3.5 Abbreviations AC Auxiliary Condensate ACB Air Circuit Breaker ACAD Atmosphere Containment Atmosphere Dilution ACD Auxiliary Condensate Drains ACRS Advisory Committee on Reactor Safeguards ADS Automatic Depressurization System ALARA As Low As Reasonably Achievable t ALRW Augmented Liquid Radwaste i ANN Annunciator ,

AOG Augmented Off Gas AOV Air Operated Valve APRM Average Power Range Monitor AR Air Removal ARM Area Radiation Monitor i AS Auxiliary Steam ASB Auxiliary Steam Boilers ATS Alarm Trip Setting ATWS Anticipated Transient Without Scram '

BF Booster Fan BLDG Building BOP Balance of Plant BPV Bypass Valve BUCLE Backup Core Limits Evaluation  !

- - . Boiling Water Reactor i CD Condensate Drain CDP Computer Data Processing CF/CFD Condensate Filter Demineralizer  :

CHF Critical Heat Flux

. CI Chemistry Instrumentation ,

CIC Component Identification Code Exercise inforrnation Page 3-6 c:16660wANUAL15ECT1_6.wP3 n

CM Condensate Makeup ,

CMFLPD Core Maximum Fraction of Limiting Power Density CNS Cooper Nuclear Station CNSNO CNS Number (Used for part numbers only)

CP Process Computer ,

CPP Control Power Panel CRDM Control Rod Drive Mechanism CR Control Room CRS Control Room Supervisor  :

CS Core Spray  :

CSCS Core Standby Cooling System ,

CSP Core Spray Pump CST Condensate Storage Tank CW Circulating Water CWP Circulating Water Pump DBA Design Basis Accident DEH Digital Electro-Hydraulic System DG Diesel Generator i DPM Disintegrations Per Minute DV Drain Valve or Dump Valve i DW Demineralized Water  ;

ECCS Emergency Core Cooling Systems  :

ECST Emergency Condensate Storage Tank EDF Equipment Data File EE Electrical Equipment EF Exhaust Fan EOF Emergency Operations Facility EOP Emergency Operating Procedure EPIP Emergency Plan Implementing Procedure  ;

EPRI Electric Power Research Institute EQ Equipment Qualification i ERP Elevated Release Point ES Extraction Steam ESS Engineered Safeguard System i FEMA Federal Emergency Management Agency ,

FO Fuel Oil FP Fire Protection FPC Fuel Pool Cooling and Cleanup ,

. G.E. General Electric GM Geiger-Mueller  ;

Exercise Infmnation Page 3-7 c:s6660wavAusicn_6.m  :

I 1

1 i

e GOEC General Office Emergency Center .

t HAD Heat Actuating Device HCU Hydraulic Control Unit HEPA High Efficiency Particulate Absorber .

HP - Health Physics or High Pressure i I

HPCI High Pressure Coolant Injection HVAC Heating, Ventilating, and Air Conditioning HX Heat Exchanger IA Instrument Air '

I&C Instrumentation and Controls i ILRT Integrated leak Rate Test l INPO Institute of Nuclear Power Operations INTK Intake Structure IRM Intermediate Range Monitor LCO Limiting Condition for Operation LER Licensee Event Report l

~

LLRT Local Izak Rate Test LOCA Imss of Coolant Accident .

i LPAP Low Power Alarm Point LPCI Low Pressure Coolant Injection LPSP Low Power Setpoint LPRM Iocal Power Range Monitor LSA low Specific Activity MC Main Condensate  ;

MCC Motor Control Center MCPR Minimum Critical Power Ratio MOV Motor Operated Valve MPC Maximum Permissible Concentration  ;

MRC Media Release Center ,

MS Main Steam MSIV Main Steam Line Isolation Valve MSL Main Steam Line MWR Maintemace Work Request NPPD Nebraska Public Power District NPSH Net Positive Suction Head  !

NRC Nuclear Regulatory Commission NRHX Non-Regenerative Heat Exchanger

. NSSS Nuclear Steam Supply System .

Execise infonnation Page 3-8 a:u60aununAsEcnfm ;

r

i i

OBE Operating Basis Earthquake OG Off Gn OPL Operating Plant Limits e I

OSC Operations Support Center i

PASS Post-Accident Sampling System l PC Primary Containment  !

P&ID Piping and Instrumentation Drawing PM Preventative Maintenance  :

PMIS Plant Management Information System  !

Q.A. Quality Assurance Q.C. Quality Control REM Rod Block Monitor RCIC Reactor Core Isolation Cooling l REC Reactor Equipment Cooling l RF Reactor Feedwater or Recire Fan i RFP Reactor Feed Pump RFPT Reactor Feed Pump Turbine i RHR Residual Heat Removal RMA Radiation Monitoring - Area RMCS Reactor Manual Control System RMP Radiation Monitoring - Process RMV Radiation Monitoring - Valve RO Reactor Operator RPIS Rod Position Information System -

RPS Reactor Protection System RPV Reactor Pressure Vessel ,

RRP Reactor Recirculation Pump RRMG Reactor Recirculation MG Set RSCS Rod Sequence Control System RTD Resistible Temperature Detector ,

RTS Reactor Trip System i RWCU Reactor Water Cleanup RWM Rod Worth Minimizer SA Service Air SDC Shutdown Cooling ,

SDV Scram Discharge Volume SDM Shutdown Margin SGT Standby Gas Treatment ,

SJAE Steam Jet Air Ejector SLC Standby Liquid Control Exercise Information Page 3-9 c:\6660MAWAUSECD_6.WP5 i

{

SORC Station Operations Review Committee '

SPDS Safety Parameter Display System SRAB Safety Review and Audit Board SRM Source Range Monitor SRO Senior Reactor Operator SRV Safety / Relief Valve SS Shift Supervisor  !

SSE Safe Shutdown Earthquake '

STA Shift Technical Advisor SW Service Water TAF Top Active Fuel (352.56" Above Vessel Bottom)

TB Turbine Building TEC Turbine Equipment Cooling TG Turbine Generator TIP Traversing In-Core Probe TLD Thermoluminescent Dosimeter ,

TSC Technical Support Center USAR Updated Safety Analysis Report WT Water Treatment ,

3.6 Definitions ALERT: The level of emergency classification which indicates that events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant.

ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS): Failure of the reactor control rods to insert into the core upon a scram signal from the Reactor Protection System or the failure of said system to initiate a SCRAM when Reactor Protection System trip limits have been exceeded.

ASSESSMENT ACTIONS: Those actions taken during or after an accident to obtain and process information that is necessary to make decisions to .

implement specific emergency measures. l CONTROL ROOM (CR): The principle onsite location from which the reactor is controlled and from which emergency control is initially exercised.

Exercise Information Page 3-10 G:\6660MANUALUECD_6.5%

i e

i CONTROLLER: A member of the Exercise control group, assigned to one or more activities or functions for the purpose of keeping the action going i according to a scenario, resolving scenario discrepancies, and supervising the l actions of the playen.  !

CORRECTIVE ACT. NJ: Those emergency measures taken to improve or terminate an emergency situation.

DECONTAhUNATION: The process by which the body or an object is relieved of radioactive substances (contamination).  ;

DOSE ASSESSMENT: The process of estimating the amount of radiation a  !

person will potentially receive as a result of exposure to a radiological release.  ;

DRILL: A supervised event aimed at evaluating, developing, and maintaining skills in a particular operation.

EMERGENCY ACTION LEVELS GALS): Radiological dose rates; specific contamination levels or airborne, waterborne, or surface-deposited -

concentrations of radioactivity; or specific plant conditions that may be used as thresholds for initiating specific emergency measures.  ;

i EMERGENCY OPERATIONS CENTER GOC): An emergency response facility from which government officials exercise direction and control. The EOCs are located as follows:  !

State of Nebraska: 1300 Military Road ,

Lincoln, NE State of Missouri: 1717 Industrial Drive  :

Jefferson City, MO Nemaha County: Auburn Fire Station Auburn, NE Richardson County: County Courthouse (Basement) ,

Falls City, NE Atchison County: 101 Highway 136 East Rock Port, MO Exercise information Page 3-11 G:\6660thtANUALLSECT1_6.WP3 l

EMERGENCY OPERATIONS FACILITY OF): The NPPD emergency response facility from which overall direction and control are exercised for emergencies at CNS. The facility also provides a central point of contact for communications and external (non-NPPD) organizations, and is fully activated for emergencies classified as an Alert or higher.

EMERGENCY PLANNING ZONES GPZs): The land areas encompassed within approximately 10 and 50 mile radii of the DBNPS, in which protective actions may be necessary to protect the public in the event of a nuclear plant-accident. The 10 mile zone is referred to as the Plume Exposure EPZ; the 50 mile zone is termed the Ingestion Exposure EPZ.

EMERGENCY RESPONSE FACILITY: Any of several onsite and offsite centers which are activated to coordinate emergency actions. Included in this category are the Control Room, Technical Support Center, Operations Support Center, Emergency Operations Facility, Media Release Center, and State and local Emergency Operations Centers.

EVALUATOR: A member of the exercise evaluation group, assigned to one or more activities or functions for the purpose of evaluating and making recommendations for improvement. An evaluator may serve in a dual capacity as both a Controller and Evaluator.

EXCLUSION AREA: The area surrounding the CNS in which the NPPD has the authority to determine all activities including exclusion or removal of persons and property from the area during accident conditions.

EXERCISE: An event which tests the overall functions and capabilities of organizations involved in responding to an emergency situation. An exercise will usually simulate an emergency that results in offsite radiological releases which require response by offsite authorities.

GENERAL EMERGENCY: The most severe level of emergency classification which indicates that events are in progress or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. Release of radioactive material can be reasonable expected to exceed PAG exposure levels offsite.

INGESTION PATHWAY: The exposure mode for which the zone of concern encompasses an area of approximately 50 mile radius from ingestion of contaminated water or foods; such as mild or fresh vegetables. The period of potential exposure could range in length from hours to months.

Excrcise Informatien Page 3-12 G:W40MANUALuEC11,,6.WP5

MEDIA RELEASE CENTER (MRC): An emergency response facility, which  !

is staffed by NPPD, local, State, NRC and FEMA officials. The MRC '

provides a forum and point of contact for a coordinated release of news and information to the news media, general public, district employees and special {

interest groups.

• i OBSERVER: Any individual who is authorized to observe the Exercise, but is ,

not authorized to interact with the players.  !

OFFSITE: All land and water areas outside the Owner-Controlled Area fence ,

surrounding the CNS. .

ONSITE: All land and water areas within the Owner-Controlled Area i surrounding the CNS.

OFFSITE MONITORING TEAMS (OMTs): Two-person teams responsible  !

for monitoring radiation levels in the environment and collecting soil, air, vegetation, snow, and water samples for laboratory analysis. l OPERATIONS SUPPORT CENTER (OSC): An onsite emergency response facility which provides a location where emergency response teams can be assembled and coordinated during an emergency.

I OWNER-CONTROLLED AREA: The area around the CNS that is owned /and to which the access controlled, by NPPD.

PARTICIPANT: An individual who has some part in the Exercise, whether as [

an Evaluator, Controller, Player or Observer, i

PL.AYERS: All individuals (CNS, NPPD personnel, and individuals from offsite organizations and agencies) who are assigned to perform functions of ,

the emergency response organization, as described in the appropriate Emergency Plan and Emergency Plan Implementing Procedures.

PLUME EXPOSURE PATHWAY: The exposure mode for which the zone of concern encompasses an area of approximately a 10 mile radius around CNS.

The principle exposure sources in this area: 1) whole body external exposure to gamma radiation from the plume and deposited material, and 2) inhalation exposure from the passing radioactive plume. The period of potential exposure could range from hours to days.

I POPULATION AT RISK: Those persons for whom protective actions would

. be taken.

E.zercise infonnation Page 3-13 c:w660wsNusturcn_6.m i I

PROTECTED AREA: The area within the Site Boundary encompassed by physical barriers and to which access is controlled for security purposes.

PROTECTIVE ACTION: Those emergency measures taken after an accident or an uncontrolled release of radioactive materials has occurred, for the purpose of preventing or minimmng radiological exposures to personnel that would otherwise occur.

PROTECTIVE ACTION GUIDES (PAGs): Projected radiological doses to individuals in the general population which warrant protective action following a release of radioactive material.

SITE AREA EMERGENCY: The level of emergency classification which ,

indicates that events are in progress or have occurred which involve actual or likely major failures of plant functions needed for protection of the public.

Any releases of radioactive material are not expected to exceed Protection Action Guide (PAG) exposure levels, except within the Site Boundary.

TECHNICAL SUPPORT CENTER (TSC): An onsite emergency response facility for use by technical and management personnel in support of the command and control functions executed in the Control Room. i UNUSUAL EVENT: The lowest level of emergency classification, which  !

indicates that events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant.

3.7 References 3.7.1 CNS Emergency Plan - Nebraska Public Power District 3.7.2 CNS Emergency Plan Implementing Procedures 3.7.3 CNS Technical Specifications 3.7.4 CNS Updated Safety Analysis Report 3.7.510 CFR 50.47,50.54 and Appendix E 3.7.6 NUREG-0654/ FEMA-REP-1, Rev.1 3.7.7 CNS Piping and Instrumentation Drawings Etercise information Page 3-14 c:vss60MANUALutcn_6.wrs

6 Section 4 CONTROLLER / EVALUATOR INFORMATION f

I

?

4. CONTROLLER / EVALUATOR INFORMATION 4.1 General Information Each Controller / Evaluator should be familiar with the following:

4.1.1 The objectives of the Exercise (Section 2.0).

4.1.2 Applicable precautions and limitations (Section 3.0).

4.1.3 The Exercise scenario, including the initial conditions and the expected course of action to be taken (Section 7.0).

4.1.4 The various locations that will be involved and the specific items to be observed at those locations.

4.1.5 The evaluation checklists provided.

4.2 Controller Instructions 4.2.1 Controllers will position themselves at their assigned locations 30 minutes prior to the activation of the facility or team for which they have responsibility.

4.2.2 Communications will be tested prior to Exercise commencement. All watches and clocks will be synchronized with the Control Room clock as part of the communications testing.

4.2.3 All Controllers will comply with instructions from the Lead Exercise l Controller.  ;

l 4.2.4 Each Controller will have copies of the messages controlling the  !

progress of the Exercise scenario. No messages shall be delivered out of secuence or other than as written unless soecifically authorized by the Lead Exercise Controller.

4.2.5 Controllers will ant Provide information to the Players regarding scenario progression or resolution of problems encountered in the course of the simulated emergency. The Exercise participants are expected to obtain information through their own organizations and exercise their own judgement in determining response actions and l resolving problems.  !

l l

l Controller / Evaluator Information Page 4-1 G:\6660MANUAUSECD_6.W3

i 4.2.6 In the event that a Player insists that certain parts of the scenario are unrealistic, the Controllers have the sole authority to clarify any questions regarding scenario content.

4.3 Evaluator Instmetions Each Evaluator will take detailed notes regardine the progress of the Exercise and resnonse of the Exercise participants at their assigned locations. Each ,

Evaluator should carefully note the arrival and departure times of participants, l the times when major activities or milestones occur, and problem areas encountered. Evaluators' comments will be used for the purpose of  !

reconstructing the Exercise chronology and preparint a written evaluation of ,

the Exercise.

Sheets containing specific emergency facility evaluation criteria are provided in Emergency Preparedness Department Procedure (EPDP) 11, Exercise and D lll Evaluation Procedure. These sheets must be completed by each hvaluator and provided to the Exercise Ccordinator at the conclusion of the  ;

Exercise.

Evaluator forms for each facility / team will be distributed at the pre-exercise .

Controller briefmg. ,

4.4 Personnel Assignments t

The personnel assignments for the Controller orgamzation are listed in Table  !

4 41. Assignments for the Evaluator organizath are listed in Table 4.4-2.

4.5 Simulator Instmetions >

4 The simulator will be relied on primarily for data generation and plsnt  !

response interactions with the Control Room crew. Should it malfunction or  !

go off-line (e.g., a loss of power to the Training Center), the Lead Exercise ,

Controller has several options to choose from. They include-l stopping the Exercise and conducting it the following day (provided l

Simulator repairs can be performed);

• completing the Exercise using the data sheets provided in the Exercise Manual; and 4

ending the Exercise if most of the objectives have been demonstrated.

(Unmet objectives would be re-scheduled for a later date.)  ;

Controller /Enluator Information Page 4-2 a:\6660wANUALtSECT1_6.WP3 i

Table 4.4-1: Controller Assignments CONTROL ROOM SIMULATOR George Reed Lead Exercise Controller Bob Hayden Control Room Management (Drill Controller)

Dave Shrader Control Room Operators Duane Shallenberger Control Room Operators Jim Surrette Instructor Station Operator '

Tim Rients Instructor Station Operator OPERATIONS SUPPORT CENTER

• Chemistry /HP Activities Dan Snyder Darrell Lisec Electrical /I&C Activities Iannie Swanson Mechanical Activities Pat Mcdonald Operations John Shrader Operations Dave Montgomery Operations TECHNICAL SUPPORT CENTER

• TSC Management Mike Krumland Gene Mace TSC Operational Table Vern Stairs Operations Team (s) i Craig Jorgensen TSC Engineering

, Mark Lyman TSC Engineering Darren Dageforde TSC Engineering Tim Niemann Repair / Rescue / Reentry Teams Larry Talmon Repair / Rescue / Reentry Teams Terry Marnell Repair / Rescue / Reentry Teams ,

Ken Talbot Repair / Rescue / Reentry Teams Steve Werner Repair / Rescue / Reentry Teams '

Ed Rotkvic In-plant Rad Monitoring Teams Mike Dorn In-plant Rad Monitoring Teams Larry Corey In-plant Rad Monitoring Teams Forrest Alderman Fire Brigade Team i

• Indicates Lead Facility Controller Controller / Evaluator information 4-3 6660/nuctInppdevex g

Table 4.4-1: Controller Assignments (continued)

EMERGENCY OPER ATIONS FACILITY ,

Bill Dunlap EOF Management Mario Vigliani Dose A.tsessment Tom Rigney Field Team Coordination Chuck Chase D/W Team #1 .

Rob Abraham D/W Team #2 GENERAL OFFICE EMERGENCY CENTER Bob Wilbur GOEC Management MEDIA RELEASE CENTER Larry Linder MRC Management t

• Indicates Lead Facility Controller ,

i i

.i i

Controller / Evaluator information 4-4 6660/nucunppdem

Section 5 PLAYER INFORMATION 9

t I

f i

I l

l 1

1

l

5. PLAYER INFORMATION 5.1 General Information This section provides guidelines for all exercise Players, which should be followed throughout the conduct of the Exercise. A pre-exercise briefing will be held for key Players to review the entire exercise process, including

" Precaution and Limitations" in Section 3.4, and the following information.

The success of the Exercise is largely dependent upon Player reaction, Player knowledge of their appropriate Emergency Plan and Implementing Procedures, and an understanding of the purpose of the Exercise. Initial conditions which  ;

will affect Player action or reaction will be provided to the Players at the time the Exercise begins. However, most of the elements of the Exercise play will be introduced through the use of controlled casualties on the " live" simulator.

Players, therefore, are responsible for initiating actions during the Exercise in ,

accordance with instructions for their particular function. Each Player will advise his/her Controller prior to performing required emergency actions during the simulated activities to ensure that the Player is credited for his/her actions.

Players are reminded not to be excessively critical with the mechanics or cause ,

of the Exercise scenario. This Exercise is desiened to evaluate the Emercency Plan. Imolementine Procedures. and the emercency nrenaredness trainine

~ ~

i procram. Additionally, the Exercise is a training vehicle for NPPD personnel  !

to practice coordination with outside organizations in a simulated emergency i environment. Players should note any needed improvements that come to their attention during the Exercise and submit them to the appropriate Controller at the conclusion of the Exercise.

l i

It is necessary to postulate series of equipment failures and other combinations of events, in order to develop an accident sequence that culminates in a  ;

significant release of radioactivity to the environment. Please accent exercise information and messaces as written. and respond as thouch the deoicted event i occurred. If corrective action; are discovered that would terminate the emergency, they should be identified to a Controller so that the Exercise can i continue on schedule.

5.2 Player Guidelines 1

5.2.1 Maintain a serious, professional attitude throughout the Exercise.

5.2.2 Teamwork is essential! Do yourjob and then help other people do j theirs. For example, if you know certain information should be Player Infonnasion Page 5-1 G:w660wANUAusEcn_6.wn [l I

available, ask for it. This makes you look good and may reduce a ,

deficiency for someone else.

5.2.3 Brainstorm and look for all nossible solutions or consequences of events. Maintain the " big picture" of what is happening.

5.2.4 Identify yourself by name and function to the Controller in your area.

• i Always wear your identification badge, 5.2.5 If you are entering normal nuclear station radiation areas, observe all  ;

rules and procedures. No one (includinn Controllers) is exempt from normal station radiological practices and procedures.

NOTE: DO NOT ENTER ACTUAL IIIGII RADIATION AREAS IN THE PLANT; FOLLOW ALARA PRINCIPLES. '

5.2.6 Observe all normal security procedures. All normal security procedures are in effect without exception. If a security condition ,

arises, obey immediately the directions of Security Guards.  ;

5.2.7 Initiate actions in accordance with instructions and responsibilities.

5.2.8 Communications should be concise and formal with use of j abbreviations minimized. Always include "This is a drill". i s

5.2.9 Use and demonstrate knowledge of the Emergency Plan and Implementing Procedures.

5.2.10 No response to an Exercise situation will be simulated without Controller approval. No action will be taken that reduces that margin of safety in the plant.

5.2.11 Keep a list of items which you believe will improve the plan and/or procedures. Provide this to your Controller / Eval-nator at the end of 1 the Exercise.

5.2.12 Remember, one of the main purposes of an exercise is for you to assure yourself that you are adequately prepared. Areas for ,

improvement or lessons learned, when identified, will improve your overall emergency preparedness.

1 I

i Player Information Page 5-2 G:\6660MANUAUSECT!,,6.MM l

l l

i i

Section 6 t

SCIEDULE OF EVENTS L

4 b

I

+

t J

t b

B

6.0 SCHEDULE OF EVENTS 6.1 Times and Places  ;

Event _ Elate Ilme Hatt Exercise Controller / Auditorium 09:00-12:00 August 12 Evaluator Walkthrough NRC Briefing Auditorium 13:00-15:00 August 16 Exercise Player Auditorium 15:30-16:00 August 16 Briefimg Conduct of Exercise / Various All Day August 17 Player Critiques Controller Critique Auditorium 8:00-12 00 August 18 Session Exercise Critique Classroom J 15:00 August 18 Presentation to Management -

Exercise Critique Classroom J 9:00-10:00 August 19 Presentation to the NRC NRC Exit Briefing Classroom J 11:00-12:00 August 19 Player De-brief Auditorium 9:00 August 19 i

4 Schedule of Ewnts Page 6-1 6660/nucunppdeux

i 6.2 Travel Information j For prior arrangements, questions, or permission to observe, contact:

Nebraska Public Power District Cooper Nuclear Station Emergency Planning Group Mr. Robert Hayden  ;

P.O. Box 98 Brownville, NE 68321 (402) 825-5270 Airports

1. Omaha, NE - Approximately SJ anites (Take Rte 73 South, Rie 6 East, Rte 29 South, Rte 136 West to Brownville, follow signs to Cooper Nuclear Station)

2. Kansas City, MO - Approximately 90 miles (Take Rte 29 North, Rtc 136 West to Brownville, follow signs to Cooper Nuclear i Station)

Motels

1. Rock Port Inn (816) 744-6282 Rock Port, MO

2. Palmer House (402) 274-3193 Auburn, NE .

-1

3. Aubum Inn (402) 274-3143 Auburn, NE

'i e

4 h .

1

Section 7 EXERCISE SCENARIO MATERIAL I

i

)

i 1

l l

i

7.. EXERCISE SCENARIO MATERIAL r

7.1 Scenario Sununary Initial conditions are established at 8:00 AM with the plant at 100% power, end of core life. A refueling outage is scheduled to begin in 6 days. Reactor coolant chemistry is in specification. An operability surveillance performed last night on the "B" LPCI injecdon valve (MO-27B) resulted in the motor operator burning itself up. The preliminary analysis indicates a potentially incorrect torque switch setting. The valve has been declared inoperable and replacement of the motor operator is scheduled to begin today.

t All plant equipment is in normal configuration with the following exceptions:

The "B" side LPCI injection valve (MO-27B) is out of service and the motor operator is being replaced. Valves tagged out for this repair include MO-25B,  ;

27B, 66B and 12B. Work is scheduled to be completed within 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />. This 7-day LCO has been in effect for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

RCIC is out of service for replacement of failed turbine governor vacuum pump  ;

seals which have caused steam leakage. MO-15 is tagged out along with the Gland Seal Pump. Work is scheduled to be completed tomorrow, day 4 of 7-day LCO.

CRD Pump *B" is out of sarvice due to a crack in the minimum flow line.

Maintenance is investigating the cause of the crack. .

A Westinghouse team is on-site for in-service vibration testing of the main turbine.

t At 0815, a process line transferring spent RWCU resin ruptures in the Sludge -

Decant Pump Room. Resin and water spray down the room and seep out from '

~

under the door. Radiation monitors in the area register an increase of greater than 1000 times. The Transfer Pump is shut down five minutes after the pipe rupture occurs. HP is dispatched to the area. The SS makes an announcement i to clear the area and declares an ALERT based on EAL 1.2.1, " Loss of control of radioactive material resulting in area radiation exceeding 1000X normal or -

expected levels within the protected area." Notifications are conducted in accordance with EPIP 5.7.6. The TSC and OSC are activated. Plant evacuation, assembly and accountability are performed. ,

l i

I l

l Exercise Scenario Material Page 7-1 August 17,1993 l

At 0905 a breaker in 480V MCC "K" develops a ground fault causing the MCC feeder breaker to trip. Components rendered inoperative as a result include LPCI <

"A" injection valve, Drywell Cooler Fans "A" and "C", REC pumps "A" and "B" and SLC pump "A". i At 1015, a packing leak develops from AO-86B, the Main Steam Line "B" outboard MSIV. Steam tunnel temperatures increase causing a Group I isolation (setpoint 196* F) and reactor trip at 1020. Main Steam Line "B" inboard and i outboard MSIVs fail to go fully closed. OPS uses the main turbine pressure set to control reactor pressure. Emergency Director declares a SITE AREA EMERGENCY per EAL 2.3.3, " Loss of any TWO fission product barriers (Primary Coolant Boundary and Primary Containment). The EOF and i GOEC/MRC activate. Electricians repair the faulted MCC-K breaker but i evacuate the Reactor Building before closing the cubicle door. [

At 1035, the condenser to condensate suction line boot fails causing a rapid loss of condenser vacuum and trip of all three condensate pumps due to cavitation.

Feedwater pumps trip on low suction pressure. Bypass valves go closed on low .

condenser vacuum. Operators use Relief Valves to reduce reactor pressure to 500 psig and HPCI to maintain vessel level.

HPCI trips due to a failed controller component in the Control Room. Operators maximize CRD flow and start a SLC pump with suction from demin water. Loss - l of ECCS pressure maintenance occurs due to a trip of the Reactor Building auxiliary condensate booster pump. MCC-K develops a short to ground due to entry of steam into the open breaker cabinet.

The RWCU bottom head drain line breaks in the drywell at 1050. The loss of coolant results in a rapid decrease in vessel level. Drywell pressure, temperature and radiation levels increase rapidly. Safety systems auto actuate on high drywell pressure. Core Spray "B" pump subsequently trips on overcurrent caused by water hammer due to the previous loss of pressure maintenance. The only source of makeup to the vessel is CRD and SLC Pump "B". The ED declares a GENERAL EMERGENCY based on EAL 2.4.1, " Loss of TWO of THREE ,

Fission Product Barriers AND the potential exists forIgn of the THIRD".

By 1115, vessel level has decreased to top of active fuel and fuel cladding damage begins to occur, increasing to 4 % over 30 minutes. Operators emergency depressurize in accordance with EOP's. A release begins from the reactor vessel into the Steam Tunnel and Reactor Building through Standby Gas Treatment and out the ERP. This results in a radioactive plume moving off-site. Reactor >

Building radiation levels increase. The Drywell radiation monitor increases to

.1500 R/hr.

Exercise Sanario Material Page 7-2 Avausrn. im

By 1115, vessel level has decreased to top of active fuel and fuel cladding ,

damage begins to occur, increasing to 4 % over 30 minutes. Operators emergency depressurize in accordance with EOP's. A release begins from the reactor vessel into the Steam Tunnel and Reactor Building through Standby Gas Treatment and out the ERP. This results in a radioactive plume moving off-site. Reactor Building radiation levels increase. The Drywell radiation monitor increases to 10,000 R/hr.

A fire starts in SGT Train "B" at 1130 due to the high degree of iodine '

absorption. A significant reduction in iodine removal capability results. The deluge valve is manually opened at the train to extinguish the fire. Dose assessment performed with SGT inoperable results in estimation of thyroid dose exceeding PAG's beyond 5 miles. PAR's are discussed with the States.

At 1230 MCC *K" is repaired and the Core Spray "A" injection valve is opened.

Core Spray "A" loop injects and recovers vessel level. Containment sprays are ,

subsequently used to reduce containment pressure. Train "A" of SGT is returned to service and reduces the offsite release rate.

By 1300, Reactor pressure is equalized, and the release terminates. The Exercise is secured. s

?

i I

Exerche Sxnario Material Page 7-3 August 17,1993 l i

w wr

FIL E 7-1 1993 Exercise Timeline Time 0730 on:oo ordo c9so 0930 10.00 loco arm liso 12:00 1230 13:00 13:1o 1490 l l l I l l  !  !  !  !  !  ! l  !  !  !  !  !  !  !  !  ! I l A A A A A AA A A A A A A A A A t

2 3 4 5 678 9 to 11 12 13 14 is 16 TIME EVENT 7:30 1 Initial Conditions: Reactor @ 100% power, end of core life. Refuel outage will begin in 6 days. The "B" LPCI inject vaht is OOS for repair, RCIC is OOS for seal replacement, CRD "B" is OOS due to crack in min flow line. A Westinghouse team is on-site to take in-sersice turbine vibration readings. RWCU resin transfer in progress. RCS chemistry is in specification.

8:15 2 Uncontrolled spent RWCU resin release occurs in the Reactor Building. ARM's increase more than 1000x normal. ALERT (1.2.1): "Any -

uncontrolled increase in direct radiation levels greater than 1000 times normal".

9:05 3 MCC-K develops a grotmd fault. Loads lost include RHR "A" vahes, SLC "A", "A" & "C" drywell coolers, "A" & "B" REC pumps, SGT Train "A".

10:15 4 Outboard MSIV on main steamline "B" develops a packing leak. Steam tunnel temperatures increase. l 10:20 5 Group I isolation on hi:;h steam tunnel temperature occurs. Main steamline "B" MSIVs fail to isolate. MCC-K is repaired but the breaker >

cubicle door is not closed.

10:35 6 Condensate suction line boot fails catastrophically. Condensate and feedpumps trip. Condenser vacuum is lost and bypass vahts isolate.

OPS uses HPCI to maintain vessel level.

10:40 7 HPCI trips on high flow due to failed controller component in Control Room. ECCS pressure maintenance is lost.

10:45 8 SITE AREA EMERGl'NCY (2.3.3): Loss of any TWO Fission Product Barriers. EOF & GOEC/MRC activate. MCC-K trips again.

10:50 9 RWCU bottom head drain line breaks in Drywell. Vessel level decreases, Dryweil pressure and rad leveis increase. Safety systems actuate, CS "B" trips due to water hammer. Only sources of vessel makeup are CRD and SLC.

I1:10 10 GENERAL EMERGENCY (2.4.1): Loss of any TWO of THREE Fission Product Barriers and the Potential Exists for Loss of the T111RD.

I1:15 11 Vessel level reaches top of active fuel, cladding damage begins. OPS emergency depressurire the reactor per EOP's. A radioactive release from the RPV to the steam tunnel to the Reactor Building through SGT and out the stack begins.

11:30 12 The "B" SGT charcoa! bed catches fire. The deluge system is manually actuated. Iodine removal capability is depleted. Dose assessment projects exceeding thyroid PAG's beyond 5 miles.

12:30 13 MCC "K" is repaired Core Spray "A" injection vaht is opened and injection is maximized. Vessel level begins increasing.

13:00 14- Reactor pressure is equalized and the release terminates.

13:30 15 Recovery /re-entry discussions begin.

14:00 16 Exercise terminates.

Exercise Scenario Material Page 7-4 August 17. I993

7.2 Initial Conditions 7.2.1 End ofBusiness, August 16,1993  ;

The reactor is at 100% power, end of core life. A refueling outage is scheduled to begin in 7 days. Reactor coolant chemistry is in specification. Operators are scheduled to perform the operability surveillance on the "A" LPCI injection valve (MO-27B) this evening. All other operations are normal.

7.2.2 Start ofExercise, August 17,1993 i Initial conditions are established at 8:00 AM, August 17,1993 with the plant a at 100% power, End of Life. The operability surveillance conducted last night on the "B" LPCI injection valve (MO-27B) resulted in the motor operator burning itself up. The preliminary analysis indicates a potentially incorrect '

torque switch setting. The valve has been declared inoperable and replacement of the motor operator is scheduled to begin today. A refueling outage is -

scheduled to begin in 6 days.

All plant equipment is in normal configuration with the following exceptions: ,

The "B" side LPCI injection valve (MO-27B) is out of service for motor operator replacement. Valves tagged out for this repair include MO-25B, 27B, 66B and 12B. The valve operator has been removed to the maintenance shop where it is awaiting a new motor that is being shipped from the factory expected to arrive in the afternoon. Work is scheduled to be completed in 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />. This 7-day LCO has been in effect for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

RCIC is out of service for replacement of failed turbine governor vacuum pump seals which have caused steam leakage. MO-15 is tagged out along with the Gland Seal Pump. Work is scheduled to be completed tomorrow, Day 4 of 7 day LCO. .

CRD Pump "B" is out of service due to a cract in the minimum flow line.  :

Maintenance is investigating cause of crack.

A Westinghouse team is on-site for in-service vibration testing of the main turbine.

Refer to Section 7.4 of this manual for additional equipment malfunction and' repair information.

7.2 Initial Conditions (Continued) j

, i Exercise Scenario Material Page 7-5 AUGU5r 17.1993 \

- - . _ _ _ =e-

7.2 Initial Conditions (Continued)

Weather forecast for the morning of August 17,1993 (08:00 AM to 12:00 PM): Southwest winds are expected from 2 to 5 knots. There will be mostly clear conditions throughout the day due to a High pressure system that is located to the South. Temperature is currently 75 degrees F, relative humidity 63%, barometric pressure steady at 29.6 inches. For the afternoon ,

temperatures are expected to reach close to 90 degrees in the southern portion  :

of the state, near 85 in the northem regions with winds continuing out of the southwest through the early evening light and variable to 8 knots. This is the National Weather Service. Have a Good Day. This is a Drill" Refer to Section 10.1 of this manual for additional meteorological information.

Simulator set-up information: (To be inserted) i i

l 1

I 1

I 1

l l

Exercise Scer.ario Material Page 7-6 August 17,1993 l

- l

7.3 Sequence of Events Clock Event Time Time Event Description 0815 0015 A spent resin transfer line rupture occurs in the Sludge Decant Pump Room in the Reactor Building causing spent RWCU resin to leak out of the door.

Radiation monitors in the area register an increase of greater than 1000 times normal. The Transfer Pump is shut down after 5 minutes. SS dispatches HP and an operator to the scene who report that resin and water are running along l the floor and down the stairwell.

0830 0030 SS declares an ALERT due to " Loss of control of radioactive material resulting in area radiation exceeding 1000X normal or expected levels within the protected area. (EAL 1.2.1). Notifications are performed and TSC and OSC activate. .

0905 0105 MCC "K" develops a fault causing a loss of logic control power to RHR "A" valves, SLC "A" pump, Drywell coolers "A" and "C", REC pumps "A" and i "B". Electrical maintenance is dispatched to troubleshoot and repair. ,

Operators vent the Drywell to maintain pressure less than 1 psig.  ;

1015 0215 A packing leak develops from the outboard MSIV on main steam line "B". 1 Steam Tunnel temperatures increase.  ;

1020 0220 High Steam Tunnel temperatures cause a Group I isolation and scram. Main  !

steam line "B" inboard and outboard MSIVs fail to go fully closed.

Opemtors use turbine pressure set to reduce reactor pressure. Electricians fix the faulted breaker on MCC-K but on evacuating (due to the steam leak), they .  ;

leave the cubicle door open. i 1035 0235 The boot sealing the condensate suction line from the condenser fails  :

catastrophically. Condensate pumps cavitate and trip on overload. Feedpumps j trip on low suction pressure. Condenser vacuum is lost causing bypass valves j to go shut. HPCI is used to maintain vessel level. J l

1040 0240 HPCI trips on high flow due to a failed controller component in the Control Room. I&C investigates. Operators maximize CRD flow and start a SLC pump with demin water suction. Trip of Reactor Building condensate booster j

, pump results in a loss of ECCS pressure maintenance.

1045 0245 Emergency Director declares a SITE EMERGENCY due to Imss of Two

. Fission Product Barriers (EAL 2.3.3). MCC-K develops a short to ground due to steam entering the open breaker cabinet.  !

1 Exercise Scenario Material Page 7-7 A UGU5r17.1993 l

l l

l

7.3 Sequence of Events 1

Clock Event Time Time Event Description I

1050 0250 RWCU bottom head line break occurs in the drywell. A loss of coolant results in a rapid decrease in vessel level. Drywell pressure, temperature and l radiation levels increase rapidly. Safety systems auto actuate on high drywell pressure. Core Spray "B" pump trips on overcurrent caused by water hammer. The LPCI "A" injection valve fails to open due to loss of MCC- t "K".

I110 0310 ED declares a GENERAL EMERGENCY based on a Loss of Two Out of Three Fission Product Barriers with Potential Loss of the Third (EAL 2.4.1).

1115 0315 Vessel level decreases to top of active fuel and fuel cladding damage begins to occur. Operators emergency depressurize in accordance with EOP's. A ,

release occurs from the reactor vessel into the Steam Tunnel and Reactor ,

Building, through Standby Gas Treatment and out the ERP. This results in a radioactive plume moving off-site. Reactor Building radiation levels increase.  :

1130 0330 A fire starts in SGT Train "A" due to the high degree of iodine absorption.

The fire suppression deluge valve must be manually opened at the train. A  ;

significant reduction in iodine removal capability results. Dose assessment i performed assuming no iodine removal results in an estimate of thyroid dose j exceeding PAG's beyond 5 miles. PAR's are discussed with Missouri.

1230 0430 MCC *K" is repaired. LPCI "A" injection valve is opened and injection is i maximized. Vessel level begins to increase. Containment sprays are used to ,

reduce pressure. j 1300 0500 Reactor pressure is equalized, and the release terminates.

i 1330 0530 Exercise is secured. The exercise will be immediately followed by player critiques in panicipating facilities. Preliminary Controller / Evaluator meetings i are conducted. ]

l 1400 0600 Exercise documentation is gathered. Facilities are restored to normal i conditions. ,

1 l

l l

Exerche Scenario Material Page 7-8 August 17.1993 j r

j

OFFSITE RELEASE PATH 9

FIGURE 7.3-1 ,

i REACTOR BUILDING l

IL TURBINE BUILDING l  !

- 5

\i Mo I -d ,

-]

x- n%

s 4

) Y ERP l

% /

TIME ACTIVITY 1015 Main Steam Line Isolation Valve develops a steam leak causing a Group 1 isolation and a Reactor Scram, the inboard MSIV fails to close (1).

1050 The RWCU bottom head drain line breaks in the drywell (2), causing drywell I temperature, pressure and radiation levels to increase.

1115 Due to several ECCS failures reactor water level drops below Top of Active Fuel and clad damage (3) starts to increase the release of radiation to secondary containment through the stuck open MSIVs, and out the ERP by way of the Standby Gas Treat. ment system.

1130 A fire starts in the operating train of Standby Gas Treatment due to the high ,

degree ofiodine absorption. This releases large amounts of radioactive Iodine out the ERP and into the environment.(4).

t I

93 Exercise Page 7-9 August 17,1993 i

t

i Table 7.3-1: Downgrading From The Emergency .i Player should be cognizant of the following conditions in order to consider downgrading from the emergency and commencing reentry / recovery discussions:

i

1. All plant radiation levels are stable or decreasing.

2. ERP vent radiation monitor readings are zero. '

3. Emergency conditions no longer constitute a hazard to the station or station personnel.

4. Reactor is cooled down and depressurized.

5. All required notifications have been made.

6. TSC and EOF agree that downgrading is appropriate. ,

7. State and County Officials concur.

t i

i i

I i

Exercise Scenario Material Page 7-10 August 17,1993 a 1

-l i

4 7.4 Master Events Summary  :

i A summary of the master events is provided under this heading.

The summary consists of a description of all scenario messages that will be issued  !

to drive simulated events and includes anticipated emergency responses by participants.

Times indicated with a "+" are floating messages that will be issued on or after the indicated time. Times that floating messages are issued are dependent on  ;

completion of specific responses or actions of participants.

1 Messages with a "X" following the message number are contingency messages <

that will only be issued upon meeting the conditions listed in the controller note of the message.

.i Messages with a "S" following the message number are simulator contingency messages that will only be issued in the event the simulator is not available (e.g.,  ;

simulator computer failure which cannot be corrected in a timely manner),  !

.i i

'f i

i l

l l

Exercise scenano Material Page 7-11 August 17, 1953

~

COOPER NUCLEAR STATION 1993 EXERCISE MASTER EVENTS

SUMMARY

TIME MSG FR OM TO EVENT / MESSAGE

SUMMARY

CONTROLLER INSTRUCTIONS CM ANTICIPATED

.NO. RESPONSE 0730 CNS Cntrir CR Initial Cond% CONTROLLER INSTRUCTIONS: Soecial Guidelines

-1 (Sim)

Staff initial conditions are established at 8:00 Provide the following initial conditions to 1. All AM, August 17, 1993 with the plant at the participating Plant Operator h assigned communications outside 100% power, End of Life. The operability to today s drill. Ensure Players have name the Simulator must surveillance conducted last night on the *B" tags and a copy of the Drill Phone List. include the phrase *This LPCI injection valve (MO-278) resulted in Get all operations participants to sign the is a drill "

the motor operator burning itself up. The attendance sheet. Ensure that procedure

,,reliminary analysis indicates a potentially 6.3.11.1 is signed by the real Shift incorrect torque switch setting. He valve

~

Supervisor, and a Gai-tronics has been declared inoperable and announcement is made when the replacement of the motor operator is Simulator is cross-tied to the Plant Gai-scheduled to begin today. A refueling tronics system. Contact the Shift outage is scheduled to begin in 6 days. Supervisor at the real Control Room and tell him that the Drill is starting and to All plant equipment is in normal initiate Message No. CNS-2.

configuration with the following exceptions:

The *B* side LPCI injection valve (MO-278) is out of service for motor operator replacement. Valves tagged out for this repair include MO-25B, 27B, 66B and 12B.

Work is scheduled to be completed in 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />. This 7 day LCO has been in effect for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Afaster Ewnt Summary . 7-12 c:ws60t93EXWSTRDWT.wr3

COOPER NUCLEAR STATION 1993 EXERCISE MASTER EVENTS

SUMMARY

TIM E MSG FROM TO EVENT / MESSAGE

SUMMARY

CONTROLLER INSTRUCTIONS CM ANTICIPATED

.NO. RESPONSE RCIC is out of service for replacement of failed turbine govemor vacuum pump seats which hava caused steam leakage. M O-15 is tagged out along with the Gland Seal Pump. Work is scheduled to be completed tomorrow, Day 4 of 7 day LCO.

CRD Pump *B*is out of service due to a crack in the minimum flow line.

Maintenance is investigating cause of crack.

A Westinghouse team is on-site for in-service vibration testing of the main turbine.

Refer to Section 7.4 of this manual for additional equipment malfunction and repair information.

Current. temperature is 75 degrees F, relative humidity 63 %, barometric pressure steady at 29.6 inches. Winds out of the Southwest at 5 mph. No precipitation expected.

Master Ewnt Summary - 7-13 a:sssso193Exws1REYNT.WP5

COOPER NUCLEAR STATION 1993 EXERCISE MASTER EVENTS SUMMA.RY TIME MSO. FROM. TO EVENT / MESSAGE

SUMMARY

CONTROLLER INSTRUCTIONS CM ANTICIPATED RESPONSE -

NO.

0800 CNS- lead CR Make the following Gai-tronics announcement Contact the Shin Supervisor in the real control Start the drill.

2 Ex. Staff when directed by the lead Exercise Controller: room and inform him of the start of the 1993 Cntrir ' ATTENTION ALL PERSONNEL. Evaluated Exercise, then have the Control .

ATTENTION ALL PERSONNEL. TIIB 1993 Room Simulator Shift Supervisor make the i

EVALUATED EXERCISE IS COMMENCING. following Gai-tronics announcement.

ALL ANNOUNCEMENTS PROCEEDED BY WS IS A DRILL" ARE FOR PLAYERS ONLY IF AN ACTUAL EMERGENCY OCCURS, AN ANNOUNCEMENT WILL BE MADE THAT THE DRILL HAS BEEN SUSPENDED UNTIL FURTHER NOTICE.

ALL PERSONNEL ARE REQUESTED TO MINIMIZE TIIH USE OF THE GAI-TRONICS UNTIL THE EXERCISE HAS BEEN COMPLETED."

Master Ewnt Summary 7-14 c.w>60mixwsmnwr.wes

-w ww m. > -- , - - --_,n ,4 - - .

, - v ,r, , -- ,- w,-- , - w---- , c, w -, , , , , ,, .< - . .r-ws 1--- -,,. , my. -- -e--. v- w. . . . - . .,. --

COOPER NUCLEAR STATION 1993 EXERCISE MASTER EVENTS

SUMMARY

TIME MSO. FROht TO EVENT / MESSAGE

SUMMARY

CONTROLLER INSTRUCTIONS CM ANTICIPATED RESPONSE NO.

0815 CNS- Cntrir CR High radiatio t in the reactor building Deliver this message only if proper indication is CNS- The radwaste control room 3S (Sim) annunciates. not available from the Simulator. 5X operator is out taking logs, Staff ARM-5 is alarming, indicating 1000 m.R/hr. (0845) and will not be able to shut off the transfer pump until 0820. SS declare an ALERT per EAL 1.2.1

" Loss of control of radioactive material resulting in area radiation levels exceeding 1000x normal or expected levels within the protected area". TSC and OSC activate.

0815 CNS- Cntric RTat There is a stream of mixed resin and water The radwaste control room ope stor is out CNS-

4 4 Spill flowing out from under the door to the sludge taking logs, and will not be aMe te shut off the SX decant pump room toward the nearest floor transfer pump until 0820. Refer to (0845) drain. Nearby ARM's and CAM are alarming. Supplemental Scenario 1 for additional details.

Marrer Ewnt Summary 7-15 . c:w,6mnenv5DtEVNT.wr3

.-e m. - - . -r

COOPER NUCLEAR STATION 1993 EXERCISE MASTER EVENTS

SUMMARY

TIME MSG. FROM TO EVENT / MESSAGE

SUMMARY

CONTROLLER INSTRUCDONS CM ANTICIPATED RESPONSE NO.

0845 CNS- Lead CR Declare an ALERT per BAL 1.2.1

• Loss of Deliver this message only if the SS has failed to SS declare the alert.

5X Ex. (Sim) control of radioactive material resulting in area classify the situation by this time. Activate the TSC and OSC.

Cottir SS radiation levels exceeding 1000x normal or expected levels within the protected area *.

0905 CNS- Cntric CR MCC *K" feeder breaker indicates tripped. Deliver this message only if proper indication is Troubleshoot fault.

6S (Sim) Drywell temperature and pressure indicate 0.22 not available from the Simulator. Loss of Operators vent the drywell to .

Staff psig and i15'F and increasing slowly. MCC *K* causes loss of drywell coolers "A" keep pressure below I psig.

and "C*, REC pumps "A" and *B", SLC pump "A", and control power to "A* train RIIR valves. Refer to Supplesnental Scenario 2 for additional details.

0905 CNS- Cntrlr Operut Ground fault indicator flags are up on MCC *K* Deliver to operators performing preliminary Tag out the breaker, rack out 7 ors feeder breaker and on REC pump *A* breaker assessment of MCC *K" fault. Refer to and inspect.

investi (when checked). Breaker will trip if reset. Supplemental Scernrio 2 for additional gating details. Team should tag out the breaker and MCC- inform OSC. Repair must be completed at "K" 0 1.1]l[.

0930 CNS- Cntrir RT Refer to Suppicsnental Scenario 2 for ne problem must be corrected by 1015, but the 8 at additional details. breaker must be left in the racked-out position MCC- so that the steam leak will cause a short in the

• K" MCC. -

Master Event Summary 7-16 ~ c:w,60uutxwsnEVNT.WP3

COOPER NUCLitAR STATION 1993 EXERCISE MASTER EVENTS

SUMMARY

l TlM E MSG FR OM TO EVENT / MESSAGE

SUMMARY

CONTROLLER INSTRUCTIONS CM ANTIC 1 PATED

.NO. RESPONSE 1015 CNS Cntrir CR Tunnel Area (W 906') Area Temperature Deliver this message only if proper Investigate cause of -

-9S (Sim) liigh Alarm Steam Tunnel Temperatures indication is not available from the rising temperatures.

Staff indicate 180 degrees. simulator. Steam leak has started from Attempt to maximize outboard MSIV on steam line "B". cooling.

1020 CNS Cntrlr RT You have completed repairs to TBD fault Players must evacuate and leave Evacuate the area, notify >

-10 at on MCC "K*. He breaker is still racked breaker (s) racked-out on MCC *K". If the control room.

MCC out. You notice a flow of steam coming players try to rack the breakers back in

-*K" from the edges of the door to the steam prior to leaving, stress best and difficulty tunnel. The flow of steam is increasing. breathing. Do not allow the players to it is getting very hot in the area of MCC rack the breakers in. Steam entering the

• K". open cabinet will later cause a short to ground in MCC *K". Refer to Supplemental Scenario 3 for additional information on the steam leak.

Afarter Ewnr Summary 1-1/ a:w660mEnusDtEYNT.WH

COOPER NUCLEAR STATION 1993 EXERCISE MASTER EVENTS

SUMMARY

TIME MSG. FROM TO EVENT / MESSAGE SUMM ARY CONTROLLER INSTRUCTIONS CM ANTICIPATED RESPONSE NO.

1020 CNS- Cntrir CR Alarms in Control Room Deliver this message only if proper indication is CNS- Operators recognize and take 1IS (Sim) Steam Tunnel Temperature High not available from the simulator. Refer to 15X action for reactor trip.

Staff Steam 'Ibnnel High Temp Chan A2 Trip Supplernental Scenario 4 for additional (1045) Operators use turbine Steam Tunnel High Ternp Chan Al Trip infonnation on the failure to isolate "B" Main pressure set to reduce reactor Steam Tunnel High Temp Chan B1 Trip Steam Line. pressure. Operators attempt Steam Tunnel High Temp Chan B2 Trip without success to cycle AO-MSIV Not Full Open Trip A2 808 and/or AO-86B to shut MSIV Not Full Open Trip B1 them. Emergency Director Reactor Scram (Auto) Chan A2 Trip declares a SITE AREA Reactor Scram (Auto) Chan B1 Trip EMERGENCY per EAL -

Group 1 Isolation Channel A2 Trip 2.3.3, " Loss of any TWO Group 1 Isolation Channel Al Trip fission product barriers Group 1 Isolation Channel B1 Trip (Primary Coolant Boundary Group 1 Isolation Channel B2 Trip and Primary Containment).

Indications in Control Room AO-80B and AO-86B red and green indicating lights are illummated.

Main steamline "B" flow indicator indicates

- ~200,000 lb/hr of flow.

Marter Ewnt Summary 7.jg g.m,g,yggyyy,7,

COOPER NUCLEAR STATION 1993 EXERCISE MASTER EVENTS

SUMMARY

. TIME MSO. FROM TO EVENT / MESSAGE

SUMMARY

CONTROLLER INSTRUCTIONS CM ANTICIPATED RESPONSF NO.

1035 CNS- Cntrlr CR Alarms in Control R J22m Deliver this message only if pmper indication is Operators use IIPCI te 12S (Sim) TG low Vacuum Pre-Trip not available from the simulater. Condensate contml vessel level.

Staff TG Exhaust flood A Spray On suction line boot seal at the condenser has failed TU Exhaust flood B Spray On catastrophically. Feed and condensate are lost.

TG Exhaust Hood A Temp > 175 *F Refer to Supplemental Scenario No. 5 for TO Exhaust flood P Temp > 17S *F additional information.

TG Low Vacuum Trip 1T) Exhaust liood A Temp > 250 *F TG Exhaust Hood B Temp > 250 *F Condensate Pump A Trip Condensate Pump A Overload or Ground RFP A Suction Pressure Low RFP B Suction Pressure Low RFP Turbine A Trip RFP Turbine B Trip Condenser Air Removel Temp fligh Condenser Air Removal Isolation litrbine Building Q Sump Level Hi-Hi Master Ewn Summary 7-19 c:wuot93exwsnumvr.wn

COOPER NUCLEAR STATION 1093 EXERCISE MASTER EVENTS SU5BfARY TIME MSG. FROM TO EVENT / MESSAGE

SUMMARY

CONTROLLER INSTRUCTIONS CM ANYICIPATED RESPONSE NO.

1040 CNS- Cntrir CR Alarms in Control Room Deliver this message only if proper indication is 19X Operators maximize CRD 13S (Sim) IIPCIImgic Actuated not available from the simulator. IIPCI Pump (11101 flow and start a SLC pump Staff HPCI Isolation Channel A Trip tripped on failure of logic module in Control To with demin water suction.

HPCI Turbine Tripped Room. Refer to Supplemental Scenario 6 for ensure ED should declare a IIPCI Pump low Flow details. This repair must not be completed GEis GENERAL EMERGENCY before 1240. less of IIPCI is a threat to the declar per EAL 2.4.1.

clad barrier, ed.

1040 CNS- Cnttir CR Alarms in Control Room Deliver this message only if proper indication is Operators may elect to 14S (Sim) Condensate Booster Pump A Trip not available from the simulator. Trip of manually start the RilR and Staff Reactor Building condensate booster pump Core Sptsy Pumps to results in a loss of ECCS pressure maintenance. maintain pressure. The Refer to Supplemental Scenario 7 for details. Control Room should notify the TSC and the OSC should dispatch a team to investigate.

1045 CNS- TSC ED Declare a SITH AREA EMERGENCY per Deliver this message only if the Emergency ED Declare the SAE.

15X Lead EAL 2.3.3, " Loss of any TWO fission product Director has failed to properly classify the loss Activate the EOF is not Cntrir barriers (Primary Coolant Boundary and Primary of two fission product barriers at 1020. A already done.

Containment). SITE AREA EMERGENCY must be declared at this time to keep the Exercise sequence of events on schedule.

bfaster Ewn: Summary 7-20 c:tcuot93cn%STREYNT.wr3

COOPER NUCLEAR STATION 1993 EXERCISE MASTER EVENTS SUMMA.RY TIME MSG. FROM TO EVENT / MESSAGE

SUMMARY

CONTROLLER INSTRUCTIONS CM ANTICIPATED RESPONSE NO.

1045 CNS- Cnttir CR Annunciators in Control Room Deliver this message only if proper indication is OSC Investigate the trip.

165 (Sim) RHR Pump Room (SW) FCU H REC Flow low not available from the Simulator. MCC *K*is Staff RHR B HX Tube to Shell DP Low lost again due to condensation from steam entering the open breaker cabinet. Refer to Indications in Control Room Supplemental Scenario 8 for additional MCC *K" feeder breaker indicates tripped. details.

Drywell Pressure indicates 0.1 psig.

Drywell temperature indicates 144 "F.

Master Ewns Summary 7 21 a:watp3ExwsTREYNT.WP3

,v~ ,_.,, . , , - . - - . . , . ~ - - - - , . - . _ ,, ,.,., , . . - - . .-_..-~--,.y---. -,-- ,, ,.,. _ . - , . . .~, , . . . , . . . . - - , , , . - , ,

COOPER NUCLEAR STATION 1993 EXERCISE '

AfASTER EVENTS SUhthfARY TIM E MSG FR OM TO EVENT / MESSAGE

SUMMARY

CONTROLLER INSTRUCTIONS CM ANTICIPATED

.NO. RESPONSE 1050 CNS Cntrir CR Annunciators in Control Room Deliver this message only if proper OSC Investigste the trip.

-17S (Sim) Drywell Pressure Iligh indication is not available from the Operators ucs CRD and gg,rr Drywen zone 1 PCmt-502 Temp liigh Drywett Fen Coil Unit D Discharge Temp lii Simulator. RWCU bottom head line break SLC for vessel makeup.

Drywett Fan Coil Unit B Discharge Temp liigh occurs in the drywell. CS *B" tripped on Drywell Zone i PC.TR-503 Temp liigh overcurrent due to water hammer. CS

• A*

Drywell fligh Pressure Alarm (PC-PS-101C) train valves fail to open due to loss of Drywell High Pressure Alarm (PC-PS-10l A) MCC *K*. Refer to Supplemental Drywell fligh Pressure Alarm (PC-PS-101B)

Drywell fligh Pressure Alarm (PC-PS-101D)

Scenario 9 for additional details.

RIIR Pung *A*Iegic Actuated RllR Pump *D'Iogic Actuated Core Sprey Pump *B" Trip DryweII Equipment Sump G lii-lii Level DryweII Equipment Sump G Temp liigh i Indications in Contret Rtem

• Core Sprey Pump *B* indicates tripped.

Drywett Pressure Irafiesten 2 psig and increasing.

Drywell temper =ture indicates 144 *F and increasing rspidly.

Reactor water levelIndientes 34.6*end dmrping.

1055 CNS Cntrir RT at The pump motor breaker overcurrent flag Refer to Supplemental Scenario 10 for Nutify the OSC. Set a 18 CS is visible. additional information. Iow priority for this Pump repair, since it will be a

• B* long-term job.

Afaster Ewnt Summary 7-22 a: wots 3txwsyFEVbT.w?$

._____m __ __ __m w- - --- - - m

-__ m, ip- ,- w y- <*wt= +r--+*w-'M e pen-~- w e v -- g a t-gas- wN-N- ---

• -v-" -- w 7 -+y sy,9ww4 _ _r+ w ,-p u,y-g .w ,== ..-e-- .v

COOPER NUCLEAR STATION 1993 EXERCISE htASTER EVENTS SUhthfARY TIME MSG. FROM TO EVENT / MESSAGE

SUMMARY

CONTROLLER INSTRUCTIONS CM ANTICIPATED RESPONSE NO.

1055 CNS- Cntrir RT at "Ihe pump motor breaker overcurrent flag is Refer to Supplemental Scenario 10 for Notify the OSC. Set a low 18 CS visible. additional infortnation. priority for this repair, since Pump it will be a long-term job.

.B*

1110 CNS- TSC ED Declare a GENERAL EMERGENCY per EAL Deliver this message only if the Emergency ED Declare the GE.

19X Lead 2.4.1, %ss of TWO of THREE fission Product Director has failed to properly classify the loss Cntrir Barriers and Potential Exists for Less of the of HPCI, with two barriers already lost, as a THIRD. threat to the clad barrier. A GENERAL EMERGENCY must be declared at this time to keep the Exercise sequence of events on schedule.

Afaster Ewns Swnmary 7-23 G:16660tHEEVSDtEYNT.WP3

COOPER NUCLEAR STATION 1993 EXERCISE MASTER EVENTS SUMMAR1 TIM E MSG FR OM TO EVENT / MESSAGE

SUMMARY

CONTROLLER INSTRUCTIONS CM ANTICIPATED

. N O.

RESPONSE

1115 CNS Cntrir CR Indications _ in Control Room Vessel level has reached the top of active Operators depressurize

-20S (Sim) Reactor vessel level indicates +74on fuel fuel . Clad ' damage begins to occur, the plant per EOPs.

Staff zone monitors. Operators emergency depressurize the Reactor Building ARMS are increasing. plant per the EOPs. A release of gap damage starts from the steam tunnel, through SGTS and the ERP off-site.

I130 CNS Cntr!r CR Indications in Control Room Deliver this message only if proper Operators open SGTS

-21S (Sim) Fire alarm indicat;on is not available from the deluge valve to Staff Simulator. He *B' SGT charcoal bed extinguish the fire.

auto-ignites due to excess heat loading Perform damage from decay of absorbed fission products. assessment. Dose ne ability of the charcoal to absorb assessment staff revise fission products is significantly reduced. projections to reflect Dose projections off-site should reflect lower absorption of this. Evacuation of Rock Port is an fission pnxlucts.

objective. See Supplemental Scenario 11 for additional details.

'1230 CNS Cntrir Repai Repairs are complete to MCC *K*. Refer to Supplemental Scenario 8 for operaton neton the Mcc.open

-22 r additional information. CS *A"tnin vWes and rnuimin Team iniection flow Vesael level at recovers and Core Spray is operated es required to reduce

, , rn***.

Master Event Summary 7-24 C:1666019]EXW51REVNT.WP3

. ___ _. __ _ - . _ _ ~ _ _ _ _ . _

COOPER NUCLEAR STATION 1993 EXERCISE 5 FASTER EVENTS

SUMMARY

TIM E MSG FR OM TO EVENT / MESSAGE

SUMMARY

CONTROLLER INSTRUCTIONS CM ANTICIPATED

.NO. RESPONSE required to reduce pressure.

1300 CNS Cntrir CR Indications in Control Room Deliver this message only if proper Players conduct

-23S (Sim) Reactor Pressure indicates ~ 18psig and indication is not available from the downgrade-Staff decreasing. simulator. Drywell and reactor pressures declassification Drywell Pressure indicates ~ 18psig and are equalized and decreasing as LPCI and discussions.

decreasing. Core Spray cool the core. With the loss of driving head, the release is terminated.

1300 CNS EOF Emer For demonstration purposes 'of the If declassification discussions have

-24X lead gency Exercise, begin declassification discussions already been initiated, do not issue this Cntr!r Direc / down-grading procedures at this time. message.

tor Players should be cognizant of the following conditions in order to use the following criteria in downgrading and commencing reentry / recovery discussions:

1. All plara radiation levels are stable or decreasing 2.ERP vent radiation men'nor readings are zero

3. Emergency conditions no longer concitute a hazard to e

the station or station personnel.

4. Reactor is cooled down and depressurized

5. All required notifications have been made.

6.TSC and EOF ogree that downgrading is appropriate.

7. State and County Officials concur.

Sfarter Ewns Summary 7-25 c:166Ect93ExwmEYNT.WP.

COOPER NUCLEAR STATION 1993 EXERCISE MASTER EVENTS

SUMMARY

TIME MSG. FROM TO EVENT / MESSAGE

SUMMARY

CONTROLLER INSTRUCTIONS CM ANTICIPATED RESPONSE NO.

1300 CNS. 12nd Fac. Simulator. TSC. OSC and EOF Terminate drill play and notify all station 25 Facility Mgrs. personnel through use of message CNS-26.

Cntrirs Tenninate drill play, notify players located Conduct facility critique sessions and ensure all outside of the facility to return. Conduct a short player comments are documented.

critique of the drill. When the critique is over, perform the following:

1. Gather all facility logs and report forms and leave them at your station

2. All radiological equipment should be returned to storage locations, batteries removed as applicable, and properly retumed to storage.

3. Chairs, tables and other miscellaneous equipment used during the Drill should be returned to their original location.

1300 CNS- Lead CR Make the following Gai-tronics announcement Contact the Shift Supervisor at the real control 26 Ex. Staff when directed by the lead drill controller: room and inform him of the completion of the

, Cntrlr Drill and to make the following Gai-Tronics

" ATTENTION ALL PERSONNEL announcement.

ATTENTION ALL PERSONNEL EXERCISE PLAY HAS ENDED.

" ATTENTION ALL PERSONNEL.

l l

Afaster Ewnt Summary 7-26 a:ws60t93ExwsnrEVNT.WP3

-___._m__ __ --_.2___.____.___m,m__ m m __u___._-________m s _.s _,w ., .y , , , . .c , ,%, , - , -

..y,..g, . . = - .,.,giy g 9 y g

3 _

E r S w _

N T. -

O N V

P E S t E D R S D W x

E s T 3 9

A t o

P -

I C w :

I T a N

A -

M C

S N _

O I

T E C S

I U _

C R .

R T S -

E XY N I

ER R 3A E 9M 9

L L

1 M O NU R OS T I ..

T S N 7 AT O 2 T

SEN C 7- .

R V A E E ER S .

LE I A

CT C R

US T NA E N RM X E E -

E M P

O Y L U ".

Y R E C T .

O A N OI C DL M N I M O DC U S R NA F -

S E A -

E T R G PD CU A LE UO S LD DY S AN NN E NE OI M OS CE Tl A I

E U

/

T Nl SQ N eY AT I

E t A EI V iL LR .

E AP PC .

O T

y M r O a .

R m F m u

. S G . t n

SO w MN E .

r E t e -

s M a I

T M .

7.5 Supplemental Scenario Information This section contains supplemental information to detail key events that occur in the Exercise. They include:

1. Spent resin transfer line rupture in the Decant Pump Room.

2. Ground fault on 480V MCC "K"

3. Packing leak on main steam line "B" outboard MSIV.

4. Main steam line "B" MSIV's failure to close on Group I isolation.

5. Condensate suction line boot failure. .

6. HPCI controller component failure. .

7. Loss of ECCS pressure maintenance.

8. MCC "K" Short to ground ,

9. RWCU bottom head drain line break.

10. Core Spray "B" Pump trip on water hammer.

I 1. LPCIInjection Valve MO-25A failure

12. Core Spray Injection Valve MO-12A Failure .

13. SGT Train "B" charcoal bed fire.

1 Each section of supplemental information contains the following elements:

• Approximate time (s)

• Imcation(s)

• Initiating condition (s)

• Controller notes

• Expected Player actions

• Completion / restoration guidelines It is designed to be provided to the repair personnel who are dispatched from the Technical Support Center / Operations Support Center during the course of the Exercise. Equipment data only is provided in this section. For radiation levels -

that personnel may encounter during repair activities, Controllers must refer to Sections 9.3 or 10.3 of this manual.

CAUTION: Drill tags are to be hung at the Simulator only. No drill tags are to be displayed or placed on any components in the plant!

Exerciu scenario Material Page 7-28 August 17.1993 4

i SUPPLEMENTAL SCENARIO NO.1 SPENT RESIN TRANSFER LINE RUPTURE  :

Annroximate Time: 0815 (00/15) Location: RB 947 El.

Descrintion:

As part of the initial conditions at 0800, it is assumed that:

• Tmnsfer of spent RWCU resin is taking place under the control of the Radwaste  ;

Control Room.

Player Information:

In the Simulator: Operators will have indication and an alarm indicating high Reactor Building radiation levels.

Upon Investication: For players involved with the in-plant investigation, the following indications must be provided:

The Radwaste Control Room Operator is out taking his logs and is not able to shut off  ;

the transfer pump until 0820.  ;

From 0815 to 0825 ,

" THIS IS A DRILL. THERE IS A STREAM OF MIXED RESIN AND WATER FLOWING OUT FROM UNDER THE DOOR TO THE SLUDGE DECANT PUMP ROOM TOWARD THE NEAREST FLOOR DRAIN. NEARBY ARM'S AND CAM ARE ALARMING. THIS IS A DRILL".

Controller Instructions:

The first Operator at the scene should notify the Control Room of these observations.

HP should initiate a survey of the area to determine dose rates. Refer to attached Figure RESPIL-1 for survey results. Once the Players understand the above, they should be observed informing the Control Room of the conditions and discussing the need to perform emergency containment, followed by repairs and cleanup. If the decision is made to perform these actions, allow HP and Maintenance to go through the steps it would take to perform the work.

i Exercise Scenario Material Page 7-29 - Aucusr17.jpp3

SUPPLEMENTAL SCENARIO NO.1 FIGURE RESPIL-1: Resin Soill Location & Dose Rates -

14 CATION: RX F31 nou l l l

+o g

^ DDD0 e

• O I I B

+o 1 i F

h9 / [

i De \( c C_

. \.

s .

rTarms l e

o lrh -0 OO  ! l

==

C SPILL AREA 2"fi;l. C""3 "9/.m oa

1. DOCE MATT INFORM ATION I GENERAL TIME mRow UNLESS NOTED I

( F NOTE S HR$ A B C 0 i 1 1 1 800 1 1 3 1000 850 130 esem opdf 816 8 13 200 '

13 200 1000 850 130 900 8 11 1s 200 1000 850 130 1116 la 200 1000 850 130 1200 11 14 200 1000 850 130 1400 11

2. A!RSORNE CONCENTRAT10NG AND CONTAMINATION 1.EVELS P ARTIC. CO*(T AM1N ATION GENfRAL TIME GAS tODINE LfVELS IN CPM NOTES HRS oC#ce vCuce uCuee 800 Ae Reed As Reed As Reed As Reed 815 Ae Reed As Reed As Reed 1.00E + 06 As Reed As Rosa As Reed 1.00E + 06 000 1115 As Reed As Reed As Reed 1.00f + 06 1.00E + 06

)

1200 As Reed As Reed As Reed A Reed As Reed As Reed 1.OOE + 06 1400 MWe Scenario Mataial Page 7 30 ,ygg,7 ,7,,,,,

b SUPPLEMENTAL SCENARIO NO. 2 MCC "K" GROUND FAULT ,

Approximate Time: 6905 (01/05) Location: RB 903 El. ,

Descrintion:

MCC "K" develops a ground fault in the REC "A" Pump supply breaker which causes the MCC feeder breaker to trip.

Player Information:

In the Simulator: Operators observe loss of loads powered by the MCC including Drywell Coolers "A" & "C", REC Pumps "A" & "B", control power to RHR "A" loop valves and SLC Pump "A", SGT "A" Fan and heaters, and feed to MCC-Q, MCC-R, and MCC-RA. The simulator provides indication ofincreasing drywell temperature and pressure on loss of coolers. Following repair of the fault at 1015, Operators observe ,

restoration of these loads.

Upon investication: The investigating in-plant team finds the breakers "1A" and "3C"  :

tripped and will not reset. The team should inform the OSC, and tag out the breakers l to investigate. Upon racking out the breaker, the team finds evidence of the following:

REC "A" breaker "3C" inspection reveals that the wiring inside the cubicle had started to break down and was oozing a liquid substance from the wires that connect the associated MCC electrical breaker to its forward and reverse contactors and was hardening on the contactors, causing them to ground out to the frame.

MCC-K feeder breaker "1 A" inspection reveals that the gap between the contacts is out of specification and caused the contacts to overheat causing an overcurrent trip. The overcurrent tripping device has sustained damage, it is blackened and discolored, and needs to be replaced.

Controller Instructions:

1. Ensure the team goes through the actual tag-out procedure as necessary.

2. The feeder breaker to MCC-K is the important breaker to concentrate the repair team efforts to repair. Time to repair the feeder breaker is 30 minutes. Repair must be complete at 1015 (02/15). l l

Exercise Scenario Materia! Page 7-31 Aucusr17,1pp3

SUPPLEMENTAL SCENARIO NO. 2 (cont)

FIGURE MCC *K"-1: Overcurrent Trippine Device P

,uw amt .

08-50 OROM BREAKER icoo wwers. cm en 4-c

/" -

gj i l l j g l '. @g

[: .

s  ! ,

{i , i ?

' f Q .

f sT Tower

- um  ;

n / wa,a 7# N l ,, ,  ?

gj. g%mD y*cSd s 838 jNo. M 1i C

~

F

[ .

g/ g/Ara P-

m. , g p\ '

r -

gg ,7,,.

D -f); @p

..3 O ,, m> sv9

.3 ,_m h, .

C g) r,.

&j .

f "m*

m r \

.L . .

E , ww

% N ] g

(* Fez M: IR *"

A \ s'1 C

, ,\.^d 14 / ,

c 1tatnsno w

y / \

~

s,s COL

\ \

AM\\ Ph%1

.s

{ ,m" cot pc _ 3 C3 pw w,ac s&9

-ove m unncur P oo D"'a = =

. s

~

_D M-CLOSED TRePCO OPCN(RCSCTI I

)

Exercise Scenario Material Page 7-32 Avausr17 im I

I I

1 1

t SUPPLEMENTAL SCENARIO NO. 2 (cont)

FIGURE MCC "K"-2: Decradation of Wiring ,

1 i

DELECmpC I anaccesstoot -

CABLE USED 9595 '

(G E Q

pg

~

im m N} D h{' ~

j l -

M POWER u sse vic l

__ w A Ol' f . CM L3 l

. niec BilEAKERE t R ::a 2.=a

/ ==fr::P ==P : \ ,

(OR M contracmna  !

~

.l I

i 7

I TT oT2 i i1 pe

- . . - amam i > a em m 5 . - a = eses mmm n.eoc.t

. - . . =sw.

?

. 5

- .- -m. - - . . - - , . . - . . - t 3 11 0 T2 . pT1 . Ol#Telns asce a '

y .

'6 I, M e j meOfeltPChA l i

b

{

I I

Exercise Scenario Material Page 7-33 August 17,1993  ?

?

i 1

a

SUPPLEMENTAL SCENARIO NO. 3 "B" OUTBOARD MSIV PACKING LEAK  ;

Annroximate Time: 1015 (02/15) Location: Steam Tunnel Descrintion:

The "B" main steamline outboard MSIV (AO-86B) develops a leak in its packing causing .

release of steam to the Steam Tunnel (see attached Figure MSPACK-1). The packing blows entirely out when the Group I isolation occurs. ,

Player Information:

In the Simulator: Operators observe increasing Steam Tunnel temperatures. High temperatures result in a Group I isolation in approximately 5 minutes. Operators should '

attempt to maximize Steam Tunnel cooling.

Upon Investigation: An in-plant team dispatched between 1020 and 1245 to investigate the high Steam Tunnel temperatures observe steam seeping out from the cracks around the door to the Steam Tunnel. The door is very hot to the touch and causes burns to the skin within 10 seconds.

I Controller Instructions:

1. Players will not be allowed to enter the Steam Tunnel due to the steam and high radioactivity condition.  :

2. This is a long-term repair. The plant must be shut down and cooled down before -

investigation and repair can occur.

i l

t l

I l

Exercise Scenario Material Page 7-34 August 17.1993 j

I SUPPLEMENTAL SCENARIO NO. 3 (cont)

FIGURE MSPACK-1: MSIV Packine Arrancement I

i MSIV PACKING App phCKING GLAND d$l

,8, rE ,

s?k l

c f

\ l a

N f/// - y,s, I '

I I' P

l

\ ,

A 4

j l

l l

I

'N! Scenario ya,,,.;,, PaCr 7-35 AucusT17,jmy I

SUPPLEMENTAL SCENARIO NO. 4 "B" MSIV'S FAILURE TO FULLY ISOLATE Annroximate Time: 1020 (02/20) Location: Steam Tunnel i Descrintion:

On a Group I isolation occurring as a result of high Steam Tunnel temperatures, both the inboard and outboard "B" main steamline MSIV's (AO-80B, A0-86B) fail to go completely closed. Cause of the failure to close of AO-80B, inboard MSIV, is failure of the ASCO solenoid valves. The core and plug have bonded together and they will not open to bleed off Nitrogen pressure and allow the MSIV to close. The outboard MSIV AO-86B has undergone mechanical binding of the closure springs against the spring guide shafts. (see attached Figure MSIV-1).

Player Information:

In the Simulator: Operators observe that both green and red indicating lights are lit on Panel 9-4 for AO-80B and AO-86B. Main steamline "B" flow indicator indicates  ;

approximately 200,000 lb/hr of flow. Attempts to cycle the valves open and closed have no affect on the indication. ,

Upon Investication: An in-plant team dispatched between 1030 and 1245 to investigate the MSIV's observe steam seeping out from the cracks around the door to the Steam Tunnel. The door is very hot to the touch and causes burns to the skin within 10 seconds.

Controller Instructions: ]

1. Any attempts to cycle the valves electrically from outside the Steam Tunnel are )

unsuccessful.

2. Players will not be allowed to enter the Steam Tunnel due to the steam and high i radioactivity condition.

3. This is a long-term repair. The plant must be shut down and cooled down before investigation and repair can occur.  ;

l i

I l

i Exercise Scenario Material Page 7-36 A UGUST17,1993

i i

i SUPPLEh1 ENTAL SCENARIO NO. 4 (cont) l FIGURE MSIV-1: MSIV Failure Mechanism l I

j I I i I i . i 19 J .=)

--l!i !l 1 4

l i i I *

• l' l' h l

j

)l p 34 SPRING GUIDE a }l' lii l 4 HEllCAL SPRINGS l 0 t b 4 SPRING SEAT 4 SPRING GUIDE SHAFT I G U' i , 39

' I

- g h

• x

_ g 1

MAIN STEAM ISOLATION VALVE Exerci.se Scenario Material Page 7-37 Aucusr17,1993

I l

l SUPPLEMENTAL SCENARIO NO. 5 CONDENSATE SUCTION BOOT FAILURE ]

Annroximate Time: 1035 (02/35) Location: TB Basement Descrintion:

The condensate suction boot develops a catastrophic tear causing a loss of condenser  ;

inventory and subsequent cavitation of the Condensate Pumps.  ;

Player Information: ,

?

In the Simulator: Operators observe indications of Condensate Pump cavitation (fluctuating amps, flow) caused by loss of NPSH. Pumps subsequently trip on high 1 current. Feed pumps trip on loss of suction pressure. Condenser level decreases rapidly along with condenser vacuum. Bypass valves go shut on loss of vacuum.

Upon Investigation: The sound of rushing water (i.e. waterfall) will be evident in the TB from 1035 to 1100. In-plant investigating team observes approximately 2-5 inches of -

water on the TB Basement Floor. On arriving at the suction boot area, a gaping tear is i evident in the suction boot with water flowing out of it (see attached Figure BOOT-1).

Controller Instructions: l

1. This is a long term repair requiring several days to complete.

2. Players should take precautions for electrical hazards when entering the flooded TB Basement.

f t

Exercise Scenario Material Page 7-38 AUGUST 17,1993

SUPPLEMENTAL SCENARIO NO. 5 (cont)

FIGURE BOOT-h Damaced Condensate Suction Boot Db C C M ENSATE CONDENSER

~

, CONDENSER { GLAND STEAW ,

A FCV-1 1-A 1*B "

1 r1. - - . . .) .

l ,

-lNTER COND

' BJAE.t-A AFTER COND 3 C TT iT T o INTER COND M

, MJAE;1-.8 AF T E R 'COM O

~

t-a b g.C CONDI AS ATX, PMMPS CONDENSATE Exercise Scenario Afaterial Page 7-39 AVGUST17,1993

SUPPLEMENTAL SCENARIO NO. 6 HPCI CONTROLLER FAULT Approximate Time: 1040 (02/40) Location: ControlRoom Descrintion; HPCI trips on high flow due to a failed flow controller in the Control Room.

Player Information; In the Simulator: Operators observe alarms and indications of the HPCI trip. The TSC is notified and an I&C team dispatched. Upon investigation, the I&C team determines that the HPCI controller has a bad flow controller (see attached Figure HPCI-1). Time to replace the component is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. A replacement of the entire controller is not' possible as a spare is not available on site.

Controller Instructions:

1. Provide information only after the players investigate the controller components.

They find the following problem, the flow controller is putting out too high a reference voltage causing the low signal selector to send that signal to the speed reference section of th EG-M control box. Normally upon HPCI initiation the governor controls turbine speed by providing positioning signals to the control valves. The governor is actuated in response to signals recieved from the HPCI system flow controller and speed signal feed back. When a start signalis recieved the flow controller generates a ramp signal. As soon as ramp voltage is greater than flow controller reference voltage, the low signal selector will sense flow controller output signal as the lowest signal and will pass the signal to the speed reference section of the EG-M control box automatically transferring speed control to the flow controller. However the flow controller is sending out a higher than normal reference voltage which causes the HPCI turbine to overspeed and trip.

2. This repair must not be completed before 1100, that is when the vessel depressurizes and HPCI is no longer effective.

Exercise Scenario Material Page 7-40 AUGustn.1993

~l h

SUPPLEMENTAL SCENARIO NO. 6 ~ q FIGURE HPCI-1: Failed HPCI Controller Comnonent j 4

i

'l SAMP ClutnAfDElstGMAL CMvl81DE FDuth Sut9LT 9hM CC-N hat s =ri c usis. ,.,o i

" fDE AC-af posta JuPPLT r

,, 4 I SurtLV es 90.*T3 segggg ggg

. af mas SIChAL cMytsTDs i & {

Rf A3 Spit 0 SETTlhG 70 TENT 14ETER I IIAIIbIIII LOW I SPIED I N*

• j r- sNS$7

==> u 1 [

1. acto. .i, .

~

RMP CPN(BATOS

} g' l

l y r

+ 1 i i

PIDN CNT70ltis ML OR flutmLS 3 4 4 1' k- i SEFFDA OrtaATED sur ClaQitT SPEE8 _

4 mrLIFita i

+

sum usa 5dLif-OFF WALV2 cuiuscTsous to INITlATIQM CGNTACTS secTiew WAC 70 WDC "

acT M

. GAIN 4* -

l ST OTnE.18 0F &Derta Liutt it ti stae41MG POINT ADJUSTABLE i SutTQi ) j WA m A . i

(. -

i

's/-

• 'I FLOW TRAM 3NITTRA Ott W11Am i VE18EL Tuallut STOP VALyt ear l -sucT 7 p_ f 1- - , -  !

.O 900515a ,L P_ ,

e.AA, '

• H u.r.C. #

h b E

%(f'

g I -

,,,, - 7 e ricos, .!

4

_l - ll l

. Tvasine mtT cortama nLvts W//////m

" I as nem

-t i

g L-____ ____ ___________ ,3. ui m u.ucT.mTuassue esive.

8 csAa p.ra To :)

vic.

Tu..., m .o. = ,,,,,;. j 3

I 1

1

~.

i 1

l Exercise Scenario Material Page 7-41 Avaust17,1993 i

i SUPPLEMENTAL SCENARIO NO. 7 LOSS OF ECCS PRESSURE MAINTENANCE &

l Annroximate Time: 1040 (02/40) Location: ControlRoom Descrintion: l The R.cactor Building Condensate Booster Pump motor winding develops a short resulting  !

in a trip of the motor power supply breaker and loss of pressure maintenance in the ECCS injection lines.

Player Information: j In the Sim4}algt: Operators may observe the indicating light for the RB Condensate Booster Pump change from red to green (not running condition). Within a few minutes, l I

the ECCS discharge low pressure alarms will annunciate in the Control Room resulting in a potential water hammer condition if the pumps start. Operators may elect to manually start the RHR and Core Spray Pumps to maintain pressure. The Control Room should notify the TSC and the OSC should dispatch a team to investigate.  ;

At the Pump: The RB Condensate Booster Pump motor casing is hot to the touch and the -

smell of overheated pump motor internals is evident. If the team meggers the motor  ;

winding the resistance is determined to be (TBD) ohms which indicates a short to ground .

situation. Time to replace the motor is 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> minimum. The team finds the thermal  !

relay at the pump motor breaker tripped. Refer to attached Figure PRSMNT-1 for a  !

drawing of the RB Condensate Booster Pump. l Controller Instructions: ,

i

1. This will become a low priority repair after 1050 (when ECCS auto initiates). -

i

2. Ensure players conduct the required inspection / investigation before providing information on the results.  !

l Exercise Scenario Material Page 7-42 A vo ust17.1993

?

SUPPLEMENTAL SCENARIO NO. 7 (cont) ,

FIGURE PRSMNT-1

-i REACTOR BUILDING CONDENSATE BOOSTER PUMP e i

t r

/ \ r- ' ~

r

.=. 1 1:::

1.: ~  ;

O  : J H ",[)

L .=- d  ;

~

a m _

s s s i apo- ,,, ,  :

i i

I

'l ,

I i

Exerche Scenario Ma:erial Page 7 4) AUGUST 17,1993 l

l

i SUPPLEMENTAL SCENARIO NO. 8 l MCC "K" SHORT TO GROUND i

Aporoximate Time: 1045 (02/45) Locatiorn RB 903 EL l l

Description; MCC "K" develops a short to ground (second fault on this component, see Supplemental  !

Scenario #2 for initial fault). Cause of the short is steam leaking out of the Steam Tunnel and into the REC Pump "A" breaker (cabinet 3C) that was not closed after repair  ;

of the initial ground fault.

Player Information: .;

ID the Simulator: Operators observe loss of loads powered by the MCC including '

Drywell Coolers "A" & "C", REC Pumps "A" & "B", control power to RHR "A" loop valves, SLC Pump "A",SGT Fan "A" and MCC-Q, MCC-R, and MCC-RA. The simulator provides indication of increasing drywell temperature and pressure on loss of coolers.

Upon Investigation: When conditions are safe to enter the Reactor Building the ,

investigating in-plant team finds the breaker handles for MCC-K tripped free and unable .

to be reset. The Drywell Cooler "A" Fan breaker is also tripped free (see attached Figure MCC "K2"-1). The team should inform the OSC, and tag out the breaker to  ;

investigate. Upon racking out the breaker, the team find evidence of moisture on the breaker internal and a ground fault condition apparently caused by the moisture. The team also discovers several loose wires on the terminal block. The team observes steam seeping out from the cracks around the door to the Steam Tunnel. ,

Controller Instructions:

1. The MCC feeder breaker "l A" is a high priority repair which must be completed at 1230.

2. Ensure players perform the necessary inspections / investigations before providing them with information. Team members should attempt to dry the inside of the -

breaker cabinet due to the steam leak and also close all breaker cabinet doors.

i a

Exercise Scenario Material Page 7-44 sucusr17.1993 >

r b

SUPPLEMENTAL SCENARIO NO. 8-  ;

MCC "K" SHORT TO GROUND ,

Annroximate Time: 1045 (02/45) Location: RB 903 EL Descrintiom MCC "K" develops a short to ground (second fault on this component, see Supplemental Scenario #2 for initial fault). Cause of the short is steam leaking out of the Steam Tunnel and into the REC Pump "A" breaker (cabinet 3C) that was not closed after repair ,

of the initial ground fault.

Plaver Information: l In the Simulator: Operators observe loss of loads powered by the MCC including ,

Drywell Coolers "A" & "C", REC Pumps "A" & "B", control power to RHR "A" loop ,

valves, SLC Pump "A",SGT Fan "A" and MCC-Q, MCC-R, and MCC-RA. The I simulator pmvides indication of increasing drywell temperature and pressure on loss of  ;

coolers.

Upon Investication: The investigating in-plant team finds the breaker handles for MCC-K i tripped free and unable to be reset. The Drywell Cooler "A" Fan breaker is also tripped free (see attached Figure MCC "K2"-1). The team should inform the OSC, and tag out the breaker to investigate. Upon racking out the breaker, the team find evidence of

• moisture on the breaker intemal and a ground fault condition apparently caused by the moisture. The team also discovers several loose wires on the terminal block. The team observes steam seeping out from the cracks around the door to the Steam Tunnel.  ;

Controller Instructions: ,

1. The MCC feeder breaker "l A" is a high priority repair which must be completed at 1230.

2. Ensure players perform the necessary inspections / investigations before providing ,

them with information. Team members should attempt to dry the inside of the breaker cabinet due to the steam leak and also close all breaker cabinet doors.

9 1

Exercise Scenario Material Page 7-44 Aucurr17.1993 1

SUPPLEMENTAL SCENARIO NO. 8 (cont)

FIGURE MCC "K2"-1: MCC "K" BREAKER TRIP P -

i s *Anc ourt 08-50 ORCtRT BREAKER / '

se;oo aumES. C00 WT5 8-C so nC Alcr4 i

/ eCONTACT i

N .

, , ,,, ,, 5 IS N l 4 "

F >

.  % < a e. a w\_.

~ J e@ ]. - g 4m-r == .

AiaW" h D -

%. g -l!0 ->

b'" ~"=" cr\

uf 1 g#'.-. '

g

.h 4 M ,

,Mg 5-i'I ]

l P  ;; /1 \^^ / .

(DwCR snD ,

i /

N i  %

eC 'lg d h C04.

6G LOVCICJRRENT c

s ac- W"" v'* ** w r

.gh.:

.u. r-TRaPPCD OPCN (RC$CT) j CLosto Exercise Scenario Material Page 7 45 Aucust17,1993 .

t

SUPPLEMENTAL SCENARIO NO. 9 RWCU BOTTOM HEAD DRAIN LINE FAILURE Annroximate Time: 1050 (02/50) Iecation: Drywell Descriotion:

The RWCU bottom head drain line fails catastrophically resulting in a LOCA greater than makeup capacity. See attached Figure LOCA-1 for location of the line break.

Player Information:

In the Simulator: Operators observe indications of a sudden decrease in vessel level and increase in Drywell pressure and temperature. Safety systems auto initiate on 2 psig drywell pressure. Operators observe the RHR MO-25A valve, LPCI injection valve fails to open (see supplemental scenario no.11). Core Spray pump A starts but the injection valve MO-12A fails to open (this is due to no power from MCC "K" to MCC *Q"). The RHR loop "B" was tagged out for repair, and Core Spray pump B suffers a water i hammer event (see supplemental scenario no.10) and trips.

Controller Instructions:

1. This is a long term repair requiring weeks to complete.

2. Player will not be able to gain access to the Drywell to investigate. There is no ;

evidence that would allow players to determine the exact location of the line break.

i i

l 1

l I

Exercise Scenario Material Page 7-46 Avaustn.1pps \

l

~I SUPPLEMENTAL SCENARIO NO. 9 (cont) l FIGURE LOCA-1: RWCU Bottom Head Drain Line Break Location t

?

t

,= mw w~ STEAM o ann i y

7 _,

o

" IT fi I _ a ^ ^ ^ ' - a an==

• enn mum,EOa un i

,-% c

/

I c" _

werem nams -"-a I

i exm _ '

c=t aa A

i mmu== mmu, n ,, ucauca '

waam - _

nn

- i cuorr  ;

meconna UGIELF.Giv ef7#

_ y

<- ncanno sun = mo= LOCATION OF-

• • *"g BREAK i

Eurcise Scenario Material Page 7-47 AvGtur17.1993

SUPPLEMENTAL SCENARIO NO.10 i CORE SPRAY *B" PUMP TRIP ,

Annroximate Time: 1050 (02/50) Location: RB 859 EL.

Descrintion:

Core Spray "B" Pump motor trips on initiation due to water hammer (caused by the previous loss of ECCS pressure maintenance).

Player information:

In the Simulator: Operators observe alarms and indications of the Core Spray "B" Pump  ;

trip. The TSC is notified and an in-plant team is dispatched.

Upon investigation: The team observes that the CS "B" Pump appears to be out of alignment. Its discharge piping is significantly out of alignment in places with damage to several pipe hangers. Water can be seen leaking from at least one flange. The pump motor casing is very hot to the touch (see attached Figure CS"B"-1). Time to repair the damage is weeks. The pump motor breaker high current flag is visible at 4160 VAC Bus -

1G.  ;

Controller instructions: [

1. Provide information only after the players investigate the appropriate components.

L i

l i

P Exercise Scenario Material Page 7-48 A UGust17.1993 l B

4 -

SUPPLEMENTAL SCENARIO NO.10 (cont)

FIGURE CS"B"-1: Damaced CS "B" Pumo CORE SPRAY ~B PUMP I L_

..] L

\

TII JL IIf I

s Discharge ( i t/ Suction r

i

/l N 1

.& i!.;:(-.:: : ... .. ..: ,*

. -a..:.._ ..s.... ..-

. '* ., < :. . . .s.

....- ..c... .

i :.. . .

n '!...>.

, ,,k :*:Y: :*r:.~ ?.. .:. . . ,l:'.::- : :c ' *-'

'k.'.'.,.'

. , ,. c '. ...

?. v. . s . .n .

y.# 7. .%.*

s

.t,..

' v..

.*i- ->. . . , ...

• 3." :w!..;' ':.

. . , . a s.

Exercise Scenario Material Page 7-49 Avav:T17.1993

P b

SUPPLEMENTAL SCENAIUO NO.11 ,

LPCIIniection Valve MO-25A Failure Anproximate Time: 1050 (02/50) Location: RB 903 EL. i

Description:

The RHR LPCI injection valve MO-25A fails to open and initiate flow into the reactor l vessel due to damage to the Limitorque motor operator.  !

Player Information:

In the Simulator: Operators observe that the indicating lights for RHR LPCI injection valve MO-25A do not change and the valve did not appear to open as indicated by a lack of flow to the vessel. The TSC is notified and a repair team is dispatched.

Upon Investigation:When conditions are safe to enter the Reactor Building, the in-plant repair team arrives at the MO-25A valve and discovers that the Motor operator has broken its holddown bolts to the valve body (see Figure LPCI-1) due to corrosion of the  ;

bolts. The Limitorque motor operator has rotated up the stem and pulled the wiring out '

of its electrical connections. The motor operator is bound up on the stem and the handwheel will not engage to open the valve. This will require extensive repair activities.  ;

Controller Instructions:  :

1. This repair should require rigging of the motor operator to remove it from the j valve and rebuild or replace the motor operator with a new unit.

2. Ensure players conduct the required inspection / investigation before providing j information on the results.

i l

4 l

l l

Exercise Scenario Material Page 7-30 Avaust17,1993 1

b i

i SUPPLEMENTAL SCENARIO NO.11  ;

FIGURE LPCI-1: LPCI Iniection Valve Motor Onerator i E

I LPCI INJECTION VALVE MO-25A

' it

~

i ' /a  !

! F'- *O

~

%d 5 O r w j HOLDDOWN i BOLTS C F '

f

_.J A_

l j J

}  !

b i I '

, .)

I

. i 3

N l o-e C '

i

-(  %  !

\,  !

Exercise Scenario Material - page 7 5; AUGUST 17,1993 m

__ _ -_ ~-

SUPPLEMENTAL SCENARIO NO.12 CORE SPRAY Iniection Valve MO-12A Failure i Annroximate Time: 1050 (02/50) Location: RB 948 EL.

i

Description:

T The Core Spray injection valve MO-12A fails to open and initiate flow into the reactor vessel due to loss of power to MCC-Q.

Player Information:

In the Simulator: Operators observe that the indicating lights for Core Spray injection i valve MO-12A do not change and the valve did not appear to open as indicated by a lack of flow to the vessel. The TSC is notified and a repair team is dispatched to operate the valve manually. i i

Upon Investication:The in-plant repair team arrives at the MO-12A valve and discovers ,

that the Motor operator de-clutch lever has sheared an internal pin an is unable to ,

manually engage the handwheel. The handwheel is unable to open the valve. This will require removing the motor oprator, disassembly and replacement of the internal pin.

Controller Instructions:

1. This repair should require rigging of the motor operator to remove it from the i valve, disassemble and replace the pin. .

2. Ensure players conduct the required inspection / investigation before providing l information on the results.

Exercise Scenario Material Page 7-52 Avausr17,1993 4

SUPPLEMENTAL SCENARIO NO.13 SGT "B" CHARCOAL BED FIRE Anoroximate Time: 1130 (03/30) Location: RB 976 EL. ,

Description:

The "B" SGT charcoal bed auto-ignites due to excess heat loading from decay of. i absorbed fission products. The ability of the charcoal to absorb fission products is significantly reduced at a result.

Plaver Infonnation:

In the Simulator: Operators observe indications and alarms for a fire in the charcoal bed.

i An in-plant Operator should be dispatched to immediately open the fire suppression deluge valve for the bed. Due to the other SGT Train being out of service, use of the "B" Train should be continued to take advantage of whatever absorption capability may remain. See attached Figure SGT-1 for a drawing of the affected part of the Train.

At the SGT Train: The Operator successfully opens the deluge valve on arrival and the fire is extinguished within 2 minutes. The Operator then shuts the deluge valve and reports to the Control Room.

Controller Instructions:

1. Deployment of the plant Fire Brigade should not occur since the charcoal bed is contained.

2. Ensure players conduct the required inspection / investigation before providing information on the results.

. l 1

[

i i

Exercise Scenario Material Page 7-53 AUGUSr17.1993 i

P SUPPLEMENTAL SCENAIUO NO.13 FIGURE SGT-h Location of SGT Charcoal Bed Fire i

L6 . f D, , CLOSED e e AO MA-638 At81 tsS Y 3 3 us Y Y 832 A 533 A(B) 635 A(B) 537 A(8)

,B) 7 0 6 4 l

{ l t t I

t

'* RELAI4V6 l RELATIVE HuutOITY HuutDITY g

L 6HJECTION SPRINKLER

. TE Rus-, NOZZLE T3-63sA ,

WOIS TUR E opt 3-631 A -- DP13-634 A DPt3-536A OPl3-638 A SEPARATOR (8) (83 (8) (83

(

'l f. l PAN i

f c

s -

1 pL -

/s,'

_' L .

ROUGH ELECTRIC A8R HIGH A CTiv ATE D HIGH

' ~

PRE FILTER HEATING EF FICIENCY CARSON SODINE TFFICIENCY ELEMENT INLET FtLTER AD&DRSER FINAL FILTER (HEPA) (HEPA) j IA-1(18-ll SA-2(18-2) rg DPt3-843A ,,

LS) v' L.O.k CONNECT i> DPIC TO EQUlPuENT DR AIN 843 )

TO FAN k VORTEX CONTROL

' l STANDBY GAS TREATMENT FILTRATION TRAIN i i

Exercise Scenario Material Page 7-54 AUGUST 17,1993 l

l l

m S(Wion 8 i

STATION OPERATIONS MATERIAL t

1

)

6 i

?

i s

l

1 L

8. STATION OPERATIONS MATERIAL This section contains information pertaining to plant operations (i.e., plant data, alarms, SPDS date, etc.) and events affecting station personnel (i.e., equipment failures, fires, medical emergencies, etc.) ,

Information hn been broken down into the following sections:

8.1 Station Messages ,

Station messages containing operational data, key indications and direction are enclosed. Each message indicates the responsible controller, player (s) intended to receive the message, and describes the circumstances under which the message should be used. Messages with numbers ending in "S" indicate those messages intended for use only in the event of failure of the CNS simulator. Messages ending in "X" indicate those mesages intended for use ,

only in specific contingencies (e.g., failure of players to appropriately classify an event) to bring Exercise play bac1" on track.

8.2 Control Room Alarms Facsimiles of Control Room alarm panels containing key alarm parameters are included. These are intended for use only in the event of failure of the CNS simulator. ,

8.3 Operations Data A summary table of operations data for key plant parameters is included. This data was collected from the CNS simulator during scenario development sessions for use as a scenario review tool. It will be available in the format of a handout page at five minute intervals during conduct of the exercise to provide plant data in the event of simulator failure. One sample copy of the handout page is provided.

8.4 PMIS/SPDS Data One sample copy each of paper facsimiles of key PMIS / SPDS screens containing significant parameters are included. Data for the screens is drawn from the operations data in section 8.3. These are intended for use only in the event of failure of the CNS simulator.

Page 8-1 0:v,660t93En5EC78-H.WH Station Operations Material

aam. + a --a - +- - - -~ -~. e s vs s e -- -- .eaa> - - - - - - - -n - -

E e

t a

SECTION 8.1 STATION MESSAGES ,

F f

o i

f

- t I

5 v

5 e

4 i

f f

1 5

w - - , - -

(

COOPER NUCLEAR STATION  !

EMERGENCY EXERCISE MESSAGE FORM MESSAGE NO: CNS-1 TIME: 0730 TO: Control Room Simulator Staff FROM: Controller ,

LOCATION: Control Room Simulator TIIIS IS A DRILL PLAYER INSTRUCTIONS Initial Conditions Initial conditions are established at 8:00 AM, August 17,1993 with the plant at 100%

power, End of Life. The operability surveillance conducted last night on the "B" LPCI injecdon valve (MO-27B) resulted in the motor operator burning itself up. The preliminary I

analysis indicates a potentially incorrect torque switch setting. The valve has been declared inoperable and replacement of the motor operator is scheduled to begin today. A refueling cutage is scheduled to begin in 6 days.

All plant equipment is in normal conhgurahwM the follondnf exceptions:

CONTROLLER INSTRUCTIONS l Provide the following initial conditions to the participating Plant Operator's assigned to today's drill. Ensure Players have name tags and a copy of the Drill Phone List. Get all l operations participants to sign the attendance sheet. Ensure that procedure 6.3.11.1 is j signed by the real Shif t Supervisor, and a Gai-tronics announcement is made when the '

Simulator is cross-tied to the Plant Gai-tronics system. Contact the Shift Supervisor at the real Control Room and tell him that the Drill is starting and to initiate Message No. CNS-2.

All communications outside the Simulator must include the phrase *This is a drill" l

EXPECTED RESPONSE:

i TIIIS IS A DRILL DO NOT INITIATE ACTIONS TIIAT MAY AFFECT STATION OPFRATIONS DO NOT INITATE ACTIONS TIIAT MAY VIOLATE SAFETY RULES Station Mwager Page 8-3 c:ts660mawzsssat.wes .

e

COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FORM MESSAGE NO: CNS-1 TIME: 0730 TO: Control Room Simulator Staff FROM: Controller LOCATION: Control Room Simulator TIIIS IS A DRILL The "B" side LPCI injection valve (MO-27B) is out of service for motor operator replacement. Valves tagged out for this repair include MO-25B, 27B, 66B and 12B. Work is scheduled to be completed in 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />. This 7-day LCO has been in effect for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

RCIC is out of service for replacement of failed turbine governor vacuum pump seals which have caused steam leakage. MO-15 is tagged out along with the Gland Seal Pump. Work is scheduled to be completed tomorrow, Day 4 of 7 day LCO.

CRD Pump "B" is out of service due to a cmck in the minimum flow line. Maintenance is '

investigating cause of crack. ,

A Westinghouse team is on-site for in-service vibration testing of the main turbine.

Refer to Section 7.4 of this manual for additional equipment malfunction and repair information.

Currently the temperature is 75 degrees F, relative humidity is 63% barometric pressure is-steady at 29.6 inches and winds are out of the southwest at 5 mph. Temperatues are expected to reach close to 90 degrees this afternoon with little or no chance of precipitation.

THIS IS A DRILL DO NOT INITIATE ACTIONS THATMAY AFFECT STATION OPERATIONS DO NOT INITATE ACTIONS TIIATMAY VIOLATESAFETYRULES Station Messages Page 8-4 Avaust17.1993

COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FORM MESSAGE NO: CNS-2 TIME: 0800 TO: Control Room Staff FROM: lead Exercise Controller LOCATION: Control Room Simulator THIS IS A DRILL PLAYER INSTRUCTIONS Make the following Gai-tronics announcement when directed by the lead Exercise Controller:

" ATTENTION ALL PERSONNEL. A*ITENTION ALL PERSONNEL. THE 1993 EVALUATED EXERCISE IS COMMENCING. ALL ANNOUNCEMENTS PROCEEDED BY 'THIS IS A DRILL' ARE FOR PLAYERS ONLY. IF AN ACTUAL EMERGENCY OCCURS, AN ANNOUNCEMENT WILL BE MADE THAT THE DRILL HAS BEEN SUSPENDED UNTIL FURTHER NOTICE. ALL PERSONNEL ARE REQUESTED TO MINIMIZE THE USE OF THE GAI-TRONICS UNTIL THE EXERCISE HAS BEEN COMPLETED."

CONTROLLER INSTRUCTIONS Contact the Shift Supervisor in the real control room and inform him of the start of the 1993 Evaluated Exercise, then have the Control Room Simulator Shift Supervisor make the following Gai-tronics announcement.

EXPECTED RESIONSE:

Start the drill.

THIS IS A DRILL DO NOT INITIATE ACTIONS THAT MAY AFFECT STATION OPERATIONS DO NOT INITATE ACTIONS THAT MAY VIOLATE SAFETY RULES l Station Messages Page B-5 a:vaotosawtsssas.wes 1

l

COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FORM MESSAGE NO: CNS-3S TIME: 0815 TO: Control Room Simulator Staff FROM: Controller LOCATION: Control Room Simulator TIIIS IS A DRILL PLAYER INSTRUCTIONS High radiation in the reactor building annunciates.

ARM-5 is alarming, indicating 1000 mR/hr.

't i

CONTROLLER INSTRUCTIONS Deliver this message only if proper indication is not available from the Simulator.

EXPECTED RESPONSE: F The radwaste control room operator is out taking logs, and will not be able to shut off the ,

transfer pump until 0820. SS declare an ALERT per EAL 1.2.1 "Ioss of control of  !

radioactive material resulting in area radiation levels exceeding 1000x normal or expected levels within the protected area". TSC and OSC activate.

TIIIS IS A DRILL DO NOT INITIATE ACTIONS THAT MAY AFFECT STATION OPERATIONS DO NOT INITATE ACTIONS TIIAT MAY VIOLATE SAFETY RULES l

Station Messages Page 8-6 c:ss60G3EXWESMGE.WP3 1

's

COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FORM MESSAGE NO: CNS-4 TIME: 0815 TO: HP / Mechanics Investigating Resin Spill FROM: Controller LOCATION: Sludge Decant Pump Room THIS IS A DRILL PLAYER INSTRUCTIONS There is a stream of mixed resin and water flowing out from under the door to the sludge decant pump room toward the nearest floor drain. Nearby ARM's and CAM are alarming.

1 CONTROLLER INSTRUCTIONS The radwaste control room operator is out taking logs, and will not be able to shut off the transfer pump until 0820. Refer to Supplemental Scenario 1 for additional details.

EXPECTED RESPONSE:

TIUS IS A DRILL DO NOT' INITIATE ACTIONS THAT MAY AFFECT STATION OPERATIONS DO NOT INITATE ACTIONS THAT MAY VIOLATE SAFETY RULES Sta* ion Messages Page 8-7 c:wsotp3textsssccwes

I l

l COOPER NUCLEAR STATION  !

EMERGENCY EXERCISE MESSAGE FORM i i

i MESSAGE NO: CNS-5X TIME: 0845  !

TO: Simulator Shift Supervisor ,

FROM: Lead Exercise Controller l LOCATION: Control Room Simulator THIS IS A DRILL  !

t PLAYER INSTRUCTIONS l Declare an ALERT per EAL 1.2.1 " Loss of control of radioactive material resulting in area radiation levels exceeding 1000x normal or expected levels within the protected area".

l i

8

+

i CONTROLLER INSTRUCTIONS ,

Deliver this message only if the SS has failed to classify the situation by this time.

EXPECTED RESPONSE: '

l SS declare the alert. - Activate the TSC and OSC. .

THIS IS A DRILL DO NOTINITIATE ACTIONS THAT MAY AFFECT STATION OPERATIONS DO NOT INITATE ACTIONS THAT MAY VIOLATE SAFETY RULES Station Menages Page 84 a:ss60tnerwisssat.wrs .

' l l

i i

i e

COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FORM MESSAGE NO: CNS-6S TIME: 0905 TO: Control Room Simulator Staff FROM: Controller LOCATION: Control Room Simulator TIIIS IS A DRILL PLAYER INSTRUCTIONS MCC "K" feeder breaker indicates tripped.

Drywell temperature and pressure indicate 0.22 psig and 115*F and increasing slowly.

CONTROLLER INSTRUCTIONS ,

Deliver this message only if proper indication is not available from the Simulator.14ss of

- MCC "K" causes loss of drywell coolers "A" and "C", REC pumps "A" and "B", SLC pump "A", and control power to "A" train RHR valves. Refer to Supplemental Scenario 2 for additional details.

EXPECTED RESPONSE:

Troubleshoot fault. Operators vent the drywell to keep pressure below 1 psig.

THIS IS A DRILL '

DO NOT INITIATE ACTIONS THAT MAY AFFECT STATION OPERATIONS DO NOT INITATE ACTIONS TIIAT MAY VIOLATE SAFETY RULES Station Messages Page 8-9 a:s6660mExwtssAct.wes

COOPER NUCLEAR STATION '

EMERGENCY EXERCISE MESSAGE FORM MESSAGE NO: CNS-7 TIME: 0905 ,

TO: Operators investigating MCC "K" FROM: Controller LOCATION: MCC "K" l TIIL". IS A DRILL PLAYER INSTRUCTIONS MCC "K" feeder breaker "1 A" and REC pump "A" breaker "3C" are in the tripped position.

The breakers will trip if reset.

CONTROLLER INSTRUCTIONS Deliver to operators performing preliminary assessment of MCC "K" fault. Refer to Supplemental Scenario 2 for additional details. Team should tag out the breaker and inform ,

OSC. Repair must be completed at 1015.

EXPECTED RESPONSE:  !

Tag out the breaker, rack out and inspect. -

TIIIS IS A DRILL DO NOT INITIATE ACTIONS TIIATMAY AFFECT STATION OPERATIONS DO NOT INITATE ACTIONS TIIATMAY VIOLATESAFETYRULES Station Messages Page 8-10 A ucust17.1993 t

i COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FORM i

MESSAGE NO: CNS-8 TIME: 0930 TO: Repair Team investigating MCC "K" FROM: Controller LOCATION: MCC "K" TIIIS IS A DRILL I PLAYER INSTRUCTIONS Refer to Supplemental Scenario 2 for additional details.

4 t

4 CONTROLLER INSTRUCTIONS The problem must be corrected by 1015, but the breaker must be left in the racked-out position so that the steam leak will cause a short in the MCC.

EXPECTED RESPONSE:

TIIIS IS A DRILL DO NOT INITIATE ACTIONS TIIATMAY AFFECTSTATION OPERATIONS DO NOT INITATE ACTIONS TIIATMAY VIOLATESAFETYRULES Station Messages Page 8-11 A UGUST17,1993 t

I

COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FORM MESSAGE NO: CNS-9S TIME: 1015 i TO: Control Room Simulator Staff  !

FROM: Controller  :

LOCATION: Control Room Simulator TIIIS IS A DRILL PLAYER INSTRUCTIONS Tunnel Area (W 906') Area Temperature High Alarm Steam Tunnel Temperatures indicate 180.

CONTROLLER INSTRUCTIONS Deliver this message only if proper indication is not available from the simulator. Steam leak has started from outboard MSIV on steam line "B".

t EXPECTED RESPONSE:

Investigate cause of rising temperatures. Attempt to mr.ximize cooling.

TIIIS IS A DRILL DO NOT INITIATE ACTIONS TIIATMAY AFFECTSTATION OPERATIONS DO NOT INITATE ACTIONS TIIATMAY VIOLATESAFETYRULES Station Messages Page 8-12 A UGUST17,1993 '

=

COOPER NUCLEAR STATION 1 EMERGENCY EXERCISE MESSAGE FORM -

MESSAGE NO: CNS-10 TIME: 1020 TO: Repair Team investigating MCC "K" FROM: Controller LOCATION: MCC "K" TIIIS IS A DRILL PLAYER INSTRUCTIONS f You have completed repairs to the fault on MCC "K" feeder breaker "1A" and have racked  !

it back into position. The breaker for the REC A pump is still racked out. You notice a flow of steam coming from the edges of the door to the steam tunnel. The flow of steam is l increasing. It is getting very hot in the area of MCC "K".

t 9

i CONTROLLER INSTRUCTIONS j Players must evacuate and leave breaker (s) racked-out on MCC "K". If players try to rack the l breakers back in prior to leaving, stress heat and difficulty breathing. Do not allow the players  ;

to rack the breakers in. Steam entering the open cabinet will later cause a short to ground in .

MCC "K". Refer to Supplemental Scenario 3 for additional information on the steam  !

leak.

EXPECTED RESPONSE: i Evacuate the area, notify the control room.  ;

TIIIS IS A DRILL '

DO NOT INITIATE ACTIONS THAT MAY AFFECTSTATION OPERATIONS DO NOT INITATE ACTIONS TIIATMAY VIOLATESAFETYRULES p

I

l COOPER NUCLEAR STATION .

EMERGENCY EXERCISE MESSAGE FORM MESSAGE NO: CNS-11S TIME: 1020 TO: Control Room Simulator Staff FROM: Controller LOCATION: Control Room Simulator w

TIIIS IS A DRILL PLAYER INSTRUCTIONS Alarms in Control Room Group 1 Isolation Channel B2 Trip Steam Tunnel Temperature High -

Steam Tunnel High Temp Chan A2 Trip Indications in Control Room .

Steam Tunnel High Temp Chan Al Trip AO-80B and AO-86B red and green indicating Steam Tunnel High Temp Chan B1 Trip lights are illuminated.

Steam Tunnel High Temp Chan B2 Trip Main steamline "B" flow indicator indicates -

MSIV Not Full Open Trip A2 ~200,000 lb/hr of flow.

MSIV Not Full Open Trip B1 ,

Reactor Scram (Auto) Chan A2 Trip Reactor Scram (Auto) Chan B1 Trip Group 1 Isolation Channel A2 Trip Group I Isolation Channel Al Trip Group 1 Isolation Channel B1 Trip CONTROLLER INSTRUCTIONS Deliver this message only if proper indication is not available from the simulator. Refer ,

to Supplemental Scenario 4 for additional information on the failure to isolate "B" Main Steam Line.

EXPECTED RESPONSE:  !

Operators recognize and take action for reactor trip. Operators use turbine pressure set to reduce reactor pressure. Operators attempt without success to cycle AO-80B and/or AO-86B to shut them. Emergency Director declares a SITE AREA EMERGENCY per EAL ,

2.3.3, "Imss of any TWO fission product barriers (Primary Coolant Boundary and Pnmary  ;

Containment). >

THIS IS A DRILL  ;

DO NOT INITIATE ACTIONS THAT MAY AFFECT STATION OPERATIONS DO NOT INITATE ACTIONS TIIAT MAY VIOLATE SAFETY RULES Station Masaga Page 8-14 0:16660t93Exwtsssac.nys 5

I l

COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FORM l

MESSAGE NO: CNS-12S TIME: 1035 i TO: Control Room Simulator Staff l FROM: Controller l LOCATION: Control Room Simulator THIS IS A DRILL PLAYER INSTRUCTIONS Alarms in Control Room TG Low Vacuum Pre-Trip Turbine Building Q Sump level Hi-Hi TG Exhaust Hood A Spray On Condenser Air Removal Isolation  !

TG Exhaust Hood B Spray On TG Exhaust Hood A Temp > 175 *F .

TG Exhaust Hood B Temp > 175 *F  !

TG I.ow Vacuum Trip TG Exhaust Hood A Temp > 250 *F  :

TG Exhaust Hood B Temp > 250 *F  !

Condensate Pump A Trip  :

i Condensate Pump A Overload or Ground RFP A Suction Pressure low RFP B Suction Pressure Iow RFP Turbine A Trip i RFP Turbine B Trip  ;

Condenser Air Removal Temp High CONTROLLER INSTRUCTIONS Deliver this message only if proper indication is not available from the simulator.  ;

Condensate suction line boot seal at the condenser has failed catastrophically. Feed and ,

condensate are lost. Refer to Supplemental Scenario No. 5 for additional information.

EXPECTED RESPONSE:

Operators use HPCI to control vessel level.

TIIIS IS A DRILL DO NOT INITIATE ACTIONS THAT MAY AFFECT STATION OPERATIONS DO NOT INITATE ACTIONS THAT MAY VIOLATE SAFETY RULES .

I Station Messages Page 8-15 c:v>ssotp3tnutsssatxrs l

w

• 6

COOPER NUCLEAR STATION EMERGENCY EXERCIfiE AfESSAGE FORM MESSAGE NO: CNS-13S TIME: 1040 TO: Control Room Simulator Staff ,

FROM: Controller l LOCATION: Control Room Simulator THIS IS A DRILL PLAYER INSTRUCTIONS Alarms in Control Room HPCI Logic Actuated HPCIIsolation Channel A Trip HPCI Turbine Tripped  ;

HPCI Pump IAw Flow CONTROLLER INSTRUCTIONS Deliver this message only if proper indication is not available from the simulator. HPCI i Pump tripped on failure of logic module in Control Room. Refer to Supplemental Scenano  ;

6 for details. This repair must not be completed before 1240. Ioss of HPCI is a threat to the ,

clad barrier.

EXPECTED RESPONSE:

Operators maximize CRD flow and start a SLC pump with demin water suction. ED should declare a GENERAL EMERGENCY per EAL 2.4.1. .

THIS IS A DRILL +

DO NOT INITIATE ACTIONS THAT MAY AFFECT STATION OPERATIONS .

DO NOT INITATE ACTIONS THAT MAY VIOLATE SAFETY RULES l Station Messages Page B-16 c:ss60tnExwEssAct.wn i i

COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FORM MESSAGE NO: CNS-14S TIME: 1040 TO: Control Room Simulator Staff FROM: Controller LOCATION: Control Room Simulator TIIIS IS A DRILL PLAYER INSTRUCTIONS Alarms in Control Room Condensate Booster Pump A Trip CONTROLLER INSTRUCTIONS Deliver this message only if proper indication is not available from the simulator. Trip of Reactor Building condensate booster pump results in a loss of ECCS pressure maintenance.

Refer to Supplemental Scenario 7 for details.

EXPECTED RESPONSE:

Operators may elect to manually start the RHR and Core Spray Pumps to maintain pressure.

The Control Room should notify the TSC and the OSC should dispatch a team to investigate.

THIS IS A DRILL DO NOT INITIATE ACTIONS THAT MAY AFFECT STATION OPERATIONS DO NOT INITATE ACTIONS TIIAT MAY VIOLATE SAFETY RULES Station Messages Page 8-17 c:\6660t93txwtssAct.wr3

f COOPER NUCLEAR STATION EhfERGENCY EXERCISE MESSAGE FORM MESSAGR NO: CNS-15X TIME: 1045 TO: Emergency Director FROM: TSC Lead Controller LOCATION: Technical Support Center TIIIS IS A DRILL PLAYER INSTRUCTIONS Declare a SITE AREA EMERGENCY per EAL 2.3.3, " Loss of any TWO fission product -

barriers (Primary Coolant Boundary and Primary Containment).

CONTROLLER INSTRUCTIONS Deliver this message only if the Emergency Director has failed to properly classify the loss of two fission product barriers at 1020. A SITE AREA EMERGENCY must be declared at this time to keep the Exercise sequence of events on schedule.

EXPECTED RESPONSE:

ED Declare the SAE. Activate the EOF is not already done.

TIIIS IS A DRILL- j DO NOf INITIATE ACTIONS THAT MAY AFFECT STATION OPERATIONS 1 DO NOT INITATE ACTIONS TIIAT MAY VIOLATE SAFETY RULES Station Messages Page 8-18 c:16660t93EnVESSAGE.WP3 l

i i

l l

l COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FORM MESSAGE NO: CNS-16S TIME: 1045 ,

TO: Control Room Simulator Staff FROM: Controller LOCATION: Control Room Simulator THIS IS A DRILL '

PLAYER INSTRUCTIONS 1 Annunciators in Control Room RHR Pump Room (SW) FCU H REC Flow IAw RHR B HX Tube to Shell DP Iow Indications in Control Room MCC "K" feeder breaker indicates tripped.

Drywell Pressure indicates 0.1 psig.

Drywell temperature indicates 144 *F.

i l

i CONTROLLER INSTRUCTIONS ,

Deliver this message only if proper indication is not available from the Simulator. MCC j "K"is lost again due to condensation from steam entering the open breaker cabinet. Refer to Supplemental Scenario 8 for additional details.

EXPECTED RE.PONSE: ,

OSC Investigate the trip, i THIS IS A DRILL DO NOT INITIATE ACTIONS THAT MAY AFFECT STATION OPERATIONS DO NOT INITATE ACTIONS THAT MAY VIOLATE SAFETY RULES ,

Station Messages Payr 8-19 G:ks660t93EXWESS,4GE.WP3

-i

.l

COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FORM MESSAGE NO: CNS-17S TIME: 1050 i

TO: Control Room Simulator Staff FROM: Controller LOCATION: Control Room Simulator l

1 TIIIS IS A DRILL j PLAYER INSTRUCTIONS i Annunciators in Control Room Indications in Control Room ,

Drywell Pressure High Core Spray Pump *B" indicates tripped.

Drywell Zone 1 PC-TR-502 Temp High Drywell Pressure indicates 2 psig and-Drywell Fan Coil Unit D Discharge Temp High increasing. '

Drywell Fan Coil Unit B Discharge Temp High Drywell temperature indicates 144 *F and ,

Drywell Zone 1 PC-TR-503 Temp High increasing rapidly.

Drywell High Pressure Alarm (PC-PS-101C) Reactor water level indicates 34.6" and Drywell High Pressure Alarm (PC-PS-101A) dropping.

Drywell High Pressure Alarm (PC-PS-101B)

Drywell High Pressure Alarm (PC-PS-101D)

RHR Pump "A" Logic Actuated i RHR Pump "D" Logic Actuated Core Spray Pump "B" Trip i Drywell Equipment Sump G Hi-Hi Level ,

Drywell Equipment Sump G Temp High CONTROLLER INSTRUCTIONS Deliver this mes.- only if proper indication is not available from the Simulator. RWCU bottom head line a ak occurs in the drywell. CS "B" tripped on overcurrent due to water  !

hammer. Core Spray MO-12A injection valve fails to open due to loss of MCC "K". LPCI 1 injection valve MO-25A fails to open due to damaged motor operator. Refer to Supplemental Scenario 10,11, and 12 for additional details. 1 EXPECTED RESPONSE:

OSC Investigate the trip. Operators use CRD and SLC for vessel makeup.

THIS IS A DRILL l DO NOT INITIATE ACTIONS THATMAY AFFECTSTATION OPERATIONS {

DO NOT INITATE ACTIONS THATMAY VIOLATESAFETYRULES  !

Station Messages Page B-20 Aucust17.I m 4

4

COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FOR11  :

MESSAGE NO: CNS-18 TIME: 1055 TO: Repair Team investigating CS Pump "B" FROM: Controller LOCATION: Core Spray Pump "B" TIIIS IS A DRILL  !

PLAYER INSTRUCTIONS -

The pump motor breaker overcurrent flag is visible.

l CONTROLLER INSTRUCTIONS i Refer to Supplemental Scenario 10 for additional information.

EXPECTED RESPONSE:

Notify the OSC. Set a low priority for this repair, since it will be a long-term job.

TIIIS IS A DRILL DO NOT INITIATE ACTIONS TIIAT MAY AFFECT STATION OPERATIONS DO NOT INITATE ACTIONS TIIAT MAY VIOLATE SAFETY RULES Station Messages Page 8-21 0:t6660tp3Exwts.uGE.sr3

COOPER NUCLEAR STATION l EMERGENCY EXERCISE MESSAGE FOiQ1 MESSAGE NO: CNS-19X TIME: 1110 TO: Emergency Director FROM: TSC Lead Controller i LOCATION: Technical Suppon Center i i

THIS IS A DRILL ,

I PLAYER INSTRUCTIONS Declare a GENERAL EMERGENCY per EAL 2.4.I, " Loss of TWO of THREE fission Product Barriers and Potential Exists for Loss of the THIRD.

i CONTROLLER INSTRUCTIONS Deliver this message only if the Emergency Director has failed to properly classify the loss of HPCI, with two barriers already lost, as a threat to the clad barrier. A GENERAL EMERGENCY must be declared at this time to keep the Exercise sequence of events on  ;

schedule.

EXPECTED RESPONSE:

ED Declare the GE.  ;

THIS IS A DRILL DO NO INrrIATE ACTIONS THAT MAY AFFECT STATION OPERATIONS DO NOT INITATE ACTIONS THAT MAY VIOLATE SAFE *1Y RULES ,

I Station Masaga etr* 8-22 0:16660t93ExwEssAct.wr3 1

COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FORM MESSAGE NO: CNS-20S TIME: 1115 TO: Control Room Simulator Staff FROM: Controller LOCATION: Control Room Simulator TIIIS IS A DRILL PLAYER INSTRUCTIONS ladicillions in Control Room Reactor vessel level indicates +74 on fuel zone monitors.

Reactor Building ARMS are increasing. ,

l 4

l CONTROLLER INSTRUCTIONS Vessel level has reached the top of active fuel. Clad damage begins to occur. Operators ,

emergency depressurize the plant per the EOPs. A release of gap damage starts from the I steam tunnel, through SGTS and the ERP off-site.

EXPECTED RESPONSE:  ;

Operators depressurize the plant per EOPs.

TIIIS IS A DRILL ,

DO NOT INITIATE ACTIONS TIIAT MAY AFFECT STATION OPERATIONS DO NOT INITATE ACTIONS TIIAT MAY VIOLATE SAFETY RULES .

Station Musages Page 8-23 a:ws60to3txwessAct.wes

COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FORM j i

MESSAGE NO: CNS-21S TIME: 1130 TO: Control Room Simulator Staff FROM: Controller ,

LOCATION: Control Room Simulator t

tills IS A DRILL I

PLAYER INSTRUCTIONS Indications in Control Room Fire alarm l

l CONTROLLER INSTRUCTIONS De r this message only if proper indication is not available from the Simulator. The "A" SGT charcoal bed auto-ignites due to excess heat loading from decay of absorbed fission products.

The ability of the charcoal to absorb fission products is significantly reduced. Dose projections off-site should reflect this. Evacuation of Rock Port is an objective. See Supplemental Scenario 13 for additional details.  !

EXPECTED RESPONSE: ,

Operators open SGTS deluge valve to extinguish the fire. Perform damage assessment. Dose  !

assessment staff revise projections to reflect lower absorption of fission products.

]

TIIIS IS A DRILL DO NOT INITIATE ACTIONS THATMAY AFFECTSTATION OPERATIONS DO NOT INITATE ACTIONS TIIATMAY VIOLATESAFETYRULES ,

l Station Messages Page 8-24 AvausT17. I993 l l

'4

COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FORM MESSAGE NO: CNS-22 TIME: 1230 TO: Repair Team at MCC "K"  ;

FROM: Controller LOCATION: MCC "K" TIIIS IS A DRILL PLAYER INSTRUCTIONS Repairs are complete to MCC "K".

i f

CONTROLLER INSTRUCTIONS [

Refer to Supplemental Scenario 8 for additional infortnation.

EXPECTED RESIONSE:

i Operators restore the MCC, open Core Spray MO-12A injection valve and maximize injection flow. Vessel level recovers and Core Spray is operated as required to reduce pressure. ,

TIIIS 5 A DRILL  !

DO NOT INITIATE ACTIONS THATMAY AFFECTSTATION OPERATIONS DO NOT INITATE ACTIONS TIIATMAY VIOLATESAFETY RULES Station Messages Page B-25 August 17,1993

COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FORM MESSAGE NO: CNS-23S TIME: 1300 TO: Control Room Simulator Staff FROM: Controller LOCATION: Control Room Simulator i

TIIIS IS A DRILL PLAYER INSTRUCTIONS Indications in Control Room Reactor Pressure indicates -18 psig and decreasing. ,

Drywell Pressure indicates ~ 18 psig and decreasing.

p i

CONTROLLER INSTRUCTIONS Deliver this message only if proper indication is not available from the simulator. Drywell and reactor pressures are equalized and decreasing as Core Spray cool the core. With the loss of driving head, the release is terminated.

EXPECTED RESPONSE:

Players canduct dwngrade-declassification discussions.

TIIIS IS A DRILL DO NOT INITATE ACTIONS TIIATMAY AITECT STATION OPERATIONS DO NOT INITATE ACTIONS THATMAY VIOLATESAFETYRULES Station Messages Page 8-26 AvousT17. Im ,

COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FORM MESSAGE NO: CNS-24X TIME: 1300 .

TO: Emergency Director {

FROM: EOF Lead Controller LOCATION: EOF 'l TIIIS IS A DRILL ,

PLAYER INSTRUCTIONS -

For demonstration purposes of the Exercise, begin declassification discussions / down-grading procedures at this time. ,

i t

CONTROLLER INSTRUCTIONS ,

If declassification discussions have already been initiated, do not issue this message.

EXPECTED RESPONSE:

Players should be cognizant of the following conditions in order to consider downgrading from the emergency and commencing reentry / recovery discussions: l

1. All plant radiation levels are stable or decreasing

2. ERP vent radiation monitor readings are zero

3. Emergency conditions no longer constitute a hazard to the station or station personnel. i

4. Reactor is cooled down and depressurized

5. All required notifications have been made.  :

6. TSC and EOF agree that downgrading is appropriate.

7. State and County Officials concur.

TIIIS IS A DRILL DO NOT INITIATE ACTIONS TIIAT MAY AFFECT STATION OPERATIONS DO NOT INITATE ACTIONS TIIAT MAY VIOLATE SAFETY RULES Station Messages Page 8-27 0:16660t93Exwes.sAct.wn

COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FORM MESSAGE NO: CNS-25 TIME: 1300 TO: Facility Managers FROM: Lead Facility Controllers LOCATION: All Facilities TIIIS IS A DRILL PLAYER INSTRUCTIONS Simulator. TSC. OSC and EOF Terminate drill play, notify players located outside of the facility to return. Conduct a short critique of the drill. When the critique is over, perform the following:

1. Gather all facility logs and report forms and leave them at your station

2. All radiological equipment should be returned to storage locations, batteries removed as applicable, and properly returned to storage.

3. Chairs, tables and other miscellaneous equipment used during the Drill should be -

returned to their original location.

CONTROLLER INSTRUCTIONS Terminate drill play and notify all station personnel through use of message CNS-26.

Conduct facility critique sessions and ensure all player comments are documented.

EXPECTED RESPONSE:

THIS 5 A DRILL DO NOi' INITIATE ACTIONS TIIAT MAY AFFECT STATION OPERATIONS DO NOT INITATE ACTIONS THAT MAY VIOLATE SAFETY RULES Station Messaga Page 8-28 musemessaat.ur3

_. _= _ _ _

COOPER NUCLEAR STATION l j

EMERGENCY EXERCISE MESSAGE FORM i

l MESSAGE NO: CNS-26 TIME: 1300.

TO: Control Room Staff FROM: Lead Exercise Controller LOCATION: Real Control Room  ;

1 TIIIS IS A DRILL PLAYER INSTRUCTIONS Make the following Gai-tronics announcement when directed by the lead drill controller:

"A'ITENTION ALL PERSONNEL. ATTENTION ALL PERSONNEL. EXERCISE PLAY HAS ENDED.

" ATTENTION ALL PERSONNEL. ATTENTION ALL PERSONNEL. EXERCISE PLAY i

HAS ENDED.

PLEASE CONDUCT AND DOCUMENT A CRITIQUE IN YOUR FACILITi."

1 CONTROLLER INSTRUCTIONS ,

Contact the Shift Supervisor at the real control room and inform him of the completion of the Drill and to make the following Gai-Tronics announcement. ,

EXPECTED RESPONSE:

TIIIS IS A DRILL e DO NOT INITIATE ACTIONS TIIAT MAY AFFECT STATION OPERATIONS 'l DO NOT INITATE ACTIONS TIIAT MAY VIOLATE SAFETY RULES l Station Messages Page 8-29 a:wsotnEXWE5 SAGE.WP3

_ _ . _ _ _ _ < , _ _ _ _ _ _ _ _ _ _ _ - - m

t I

i i

i SECTION 8.2 CONTROL ROOM ALARMS i

h 4

'k e

t 0

i

f 4 .o a

f b

f i

F 5

P h

3 I

SECTION 8.3 OPERATIONS DATA i

i n

t b

i l

I i

1 l

I I

i 1

a

I l

> d

$ E E 888 8888 888 8882 o o o o o o o o o o o o o

• a I E li > @s w '$ ei E

> E 88 8888 88 8 888 89 e c o c oc o o o o o o o z

B

t. E E ba

$ 888 88 8 8 8 8 8 8 8 R R o o o o o o o o o o o o o 2

5

._3 5

!!!!!!!!!$$$$$3$2$ENR8N " * *

• i 2

m s co

% h 0 o o o o o o o o o o s y

.a t g B

g ggggg g gg ))@ gg@2 @GNR8R = = = =

z D E. i oe "

2 4 PI g o o o o o o o o o a

s- -s s- s s- s- s- s o s

- @ @ @ @ m g@G@3RR8A a = = =

H<c<- E D a

%k =

<< 1 E

o S $ $ 2 9 9 9 9 9 0 0 0 - - - - o - o o o o o - - - -

m o  ?,

d

• D >W @

s Z m geg es eg o o . . . o o o o o o o o o o o o o o o

%gA 3 Wo A

a u.

O> g ggg ggg gggggg , , , , , , , , , , , , , , ,

o% , - - - - - - - - - ,

U<w <

e w E  ! 8 8

8 8 99 999gsg o o o o o o o o o o o o o o o m

o E 8 88 88 8 8 gg g ggo o o o o o o o o o o o o o o g E, - - - - - - .-

m <

B u

$@ ggggggggg ggg o o o o o o o o o o o o o o o z u 5

! gy y By g yyy 2E E o o o o o o o o o o o o o o o ,

< i

(

! @ @ @ @@ @ @ @ @ 8 8 2 o o o o o o o o o o o o o o o i Et s l . . . . . . . . . . . * . . . . . . . . . . . . . . . a J

,5 )

w 9 - * - a v . ~ a s e * "

an nsM MMM E RA M d g

j i

E E E EE E E E E E E E E E E E E E E E E E E E E E E E

: : :: : : : : : : : : : : : : : : : : : : : : : : y 4  ;

1 i

1 1

'l

COOPER nut AR STATION

SUMMARY

OF KEY PLANT PARAMETERS Reactor Vessel Level Feed Flow Drywell RX WR A LEV RX WR B LEV RX FZ A LEV RX FZ B LEV RX SD LEV CORE FLOW FW A FLO FW 8FLO DW PRES CONT H2 A CONT H2 B DW PR A NR DW PR B NR 97:30 40 40 184 182 32 72 5 5 0 0 0 0 0 07:45 40 40 184 182 32 72 5 5 0 0 0 0 0 05:00 40 40 184 182 32 72 5 5 0 0 0 0 0 08:15 40 40 184 182 32 72 5 5 0 0 0 0 0 03:30 40 40 184 182 32 72 5 5 0 0 0 0 0 08:45 40 40 184 182 32 72 5 5 0 0 0 0 0 09:00 40 40 184 182 32 72 5 5 0 0 0 0 0 09:15 41 41 184 182 35 72 5 5 1 0 0 1 1 09:30 41 41 184 182 35 72 5 5 0 0 0 0 0 09:45 41 41 170 170 35 59 4 4 0 0 0 0 0 10:00 41 41 170 170 35 59 4 4 0 0 0 0 0 10:15 41 41 170 170 35 59 4 4 0 0 0 0 0 10:30 58 58 167 137 35 14 0 0 0 0 0 0 0 10:45 50 50 157 129 31 13 0 0 0 0 0 0 0 11:00 18 18 108 108 13 12 0 0 2 0 0 5 5 11:15 -25 -25 75 75 0 11 0 0 2 0 0 5 5 11:30 -150 -150 -81 -81 0 2 0 0 2 0 0 5 5 11:45 -97 -97 32 32 0 11 0 0 2 0 0 5 5 12:00 -150 -150 -53 -53 0 2 0 0 2 0 0 4 4 12:15 -84 -84 -31 -31 66 2 0 0 2 0 0 5 5 12:30 -75 -75 -38 -38 75 2 0 0 2 0 0 5 5 12:45 -74 -74 -48 -48 76 - 0 0 0 2 0 0 5 5 13:00 -72 -72 -55 -55 78 0 0 0 2 0 0 5 5 13:15 -8 -8 138 138 71 11 0 0 2 0 0 5 5 13:30 -47 -47 106 105 30 11 0 0 2 0 0 5 5 13:45 -47 -47 106 106 30 11 0 0 2 0 0 5 5 14:00 -47 -47 106 106 30 11 0 0 2 0  ! O 5 5 Operational Data 8-41 Gn666mEDOPSUMAS

COOPER NUL_ AR STATION

SUMMARY

OF KEY PLANT PARAMETERS Drywell Torus DW PR A WRI DW PR B WR DW PR A WR'DW PR B WRlDW TEMP DW TEMP TOR PRES TOR LEV NR TOR LEV A TOR LEV B TOR WAT TEM 1A TOR WAT TEM 10 07:30 0 0 0 0 115 121 0 0 13 13 80 80 07:45 0 0 0 0 115 121 0 0 13 13 80 80 08:00 0 0 0 0 115 121 0 0 13 13 80 80 08:15 0 0 0 0 115 121 0 0 13 13 80 80 08:30 0 0 0 0 115 121 0 0 13 13 80 80 08:45 0 0 0 0 115 121 0 0 13 13 80 80 09:00 0 0 0 0 115 121 0 0 13 13 80 80 09:15 1 1 1 1 139 146 1 0 13 13 80 80 09:30 0 0 0 0 141 148 0 0 13 13 80 80 09:45 0 0 0 0 143 150 0 0 13 13 80 80 10:00 0 0 0 0 143 151 0 0 13 13 80 80 10:15 0 0 0 0 143 151 0 0 13 13 80 80 10:30 0 0 0 0 137 145 0 0 13 13 80 80 10:45 0 0 0 0 136 143 0 0 13 13 80 80 11:00 9 9 9 9 205 216 2 2 13 13 81 81 11:15 13 13 13 13 211 222 2 3 13 13 84 84 11:30 6 6 6 6 172 181 2 8 13 13 99 99 11:45 5 6 6 5 160 168 2 2 13 13 89 89 12:00 4 4 4 4 136 142 2 4 13 13 91 92 12:15 25 25 25 25 229 241 2 10 14 14 124 124 12:30 33 33 33 33 242 254 2 10 15 15 146 146 12:45 36 36 36 36 246 258 2 10 15 15 154 154 13:00 23 23 23 23 249 261 2 10 16 16 159 159 13:15 8 8 8 8 211 221 2 10 4 15 158 158 13:30 6 6 6 6 125 131 2 10 5 16 123 123 13:45 6 6 6 6 125 131 2 10 5 16 123 123 14:00 6 6 6 6 125 131 2 10 5 16 123 123 Operational Data 8-42 ax66cnsmusvu.tu

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

COOPER NUL .AR STATION

SUMMARY

OF KEY PLANT PARAMETERS Torus Diesel Generators RHR Pump Status j j RHRSW Pump Status

~

TOR WAT TEM 20 TOR WAT TEM 2E DG #1 STATUS DG #2 STATUS RHR A RHRB RHR C RHR DRHR A FLOWRHR B FLOW RHRSWP 1 A'RHRSWP 18 RHRSWP 1C 07:30 80 80 1 1 0 0 0 0 0 0 1 1 1 07:45 80 80 1 1 0 0 0 0 0 0 1 1 1 08:00 80 80 1 1 0 0 0 0 0 0 1 1 1 08:15 80 80 1 1 0 0 0 0 0 0 1 1 1 08:30 80 80 1 1 0 0 0 0 0 0 1 1 1 08:45 80 80 1 1 0 0 0 0 0 0 1 1 1 09:00 80 80 1 1 0 0 0 0 0 0 1 1 1 09:15 80 80 1 1 0 0 0 0 0 0 1 1 1 09:30 80 80 1 1 0 0 0 0 0 0 1 1 1 09:45 80 80 1 1 0 0 0 0 0 0 1 1 1 10:00 80 80 1 1 0 0 0 0 0 0 1 1 1 10:15 80 80 1 1 0 0 0 0 0 0 1 1 1 10:30 80 80 1 1 0 0 0 0 0 0 1 1 1 10:45 80 80 1 1 0 0 0 0 0 0 1 1 1 11:00 81 81 0 0 0 1 0 1 0 14400 1 1 1 11:15 84 84 0 0 0 1 0 1 0 14400 1 1 1 11:30 99 100 0 0- 0 1 0 1 0 5550 1 1 1 11:45 89 89 0 0 0 1 0 1 0 15000 1 1 1 12:00 91 92 0 0 0 1 0 1 0 13000 1 1 1

'12:15 124 124 0 0 0 1 0 1 0 12900 1 1 1 12:30 146 146 0 0 0 1 0 1 0 12900 1 1 1 12:45 154 154 0 0 0 1 0 1 0 12900 1 1 1 13:00 159 159 0 0 0 1 0 1 0 12900 1 1 1 13:15 158 157 0 0 1 1 1 1 9900 12900 1 1 1 13:30 123 123 0 0 1 1 1 1 9930 13000 1 1 1 13:48 123 123 0 0 1 1 1 1 9930 13000 1 1 1 14:00 123 123 0 0 1 1 1 1 9930 13000 1 1 1 Operational Data 843 a wwnawrstsuu .

COOPER NUL AR STATION

SUMMARY

OF KEY PLANT PARAMETERS t

Serv 6ce Water Flow Core Spray. Control Rod Drive RHRSWP1D HPCIFLO HPCI RC!C FLO RCIC SW A FLOW SW B FLOW CS A FLO CS B FLO CS A PMP CS B PMP Status CRD 1A Status CRD 18 Status 07:30 1 2 0 0 0 4 4 121 0 0 0 0 1 0 07:46 1 2 0 0 0 4 4 121 0 0 0 0 1 0 08:00 1 2 0 0 0 4 4 121 0 0 0 0 1 0 08:15 1 2 0 0 0 4 4 121 0 0 0 0 1 0 08:30 1 2 0 0 0 4 4 122 0 3 0 0 1 0 08:45 1 2 0 0 0 4 4 121 0 0 0 0 1 0 09:00 1 2 0 0 0 4 4 121 0 0 0 0 1 0 09:15 1 2 0 0 0 4 4 122 0 0 0 0 1 0 09:30 1 2 0 0 0 4 4 122 0 0 0 0 1 0 09:46 1 2 0 0 0 4 4 131 0 0 0 0 1 0 10:00 1 2 0 0 0 4 4 131 0 0 0 0 1 0 10:15 1 2 0 0 0 4 4 131 0 0 0 0 1 0 10:30 1 2 0 0 0 4 4 13) 0 0 0 0 1 0 10:46 1 2 0 0 0 4 4 3 0 0 0 0 1 0 11:00 1 2 0 0 0 4 4030 2 0 0 0 0 1 0 11:16 1 2 0 0 0 4 4030 2 0 0 0 0 1 0 11:30 1 2 0 0 0 4 4030 2 0 0 0 0 1 0 11:45 1 2 0 0 0 4 4250 2 0 0 0 0 1 0 12:00 1 2 0 0 0 4 4250 2 0 0 0 0 1 0 12:16 1 2270 1 0 0 4 4250 2 0 0 0 0 1 0

! 12:30 1 1700 1 0 0 4 4250 2 0 0 0 0 1 0 12:45 1 1340 1 0 0 4 4250 2 0 0 0 0 1 0 13:00 1 784 1 0 0 4 4240 2 0 0 0 0 1 0 13:16 1 1590 1 0 0 4070 4250 2 3780 0 1 0 1 0 13:30 1 2240 1 0 0 4070 4250 2 3780 0 1 0 1 0 13:45 1 2240 1 0 0 4070 4250 2 3780 0 1 0 1 0 14:00 1 2240 1 0 0 4070 4250 2 3780 0 1 0 1 0 Operational Data 8-44 a vswgjawPsw11s

COOPER nut .AR STATION

SUMMARY

OF KEY PLANT PARAMETERS Standby Uquid Control Rette! Valves CRD FLO SLC TK LEV SLC 1A Status SLC 18 Status RV-71A RV-718 RV-71C RVJ1E RV-71G RV-71H RVJ10 RV-71F AOiOA A0400 A040C

~ - ~

07:30 47 73 0 0 0 0 0 0 0 0 0 0 1 1 1 07:45 47 73 0 0 0 0 0 0 0 0 0 0 1 1 1 08:00 47 73 0 0 0 0 0 0 0 0 0 0 1 1 1

.08:15 47 73 0 0 0 0 0 0 0 0 0 0 1 1 1 08:30 47 73 0 0 0 0 0 0 0 0 0 0 1 1 1 08:45 47 73 0 0 0 0 0 0 0 0 0 0 1 1 1 09:00 47 73 0 0 0 0 0 0 0 0 0 0 1 1 1 09:15 47 73 0 0 0 0 0 0 0 0 0 0 1 1 1 09:30 47 73 0 0 0 0 0 0 0 0 0 0 1 1 1 09:45 47 73 0 0 0 0 0 0 0 0 0 0 1 1 1 10:00 47 73 0 0 0 0 0 0 0 0 0 0 1 1 1 10:15 47 73 0 0 0 0 0 0 0 0 0 0 1 1 1 10:30 156 73 0 0 0 0 0 0 0 0 0 0 0 1 0 10:45 66 73 0 0 0 0 0 0 1 0 0 1 0 1 0 11:00 156 71 0 1 0 0 0 0 1 0 1 1 0 1 0 11:15 156 54 0 1 0 0 0 0 1 0 1 1 0 1 0 11:30 156 27 0 1 0 0 0 0 1 0 1 1 0 1 0 11:45 156 67 0 1 0 0 0 0 1 0 1 1 0 1 0 12:00 156 50 0 1 0 0 0 0 1 0 1 1 0 1 0

. 12:15 156 34 0 1 0 0 0 0 1 0 1 1 0 1 0 12:30 156 17 0 1 0 0 0 0 1 0 1 1 0 1 0 12:45 156 6 0 1 0 0 0 0 1 0 1 1 0 1 0 13:00 156 0 0 1 0 0 0 0 1 0 1 1 0 1 0 13:15 156 0 0 0 1 0 0 0 1 0 0 1 0 1 0 13:30 156 0 0 0 1 0 0 0 1 0 0 1 0 1 0 13:46 156 0 0 0 1 0 0 0 1 0 0 1 0 1 0 14:00 ;6e 0 0 0 1 O O O 1 0 0 1 0 1 0 Operational Data 8-45 c:tescot93ExtorstM172

. ._ . - ~ .

COOPER nut .AR STATION

SUMMARY

OF KEY PLANT PARAMETERS Safety Signal Status A04CD A046A AO468 A046C AO460 GRP 6(A)ISOL GRP 6(A)ISOL GRP 7(A)ISOL OT:30 1 1 1 1 1 1 1 1 57:45 1 1 1 1 1 1 1 1 08:00 1 1 1 1 1 1 1 1 08:15 1 1 1 1 1 1 1 1

, 08:30 1 1 1 1 1 1 1 1 08:45 1 1 1 1 1 1 1 1 09:00 1 1 1 1 1 1 1 1 09:15 1 1 1 1 0 1 1 1 09:30 1 1 1 1 0 1 1 1 09:45 1 1 1 1 0 1 1 1 10:00 1 1 1 1 0 1 1 1 10:15 1 1 1 1 0 1 1 1 10:30 0 0 1 0 0 1 1 1 10:45 0 0 _1 0 0 1 1 1 11:00 0 0 1 0 0 1 0 1 11:15 0 0 1 0 1 0 0 1 11:30 0 0 1 0 0 0 0 0 11:45 0 0 1 0 0 0 0 0

• 12:00 0 0 1 0 0 0 0 0 12:15 0 0 1 0 0 0 0 0 12:30 0 0 1 0 0 0 0 0 12:45 0 0 1 0 0 0 0 0 13:00 0 0 1 0 0 0 0 0 13:15 0 0 1 0 0 0 0 0 13:30 0 0 1 0 0 0 0 0 13:45 0 0 1 0 0 0 0 0 14 00 0 0 1 0 0 0 0 0 OperationalData 846 axmpstwesw11s

COOPER NUCLEAR STATION EMERGENCY EXERCISE CONTROL ROOM DATA SHEET TIME: 7:30 TO: CONTROL ROOM OPERATORS T: -30 FROM: CONTROLLER THIS IS A DRILL ,

CONTROLLER INSTRUCTIONS:  ;

Provide the following plant data only if the Sirnulator is unavailable.

PLAYER INFORMATION:

PANEL 9-3 SRV GREEN AMBER RED MSIV GREEN RED LEGEND

• RV-71 A ON OFF OFF AO-80A ON OFF ' = ADS

• RV-71 B ON OFF OFF AO-80B ON OFF OP = Operating ,

'RV 71C ON OFF OFF AO-80C ON OFF SEC = Secured

'RV 71E ON OFF OFF AO-80D ON OFF oos = out of Servie

• RV-71 G ON OFF OFF AO-86A ON OFF STBY = Standby

• RV-71 H ON OFF OFF AO-868 ON OFF RV-71 D ON OFF OFF AO-86C ON OFF RV-71 F ON OFF OFF AO-86D ON OFF ECCS STATUS PRESS FLOW ECCS STATUS PRESS FLOW RHR A STBY 0.0 0.0 RHRB STBY 0.0 0.0 ,

iR C STBY 0.0 RHR D STBY 0.0 PANEL 9-4 SYSTEM STATUS PRESS FLOW CONTAINMENT PARAMETERS RCIC STBY 0.0 ,0.1 PRESS. TEMP LEVEL RWCU A OP 1180.0 160.0 DRYWEu. 0.2 121.0 RWCU B SEC 0.0 0.0 TORUS 0.2 79.8 RRP A - 100.0% SPD RRP B - 100.0% SPD SUPPRESSION POOL 79.8 0.1 PANEL 9-5 i POWER PRESS LEVEL FLOW (1E6 LBM/HR)

RPV 100.8 1010.0 35.7 STEAM 9.5 FEED 9.5 47.4 -l CRD A OP 1357.0 CRD B STBY 0.0 0.0 SLC A STBY 0.0 73.4  !

SLC B STBY 0.0  !

PANELS Bd-A/B/C CP A OP B OP C OP SWPA OP C OP CBP A OP B OP C OP SWPB OP D OP DG 1 STBY DG 2 STBY PANELS VBd-H/K DW L 'LFRS SBGT A OP SBGT B STBY THIS IS A DRILL l

1993 Exercise 8-47 August 17,1993

_.4 - a r.o * .. s l

1 i

I l

.I i

l 1

i i

SECTION 8.4 PMIS DATA i

l i

.-ser-vw+,-,., .g. ,, ,,..,,_, , . , _ , , , . , , , ,., , , _ , , , , , ' , ,,, .,

8/17/93 7:30 SPDS01: PLANT OVERVIEW REACTOR BUILDING WATER LEVELS ~7 J' ERP EFF O.915 uCi/SEC p "~

RAD LEVELS  ??- ,-

SN TEMP LEVELS o ~ / W ii 0 % H' EXHAUST RAD 0.194 MR/HR REACTOR 104 %PWR 1010 PSIG M idh. : . - . i BUILDING EFFLUENT RAD RX 3LDG O.194 uCi/SEC

" ' ' " ~ ~ " ' ~

TURD BLDG 13.7 uCi/SEC CONTROL AOG/RW BLDG 0.765 uC1/SEC REACTOR ROD POSmON SCRAM

[}

~ ~}

'.5-5.> e -

^ ^ ^ ~ ~ ~ ~ '

i :(i" ^.'.- ^ - ^f [ COMBINED BLDG EFFLUENT RAD TORUS EXCEEDING EXCEEDING GROUP ISOLATION O % H.

TECH SPECS 10 TECH SPECS 1 2 3 4 5 67 0.215 PSIG l l l l l l l l [ 79.8 DEGF

YES'

l l- NO: l CPU ;S . RPV,., '. 'J PRIMAR_YQ .iSECONDARY( RADIOACTIVE O B CONTROL'- f CONTAINMENT ' CONTAtNMENT. : RELEASE 00 F1 = CLEAR F2 = F3 = MENU F4 = SPDS INPT F5 = F6 =

CANC HARDCOPY = BUSY MODE = RUN EVENT = NORMAL

O/17/03 7:30 SPDS03: RPV CONTROL DATA '

RPV LEVEL RPV PRESSURE CONTAINMENT LEVEL N ARROW R ANGE 'A' 35.7 IN RPV PRESS 'A' 1010 PSIG N ARROW R ANGE O.6 IN NARROW RANGE3 B' 35.7 IN RPV PRESS *B' 1010 PSIG NARROW RANGE 'C' 3S.7 IN WIDE RANGE 'A' 12.8 FEET "

REUEF VALVE 'A' CLOSED WIDE RANGE 'B' 12.8 FEET WIDE R ANGE ' A' 40.3 IN REUEF VALVE *B' CLOSED WIDE RANGE *B' 40.3 IN RELIEF VALVE *C' CLOSED WIDE RANGE 'C' 40.3 IN RELIEF VALVE 'D' CLOSED CONTAINMENT TEMP REllEF VALVE *E' CLOSED AVG DRYWELL 118.0 DEGF FUEL ZONE *A' 184 IN REUEF VALVE 'F' CLOSED AVG SUPR POOL 79.8 DEGF FUEL ZONE 'B' 182 IN RELIEF VALVE 'G' CLOSED FUEL ZONE 'C' 183 IN RElfEF VALVE *H' CLOSED CONTAINMENT PRESSURE RPV INJ SYSTEMS RPV POWER OW PRESS 'A' O.21 PSIG CS LOOP *A* O.0 GPM CONTROL RODS OUT DW PRESS *B' O.21 PSIG CS LOOP 'B' O.O GPM TORUS PRESS 0.22 PSIG AVG APRM 100.8 %  ;

RHR LOOP 'A' O.O GPM RDR LOOP 'B' O.O GPM APRM 'A' 104.0 % GROUP ISOLATIONS APRM 'B' 101.0 % CHANNEL A GROUP CHANNEL B HPCI 1.8 GPM APRM 'C' 97.1 % STBY 1 STBY APRM *D' 99.7 % STBY 2 STBY RCIC O1 GPM APRM *E' 102.0 % STBY 3 STBY APRM 'F' 101.0 % STBY 4 STBY MAIN COND 9460000 GPM STBY 5 STBY SLC PUMP 'A' STBY STBY 6 STBY CRO 47.4 GPM SLC PUMP 'B' STBY STBY 7 STBY i

CPU

~,# 8.A'MPV:e

>4.z.s[.;.[. 3,,p.n

d PR.X.;-vf

4 'd 6 ;M@.q

IMARY u g - iSEC M %:~a 4.;.:

4 ..::....,OND ARYi)

T '4- p.

R, ADl0A.g

. 0: w CTIvr.VF.

y O

B FCONTROL% ICONTAWMENTi $CONTAINMENTi ?MetEAtEs 00 F1 = CLEAR F2 = F3 = MENU F4 =SPDS INPT F5 = F6 =

CANC HARDCOPY = BUSY CONSOLE = PRIM /BAC MODE = RUN EVENT = NORM A?.

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

I . , , , i ,.[ t t  ! e l

O 0 0 L .

= A k 6 M h' F R r O .

3 0 N 9 3 0 U l

=

/ :

5 8 1

/

V0 L 4L

)

V 85LLV20T2R)W7 I

4E 8 RU 03 0

2 D E E C T N

6 1 L 1 1 3 E M M M M S Y V -

0 S T E A 0 0 0 0 E I D S T 6 1 1 R S A

1( ( ( (

P 'E MI A V D A A A A C U L

_ T T T T I H C T T T G TI E S

_ T E

E H

E H

E H

E H

R T E Y DDDS I C A A E M T T T T E M

V TI L

M 0 MMM IO EL R A A A A I

T I 0 0 6 0 0 D O B AR 1

E A 1 H M M M M R L A 1

=

T G I

G t tG G I A E T R 5 -

O S S S S B R S F .

- 9 6 3 )

=

. D 4 0 M* T E N 0 N _i

)

E O 1

! T D M) D M L P I T M

- I O Y N T E N 0 E N 0 V S C P R E P L O O 0 1

A M E

1 L E D E N N

~

S V P I

- 6 L P I -

1 R

0 W D IN E

U L S 7 T 5 M5 C 4 0 V

L S 2 T C 4 0 0 M3 R T

N I

D I

1

( E N, A I

S U

R R D 6 E D D L

A T

N R 0 0 01

- R D 5 E 0 0 4 N R 1 M W T D

O C N T P =

M I

( T I

( o S ED V I D M W I

D 5 E_O _

Y R 0 0

W T D 0 T

D t

8 6 3

2 4

S C 4

=

O _

AEW 1 6 4 0 0 - 4 F M .

L O PT -

SR E I -

T

- DE M i J

U N

E N0 1 _ M ODN I 3

= -

~ TA F AR E -

ME T 0 0 o 0 T

N R M0

• 5 0 4 3 0

1 1 0

2-0 3

- # Y E RM .

O0

- l N

F 1 yA l

I R T N N I

T ]C O E R -

M W T -

R T

M .

0 0

1

. Y

. S T

• U N H -

B OG I f L =

TI N O Y

.- A D T M I

1 {T P

R N R P O _

C I l

- P 4 3 2 0 O I

E C D _

C C E ,nCH 3 - R .

N R I 2 A P S F H C C C F G G G G -

E E E E D 0 .

T E MP E R A T U R E

• 2 D 0 2 D 1

2 D 96 _

M M M M -

0 0 0 0 0 6 1 1 1

E C

N N 0 R A 1

T W C C MN E

O

$ T R U P B R

R T A R C E D F M L D 2 4 6 0 2 4 0 C N

I W e 2 0 8 8

6 3 1 4-

~

g 1 -

1 1 , 1 W F 4 .

,.  ; i  !

6/15/93 8:30 SPDS25: RADIOACTIVE RELEASE CONTROL DATA ERP/ BLDG RADIATION MET DATA ERP NORMAL RANGE 0.7 uCl/s 10 METER TOWER TURB NE BLDG NORMAL RANGE 8.1 uCi/s AOG/RW NORMAL RANGE 0.0 uCi/s SPEED 7.4 MPH REACTOR BLOG NORMAL RANGE 0.0 uCi/s DmECTION 297.1 DEG TEMPERATURE 11.7 DEGC ERP HIGH R ANGE 104.7 uCi/s TURBINE BLDG HIGH RANGE 104.1 uCl/s 100 METER TOWER AOG/RW HIGH RANGE 105.0 uCile 10 METER SPEED 10.4 MPH -

ERP! BLDG FLOW 10 METER DIRECTION 299.2 DEG 10 METER TEMPERATURE 11.3 DEGC ERP 53629.6 CFM TURBlNE BU!LDING 119670.0 CFM STABILITY CLASS AOG/RW ButLDING 40189.1 CFM REACTOR BUILDING 3051.8 CFM 100M DT C 60M DT E COMBINED EFFLUENT 10M DT D 10 M SIG G EXCEEDING TECH SPEC LIMIT NO EXCEEDING E0P LIMIT NO MISC GROUP SIX ISOLATION NORMAt.

CPU JW %RPVe &44fPftlMAMY

m .. u+rw!!v ESECONDA i .' RAD, IO,.o ACTIVE O

• gpx m&'t;g. .n.y v< acen w ~RY.m : ~ n .. t B Jc6NTROL F SCONTAthMGNT 4 (CONTAINMtkT f +fAtttAst @. 00 F1 = CLEAR F2 = F3 = MENU F4 = SPDS INPT F5 = F6 =

CANC HARDCOPY = BUSY CON $0LE = PRIM /BAC MODE =RUN EVENT = NORMAL

Section 9 RADIOCIIEMISTRY AhT IN-PLANT RADIATION MATERIAL I

i P

9 i

l l

9. RADIOCIIEMISTRY AND IN-PLANT RADIATION MATERIAL This section provides radiological and radiochemical information for the duration of the .

scenario. This information will allow participants to evaluate the extent of core damage and determine the effect of the release on in-plant radiation and contamination levels, and to respond accordingly.

9.1 Radiochemistry Data A summary table of radiochemistry data is provided by sample type for various times in the scenario. Radiochemical data will be presented to the players in the form of individual data sheets (sample enclosed) upon completion of the appropriate sample analysis, i 9.2 Process and Area Radiation Monitor Data A summary table of radiation monitors is provided. Information will be provided to players in the form of individual data sheets (sample enclosed) in the event that the simulator fails to provide proper radiological data in accordance with the time line.

9.3 In-plant Radiation and Contamination Maps Maps are provided for key areas of the plant which players may be required to enter during the scenario. The maps contain data on local area radiation, surface contamination and airborne contamination levels for various time periods. Infomation on the maps will be provided to players verbally by controllers as they traverse areas of the plant.

in-Plant Radiation Material Page 9-1 0:sss60t93Exaccn-11.un

k 6

i r

F SECTION 9.1 RADIOCHEMISTRY DATA i

a i

P b

E t

I i

3

i REACTOR COOLANT SAMPLE

SUMMARY

ACTIVITY CONCENTRATION (uCi/0) AT INDICATED TIME Sample 1 Sarnple 2 Sample 3 I lootope 730-1115 1115-1300 1300-1400 Kr85m < MD A 3.81 E + 03 2.79 E + 03  !

Kr85 < MDA 1.79E + 02 1.'9E + 02 Kr87 < MD A 6.40E + 03 2.15E + 03 Kr88 < MD A 1.00E + 04 6.15E + 03 .!

Xe133 < MD A 3.29E + 04 3.25E + 04 Xe135 < MD A 4.15E + 03 3.56E + 03 .

1131 4.95E-06 6.25E + 03 6.21 E + 03  !

1132 7.65E-05 8.25E + 03 4.49E + 03 1133 4.02E-05 1.30E + 04 1.21 E + 04 1134 8.15E-05 1.11 E + 04 2.28 E + 03 1135 9.01 E4DS 1.19E + 04 9.64E + 03 Cs134 4.15E.06 1.28E + 03 1.2BE + 03 Cs137 6.06E-06 7.89E + 02 7.89E + 02 Cs138 < MD A 7.54E + 03 5.70E + 02 .

Te132 < MD A < MD A < MD A Mo99 <MDA <MDA < MDA ,

Ru103 < MD A i

< MD A < MD A Sr91 8.63E-05 6.60E-05 5.71 E-05 Sr92 6.90E 06 2.70E-06 1.62E-06 Ba140 1.68E-05 1.66E-05 1.66E-05 i Y92 < MD A <MDA <MDA La140 < MD A < MDA <MDA '

Co141 < MD A < MD A <MDA Ce144 < MD A < MDA <MDA Zd5 < MD A <MDA <MDA ZrS7 < MDA < MDA <MDA Gross Noble Gas <MDA 5.74E + 04 4.73 E + 04 Gross lodines 2.9 3E-04 5.04E + 04 3.47E + 04 -

Gross Particulates 1.20E-04 9.61 E + 03 2.64E + 03 Exposure Rates During Sampling (mR/hr) ,

10 mi sample (contact, no sNeid) 3.18 E-05 5.70E + 03 2.87E + 03 10 rni semple (1 foot, no sNeld) 2.21 E-0. 3.96E + 01 1.99E + 01 10 rnt sample (contact, 2" Pb shield) 3.18E-06 5.70E + 02 2.87E + 02 10 rni sample (1 foot,2* Pb shield) 2.21 E-08 3.96E + 00 1.99E + 00 10 rnt sample (contact,4" Pb sNeld) 3.18E-07 5.70E + 01 2.87E + 01  ;

10 mi sample (1 foot,4" Pb sNeld) 2.21 E-09 3.96E-01 1.99 E-01  ;

.1 rni sample (contact, no sNeld) 3.18E-07 5.70E + 01 2.87E + 01

.1 rni sample (1 foot, no sNeld) 2.21 E-09 3.96E-01 1.99E-01

.1 mi sample (contact,2* Pb sNeld) 3.18E-08 5.70E + 00 2.87E + 00

.1 mi sample (1 foot,2* Pb shield) 2.21 E-10 3.96E-02 1.99 E-02

.1 rni ser, vie (contact,4" Pb shield) 3.18E-09 5.70E-01 2.87 E-01

.1 mi sample (1 foot. 4" Pb sNeld) 2.21 E-11 3.96E-03 1.99E-03 i

l t

RadiochemistryData 9-3 G:\666063EDCHBfFORM.XIS l

1 l

DRYWELL AIR SAMPLE

SUMMARY

ACTIVITY CONCENTRATION (uCi/cc) AT INDICATED TIME Sample 1 Sample 2 Sample 3 lootope 730-1115 1115-1300 1300-1400 Kr85m < MDA 2.03E + 01 1.49E + 01 Kr85 < MD A 9.56E-01 9.56E-01 Kr87 < MDA 3.41 E + 01 1.15E + 01 Kr88 < MD A 5.35E + 01 3.28E + 01 Xe133 < MDA 1.75E + 02 1.73E + 02 Xe135 < MD A 2.21 E + 01 1.90E + 01 l 1131 2.64E-OS 3.33E + 01 3.31 E + 01 ,

1132 4.0SE-07 4.40E + 01 2.39E + 01 1133 2.14E-07 6.91 E + 01 6.47E + 01 1134 4.34E-07 5.91 E + 01 1.22E + 01 1135 4.80E-07 6.34E + 01 5.14E + 01 1 Cs 134 2.21 E-08 6.81 E + 00 6.81 E + 00 l Cs137 3.23E-08 4.21 E + 00 4.21 E + 00 3 Cs138 < MDA 4.02E + 01 3.04E + 00 i Te132 < MDA < MDA <.MDA MoS9 < MDA < MDA < MD A Rul03 < MD A < MDA < MD A Sr91 4.60E-07 3.52E-07 3.04E-07 Sr92 3.68E-08 1.44E-08 8.63 E-09 I Ba140 8.95E-08 8.88 E-08 8.84E-08 {

YS2 < MD A < MDA < MD A La140 < MD A <MDA < MDA Ce141 < MD A <MDA <MDA Ce144 < MD A < MD A < MD A Zr95 < MDA < MD A < MD A Zr9'/ < MDA - < MD A < MDA l

Gross Noble Gas < MD A 3.06E + 02 2.52E + 02 Gross lodines 1.56E-06 2.69E 4 02 1.85E + 02 Gross Particulates 6.41 E-07 5.13E + 01 1.41 E + 01 .

Exposure Rates (mR/hr) i 10 mi sample (contact, no sNetd> 1.70E47 3.04E + 01 1.53E + 01 10 mi sample (1 foot, no sNeld) 1.18E-09 2.11 E-01 1.06E-01 10 mi sample (contset. 2* Pb sNeld) 1.70E-08 3.04E + 00 1.53 E + 00 10 mi s. ample (1 foot, 2* Pb sNeld) 1.18E-10 2.11E-02 1.06E-02 10 mi sample (contact. 4* Pb sNeld) 1.70E49 3.04E-01 1.53E-01 10 mi sample (1 foot. 4* Pb sNeld) 1.18E-11 2.11E-03 1.06E-03 i

l l

1 e

l Radiochemistry Data 9-4 G:\6660\93EX\CHEMFORM.XLS l

i

TORUS AIR SAMPLE

SUMMARY

ACTIVITY CONCENTRATION (uCi/cc) AT INDICATED TIME Sample 1 Sample 2 Sample 3 isotope 730-1115 1115-1300 1300-1400 Kr85m < MD A 1.26E + 01 9.22E + 00 "

Kr85 <MDA 5.92E-01 5.92E-01 Kr87 <MDA 2.11 E + 01 7.09E + 00 Kr88 <MDA 3.31 E + 01 2.03E + 01 ,

Xe133 < MD A 1.08E + 02 1.07E + 02 l Xe135 < MD A 1.37E + 01 1.18E + 01

• 1131 < MD A <MDA <MDA 1132 < MD A <MDA <MDA 1133 < MD A <MDA <MDA ,

1134 < MD A <MDA < MDA 1135 < MD A <MDA <MDA Cs134 < MD A <MDA < MD A Cs137 < MD A <MDA < MD A Cs138 < MD A <MDA < MDA Te132 <MDA *.MDA < MD A MoS9 < MD A < MD A < MD A Rut 03 < MDA <MDA < MD A Sr91 < MD A <MDA < MDA 't Sr92 < MD A <MDA < MD A Ba140 <MDA <MDA < MD A YS2 < MD A < MDA < MD A La140 < MDA <MDA < MD A Ce141 <MDA <MDA < MDA Ce144 <MDA <MDA < MDA ZrSS < MD A <MDA < MDA l' ZrS7 < MD A < MDA < MD A Gross Noble Gas < MD A 1.90E + 02 1.56E + 02 '

Gross lodines < MD A <MDA < MDA '

Gross Particulates <MDA < MDA <MDA Exposure Rates (mR/hr) 10 rrd sample (contact, no stueld) 0.00E + 00 3.49E + 00 2.04E + 00 to rnt sample (1 foot, no shield) 0.00E + 00 2.43E42 1.42E-02 10 rnt sample (contact,2" Pb shield) 0.00E + 00 3.49E 01 2.04E 01 10 rni sample (1 foot,2* Pb shield) 0.00E + 00 2.43 E-03 1.42E-03 ,

10 rni sample (contact,4* Pb shield) 0.00E + 00 3.4S E-02 2.04E-02 10 mi semple (1 foot 4* Pb shield) 0.00E + 00 2.43 E-04 1,42E-04 i

RadiochemistryDato 9-5 G:\6660\93EX\CHDLEORM.XLS

.aw, -~

TORUS WATER SAMPLE

SUMMARY

ACTIVITY CONCENTRATION (uCi/cc) AT INDICATED TIME Sample 1 Sample 2 Sample 3 isotope 730-1115 1115 1300 1300-1400  ;

Kr85m < MD A < MD A < MDA Kr85 < MD A <MDA < MDA Kr87 < MDA < MD A < MDA Kr8B < MD A < MD A < MD A Xe133 <MDA < MD A < MD A Xe135 < MD A <MDA <MDA 1131 1.64E-08 2.06E + 01 2.05E + 01 1132 2.53E-07 2.72 E + 01 1.48E + 01 1133 1.33E-07 4.28E + 01 4.00E + 01 1134 2.69E-07 3.65E + 01 7.53E + 00 1135 2.97E-07 3.93E + 01 3.18E + 01 Cs134 1.37E-08 4.22E + 00 4.22E + 00 Cs137 2.00E-08 2.60E + 00 2.60E + 00 Cs138 < MDA 2.49E + 01 1.88E + 00 To132 < MD A < MDA <MDA MoS9 < MD A <MDA < MD A Rut 03 < MD A <MDA < MD A Sr91 2.85E-07 2.18E-07 1.88E-07 Sr92 2.28E-08 8.91 E-09 5.34E-09 Ba140 5.54E-08 5.49 E-08 5.47E-08 Y92 < MD A < MDA < MD A La140 < MD A < MDA < MDA Ce141 < MD A <MDA <MDA Ce144 < MD A <MDA < MDA Zr9S < MD A <MDA < MDA Zr97 < MD A < MDA < MDA Gross Noble Gas <MDA <MDA <MDA Gross lodines 9.6BE-07 1.66E + 02 1.15E + 02 Gross Particulates 3.97E-07 3.17E + 01 8.70E + 00 Exposure Rates (mR/hr) 10 mi sample (contact, no stueld) 1.05E-07 1.53E + 01 7.44E + 00 10 mi semple (1 foot, no shield) 7.30E-10 1.06E-01 5.16E42  !

10 mi sample (contact,2* Pb sNeid) 1.05E-08 1.53E + 00 7.44E-01 10 mi semple (1 foot,2" Pb sNeld) 7.30E-11 1.06E-02 5.16E-03 to rni sample (contact. 4* Pb sNeld) 1.05E-09 1.53E-01 7.44E-02 10 rn! sample (1 foot 4* Pb eNeld) 7.30E-12 1.06E-03 5.16E44 .;

i l

i i

Radiochemistry Data 9-6 G:\6660L93EX\CHEhfFORM.XIS  ;

Y r - e-- -

h TURBINE BUILDING VENT SAMPLE

SUMMARY

L ACTIVITY CONCENTRATION (uCi/cc) AT INDICATED TIME i

Sample 1 Sample 2 Sample 3 7 le otope 730-1115 1115-1300 1300-1400 Kr85m < MD A 1.76E-08 1,76E-08 Kr85 < MD A 7.99E-10 7.99 E-10

• Kr87 < MDA 3.27E-08 3.27E-08 Kr88 <MDA 4.75E-08 4.75E-08  !

Xe133 < MD A 1.47E-07 1.47E-07 Xe135 < MD A 1.88E-08 1.8B E-08 1131 6.27E-09 2.79E-08 ' 2.79E-08 1132 1.07E-07 3.96E-08 3.96E !133 5.14E-08 5.82E-08 5.82E-08 1134 1.34E-07 6.01 E-08 6.01 E-08 1135 1.18 E-07 5.44E-08 5.44 E-08 Cs134 5.25E-09 5.69E-09 5.69E-09 Cs137 7.67E-09 3.51 E-09 3.51 E-09 Cs138 < MDA 4.64E-08 4.64E-08 Te132 < MD A <MDA < MD A Mo99 < MD A <MDA <MDA Rul03 <MDA <MDA < MDA  ;

Sr91 1.12E-07 3.00E-16 3.00E-16 i Sr92 9.50E-09 1.28E-17 1.28E-17 Ba140 2.13 E-08 7.42E-17 7.42E-17 Y92 < MD A < MD A <MDA

• La140 < MD A <MDA < MD A Ce141 < MD A <MDA < MD A Ce144 < MD A <MDA < MDA ZrSS < MD A < MDA < MD A ZrS7 < MD A <MDA < MDA Gross Noble Gas < MDA 2.64E-07 2.64E-07 Gross lodines 4.17E-07 2.40E-07 2.40E47  ;

Gross Particulates 1.56E47 5.56E-08 5.56E-08  ;

Exposure Rates (mR/hr) 10 mi semple (contact, no shield) 4.54E-08 2.88E-08 2.88 E-08 10 mi sample (1 foot, no sNeld) 3.15E-10 2.00E-10 2.00E-10  ;

10 mi sample (contact,2* Pb shield) 4.54E-09 2.88E-09 2.88 E-09 ,

10 ml sample (1 foot,2* Pb sNeld) 3.15E-11 2.00E-11 2.00E-11 l 10 mi semple (contset,4* Pb sNeld) 4.54E-10 2.88E-10 2.88E-10 10 mi sample (1 foot,4* Pb sNeid) 3.15E-12 2.00E-12 2.00E-12 '

i c

r b

RadiochemistryData 9-7 G:\666033EDCHEMFORM.XLS i

TURBINE BUILDING SUMP SAMPLE

SUMMARY

ACTIVITY CONCENTRATION (uCi/cc) AT INDICATED TIME Sample 1 Sample 2 Sample 3 leofope 730-1115 1115-1300 1300-1400 Kr85m < MD A < MD A <MDA Kr85 <MDA < MD A < MD A Kr87 <MDA < MDA <MDA Kr8B < MDA < MD A < MD A Xe133 < MD A < MD A <MDA Xe135 <MDA < MDA < MDA 1131 1.25E-09 5.57E-09 5.57E-09 1132 2.14E48 7.93E-09 7.93E-09 1133 1.03E-08 1.1GE 48 1.16E-08 1134 2.68E-08 1.20E-08 1.20E-08 1135 2.36E-08 1.09 E4B 1.09E-08 Co134 1.05E-09 1.14 E-09 1.14E-09 Cs137 1.53 E-09 7.03E.10 7.03E-10 Cs138 <MDA 9.28E-09 9.28E-09 Te132 < MDA <MDA < MDA MoS9 <MDA <MDA < MDA Rut 03 <MDA < MD A < MDA Sr91 2.24E-08 5.99E-17 5.99 E-17 Sr92 1.90E-09 2.56E-18 2.56E-18 Bal oo 4.25E-09 1.48E-17 1.48E-17 Y92 <MDA < MD A <MDA La140 <MDA <MDA < MD A Ce141 <MDA < MDA <MDA Ce144 <MDA < MD A <MDA Zr95 <MDA < MD A < MDA Zr97 < MD A < MD A <MDA Gross Noble Gas <MDA < MD A <MDA Gross lodines 8.34E-08 4.80E-08 4.80E-08 Gross Particulates 3.11 E-08 1.11 E-08 1.11 E-08 Exposure Rates (mR/hr) 10 mi semple (contact, no stueld) 9.08E-09 4.75E-09 4.75E-09 10 mi semple (1 foot, no sNeid) 6.31 E-11 3.30E-11 3.30E-11 to mi semple (contact, 2" Pb eNeld) 9.08E-10 4.75E-10 4.75E-10 to mi semple (1 foot,2" Pb sNeld) 6.31 E-12 3.30E-12 3.30E-12 10 rni sample (contact. 4" Pb sNeld) 9.08E-11 4.75E-11 4.75E-11 to mi sample (1 foot. 4" Pb sNold) 6.31 E-13 3.30E-13 3.30E-13 Radiochemistry Data 9-8 G:\6660\93EX\CHFlfFORM.172

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

REACTOP COOLANT SAMPLE 1 Activity lootope Concentration (uCilg)

Kr85m <MDA Kr85 < MDA Kr87 <MDA Kr88 <MDA Xe133 <MDA Xe135 < MD A 1 1131 4.95E406  !

I 1132 7.65E-05 1133 4.02E45 1134 8.15E-05 1135 9.01 E435 Cs134 4.15E4D6 ,

i Cs137 6.06E-06 Co138 < MD A Te132 < MD A '

MoS9 <MDA Rul03 < MD A ,

Sr91 8.63 E-05 Sr92 6.90EHD6 Ba140 1.68E-05 Y92 <MDA La140 <MDA. 1 Co141 < MDA Ce144 <MDA Zd5 < MDA ZrS7 < MD A I

s e

)

r I

?

i l

l l

t Radiochemistry Data 9-9 G:\6660\93EX\CHEA[FORAfXLS ,

8 i

.r r

i I

i f

a SECTION 9.2 PROCESS AND AREA RADIATION MONITORS

'l l

I I

i

)

'l

.i .

r

l I

i i

s .$ '

O N

• N *

• N

• N O O w w e A

• A e A N N N N e w N N N m e e e O e h

e e e e 0 0 0, 0 0 I O O O, h, 0 0, 0, 0, b, O, b, O. O, O, , 0, 0, 0 0 +

0 0 0 0 0 0, 0,

+

0 0 0, 0, h, o, 0 0 0, 0+ 0, 0, 0, 0, ,

1 9 W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W y-

$ W w w W M O O O W w O c W W W W w

@ o m O N C> N eW @ N N e O @ @ @ @ O O @ @ 0 4 4 A O N O c O 4 4 N c N e D

O "N > Q 0 0 p. 4 0 4 @

e. >. O. O.

w e. c. e. O. m. O. c.

0 0 O. c. c. e. e. . N. N. . e. d. e. e. . e. O. W. S. O. O. @. . O. N. N. Q.  %

N e m e e N e m e m 4 e N N e e @ e e 4 N e c M

• M N e N N e e @ e w e N e m m e d. e m 1

• l 4 e O p O O N e N w

• N N O O O w e e e O e e e @ e A e A N N N N e w N O N N A e O w O

• e 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0, M

@ @ + + + + + + + + + + + + + + + + + + + + e + + + + + +

" W W W W W W W W W W rW W W W W W W W W W W W W W W W W W W  %

W W W W W W W W W W W

"% e C e O O c 4 k G > k k e e k k wW O @ @ @ > 0 4 p 0 4 4 e O N O c 4

O @ 4 N e N 4

6 O" @ @ 4 4 0 0 0 4 C O e. . O. O. O. c. m. d. e. . N. . . e. d. e. e. c. e. C. . O. O. . O. . S. e. O. M. O. G. N. N. m. .

N e m e e N e w m c 4 e N N e e @ e e 4 N e c A e n N e N h e e @ e e e N e e e m 4 e m ,

0 l i

N O N N M e O e o e O e O O N " N e e N e N C O O w e e e C e e

• m e m e M N N N N * * '

1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

+ + + + + + + + + + + + + + + + e + + + + + + + + + + 1 8**@ g '

W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W N e O N O O c @ @ @ O N S N e @ c O

• O S @ @ @ O S o @ @ O c d e O N O A O @ d N N O

• 4 4 4 @ 4 l 0 0 e. @

. O. O. O. G. C. e. N. N. N. . m. e. e. e. O. e. O. C. O. @. O. e. c. o. O. O. . e. O. M. O. @. O. N. N. @. c. . l N e m e e N e @ m c 4 e N N e e @ e

• 4 N e m m e A N e N N e e s e w e k e m e e d e m i e

9 O N O N N A e O e O e D e O O N e N *

• N e N O O O w e e

• O e w e @

• A e @ N N N N e w 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

@ A + + + + + + + + + + + + + + + + + + + + + e + + + + +

O W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W 4** N c O N O O c O @ O N O N e @ m d e O S O C O @ O c @ O c 4 c O N O c Q @ @ N N N 0

e. >.

0 w 4 @ 4 C o O. O. O. C. .

4

e. N. N. N. . m.

4

e. ". O. ". O. . C. O. S. O. e. c. Q. O. O. . e. O. M. O. C. O. N. N. C. m.

N e m e e N e @ m e d e N N e e @ w e 4 N e m M e M N e N N e * @ e e e N e m e c t e m.

9 9 9 N O N N M e O

• O e O

• C O N a N e e N e N O O O w e e 9 O e e e m a m e M N N N N

• e Q 0, 0, 0, 0, 0 0 0 0 0 0 0 0, 0 0 0 0 0, 0, 0, 0+ 0 0 0 , 0, 0, 0, 0, 0, 0, 0, 0, 0, 0+ 0+ 0 0 0+ 0 0 0 0 0+ 0, 0, 0, +

N N W W W W W W W W W W W W W W eW W W W *W W p W W W W W p W W W W W W W W W W W W W W W W W N c O N O O e @ @ @ O N > N > O O O e @ @ O J O @ @ O c d e O N O c o @ @ N N N C" O

e. >. O. O. O. O. M. W. e. N. N. N. w . m.

0 0 @ 4 0 4 0 0 4

e. e. O. ". C. 4 &. o. O. O. O. *. e. o. . e. o. m. O. N. N. C. m. .

N e m e w N e w m m d e N N e * @ e e 4 N e e m e m N e N N e e s e e e k e m m e d e m e

O N O N e n e O

• O w Q e O O N e N

• e N e N O O C e *

• e D e w o M e A e @ N N N N e w 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 M A + + + + + + + + + + + + + + + + + + + + + + + + + +

" W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W ** "N e g m N O c o J c O N M O @ O N @ N e @ C Q e O S @ @ O S O 4 w$ O 4 c O @ @ N N N C O

e. >.

m w 4 w 4 W @

q C O O. M. O. O. . @d. e. N. N. N. . c. e. . O. e. O. . O. O. @. O. w. e. O. O. O. S. e. O. M. O. C. O. N. N. . m. .

> N e M 4 e N * > m m 4 e N N e e @

• e 4 N e m A e n N e N k e 9 @ p e e N e m e m 4. e m W

N O N e O e O e O e O e O O N e N o e N o N O O O m e e e O e w e n e A e A N N N N e w 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

+ + + + + + + + + + + + + + + + + +

8 8% + +

W W W

@ O N W W W W

+

W W W W

+

W W W W W W W W W W W W W W W W W O S

+ + +

W W W W W W W W W W c O 4

+

W W W W 4 N N N e G e Q 4 O N @ N e @ O @ e @ @ C @ O @ O e W A O N O  %

0** 0 C O e. >. O. e. N. G. . c. e. N. N. N. w

. e. d. e. e. c. e. C.

4 O. O. @. O. P. . O.

.c G. O.

Q S. e. . M. O.

4 G. N. N.

4

@. c. .  %,

N e m e e N e w m e d e N N e e @ e e 4 N e. m m e m N e N N e w @ e w e N e m m m 4 e m Q N O N e O w O e O e O w O O N e N

• w N e N O O O w e e " O e e e n e m e n N N N N e w 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 O C 0 0 0 0 0 0 0 0 0 0 0 0 0 O + + + + + + + + + + + + + + + + + + + + + + + + + +

W W W W W W W #p W W W W W W W W W W W W W g W W W W g M. .

~

e d' N e o c O $$d8 R -

4 c o Q @ $

0 4 0 &;

0 7

$ $ 4 ps m o c Q c o

$ $M 4 N N

. @. O. e. N. e. . e. . N. N. N. . e. . . C. e. o. 4 . . . c. o. m. O. S. e. O. m. . . O. ~. ~. C. m. .

N e m e e N e @ m m 4 e N N e e C e e 4 N e m m e m N e N N e p @ w e e N e m e m d e m M u N O e N O o e. c e O O N O C O O e e O w N

c. N. M. N. M. N. + + +

N N N e

+ + N. + e. + + e. + + + + + + e. N. + e. N. e. N. + + + e. e. + + + + M. + + e.

8 W W W W W % W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W

e. c. O. 4 0 w . C. O. 4 e

g O. Q. c. @. e. M. N. O. O. N. O. S. O. M. N. O. O. O. O. Q. N. O. o. o. m. O. N. O. O. O. O. O. O. O.

e e M e W e e @ @ M c N e d e e m e e N a N e d e N N e e N e w e e e e e e m M M M M @

a M

M A M M M g E M M M A ) V A A M e e O ^ ^ Q O J J L e ( O O ^ ~ J J

= = M 2 3 ( 4 W O E 4 W W M

O w W 2 w M w w O Q w

Q 2 4 W w W

Q E

Q W

M 3 a

> > ^ ^ ^

a N $

^ ^ Q N w ( ( 3 w W O ( E K N N N M 4 z E a m x W W M 3 3 O = 0 0 > d d e 4 w w E m M W E g a w M 2 W E M N

• w w 2 e e e e m e m W w C O ( ( w w M ( U ( & W W M A m 3 2 W E @ D E W = m J W W 3 ( m ( m 4 =

W W M w r O O 2 m E N N 3 M 0 0 > J m

E M M W w r =% % g g & 4 7 4 O O W = 2 2 2 . * . . O p w w M ( M > u u s

• O

• E O W > < (

g g

( W m z z z z ( %

w R u > g N N M E M U 2 & = K J 3 W W U U U g C E J = W M O 3 3 A 2 W K

• W E J w w w w 2 u N J r O u O A A a . E w J w > O r z r z m J > O O m e O

=

8 4

W W % F F E %

3 0 W O O M & R N W O W U N M W W 0 0 W E 2 W E E W

W 3

> 0

=

0

=

m W E g

E 2

W W

X W W W W O X X R a d >

=

(

> m O M M E Z  % W W W W W M a W = > O O E E W O 3 = = = = = 2 J J g r

• w w = U m E m m > J W E M E F m 2 W O = J E S J J J J M W {

W W 3 W

J 3 3 3 K U a

K W =

r r u M W W W W W m

( O -O O ( W O 4 m O u d W W M.

• r z

• X E E m W m O E M O G E g r u

( > -w D O J W W O O U -

J m m 2 M W 2 E M E Z E K W W E X E D E U

= W "W W W W W W W W 0 0 W W > M M W u u E U - ( (r 4 4 O

E.

= = = 3 3 K E E W W W W m

• W O O O O O O O O O O O O O O m e m O O O W a > > > > m m m Z 2 0 4 4 M W 3 > > > > m o {w g O Q Q O O O O O Q Q O O O O O K K N ( 2 W M M M M M M M - = = = C *

• 2 2 W 3 M M M M O J u w J J J J J J J J J J J J J J 3 3 3 W D m m m e > > > w u 2

• 3

( ( ( ( ( ( M N ( 4 J M M W W

> N

( & m

• O

~ m a m m s a m m m m 3 3 3 3 3 * * > > m ( I X X X W E t

~ m 0 0 0 0 0 0 2 3 z & & 3 % = = = = ( . t x x x x w w a a a a - a a M M M N W M M X a m m m a a a w a - - - - -e r

( g ( ( ( ( (

a a a a a - u u W W W O u

x m a m a W W -

m m 3 p.

- - g g w w e (E M a . .

0 E E

= 0 M 4 g C 2 E E u u o u u u o u u o u u u u o u o u u o u u u u u . c o u

.  %.%. %%.W. . . o u u u u c i a, 5 c o r r e r e m m e t r e c m c o r c e r c z t r e c c o

% % % % % % % % % %  %  % % % % E u u C

• *% w% =%

=

% c o m e r t E =

Y Y Y Y t f i f t f f f f f f f 1 1 % % f f T T Y T f f t  ?? 8 8 8 =8 8 8 =8 T 1 % Y t t . 4

- ( em eu O 1O e ( m ( m ( m e - O N w O O O W m O O O O c m m e o m n 4 4 4 5

- r r

n. A. N. N. A. n. N. N. N. N. e. 4 ..

a r r r r r r r r r r r r o

?g

= 3 w w w t,,

M. m. E. M. M. N. M. M. M. M. . a. 3

> A W g ( D a A > > > > & & A & g D e N e d m 4 N C @ O e N M 4 e @ c O O L E E E r r r r E K E E E E E W e N A 4 @ @ k C @ e e e e e e e e

• e N N N N N N N N N A m u u w a w w w w a m w w w w ,

e

e p 9 3 D m O e O n O O N N a N m e e e A e m O O O P =

m e N

0 8 N N 0 0 e

0, + 5 0

O w

+

0 0 0

+

0 0 0

+ + + + +

8 0 0 0 0 0 N

0 e

0 N

0 O O O w 0 0 0 0

+ + +

e 0

e 0

e 0

+

N 0

+

N 0

+

0 0 0 0 0 0 0 0

+ + +

8

+ + + +

0 0 0 0

- m f Y f a d e O $ $ $ Y N 4 O

. 3

- O > . O. N. O. O. O. O. ~. e. O. m. M. e. 4 4 0 ~. c. ~. N. O. e. O. O.

4 4 4

c. 0 0 0 e. O.

4

m. O. 4 0 0 0 0 0 . h e e e e e N e e m 4 N e N N N N e > 4 4 N e e m e N e w N e 4 w e c e e c e e e e e @ 4 O 4

. l 4 N O N O 0 0 0 0 0 N m e O - O -

0 0 0 0 0 0 0 O

• O O 0

O 0

N N 0 0 0 0 e N N 0 0

- N 0

C 0

O O 0

e 0 0 0 0 0

• N 0 0 N m e 0 0 0 m e 0

m 0

0 0 m O O O O 0 0 0 0 0 0 e -

g

+ + + + + + + + + + + + + + + + +

8 8%

D

+ +

W eW W

4

+ + +

W W O m e e

W

+

W W W W W 4 c e O C W

4 W

4 e

W W W W O 0 4 0 e

W Q

W O

W w

W e

W W W e O e W W W W W c 4 W W W C e 0 W

4 e

W W W O N O e

W W W W W O O 0 0 4  %

" M 0 4 4 4 e0 4 0 0 0 0 0 4

• e o &. O. N. . O. O. O. N. e. O. m. M. e. @. e. O. N. A. N. N. A. Q. e. O. >. e. e. O. M. O. .

e e e e e N e e m 4 N e N N N k c % 4 4 N. e h m e N e e N N N > W e e e e e e e e e > 4 e "4 0 9 .

N O N N A

• O

• O e O e O O O N N e N N e N O O O e e e N N w e m e m e m O O O O

• e 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 "0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 W e + * + + + + e + + + + + + e + + + + + + + + + + + +

4 W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W 4** % O eW O O m e N 4 e e C O O O O 4 O O O O e eW e O w eW N O e O 4 0 N O O O O O 4 0 O N y p 4 4 4 g 4 e O . c. . O. o. o. c. N. c. o. m. . c. o. e. o. N. c. N. k. O. . O. O. e. eO. . . m. e. o. m. O. o. o. o. o. o. c. m.

e e e e e N e e m 4 N e N m N k e O 4 4 N e m m e N e w N N N e W e e e e e e e e e W e

+

9 O N O N N M

• O e O e c e O O O N N a N N e N O O O e e

• e N N

• e M e n e m O O O O O e C 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Q Q 0 0 0 0 0 0 0 0 0 0 0 0 0 W e + + + + + + + + + + + + e + + + + + + + e + + + + +

M M W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W

% d e 4 0 0 m 4 N 4 6 e O O O O g o 4 0 0 0 0 eW -W - O

• e e O O C a O 4 0 N O O O O O O O O" N 4 4

o. W. N. c. N.

4 4 e Q g.

. c.  %. o. o. g. e. N. e. o. m. e. c. 4 N. o. c. O. O.

4

c. o. m. e. o. m. o. 4 o. o. o. o. o. N. c.

e e e e e N e e m 4 N e N N N k e > 4 4 N e c m e N e w N N N e w e e e e e e e e e e e e

9 9 N O N N e e O e O

• O e O O O N N " N N e N O O O e e e e N N *

• m e M e M O O O O O e O O 0 0 0 0 0 0 0 0

+ +

0

+

0 0

+ +

0 0 0, 0 0 0

+ + +

0 0, 0 0 0 0 0 0 0 0 0 0 0

+ + + + +

0 0 0, 0

+ + +

0 0 0 0 0

+

0

+ + 0, 0+ 0, 0 M M W W W W W W W W W W W W W W W W W W W W W W eW eW W W W W W W W W W W W W W W W W W W

% O e 4 Q Q m 4 N 4 c eW O w e m s O 4 O O O Q G e e Q N 4 e O 4 0 N O O O O O N O" N W 4 4 4 4 c. "0 4 4 4 0 0 0 0 4 e O . O. N. O. O. O. O. N. e. O. M. M. c. @. O. N. A. N. N. o. e. "O.O. m. e. O. M. O. . N.

e e e e e N e e m 4 N e N N e N e O 4 4 N e e m e N e w N N N e > e w e e e e e e e e m o

9 9 N O N N e e c e O e G e O O N e N O e N e N O O c e e e e 0 0 e e m e m e m N N N N e w C 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 O O 0 0 0 0 0 0 0 0 0 0 0 0 M e + + + + + + + + + + + + + e + + + + + + + C. + + + + + +

" W W y W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W O

• • "N N

N e v 0 0 m d e 4 m 4 e 4 4 N 4 4 4 4 N N e m N m m e O m A O N O N o e e N N 4 4

@ 4 4 4 4 4 0 0 e W e O e. . e. O. O. N. . M. S. e N. e. d. e. e. O. O. N. . O. O. O. O. A. O. e e. O. m. O. M. O. O. Q. e e. M. O.

N e O d e t e N N e

• 4 > N a n e m N e N k W

• O e *

• k e 4 4 4 m e e N e d e e e 4 e

~ .  :

& N O N N m e O e O

• O e O O N e N O e N e N O O O * * *

• O O e n M e m e n N N N N e w C 0 0 0 0, 0 0 0 0 0 0 0 0 0, 0 0 0 0 0 0 0 0 0 0 0 0 0, 0 0 0, 0, 0 0 0 0 0 0 0 0 0 0 0 0 0 O

O g + +

W W W

+ + +

W W W

+

W W W

+

W

+ +

W W W W W W

+ +

W W W W W

+

W

+ +

W W W W W W

+ +

W W W W W W

+

W W W

+ +

W

+ + +

W W W W

% N 4 6 O m 4 4 c e m 4 4 4 ,4 N 4 4 4 m N N 4 e m N M e e O m g e O N O N O eW

• N N 4 4 O" N p p q q g g g e O e. . c. o. o. N. e. m. . . . N.

4

c. . e. o. d. o. s. a. g. o. o. . o. o. c. o. o. .

w

. e. o. m. o. m. o. o. . e. c. m. o.

N e 4

• e N # C 4 e 4

• N N e e 4 & e 4 N e e m e m N e N N O e > e e e N

• 4 4 4 m e e N 8

4 e e  %

N O N N m e O e O e O - O O N e N O e N e N O O O e * *

• O O ~ ~ m e m e m N N N N e e Q 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0, M W + + + + + + + + + + + + + + + + e + + + + + + + + + +

4 4 W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W m e O c @ m e m g N m h

D" Q

A "Q

M 4 C w @

. . e.

O O 4 4 0 O. O. N. O. M.

4 N

4 4 4 4 @

N.

4

e. e. e. Q. 4 0 N. 4 N

&. O. O.

w 4 d

o. o. e.

e O.

0 0 0 0 N

W A O N

. e. O. M.

O S O N O. M. O. e.

4 N O

e. m. N.

N M. O.

N e d e e N e O d e d e N N e 4 % e 4 N e m e m N e N k.> * > e e e N e 4 4 4 m e c

& e e L N O e o o O O N w N O O w

• e e

m. e.

N N N. m. N. m. N. + + N. + + .

N e w Q + + N. + e. N. + e. + e. c. e. + + + e. N. O. . N. e. e O. + + . e. . + O. +

g W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W 4 0 4 W. O. Q. Q. A. 4 W. e. m. N. O. O. N. O.

e g c. e. Q. S. Q. m. e. N. Q. Q. O. O. O. N. O. e. G. e. O. N. O. O. O. O. O. O. O.

e e m e W e * > > M e N e d e e s t e N e N e d e N N e e h e e s *

• e w e m m A m m e m

a

^ ^ O a m > < g

^ ^

M

• M M A 3 O W e e O M M O O J J A e 4 0 0 ^ = J J

^ = M 2 3 4 4 W O E < W W O w W w w C 3 3 2 4 a w W J 3 a

^ 2 w e O O w 3 O O w > > ^ ^ ^ N m

^ ^ O N w ( 4 3 0 u c 4 m a N N N d e t r a k N W W M 3 3 O = Q Q > d e d <

> > E M M W E m W w W X W K J K

• w w X e w e e m e c

• w o u < < w w M 4 0 m 4 A W W d A m 3 2 W  % m 4 D E O W - E J W W 3 ( 5 4 m < g =

W W M w = E C O 2 > W a m & W 0 0 > J W W W v 2 % % M m 5 A < = < O 3 W >

= z u z w . . .

r z z z q w

. O -

w w M s m > v u m - O

• A o W < < < W w E

v 2 W > N N N E E M U 2 A E J m E 3 W U U U W E D J J = W M Q 3 3 4 & W N~ > < W J w w w w 2 G W J Z O U U A A w

• E W J 2 > O Z Z Z Z w J > O Q = w8 O W W N 2 2 E E M A R N W O O O m W > *

• 0 0 w W X W W W W W O

= 3 0 w C O u O N w w m u m E =z W u m ~ ~ w E r w a m x x z J > <

> w O m m E E  % W W < W W > A W > O O x x m O 3 - = = = z J J Q W p w p - U w E m

• w J M 2 M E 2 m 2 W W O = J Z E =J J J J M W E W W 3 a 3 3 3 g u m w = < O O O < W O < . = = a z z w e r < > =m 3 3 W J W W O O A r z u M W W W g m a > U m O U J W W 2 2 W w = O E E F E C J w W E m M B E W E E m W M U E X X O 2 > U 0 0 W W D W W W E ~ 4 4 4 < .

- = > W 2 < W W W W W W 3 D E E U U Z W W W W w d E.

W O O O O O O O O O O O O O O m m'=m W O O W - - - - ~ ~ w w 2 2 O s c * ~ 3 - - * *

• O E .

O Q 0 0 0 0 Q 0 0 0 0 0 0 0 Q w w z < r u m M H w m m m = = = = Q w w z z m 3 m m M M Q J w J J J J J J J J J J J J J J D 3 3 W O < < < < < < -w K < < J W @ W W < u m ew

- m m a m m m m m m m m m m e w w

• s u r . 3 3 3 3 3 3 m - - m > >  % < ~m =a =z z W z

= m O O O O O O F X 2 2 A A 3  % = < . ,t M M M M M W M M M M M M M M m e m e s t o c < d q < < W W 0 0 M a a m e m 3 < < < < w M e o w w w w w w w w w w w w w w w E & w M N w U U V N W W w w w E E E E @ w 6 M M M M M M U Q

E 8

=

. =

Q M

U U U U U U U

= 6 @ h @  % W W A.

w L L L L L L L L L L L L L L L L L L L L L e m m e e e m L L L L L L 5

L L L L L x x x x x x x x x z z L L L z x x x c r x x x r x x x x x r r r L L

%  %  % z z z z z n -h  %

%  %  %  %  %  %  %  %  %  %  % % % % % % % % % % % % % % % % % % % I E * * *% %  %  %  %  % % E g

% % % % % % % % 1 % % % I % % % 1 % % % % % % 1 % % T 1 % U2 3 3 3 *3 3 3 3 % I T I I I . x

- < m W O 1

M < 3 < m < m e e e e O N  %

O O C 4 m O O O O c e c c e e W

m. A. e N. m. m. N. N. N. Ne e 4 ..

4 4 4 N e O

• E E E K E E E E E E E E E E K O w

u. e a. M. Me we m. m. a. ae a. a. m. yx

= u

. M.

< < > A A > > > > A A A A > A u O e N M 4 e 4 N O S O e N m 4 e 4 C O O E E E E E E E E E E E E E E E W e N A 4 e 4 h O & w e e e e e e e e e N N N N N N N N N m w w w w w w a w a w w w w a w J

o e e e e n ~e l

3 3 3 $ 8 3 D D 3 3 3 3 i M e O N M M O N N e N N e e O N N " N N e N O O O w a e M M M c N e m e M O O O O w e  !

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 e0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 a m e + + + + + + + + + + + + + + + . + + + + + + + + + + + + + +

W W W W W W W W W W W W W W W W W W W W W W W W

• W O W eW W W W e W W W W W W W W W W W W

"% eW > 4 Q O c e e m e n c e eW O O C 4 O O O O e e 4 4 C O G 4 O N O O O Q Q 4 M** e Q 4 4 w4

• . 4

c. Q.w w O M. N. N. O. O. O.

4 0 0

e. Q Q. M. M. M. O. N. e. N. N. . e. O. *O. m. o. C. e. c. O. M. O. O. O. O. O. Q. >i N N w e e e m e e N e. e e e n k e w 4 4 N e c M e N e w N M M w e N e e e e e e e e s 4 Q

O 9 9 9 9 9 9 9 9 0 . O M e O N M M O N N e N N e e O N N N N e N O O c e - e e M M M c N e M e M O O O Q e Q 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 e0 0 0 0 0 0 0 0 0 0 0 0 O O 0 0 0 0 0 0 0 0 0 0 0 m0 0

+ + + + + e + + + + + + + + + + + + + t + + + + e + + + +

W W W W W W W W W W W W W W W W y W W W W W W W W W W W W W W W W W W W W W W W W

• • % eW > 4 G O c e c c e c c e N c O O v 0 0 0 0 *

• e O wW eW e N N C O S W O N O O O O O 4 C m M e Q 4 4 4 c. o. 4 4 0 0 4 m e Q M. N. N. O. O. O. S. O. O. . O. O. M. M. c. O. N. c. N. N. . e. O. O. M. A. Q. &. M. O. C. O. Q. c. e N N 4 e e e M e e N e w e e h h e 7 4 4 N e c M e N e w N M M O w e e e e e e e e e  % 4 Q

. . . . . . E

. . . e . . e. . . . . . r M e Q N M M O N N e N N e w O N N e N N e N O O O w e e e M M M c k e M e M O O O O w e O 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0, 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 e m + + + + + + + + + + + + + + + + + e + + + + + + + + + +

4 4 W W W W W W W W W W W W W W W W W W W W W W W eW W W W W W W W W W W W W W W W W W W

% e > < O O e D e e c e c e e N Q O D O O O O e O wW eW 4 O M O G 4 O N 0 0 Q O Q 4 M

o. o. e. 4 N** 4 e o M. N. N. C. O. O. S. Q. Q. e. O. O. M. M. N. O. N. c. N. N. O. e. wO. O.

4 4 e4

e. o. M.

4

e. O. A. M. O. 4 0 0 C.

N N 4 e e e M e w N e e e e k k e > 4 4 N e e M e N e e N 4 4 O w e v e c e w e e e O 4 e e e e e e e 9 4 e e 9 e e 6 0 9 . 4 M e O N M M O N N e N N e e O N N e N N e N O O O w e e e M M M c N e M e M O O O O e e 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 O O 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 + + + + + + + + + + + + + + e + + + + + + + + + + + + + + s N N W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W

% eW > 4 O O c o c e m e c eW eW M O O v 0 G O O eW O -W eW 4 N C O N 4 0 N O O O O O 4 O N" 4

" O M. N. N. O. O. O. @. Q. O. *. O. O. M. M. C. O. N. c. N. N. O. e. O. -O.e4 4 4 c. e0 M.

4

c. o. c. M. O. D. O. O. O. O. O. m. 4 N N 4 e e e M e e N e e e e k k m > 4 4 N

• e M e N e w N 4 4 W e e e m% e w e v e  % 4 e e 9 9 e e e

. 9 9 4 . . 4 4 6 9 9 +

M e O N M M O N N e N N e e O N N N N e N O O O

• e e

• M M M c N e M e M O O O O w e 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 "3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 e e + + + + + + + + + + + + + + + . . . . . + + + . . + + + + + + + e + + + + e

" W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W y

• • "% eW > 4 O O c e c c e e c e e O O O 4 0 0 O O wW eW e O w e eW 4 k D 0 4 4 O N O O O O O v N 4 4 e O M. N. N. O. O. O. S. C. O. *. O. O. M. M. Q. Q. N. c. N. N. o. c. Q. Q. 4 4 4 e. o. N. M. e. O. M. M. O. Q. O. O. O. O. c. .

N N 4 e v e M e e N e e e

• G k c O 4 4 N e c M e N

• e N 4 4 O w e e e e e e e e e > 4 e e e e . e

• O 4 9 4 e 9 e 4 4 4 4 9 9 M e O N M M O N N e N N e e M N N e N N e N O O O w e " M M M c A e M

• M O O O O *

• 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 e0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

+ + + + + + + + + + + + + + + + + + + + + + + + + + + + + e Q Q W W W W W W W W W W W W W W W W W W W W W W W eW eW W W W W W W W W W W W W W W W

% D N O O O m c e n c e w e m O 0 4 0 0 O D eW *W *W Q 4 @ 0 % 4 O N O O O O O 4 C N" T 4 4 e4 e0 0 4 0 0 0 4 W e Q N. N. e. O. O. O. . O. O. e. O. O. M. M. O. O. N. c. N. N. Q. e. Q. C. c. 0 A. Q. Q. M. O. G. O. c.

g w e M e w e M e e N e e e e e k c W 4 4 N e c M e N e e N w e W e e e e e e e e e e p p a . . .

9

. e. . . .

e

" M e Q N M M O N N e N N e e M N N e N N e N O O O w e = e M M M c D e M e M O O O O * * }

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 e e + + + + + + + + + + + + + + + + + + + + + + + + + e + + + +

• d W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W

• • % eW > 4 0 0 c e c e e c e e e c O O 4 0 G O O w eW O w eW e N 4 m o e 4 C N O O O O O 4 e

$ " O Q 4 4 4 0 4 4 e 4 Q m e "O M. N. N. O. O. O. S. e . e. O. O. M. M. O. O. N. c. N. N. o. e. eO.O. c. c. O. e M. O. e G. O. O. O. e e. e N N d e e e M e e N e e e e e  % c O 4 4 N e c M e N e e N e e W e c e e c e e e e e  % e  %

e e e 4 9 e  %.

• e e . e e e e e e . 4 M e o N M M O N N e N N e e M N N e N N e N 0 0 O w e e e M M M c D e M e M O O O c e e 0 0 0 0 0 0 0 0 0 C O 0

+

0 0 0

+ + +

0 0

+ +

0

+

0

+ +

0 0, 0 0 0 0 0 0

+ + + + +

0 0 0 0 0 0 0, 0, 0+ 0 0 0+ 0+ C, O, C. +

0 0

+ + +

0

+ + +

M M W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W h "

• • % e > 4 0 0 e d e c e m e e e e O O O O O O O -W eW eW c eW e e m 0 0 0 4 Q N O O O O O 4 C

" " "O M. N. N. O. O. O. &. O. Q. e. Q

. O. M. M. O. O. N. c. N. N. o. e. O. Q.

4 4 e4

e. c. 4 4

e. O. G. M. O. 4 0 C. O. O. O. c. 4

& N N 4 e v e M e w N e e * *

• k e 0 4 4 N e c M e N e w N w e >

• 4

• e c e e * *

• O 4

~

N O w N O O O O O N O O O O w

• e O

• N N N N e w fL J

e e

+ + N. + . + $ e. + e. + + + + $ e. N. + e. N. e. N. + + + . s + +

e

+ + M. e. N. M. N. M. N. + + + + 4 .

O W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W e

g c. e. O. 4 O. vQ. C. O. O. O. c. 4 C. c. M. N. O. O. N. O. S. O. M. e. N. O. G. O. O. O. N. O. c. O. c. Q. N. O. O. O. O. O. O. O.

w e M e D e e > > M e N e 4 e e c e e N e N e w e N N e e h e e f e w e e n M M M M M 4 m

m a n O m w w 4 u m a g w M M a 3 O M e e O m A O A J J L e 4 0 O =O J J

^ = M 2 3 4 4 W Q K d W W O W W w w O 3 3 2 4 E & W 3 3 ^

^ 2 w M 0 0 w 7 0 0 m > > a n a N 5

^ ^ O N w d ( 3 D W O 4 m W N N N e W E E m m M W W M 3 3 O = O O = 4 W M (

• Z M M W E W m w M 2 W E M E . w w 2 e w e e W m e ~ w C W 4 4 w w M 4 U K ( 1 W W M &

e 3 2 W m > O m o W = m J W W D ( m 4 m 4 =

W W M * = E D O T 2

• Q E g W 3 M 0 0 > J m M M W w 2 % % w h D A 4 2 4 O O W = 2 2 2 m . . . . D e w w M ( M > U W E W O W & Q W > ( 4 4 W m Z Z Z E 4 %

w 2 W > w  %  % 0.c M U K r a

= E J m W D W W W U Q g o E J = W M O 3 D E E W P E M 4 K J w w w w 2 L t 2 J E O U U & & >

• E a D E J 2 > O T E Z E w J = 0 Q = a O

=

8 a

W W D o w N

5 2 0

x x M a o 5 N W O

~ M W A

= v O O m W m K 2 W

> w

- 3

- 0

=

0

=

w e W r r W 7 W 2

W W W W O 2 2 2 2 J - 4

=  !

• w O m a r z  % a W W W W

• E w = > 0 0 Z Z u c 3 = = = = = 2 J J O n > * * = U w E S w - J K 2 M E g m 2 > O = J T m J J J J M W E W W 3 3 3 3 3 W U r s = 4 0 0 0 < W J a M. > w 2 2 r m c i r < >

=b D O W J W W O O A s t u M W W W w M a

• W m o u d w W 2 2 W w - O c E E E r d J w w 2 M M X 2 W Z Z E M E G 2 2 2 0 2 ~ O O Q W W > M M W 7 W = 4 d ( ( .

=

• W 2 4 W W W W W W 3 D X Y U U E W W W W w G E. &

O O O O O O O O O O O O O O M S W O W M w w ~ > 3 > > w W O M M M M O J {

E W O ~ > > > 2 2 0 4 4 >

O O O O O O O O O O O O O O O K E E d 2 U m M "M M M M M = = = = O w 2 2 k 3 e

• J J J J J J J J J J J J J J 3 3 3 W D 4 4 4 4 M M m E 4 4 J ~M M W W 4 W m e

= M E M E M G M M S W W W E N W M M E W 2

• 3 3 3 3 3 3 r * *

• m 7 > s e 2 2 2 2 W E  %

- M 0 0 0 0 0 0 2 2 2 y a & 3 N = = = - 4 . t M M M M M M M M M M M M M M S S m e m S O W d 4 4 4 4 W W 0 Q M x t T T w 3 C ( ( ( M M O W m W W M m a m u a w w a M w w ~ ~

• n & a a m W W E O O O U M w & n

• W E E E E M W e. Q E

4 E.

=

=g e M 4 w U U U U U U U

= 6 4 4 b b & W f 'E 2 L L L L L L L L L L L L L L L L L L L L L L L L L L L L L e e v e + y m L L L L L L p -

D L & K C L L L C L E L R C E E E C & L C L L E L L C L C E L L  % % % % % % % C C E A L K O I C I g

%  %  %  %  %  %  %  %  %  %  %  %  %  %  %  %  %  %  %  %  %  %  %  %  %  % %  %  %

• e a e -  %  %  %  %  %  % *E f f f f f % % % % Y T Y f f f ! f f f f f f % 1 7 % % % % 22 S *T SSS -Y S i f f f % % e x e

• • 4 m U O O

% d M 4 @ t @ e w e e O N m O O O W m Q,0 0 0 c e m e e m W 4 4 4 N n.* 4  %

O e E E E

m. #'I. M. M. N. N. N. N.

Y E E E E E E E O

== y '1% *r 2

a. a. a. . . a. a. a. a. a. m. W 4 4 D a a's .e f ^i' >>.>l v.

7 a a a a > a u c e N M 4 e N C O O

• N M 4 c 4 C @ O E I I E " E E Y s w w w aE uE W

~' \n 7 E e N m 4 e s k c O w e e e e e e4 e e e N N N N N N N N N m m w w w -

~~is J

RADIATION MOL SUPPARY TABLE 13:30 13:45 14:00 MONtioR #: UNITS MONII0R LOCAlloN 100% 05/30 05/45 06/00 Pcuer 1 M/hr RX BLDG FUEL POOL (SE STH) 1.5E+2 2.31E+03 2.31E+03 2.31E+03 2 mR/hr RX BLDG FUEL POOL (SE SiH) 1.5E+0 2.2VE+01

• 2.29E+01

• 2.29E+01

• 3 mR/hr RX BLDG NEW FUEL (SE 51H) 3.0E-2 4.24E+00

• 4.24E+00

• 4.24E+00

• 4 W/hr RX BLDG RWCU DEMIN (SW 3RD) 1.4E+1 1.00E+02

• 1.00E+02

• 1.00E+02

• 5 m/hr RX BLDG SLUDGE / DECANT (S 2ND) 8.0E-1 1.00E+03 " 1.00E+03 " 1.00E+03 "

6 mR/hr Rx BLDG NEUTRON SYS/INDEX (TIP ROOM) 1.6E+2 1.05E+03 " 1.05E+03 " 1.05E+03 **

7 M/hr Rx BLDG NEUTRON DRV/ MECH (SE 1ST) 1.8E+0 3.96E+00 3.96E+00 3.96E+00 8 m/hr RX BLDG SOUTH HCU/CRD AREA (S 151) 9.0E-1 1.05E+02 " 1.05E+02 " 1.05E+02 "

9 W/hr RX BLDG NORTH HCU/CRD AREA (N iST) 9.0E+0 1.05E+02 " 1.05E+02 ** 1.05E+02 "

10 M/hr RX BLDG HPCI PUNP Rom (SW QUAD) 3.0E-1 2.15E+01

• 2.15E+01

• 2.15E+01

• 11 W/hr RX BLOG RNR PUMP ROOM (SW QUAD) 5.5E+0 1.05E+02 " 1.05E+02 " 1.05E+02 "

12 m/hr RX BLDG RNR PUMP ROOM (WW QUAD) 2.4E+1 1.05E+02 " 1.05E+02 " 1.05E+02 "

il m/hr RX BLDG RCIC/CS PUMP ROOM (NE QUAD) 1.8E+0 1.31E+01 1.31E+01 1.31E+01 14 m/hr RX BLDG CS PUMP ROOM 9SE 00AD) 4.5E+0 1.31E+01 1.31E+01 1.31E+01 15 m/hr TB TURBINE FRONT STANDARD 1.3E+2 7.23E+00 7.23E+00 7.23E+00 16 W/hr 18 TURBINE MEZZ. CONTROL CORRIDOR 1.7E-1 7.00E-02 7.00E-02 7.00E-02 17 m/hr TB TURBINE BASEMENT CORRIDOR 5.0E 2 5.20E-02 5.20E-02 5.20E-02 18 M/hr IB react 0R FEEDPUMP Rom 6.0E+0 9.56E-01 9.56E-01 9.56E-01 19 mR/hr IB CONDENSATE PUMP AREA 1.2E-1 6.20E-02 6.20E-02 6.20E-02 20 m/hr MAIN CONTROL ROOM 2.0E-2 4.70E-02 4.70E 02 4.70E-02 21 mR/hr 903' REACTOR CORRIDOR 1.9E-1 2.00E 01 2.00E-01 2.00E-01 22 M/hr RADWASTE CONTROL Rom 2.0E-2 1.50E-02 1.50E-02 1.50E-02 23 mR/hr RADWASTE PUMP ROOM 5.3E+0 5.01E+00 5.01E+00 $.01E+00 24 M/hr RADWASTE BASEMENT EQUIP. AREA 4.1E+0 3.01E+00 3.01E+00 3.01E+00 25 m/hr RADWASTE DEMIN VALVE ROOM 1.2E+0 1.41E+00 1.41E+00 1.41E+00 26 mR/hr RADWASTE CONVEYOR AISLE 2.0E-1 2.60E-01 2.60E-01 2.60E-01 28 M/hr RADWASTE LAB 2.0E-1 1.61E-01 1.61E-01 1.61E-01 29 mR/hr CENTRIFUGE-NORTH 1.0E+1 1.51E+01 1.51E+01 1.51E+01 30 mR/hr CENTRIFUGE-SOUTH 1.0E+1 2.01E+01 2.01E+01 2.01E+01 RMA-RM-40A R/hr CONTAINMENT HIGH RANGE (DRTWELL) 7.0E+0 4.46E+03 4.46E+03 4.46E+03 RMA-RM-408 R/hr CONTAINMENT HIGH RANGE (DRYWELL) 1.2E+1 4.60E+03 4.60E+03 4.60E+03 RMV-RM-40 uCi/sec RX BLDG VENT EFFLUENT 1.0E-3 9.58E-03 9.58E-03 9.58E-03 RMP-RM-3A UCi/sec ERP STACK NORMAL 5.5E-1 1.00E+05

• 1.00E+05

• 1.00E+05

• RMP RM-3B UCi/sec ERP STACK HIGH 1.0E-2 2.36E+07 ** 2.54E+07 " 2.72E+07 "

RMV-RM-20A UCi/sec TB VENT EFFLUENT 1.5E-3 1.34E+01 1.34E+01 1.34E+01 RMV-RM-208 uti/sec TB VENT MIGH 1.0E-2 1.00E 03 1.00E-03 1.00E-03 RMV-RM-30A UCi/sec RW/ARW COMBINED EFFLUENT 1.2E-3 5.62E 01 5.62E-01 5.62E-01 RMY-RM-308 uCi/sec RW/ARW HIGH 1.0E-2 1.00E-03 1.00E-03 1.00E-03 RMP RM 251A mR/hr MAIN STEAM LINE (CH. A 142) 3.0E+2 1.00E+00 1.00E+00 1.00E+00 RMP-RM-2518 mR/hr MAIN STEAM LINE (CH. 8 112) 3.0E+2 1.00E+00 1.00E+00 1.00E+00 RMP-RM-251C mR/hr MAIN STEAM LINE (CH. A 1&2) 3.0E+2 1.00E+00 1.00E+00 1.00E+00 RMP-RM-251D W/hr MAIN STEAM LINE (CH. 8 1 52) 3.0E+2 1.00E+00 1.00E+00 1.00E+00 RMV-RM-150 mR/hr SJAE OFF GAS LOG RAD A&B 3.CE+1 9.56E-01 9.56E-01 9.56E-01 RMP-RM-452 M/hr RX. BLDG. VENT IND/ TRIP A&B 6.0E 1 6.68E-01 6.68E-01 6.68E-01 LEGE ND:

• Migh Alarm ** Migh-High Alarm Process amtArea Radiation Modtors 9-14 G:16669.93EM4DMONES

COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS DRILL RADIATION MONITOR DATA REAL TIME 08:00 ELAPSED TIME 00/00 Monitor # Units Monitor Location 100 % Power Current 1 mR/hr RX BLDG FUEL POOL (SE STH) 1.54E + 0 2 2.15E + 02 2 mR/hr RX BLDG FUEL POOL (SE STH) 1.50E + 00 1.98E + 00 3 mR/hr RX BLDG NEW FUEL (SE STH) 3.00E-02 5.02E-02 4 mR/hr RX BLDG RWCU DEMIN (SW 3RD) 1.35E + 01 1.15E + 01 5 mR/hr RX BLDG SLUDGE / DECANT (S 2ND) 8.00E-01 1.20E + 00 6 mR/hr Rx BLOG NEUTRON SYS/INDEX (TIP ROOM) 1.64E + 02 2.85E + 01 7 mR/hr RX BLDG NEUTRON DRV/ MECH (SE 1ST) 1.80E + 00 1.8 6E + 00 8 mR/hr RX BLDG SOUTH HCU/CRD AREA (S 1ST) 9.00E-01 9.50E-01 9 mR/hr RX BLDG NORTH HCU/CRD AREA (N IST) 9.00E + 00 5.19 E + 00 10 mR/hr RX BLDG HPCI PUMP ROOM (SW CUAD) 3.00E-01 5.70E-01 11 mR/hr RX BLDG RHR PUMP ROOM (SW QUAD) 5.50E + 00 4.77E + 00 12 mR/hr RX BLDG RHR PUMP ROOM (NW QUAD) 2.40E + 01 1.79 E + 01 13 mR/hr RX BLDG RCIC/CS PUMP ROOM (NE QUAD) 1.80E + 00 2.56E + 00 14 mR/hr RX BLDG CS PUMP ROOM 95E QUAD) 4.50E + 00 2.57E + 00 15 mR/hr TB TURB1NE FRONT STANDARD 1.31 E + 02 1.40E + 02 16 mR/hr TB TURBINE MEZZ. CONTROL CORRIDOR 1.70E-01 1.19 E-01 17 mR/hr TB TURBINE BASEMENT CORRIDOR 5.00E-02 6.18E-02 mR/hr TB REACTOR FEEDPUMP ROOM 1.08 E + 01 18 6.00E + 00_

19 mR/hr TD CONDENSATE PUMP AREA 1.20E-01 1.11 E-01 20 mR/hr MAIN CONTROL ROOM 2.00E-02 4.80E-02 21 mR/hr 903* REACTOR CORRIDOR 1.90E-01 2.49E-01 22 mR/br RADWASTE CONTROL ROOM 2.00E-02 1.99 E-02 23 mR/hr RADWASTE PUMP ROOM 5.30E + 00 5.06E + 00 24 mR/hr RADWASTE BASEMENT EQUIP. AREA 4.10E + 00 3.06E + 00 25 mR/hr RADWASTE DEMIN VALVE ROOM 1.20E + 00 1.90E + 00 26 mR/hr RADWASTE CONVEYOR AISLE 2.00E-01 3.09 E-01 28 mR/hr RADWASTE LAB 2.00E-01 2.10E-01 29 mR/hr CENTRIFUGE-NORTH 1.00E + 01 1.56E + 01 30 mR/hr CENTRIFUGE-SOUTH 1.00E + 01 2.06E + 01 RMA-RM-40A R/hr CONTAINMENT HIGH RANGE (DRYWELL) 7.00E + 00 1.57E + 02 RMA-RM-40B R/hr CONTAINMENT HIGH RANGE (DRYWELL) 1.20E + 01 1.05E + 01 Procese:

RMV-RM-40 uCi/sec RX BLDG VENT EFFLUENT 1.00E-03 1.95E-01 RMP-RM3 A uCi/sec ERP STACK NORMAL 5.50E-01 9.15E-01 RMP-RM-3B uri/sec ERP STACK HIGH 1.00E-02 1.00E-02 RMV RM20A uCi/sec TB VENT EFFLUENT 1.50E-03 1.38E + 01 RMV-RM-20B uCi/see TB VENT HIGH 1.00E-02 9.58E + 01 RMV-RM30A uCi/sec RW/ARW COMBINED EFFLUENT 1.20E-03 7.65E-01 RMV-RM-308 uCi/see RW/ARW HIGH 1.00E-02 9.58E + 01 RMP-RM251 A mR/hr MAIN STEAM UNE (CH. A 1&2) 3.00E + 02 5.20E + 02 RMP-RM-251 B mR/hr MAIN STE AM UNE (CH. B 1&2) 3.00E + 02 5.20E + 02 RMP-RM251 C . mR/hr MAIN STEAM UNE (CH. A 1&2) 3.00E + 02 5 41 E + 02 RMP-RM-251 D mR/hr MAIN STEAM UNE (CH. B 1 &2) 3.00E + 02 4.62E + 02 RMV-RM150 mR/hr $JAE OFF GAS LOG RAD A&B 3.00E + 01 1.57E + 01 RMP-RM-452 mR/hr RX. BLDG. VENT IND/ TRIP A&B 6.00E-01 5.06E-01 l! LILT"L4 Hi0h Alarm ** Offscale Alarm Rad >at onMonnor}landout  %)5 G:16660\93E1MRMSRS

K-I b

t k

f i

I SECTION 9.3  ;

IN-PLANT RADIATION AND CONTAMINATION MAPS

)

l i

i e

i l

I

'I

~l

{

. . ,1

REACTOR BUILDING 903' E. ELEVATION (FIRST FLOOR)

Reactor Building 903' E A w~ ~ N

o. mm -

1 11 1

- ~

.. e. 1 l l -

F o. o+ -

B LJ l O 9 aaovere motus a 81=. i

C g*  : D ca n "

r i i C o, E o. [gg i Il I

[_] _

I

~

II

~

I r=

g

~ w I m a. _

1. DOSE RATE INFORMATION TIME mR/hr UNLESS NOTED GENERAL HRS A B C D E F NOTES 800 10 12 3 45 3 8 1100 9 12 3 45 3 8 1115 125 156 107 1003 105 104 1200 128 158 107 1002 105 105 1300 126 158 107 1001 105 105 1400 128 158 107 1002 105 105

2. AIRBORNE CONCENTRATIONS AND CONTAMINATION LEVELS TIME GAS IODINE PARTIC. CONTAMINATION GENERAL HRS UCl/cc uCilee uCi/cc LEVELS IN CPM NOTES 800 As Reed As Reed As Reed As Reed 1015 2.77 E-09 As Reed As Reed As Reed 1115 4.87E-08 As Reed As Road As Reed 1130 1.05E-07 As Reed As Reed As Reed 1200 1.05E-07 As Reed As Reed As Reed 1400 1.05E-07 As Reed As Reed As Reed ,

IPMAP.XLS\ EXERCISE 9-17 REV, 6/3/93

REACTOR @UILDING ,

903' W. ELEVATION (FIRST FLOOR)

LOCATION: RX 903 W g N

I FTAut3 l g I

A 5 O I i F g A ilA JO 3 p O 5

38 nitama. v4Lvsmoems E

O 1 i C

mAu= 4== g D _

sT4nts I l

I i

1. DOSE RATE INFORMATION TIME mR/hr UNLESS NOTED

' GENERAL HRS A B C D E F NOTES 800 2 2 1.9 1.8 2.16 1 1100_ 2 2 1.9 1.8 2.16 1 111b 76 86 3.7 3.6 4.32 23 1200 76 86 3.8 3.7 4.44 23 '

1300 76 86 3.8 3.7 4.44 23 1400 76 86 3.8 3.7 4.44 23 '

2. AIRBORNE CONCENTRATIONS AND CONTAMINATION LEVELS TIME GAS 10 DINE l PARTIC. CONTAMINATION GENERAL HRS uCl/cc UCi/cc '

uCi/ec LEVELS IN CPM NOTES 800 As Reed As Reed As Reed As Reed 1100 As Reed As Reed As Reed 'As Reed j 1115 i As Reed As Reed As Reed As Reed 1200 As Reed As Reed As Reed As Reed 1300 As Reed As Reed As Reed As Reed 14Gs As Reed As Reed As Reed As Reed i I

IPMAP.XLS\ EXERCISE 9-18 REV. 6/3/93 i

I REACTOR BUILDING l 931' ELEVATION l (SECOND FLOOR) l 1

LOCATION: RX931 1 N

d STMK3 l l o O '

^ 0000 o

• I I

< i i O F

l lr -

t__.

~

9 / [ f k

l -

E

• , c E

sTuus l

<O - lIb ms= ws aaan ..

."% SPILL AREA

, !!! O(~h

1. DOSE RATE INFORMATION TIME mR/hr UNLESS NOTED GENERAL HRS A B C D E F NOTES 800 1 1 3 1 1 1 815 8 13 200 1000 850 130 resin spill 900 8 13 200 1000 850 130 1115 11 14 200 1000 850 130 1200 11 14 200 1000 850 130 1400 11 14 200 1000 850 130

2. AIRBORNE CONCENTRATIONS AND CONTAMINATION LEVELS TIME GAS LODINE PARTIC. CONTAMINATION GENERAL HRS uCl/cc uCl/ce uCi/ec LE_VELS IN CPM NOTES 800 As Reed As Reed As Reed As Reed 815 As Reed As Reed As Reed 1.00E + 06 900 As Reed As Reed As Reed 1.00E + 06 1115 As Reed As Reed As Reed 1.00E + 06 1200 As Reed As Reed As Reed 1.00E + 06 1400 As Reed As Reed As Reed 1.00E + 06 IPMAP.XLS\EXERCtSE 9-19 REV. 6/3/93

REACTOR BUILDING 958' ELEVATION (THIRD FLOOR) 14CADON: RX 958'

[

N l stAms l r-9 F A L n i

S 9

S 9 E -

l 9

O 5

LJ B

dC

_ e -

l stAms j 9 1

l _

1. DOSE RATE INFORMATION TIME mR/hr UNLESS NOTED GENERAL HRS A B C D E F NOTES 800 1 1 11 6 3 1 815 1 1 99 50 30 1 900 1 1 100 50 30 1 1115 6 8 110 55 33 6 1200 6 8 110 55 33 6 1400 8 8 110 55 33 6

2. AIRBORNE CONCENTRATIONS AND CONTAMINATION LEVELS TIME GAS LODINE PARTIC. CONTAMINATION GENERAL HRS uCl/ce uCi/ce uC1/ce LEVELS IN CPM NOTES

• 800 As Reed As Reed As Reed As Reed 815 As Reed As Reed As Reed As Reed 900 As Reed As Reed As Reed As Reed 1115 As Reed As Reed As Reed As Reed 1,'!OO As Reed As Reed As Reed As Reed

_'400 As Reed As Reed As Reed As Reed IPMAP,XLS\ EXERCISE 9 20 REV. 6/3/93 4

REACTOR BUILDING 976* ELEVATION (FOURTH FLOOR)

~

LOCATION: RX 976' MONTHLY A N

l nuas lr'l -

I I .

O F 00 E

__ _ A 7

J -

D C B!

I nuns 1 -- - l l l lt

1. DOSE RATE INFORMATION TIME mR/hr UNLESS NOTED GENERAL HRS A B C D E F NOTES 1 800 As Reed As Reed As Reed As Reed As Reed As Reed 1100 As Reed As Reed As Reed As Reed As Reed As Reed 111S As Reed As Reed As Reed As Reed As Reed As Reed 1200 As Reed As Reed As Reed As Reed As Reed As Reed 1300 As Reed As Reed As Reed As Reed As Reed As Reed 1400 As Reed As Reed As Reed As Reed As Reed As Reed

2. AIRBORNE CONCENTRATIONS AND CONTAMINATION 11VELS TIME GAS IODINE PARTIC. CONTAMINATION GENERAL HRS uCi/cc uCi/cc uCl/cc LEVELS IN CPM NOTES 800 As Reed As Reed As Reed As Reed 1100 As Reed As Reed As Reed As Reed 1115 As Reed As Reed As Reed As Reed 1200 As Reed As Reed As Reed As Reed 1300 As Reed As Reed As Reed As Reed 1400 As Reed As Reed As Reed As Reed ,

l IPMAP,XLS\ EXERCISE 9-21 REV. 6/3/93 l 2

-l

REACTOR BUILDING 1001' ELEVATION (FIFTH FLOOR)

LOCATION: RX 1001' MONTHLY A N

2 R A o D F g 7

/

1 O ,

i 0

2 B '

marus 2

E

/ _

g -

C -

D -

1. DOSE RATE INFORMATION TIME mR/hr UNLESS NOTED GENERAL HRS A B C D E F NOTES 800 As Road As Reed As Reed As Reed As Reed As Reed 1100 As Reed As Reed As Reed As Reed As Reed As Reed 1115 As Reed 7 5 4 5 As Reed 1200 As Reed 7 5 4 5 As Reed 1300 As Reed 7 5 4 5 As Reed r 1400 As Reed 7 5 4 5 As Reed

2. AIRBORNE CONCENTRATIONS AND CONTAMINATION LEVELS TIME GAS IODINE PARTIC. CONTAMINATION GENERAL HRS uCi/cc uCi/cc uCi/cc LEVELS IN CPM NOTES 800 As Reed As Reed As Reed As Reed 1100 As Reed As Reed As Reed As Reed 1115- As Reed As Reed As Reed As Ree:S 1200 As Reed As Reed As Reed As Reed 1300 As Reed As Reed As Reed As Reed 1400 As Reed As Reed As Reed As Reed i

I IPMAP.XLS\ EXERCISE 9 22 REV. 6/3/93 I

i

]

CONTROL ROOM C32' ELEVATION l

LOCATION: 932' CONTROL BLDO (MONTHLY)

A N ,

~ ~

I CONTROL 5AS ROOM COMPUIER l

ROOM I

/ <

A l t nav C F l I

• " I y STADL3 l_

i i 5

E -

REST RITCHEN BREAK ROOM AREA STAIR $

D i

l

1. DOSE RATE INFORMATION TIME mR/hr UNLESS NOTED GENERAL HRS A B C D E F NOTES 800 As Reed As Reed As Reed As Reed As Reed As Reed 1100 As Reed As Reed As Reed As Hood As Reed As Reed 1115 As Reed As Reed As Reed As Road As Reed As Reed 1200 As Reed As Reed As Reed As Reed As Reed As Reed 1300 As Reed As Reed As Reed As Reed As Reed As Reed 1400 As Reed As Reed As Reed As Reed As Reed As Reed

2. AIRBORNE CONCENTRATIONS AND CONTAMINATION LEVELS TIME GAS LODINE PARTIC. CONTAMINATION GENERAL HRS UCi/cc UCl/cc uCi/cc LEVELS IN CPM NOTES 800 As Reed As Road As Reed As Reed 1100 As Reed As Reed As Reed As Reed 1115 As Reed As Reed As Reed As Reed 1200 As Reed As Reed As Reed As Reed 1300 As Reed As Reed As Reed As Reed 1400 As Reed As Reed As Reed As Reed l

IPMAP.XLS\ EXERCISE S-23 REV. 6/3/93 4

_ ___ m_..

CONTROL CORRIDOR AREA I 903-918' ELEVATION LOCATION: 903 - 918 CONTROL CORRIDOR canz2 EXFAN5 ION ROOM N l 918' i .rms l

A I -

)

i -

t u i i 1

]

O oju u i g o

% B nm [ 0 o n i 101 RW BLDG.

. - l l

c 15 l AI H 5 i T!FtPTTE ATOR RDOM i 1 I i i a RCA ACCES$

Naaa0 F D g d

CLOTHING SIOHAGE g

=

903' o

1. DOSE RATE INFORMATION TIME mR/hr UNLESS NOTED GENERAL HRS A B C D E F NOTES 800 As Reed As Reed As Reed As Reed As Reed As Reed 1100 As Reed As Reed As Reed As Reed As Reed As Reed 1115 As Reed As Reed As Reed As Reed As Reed As Reed 1200 As Reed As Reed As Reed As Reed As Reed As Reed 1300 As Reed As Reed As Reed As Reed As Reed As Reed 1400 As Reed As Reed As Reed As Reed As Reed As Reed

2. AIRBORNE CONCENTRATIONS AND CONTAMINATION LEVELS TIME GAS IODINE PARTIC. CONTAMINATION GENERAL HRS UCi/cc uCi/cc uCuce t.EVELS IN CPM NOTES ,

800 As Reed As Reed As Reed As Reed 1100 As Reed As Reed As Reed As Reed 1115 As Reed As Reed As Reed As Reed 1200 As Reed As Reed As Reed As Reed 1300 As Reed As Reed As Reed As Reed 1400 As Reed As Reed As Reed As Reed IPMAP.XLS\ EXERCISE 9-24 REV. 6/3/93

REACTOR BUILDING C59' Et.EVATION OUADS A

LOCATION: ft57' RX BLDG QUADS y 5Tm1l ' ,= = .,

j F l

= - ,

~

A

's L NORTHWEST NORTHEAST Y O -

SOUTHWEST SOUTHEAST g

& L B

E ia

n C D -

sTa8l lLl g% #""

?

1. DOSE RATE INFORMATION )

TIME mR/hr UNLESS NOTED GENERAL HRS A B C D E F NOTES 800 3 2 3 8 8 8 [

1100 3 2 3 8 8 8 ,

1115 130 124 127 100 100 100 l 1200 130 124 127 100 100 100 1300 130 124 127 100 100 100 1400 130 124 127 100 100 100 5

2. AIRBORNE CONCDfTRATIONS AND COP (TAMINATION LEVELS TIME GAS IODINE PARTIC, CONTAMINATION GENERAL HR$ uCl/cc uCi/cc uCi/cc LEVELS IN CPM NOTES 800 As Reed As Reed As Reed As Reed ,

1100 As Reed As Reed As Reed As Reed 1115 As Reed As Reed As Reed As Reed 1200 As Reed As Reed As Reed As Reed 1300 As Reed As Reed As Reed As Reed l 1400 As Reed As Reed As Reed As Reed 1

IPMAP.XLS\ EXERCISE 9-25 REV 8/3/93 l b

e

REACTOR CUILDING 881* ELEVATION OUADS LOCATION: art'ItX BLDG QUADS N

STADis l I

F -

A l

1 mac i

^

v E NORTIIMT.ST NORTIIEAST O

6 astn

N N D SOUIHWEST SOUTHEAST g a

b lmbel h STOS C -- '

l .,.I

1. DOSE RATE INFORMATION TIME mR/hr UNLESS NOTED GENERAL HRS A B C D E F NOTES BM 2 1 2 4 4 4 i 1100 2 1 2 4 4 4

'~

1115 65 62 64 50 50 50 1200 65 62 64 50 50 50 1300 65 62 64 50 50 50 140') 65 62 64 50 50 50

2. AIRBORNE CONCENTRATIONS AND CONTAMINATION LEVELS TIME GAS IODINE PARTIC. CONTAM N ATION GENERAL HRS uCi/cc uCi/cc uCUce LEVELS IN CPM NOTES 800 As Reed As Reed As Reed As Reed 1100 As Reed As Read As Reed As Reed 1115 As Reed As Reed As Reed As Reed 1200 As Read As Read As Read As Road 1300 As Road As Reed As Read As Road 1400 As Reed As Reed As Read As Reed t

IPMAP.XLS\ EXERCISE 9-26 REV. 613/93 -

l

REACTOR QUILDING  !

HPCI ROOM LOCATION: H.P.CJ. ROOM -

A  :

N '

100 DISCliAAGr, F " .j us tr (munrAo l

[ '

nratursn

[ A _

~

se i

i C.

>: g e

nc 5

9 J_

B  !

D C E-l

1. DOSE RATE INFORMATION TIME mR/hr UNLESS NOTED GENERAL HRS A B C D E F NOTES 800 1 1 1 1 1 1 I 1100 1 1 1 1 1 1 1115 23 25 21 25 23 23 1200 23 25 21 25 23 23 [

1300 23 25 21 25 23 23 1400 23 25 21 25 23 23 4

2. AIRBORNE CONCENTRATIONS AND CONTAMINATION (EVELS TIME GAS IODINE PARTIC. CONTAMINATION GENERAL HRS UCi/cc uCi/cc uCi/cc LEVEL.S IN CPM NOTES 800 As Reed As Reed As Reed As Read 1100 As Reed As Reed As Road As Reed 1115 As Reed As Reed As Reed As Reed 1200 As Reed As Road As Road As Reed 1300 As Reed As Read As Road As Road I 1400 As Reed As Read As Reed As Reed ,

t IPMAP.XLSEXERCISE 9-27 REV. 6/3/93 i

I

TURBINE CUILDING BASEMENT LOCATION: TG BASEMENT A N ,

a e e

• w U TEC HX ()

~

A

! i +o I_f I

J e OI n rei m te n

n U

I-

- e 0 e e

{ q - -

~

w a i O O e 8

• O O m D c' '"

• O O F E "

O O t] D -

r j eo i I J e D dd eo b" i c e i

w I i

1. DOSE RATE INFORMATION TIME mR/hr UNLESS NOTED GENERAL HRS As Reed B C D E F NOTES 800 As Read As Reed As Reed As Road As Read As Reed '

1100 As Reed As Reed As Reed As Reed As Reed As Reed 1115 As Reed As Reed As Reed As Reed As Reed As Reed 1200 As Reed As Reed As Read As Reed As Reed As Reed 1300 As Read As Reed As Reed As Read As Reed As Reed 1AOO As Road As Reed As Read As Reed As Reed As Road

2. AIRBORNE CONCENTRATIONS AND CONTAMINATION LEVELS TIME GAS IODINE PARTIC. CONTAMINATION GENERAL HRS uCi/cc uCi/cc uCi/cc LEVELS IN CPM NOTES 800 As Reed As Reed As Reed As Reed j 1100 As Reed As Road As Read As Read l

1115 As Reed As Reed As Reed As Reed 1 1200 As Reed As Reed As Reed As Reed 1300 As Reed As Reed As Reed As Reed 1400 As Reed As Reed As Read As Reed I

1 IPMAP.XLS\ EXERCISE 9-28 REV. 6/3/93 i

l I

- 1 I

TURBINE BUILDING 903-909' ELEVATION A

LOCATION: TG M3 - M N N

• A 0 e n _o o -

lF g , g g7 I em 3

~~

$ h 2 o a a

• m 3

• EO -

o P , , "I ,i 4

0 t carssott o .I I I I dl CORAIDOs 'y' O'M ( conDmsen B o

O } 40 w , w C )

a ,~

O ' ' '

2 *

" 0 Ob~ ~

0

• Mnmni ~

O 1571Ili3 o _

0.

O o *c =

Cm

• o a i -

as h( 0 o N

sam::E 6

1. DOSE RATE INFORMATION TIME mR/hr UNLESS NOTED GENERAL HRS A B C D E F NOTES 800 As Reed As Road As Read As Read As Reed As Reed 1100 As Reed As Read As Reed As Reed As Reed As Reed 1115 As Read As Reed As Road As Read As Raad As Read 1200 As Reed As Road As Read As Road As Read As Road 1300 As Reed As Reed As Reed As Read As Reed As Reed 1400 As Read As Reed As Read As Reed As Reed As Reed

2. AIRBORNE CONCENTRATIONS AND CONTAMINATION LEVELS TIME GAS IODINE PARTIC. CONTAMINATION GENERAL HRS UCi/cc uCi/cc uCi/cc LEVELS IN CPM NOTES j 800 As Reed As Reed As Reed As Road i 1100 As Reed As Road As Read As Road i 1115 As Reed As Reed As Read As Read l 1200 As Read As Reed As Road As Reed l

1300 As Road As Reed As Reed As Reed i 1400 As Read As Reed As Read As Road l I

I IPMAP,XLS\ EXERCISE 9-29 REV. 6/3/93 l

TURBINE BUILDING 932' ELEVATION '

LOCATION: TG 932

~

1 N .

sun-----e isTAlas) l l I

CRANI stas to sor_ comysL HA1CM jF A i' IAC =

so -

,,,,)

F Fl  ;

= *O* c j

<o  ?

c - C

~

m +c f _

C 'C U g b ET AJR$ j L

' ~

C l, C

pg_ - -

~ -- .

E isTA1Asl ia C 4e

• o g m-918' - / t T. -E D .o i CRANE HATCM

1. DOCE RATE INFORMATION f T1ME - mR/hr ('NLESS NOTED GENERAL -[

HRS A B C D E F NOTES .;

800 141 141 141 141 141 141 1020 2 2 2 2 2 2 '

1115 1050 1050 1050 1050 1050 1050 l 1200 1050 1050 1050 1050 1050 1050 j j 1215 7 7 7 7 7 7 1400 7 7 7 7 7 7

2. AIRBORNE CONCENTRATIONS AND CONTAMINATION LEVELS l TIME GAS BODINE PARTIC. CONTAMINATION GENERAL HRS uCi/cc uCl/cc uCi/cc LEVFLS IN CPM NOTES 800 As Reed As Reed As Reed As Road 1020 1,23E.10 As Reed As Reed As Reed 3

1115 1.14E-06 As Reed As Reed As Reed 1200 1.10E-07 As Reed As Reed As Reed 1215 7.34E-10 As Reed As Reed As Reed 1400 7.35E-10 As Reed As Reed As Reed i

j W

l l

k IPMAP.XLS\ EXERCISE 9-30 REV. 6/3/93 i

0 Section 10 AETEOROLOGICAL AND RADIOLOGICAL RELEASE h

i 9

e

i i

i

10. METEOROLOGICAL AND RADIOLOGICAL RELEASE i i

This section provides radiological release information, meteorological data, and on-site and l off-site field data for the duration of the scenario. This information will allow participants to I evaluate the magnitude of the radioactive release and respond accordingly. j 10.1 Radiological Release Information This information is a graphical representation of the noble gas and iodine release rate for the duration of the scenario. It is included for informational purposes only, and is not to be provided to players during the exercise.

10.2 Meteorological Summary and Data Sheets ,

l This section contains a weather forecast and meteorological data summary table containing all information required for dose projection during the .

scenario. Meteorological information will be provided to players via individual data sheets for each time period. One sample of these sheets is i provided following the summary table. ,

10.3 On-Site Field data and Maps This section contains field radiological survey (dose rates, count rates for iodine and particulate samples ) data for areas outside the plant, out to the site boundary. Information is presented for several locations referenced to a site  ;

map versus time.

l i

10.4 Off-Site Field data and Maps This section contains field radiological survey (dose rates, count rates for iodine and particulate samples ) data for areas outside the site boundary, to the 10 -mile EPZ boundary. Individual maps are presented for each time period, showing the locadon of the plume during that period, along with a table of sample data by location within the plume.

i Me:eorologicaVRelease Material Page 10-1 c:v,660t93Entcn-n.wes }

i l

b b

P 1

i e

i t

i i

SECTION 10.1 RADIOLOGICAL RELEASE INFORMATION I

1 l

l

.i i

I l

I i

I

O i d ,

(oss/gon) outpoi geto1 N aaaaaaaaa8 8

• +

a o$& 8 aoo$ceo 8 8 vi 4 4 6 n N N o a en 8-8 8 o

8 8 8 c;,

00'F L ~ 3 OG:CL O

OP:CL rk ,

0C:06 m l 03:CL $

01:C1 b 3

00:C1 y

.,***, -Oszs

., 0*zt

'.. OCzs  :

azs 0&zt 0021 x, g - Os:n Cm E 0*:16 hb -

o DC*ll 4 ,g g' .E .,

0 : 51 wX rp -

- og:gg

• W

<c m

% Mit  !'

'w e Os:06

• m F e m Ot:06 p E 6- . -

$3 g ,< f

_ DCVI 0:05

[h _8 f.. 0141 Om CD S9 00:06 O** 3 E 09:6 '

'O m

$" 3 2 . pp:6 E

3o w g g DC:6

. - 036 l 01:6

00:e 09'8 OP:9  !

OC:9 038 06:9 g .

00:9  %

- 09:4 E -

OP:L h >

- - OC L g 8 8 8 8 8* 8 8 a 8

8 8 $

8 8

4' s m ,8 n N a e 8 (oss/ ton) sen siqoN 18101 8e

$e '

t 4

e

'l i

t V

SECTION 10.2 METEOROLOGICAL

SUMMARY

AND DATA SHEETS .

i I

i E

9 F

3 4

?

t t

COOPER NL .AR STATION METEOROLOGICAL DATA

SUMMARY

SilEET Wind Direction Wind Speed Temperature Scenario (from, degrees) (mph) ( F) ( C)

Time 100m 60 m 10 m 100m 60 m 10 m 100m 60 m 10 m 100m 60 m to m 8:00 240 242 240 5.2 5.1 4.8 73.7 75.0 75.9 23.2 23.9 24.4 8:15 241 243 242 5.1 5.1 4.9 73.9 75.2 76.2 23.3 24.0 24.6 8:30 240 242 240 5.5 5.2 4.9 74.5 75.7 76.7 23.6 24.3 24.8 8:45 241 243 242 5.4 5.3 5.2 74.9 75.9 76.8 23.8 24.4 24.9 9:00 243 245 243 5.5 5.5 5.2 75.3 76.2 77.2 24.1 24.6 25.1 9:15 244 244 243 5.6 5.3 5.2 75.5 76.5 77.5 24.2 24.7 25.3 9:30 245 244 244 5.4 5.4 5.4 75.8 77.2 78.2 24.3 25.1 25.7 9:45 243 245 243 5.3 5.3 5.1 76.0 77.5 78.6 24.4 25.3 25.9 10:00 244 244 243 5.5 5.4 5.3 76.7 77.7 78.7 24.8 25.4 25.9 10:15 246 245 246 5.6 5.4 5.2 76.5 78.0 78.9 24.7 25.6 26.1 10:30 247 249 248 5.5 5.3 5.2 76.8 78.4 79.4 24.9 25.8 26.3 10:45 250 251 249 5.5 - 5.2 5.1 78.3 79.3 80.3 25.7 26.3 26.8 11:00 251 250 252 5.4 5.2 5.2 78.5 79.5 80.4 25.8 26.4 26.9 11:15 250 252 251 5.5 5.2 5.0 78.5 79.9 80.9 25.8 26.6 27.2 11:30 251 250 252 5.3 5.2 5.I 79.I 80.7 81.7 26.2 27.0 27.6 11:45 253 252 251 5.5 5.3 5.2 79.6 80.7 81.6 26.4 27.1 27.6 12:00 251 250 252 5.6 5.4 5.4 80.0 81.6 82.6 26.7 27.5 28.I 12:15 252 250 251 5.6 5.6 5.4 80.4 81.9 82.9 26.9 27.7 28.3 12:30 250 251 252 5.5 5.4 5.3 81.0 82.5 83.4 27.2 28.0 28.5 12:45 252 253 251 5.6 5.5 5.2 81.5 82.9 83.8 27.5 28.3 28.8 13:00 250 251 252 5.5 5.4 5.3 81.7 83.3 84.3 27.6 28.5 29.1 13:15 252 250 252 5.6 5.5 5.2 81.9 83.5 84.5 27.7 28.6 29.2 13:30 250 251 253 5.6 5.6 5.7 83.0 84.2 85.1 28.3 29.0 29.5 13:45 251 252 251 5.7 5.7 5.6 83.1 84.8 85.7 28.4 29.3 29.8 14:00 253 252 254 5.6 5.7 5.5 85.0 86.0 86.9 29.4 30.0 30.5 Legend: 100m = 100 meters 60m = 60 meters 10m = 10 meters mph = Miles per Hour CF)= Degrees Fahrenheit fC)= Degrees Celsius 1993 Exercisc 10 - 5 August 17 1993

COOPER NUs ,AR STATION METEOROLOGICAL DATA

SUMMARY

SHEET Temperature DilTerence ('C) Stability Class Scenario AT Time 100m 60 m 10 m 100m 60 m 10 m DPT (* C) 8:00 -1.22 -0.72 -0.50 D D D 22.39 8:15 -1.29 -0.74 -0.54 D D D 22.36 8:30 -1.20 -0.64 -0.56 D D D 22.53 8:45 -1.08 -0.58 -0.50 D D D 22.59 9:00 -1.06 -0.50 -0.55 D D D 23.11 9:15 -1.11 -0.58 -0.54 D D D 23.18 9:30 -1.33 -0.78 -0.55 D D D 22.87 9:45 -1.44 -0.86 -0.59 D D D 23.69 10:00 -1.11 -0.53 -0.58 D D D 23.34 10:15 -1.33 -0.84 -0.50 D D D 23.06 10:30 -1.44 -0.90 -0.54 D D D 23.63 10:45 -1.11 -0.55 -0.56 D D D 24.43 11:00 -1.06 -0.56 -0.50 D D D 24.79 11:15 -1.33 -0.76 -0.57 D D D 24.47 11:30 -1.44 -0.88 -0.57 D D D 25.41 11:45 -1.11 -0.61 -0.50 D D D 24.95 12:00 -1.44 -0.86 -0.58 D D D 25.61 12:15 -1.39 -0.86 -0.53 D D D 26.18 12:30 -1,32 -0.82 -0.50 D D D 25.94 12:45 -1.28 -0.76 -0.52 D D D 26.08 13:00 -1.44 -0.90 -0.54 D D D 26.76 13:15 -1.44 -0.90 -0.54 D D D 26.77 13:30 -1.17 -0.67 -0.50 D D D 26.80 13:45 -1.44 -0.93 -0.52 D D D 27.13 14:00 -1.06 -0.56 -0.50 D D D 28.40 Legend: cc)= Degrees Celsius 100m = 100 meters 60m = 60 meters 10m = 10 meters 1993 Exercise 10 - 6 August 171993

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

COOPER NUCLEAR STATION EXERCISE MET DATA SHEET j i

SHEET NO. MET-001 TIME: 8:00 -

TO: DOSE ASSESSMENT PERSONNEL FROM: CONTROLLER T: 00:00 ,

TIUS IS A DRILL 1 Wind Direction (Deg. From) 100 meter 240 l 60 meter 242 q 10 meter 240 .;

1 Wm' d Speed (mph) 100 meter 5.20470918  ;

60 meter 5.1 l 10 meter 4.81921399  !

Temperature (Deg. F)  !

100 meter 74  :

60 meter 75 - ,

10 meter 76- 9 Temperature (Deg. C) 100 meter 23.2 I 60 meter 23.9 -

10 meter 24.4 l Delta T (Deg. C) j

- 100 meter -1.22 60 meter -0.72 10 meter -0.50  ;

THIS IS A DRILL  !

i 1

1993 Exercise 10-7 August 17,1993

-(

+

1 i

l i

l I

i 1

ii SECTION 10.3 ON-SITE FIELD DATA AND MAP r

r s

I i

)

s b

ON-SITE INSTRUMENT READINGS TIME: 8:00- 11:15 Survey Meter Air Samples Air Samples lodine Smears 3 feet 3 inches E-140-N / pancake RO-2 Calc.

Plume W.O. W.C. W.O. W.C. Cartridge Filter Cartridge Filter Location (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR./hr) (mR/hr) (uCi/cc) (cpm)

All as read as read as read as read as read as read as read as read < MDA as read 1

Notes: The plume has not touched down, therefore, all measurements are as a result of shine.

" Radiological Measurements not incorporated in this section should be given as read.

Abbreviations:

a. LMD = Less than Minimum Detectable c. W.O. = Window Open

b. CPM = Counts per Minute d. W.C. = Window Closed

+

On-Site Data andMaps 10-9 G:\6660\93EAV10NENil73

~ . Y!* + ~. V~ h N ' 5 3'.2lh i ,

~ W~ :$'Q+!? .

i ':h,!'*

'>Qlf Yd 4% , '

N';[4f.p,jg,l5l&

~

O '

..r ,

u;o(

(s$

% \'

puse7,l

%Y s

.\'

?.

, q 04o i ~ '

93 gg.

7 .gg9 i ,

~.

y ;a r e 4 '

y /'

4w i

D

/

~ $ -

yi ,

- /

e, /  :

,, / .4 k

,,  % /

/

v l'

' /

/ / f e

/

/

% i &y h

/

boy 00

\

E

% N N N N N D %o, N N N N N gp

/

\-

ON-SITE INSTRUMENT READINGS TIME: 11:15- 11:30 Survey Meter Air Samples Air Samples lodine Smears 3 feet 3 inches E-140-N / pancake RO-2 Calc.

Plume W.O. W.C. W.O. W.C. Cartridge Filter Cartridge Filter Location (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR./hr) (mR/hr) (uCi/cc) (cpm) -

A. (Centerline) 10.0 10.0 12.0 12.0 1.3 4.8 0.5 1.2 1.48E-06 as read (Off Centerline) 1.0 1.0 1,2 1.2 0.1 0.5 as read 0.1 1.48E-07 as read Notes: The plume has not touched down, therefore, all measurements are as a result of shine.

• • Radiological Measurements not incorporated in this section should be given as read.

Abbreviations:

a. LMD = Less than Minimum Detectable c. W.O. = Window Open

b. CPM = Counts per Minute d. W.C. = Window Closed On-Site Data andMaps 10-11 G:\6660\93EAM?XONEll!XLS

. \k\

g s

agb,mb h

\ -

• tINT

~.

'gfs -

- /

y[(,khykfh 6\ ;.- .'-

Y J/;Nh'[h

' v

\\

\'I /

N N F'-

• WY[d Ap Myk . fi b

s

@ $'\- 4y

.k kh2 Mk ' ^

O s .

t * -s

\*

k 04u

x. '

., l

? /

$v s

< 0

/ /

O @

~

90J)

1. 2 8- -I s

/

/[ .

vet RO AD T / '

LE / ,

eb l

>c<

,/"  % ,

T / f I' /

g  % '

, g c

E Q y f o 8

% *' ~

N N N N

's  %

7**ee

ON-SITE INSTRUMENT READINGS TIME: 11:30- 11:45 Survey Meter Air Samples Air Samples lodine j Smears 3 feet 3 inches E-140-N / pancake RO-2 Calc.

Plume W.O. W.C. W.O. W.C. Cartridge Filter Cartridge Filter Location (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR./hr) (mR/hr) (uCi/cc) ' (cpm)

A. (Centerline) 15.7 15.7 18.8 18.8 5.2 18.5 1.8 4.5 5.75E-06 as read (Off Centerline) 1.6 1.6 1.9 1.9 0.5 1.9 0.2 0.5 5.75E-07 as read '

O. (Centerline) 14.5 14.5 17.4 17.4 1.2 4.2 0.4 1.0 1.32E-06 as read (Off Centerline) 1.5 1.5 1.7 1.7 0.1 0.4 as read 0.1 1.32E-07 as read Notes: The plume has not touched down, therefore, all measurements are as a result of shine.

• Radiological Measurements not incorporated in this section should be given as read.

Abbreviations:

a. LMD =' Less than Minimum Detectable c. W.O. = Window Open

b. CPM = Counts per Minute d. W.C. = Window Closed Onsite Data andMaps '10-13 G:\6660Lo3EDEXONEV11'LS

ON-SITE INSTRUMENT READINGS TIME: 11:45- 12:00 Survey Meter Air Samples Air Samples lodine Smears 3 feet 3 inches ' E-140-N / pancake RO-2 Calc. -

Plume W.O. W.C. W.O. W.C. Cartridge Filter Cartridge Filter Location (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR./hr) (mR/hr) (uCi/cc) (cpm)

A. (Centerline) 20.8 20.8 25.0 25.0 8.8 31.5 3.1 7.7 9.77E-06 as read (Off Centerline) 2.1 2.1 2.5 2.5 0.9 3.1 0.3 0.8 9.77E-07 as read B. (Centerline) 19.9 19.9 23.9 23.9 4.6 16.5 1.6 4.0 5.11 E-06 as read (Off Centerline) 2.0 2.0 2.4 2.4 0.5 1.6 0.2 0.4 5.11 E-07 as read Notes: The plume has not touched down, therefore, all measurements are as a result of shine.

" Radiological Measurements not incorporated in this section should be given as read.

Abbreviations:

a. LMD = Less than Minimum Detectable c. W.O. = Window Open  ;

b. CPM = Counts per Minute d. W.C. - Window Closed i

On-Site Data andMaps 10-14 G:\6660\93EXEYONEN1.173

ON-SITE INSTRUMENT READINGS TIME: 12:00- 12:15 Survey Meter Air Samples Air Samples lodine Smears 3 feet 3 inches E-140-N / pancake RO-2 Calc.

Plume W.O. W.C. W.O. W.C. Cartridge Filter Cartridge Filter location (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR./hr) (mR/hr) (uCi/cc) (cpm)

A. (Centerline) 24.0 24.0 28.8 28.8 12.2 43.7 4.3 10.7 1.36E-05 as read (Off Centerline) 2.4 2.4 2.9 2.9 1.2 4.4 0.4 1.1 1.36E-06 as read

8. (Centerline) 23.6 23.6 28.3 28.3 7.8 27.9 2.8 6.8 8.68E-06 as read (Off Centerline) 2.4 2.4 2.8 2.8 0.8 2.8 0.3 0.7 8.68E-07 as read Notes:

• The plume has not touched down, therefore, all measurements are as a result of shine.

• Radiological Measurements not incorporated in this section should be given as read.

Abbreviations:

a. LMD = Less than Minimum Detectable c. W.O. = Window Open

b. CPM = Counts per Minute d. W.C. = Window Closed On-Site Data andMaps 10 15 G:\6660\93EX\EXONEN1.XLS

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

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

ON-SITE INSTRUMENT READINGS TIME: 12:15- 12:30 '

Survey Meter Air Samples Air Samples Iodine Smears 3 feet 3 inches E-140-N / pancake RO-2 Calc.

Plume W.O. W. C. W.O. W.C. Cartridge Filter Cartridge Filter Location (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR./hr) (mR/hr) (uCi/cc) (cpm)

A. (Centerline) 19.9 19.9 23.9 23.9 15.4 55.4 5.5 13.5 1.72E-05 as read (Off Centerline) 2.0 2.0 2.4 2.4 1.5 5.5 0.5 1.4 1.72E-06 as read B. (Centerline) 19.6 19.6 23.5 23.5 10.8 38.8 3.8 9.5 1.21 E-05 as read (Off Centerline) 2.0 2.0 2.4 2.4 1.1 3.9 0.4 0.9 1.21 E-06 as read Notes: Air sample counts assume a sample volume of 10 cubic ft. and counting efficiency of 25

• Radiological Measurements not incorporated in this section should be given as read.

Abbreviations:

a. LMD = Less than Minimum Detectable c. W.O. = Window Open

b. CPM = Counts per Minute d. W.C. = Window Closed Onsite Data andMaps 10-16 G:\6660\93EX\EXONENI.XLS

ON-SITE INSTRUMENT READINGS TIME: 12:30- 12:45 Survey Meter Air Samples Air Samples Iodine Smears 3 feet 3 inches E-140-N / pancake RO-2 Calc.

Plume W.O. W.C. W.O. W.C. Cartridge Filter Cartridge Filter Location (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR./hr) (mR/hr) (uCi/cc) (cpm)

A. (Centerline) 22.6 22.6 27.1 27.1 18.5 66.5 6.6 16.3 2.07E-05 as read (Off Centerline) 2.3 2.3 2.7 2.7 1.8 6.6 0.7 1.6 2.07E-06 as read B. (Centerline) 22.2 22.2 26.6 26.6 13.7 49.2 4.8 12.0 1.53E-05 as read (Off Centerline) 2.2 2.2 2.7 Z.7 1.4 4.9 0.5 1.2 1.53E-06 as read Notes: Air sample counts assume a sample volume of 10 cubic ft. and counting efficiency of 2%.

" Radiological Measurements not incorporated in this section should be given as read.

Abbreviations;

a. LMD = Less than Minimum Detectable c. W.O. = Window Open

b. CPM = Counts per Minute d. W.C. = Window Closed On-Site Data andMaps 10-17 G:\6660\93EX\EYONEN1.X13

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

ON-SITE INSTRUMENT READINGS TIME: 12:45- 13:00 Survey Meter Air Samples Air Samples lodine Smears 3 feet 3 inches E-140-N / pancake RO-2 Cate.

Plume W.O. W.C. W.O. W.C. Cartridge Filter Cartridge Filter Location (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR./hr) (mR/hr) fuCi/cc) (cpm)

A. (Centerline) 25.7 25.7 30.8 30.8 21.4 77.1 7.6 18.9 2.40E-05 as read (Off Centerline) 2.6 2.6 3.1 3.1 2.1 7.7 0.8 1.9 2.40E-06 as read B. (Centerline) 25.3 25.3 30.4 30.4 16.4 59.0 5.8 14.4 1.83E-05 as read (Off Centerline) 2.5 2.5 3.0 3.0 1.6 5.9 - 0.6 1.4 1.83 E-06 as read Notes: Air sample counts assume a sample volume of 10 cubic ft. and counting efficiency of 2%.

Radiological Measurements not incorporated in this section should be given as read.

Abbreviations:

a. LMD = Less than Minimum Detectable c. W.O. - Window Open

b. CPM = Counts per Minute d. W.C. = Window Closed l

On-Site Data andMaps 10-18 G:\6660\93EY\EYONENI.XLS

ON SITE INSTRUMENT READINGS TIME: 13:00- 13:15 Survey Meter Air Samples Air Samples lodine Smears 3 feet 3 inches E-140-N / pancake RO-2 Calc.

Plume W.O. W.C. W.O. W.C. Cartridge Filter Cartridge Filter l Location (mR/hr) (mR/hr) (mR/hr) (mR/hr) _ (mR/hr) (mR/hr) (mR./hr) (mR/hr) (uCi/cc) ' (cpm)

A. (Centerline) 16.2 16.2 19.4 19.4 11.1 40.0 3.9 9.8 1.24E-05 as read (Off Centerline) 1.6 1.6 1.9 1.9 1.1 4.0 0.4 1.0 1.24E-06 as read -

B. (Centerline) 27.7 27.7 33.2 33.2 19.1 68.5 6.8 16.7 2.13E-05 as read (Off Centerline) 2.8 2.8 3.3 3.3 1.9 6.9 0.7 1.7 2.13E-06 as read ,

Notes: Air sample counts assume a sample volume of 10 cubic ft. and counting efficiency of 2%.

Radiological Measurements not incorporated in this section should be given as read.

Abbreviations:

a. LMD = Less than Minimum Detectable c. W.O. = Window Open

b. CPM - Counts per Minute d. W.C. = Window Closed t

t On, Site Data andMaps 10-19 G:\6660\93EX\EXONENI.XLS  ;

,.....m. . _. . _ . , _ . , . , .,,m -. - _ . - , . ,mm... .. . . , ~ . , , - - . -

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

ON-SITE INSTRUMENT READINGS TIME: 13:15- 13:30 Survey Meter Air Samples Air Samples lodine Smears  ;

3 feet 3 inches E-140-N / pancake RO-2 Calc.

Plume W.O. W.C. W.O. W.C. Cartridge Filter Cartridge Filter Location (mR/hr) (mRlbr) (mR/hr) (mR/hrl (mR/hr) (mR/hr) (mR./hr) (mR/hr) (uCi/cc) (com)

A. (Centerline) 0.2 0.2 0.2 0.2 0.4 1.6 0.2 0.4 4.99E-07 as read (Off Centerline) as read as read as read as read as read 0.2 as read as read 4.99E-08 as read a

B. (Centerline) 11.0 11.0 13.2 13.2 9.9 35.6 3.5 8.7 1.11 E-05 as read (Off Centerline) 1.1 1.1 1.3 1.3 1.0 3.6 0.4 0.9 1.11 E-06 as read Notes: Air sample counts assume a sample volume of 10 cubic ft. and counting efficiency of 2%.

" Radiological Measerements not incorporated in this section should be given as read.

Abbreviations:

a.. LMD = Less than Minimum Detectable c. W.O. = Window Open

b. CPM = Counts per Minute d. W.C. = VAndow Closed On-Ste Data andAfaps !0-20 G:\6660\93E.DEXONENI.XLS

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

ON-SITE INSTRUMENT READINGS TIME: 13:30- 13:45 l

Survey Meter Air Samples Air Samples lodine Smears 3 feet 3 inches E-140-N / pancake RO-2 Catc.

Plume W.O. W.C. W.O. W.C. Cartridge Filter Cartridge Filter Location (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR./hr) (mR/hr) (uCi/cc) (cpm)

A. (Centerline) as read as read as read as read as read as read as read as read 2.96E-09 as read (Off Centerline) as read as read as read as read as read as read as read as read 2.96E-10 as read B. (Centerline) as read as read as read as read 0.4 1.4 0.1 0.3 4.43E-07 as read (Off Centerline) as read as read as read as read as read 0.1 as read as read 4.43E-08 as read

'I Notes: Air sample counts assume a sample volume of 10 cubic ft. and counting efficiency of 2%

" Radiological Measurements not incorporated in this section should be given as read.

Abbreviations:

a. LMD = Less than Minimum Detectable c. W.O. = Window Open

b. CPM = Counts per Minute d. W.C. = Window Closed On. Site Data andMaps I0-21 G:\6660\93Fl\EXONENI.XLS

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

ON-SITE INSTRUMENT READINGS TIME: 13:45- 14:00 Survey Meter Air Samples Air Samples lodine Smears 3 feet 3 inches E-140-N / pancake RO-2 Catc.

Plume W.O. W.C. W.O. W.C. Cartridge Filter Cartridge Filter location (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR/hr) (mR./hr) (mR/hr) (uCi/cc) (cpm)

A. (Centerline) as read as read as read as read as read as read as read as read 4.93E-10 as read (Off Centerline) as read as read as read as read as read as read as read as read 4.93E-11 as read B. (Centerline) as read as read as read as read as read as read as read as read 2.63E-09 as read (Off Centerline) as read as read as read as read as read as read ' as read as read 2.63E-10 as read Notes: Air sample counts assume a sample volume of 10 cubic ft. and counting efficiency of 2%.

• Radiological Measurements not incorporated in this section should be given as read.

Abbreviations:

a. LMD = Less than Minimum Detectable c. W.O. = Window Open

b. CPM = Counts per Minute d. W.C. = Window Closed On-Site Data andMaps 10-22 G:\6660\93EMYONENI.XES

_ _ _ _ _ _ .-_ .-_ _ _ _ . _ . . . _ _ , _ . _ _ _ ~ _ . . _ . _ _ . _ _ _ _ _ _ _ , . _ - _ ._.. . . , , . , _ . . _ _ _ . _ __ 2 . _ _ .. _ - - , .

t f

D I

4 9

L 1

i I

f i

SECTION 10.4 i

OFF-SITE FIELD DATA AND MAPS

.i i

l 1

I I

l l

l I

i e

OFF-SITE INSTRUMENT READINGS TIME: 8:00- t h15 t Air Semples Air Semples Air Semples todane smears ,

Survey Meter E-140 ( CNS ) Ludlum 2218 (Missouri) E-52o (Netneeks) Cele. ,

Plume W,0. W.C. Cartridge Filter Cartndge Filter Cartridge Filter location (mR/hr) (mR/hr) (mR/hr) (mR/hr) (com) (cpm) (epm) (com) (uCi/cc) (cpm)

ALL se rood asreed as read as read as reed es reed as read as reed < MDA as read l

ft!otes: Air sample counts assume a sample volume of 10 cubic ft. and counting efficiency of 3.2 %

for Ludlum 2218, and 0.2% for E-520. Divide counts by 2 for 5 cubic foot samples.

• Radiological Measurements not incorporated in this section should be given as read.

Abbreviations:

a. LMD = Less than Minimum Detectable c. W.O. = Window Open  !

b. CPM = Counts per Minute d. W.C. = Window Closed 1

2 i

h i

Of,Sae Data andMaps 10-24 G:\6660\93EAY10FFEN1.Xl.S I

,,(- .

o -

Ig -( '

/

+

~.

j_

hg M 3 _ .t 3

7 _ ~ -

Y< r1 ie r il

~- (3 _

R e .

z.t / ' j aV _

h%

' Lr-g .

i q

s L -

T i l

)q

(

b _

p I

2 ~

N)x 5

N T

- ,s -

V ib'

/

,: )

?"

/.

~ s gi ,  : _

- l

,/

/ /- s a _ i 1

<# g" - f*.

=I (7 \

N

. s e x y.e  ; ,

s t

b i r ,l}l t ,

6

[ c l)g ~ ha NM l

m e l

s. .A .

/If Id m. 1 .

j v w f e

N t

lkf

_a _

ps.e c ,_ff p

d

[

i' ,

I 3

/L__"C3c

/ _

3 -

' AN

.g/

n u -

g 'w ,ji

/s h

[%

4 ..

,gm_'j-71 m

m- k

_{6A>_O

,i ' if,"

}~L LmmY~g k_/t m

,A 'N /

f '

(

(

\ ' ow _. i

)b s(

)* ,l

' s, m gL 3 . .

_g "

I, A

,fx l

N f

, i4o r .

T

- e "3

_ - )

. h.;1 3 e .

fkm n _ .

A ' , ,I U

N e f f

p T: hy~. I. es H

d\

ea j[

S - ,

,s s pi S

,I,g Nv

) '

l I l

rr gj j

4

NW s 5Lq ,'N, ) r I

f

, g)j p /

s 1 gIthp"f f d l

OFF-SITE INSTRUMENT READINGS l l

TIME: 11:15- 11:30 l

Air Samples Atr Samrdes Air Samples tContset lodine Srneare l Survey Meter E-140 ( CNS ) Ludium 2218 (Missouri) E.520 (Netweeks) Cole Plume W.O. W.C . Cartndge Filter Cartridge Filter Certndge Filter Location (mR/hr) (mR/hr) - (mR/hr) (mR/hr) (cpm) (com) (com) (corn) (uCi/ce) (cpm)

A. (Centerline) 3' 10.0 l o.o 1.3 4.0 27947.1 7o59.1 1860.9 13755.o 1.4BE-oo as read (Centerline) 3* 20.0 20.o A. (Edge of Plume) 3' 1.o 1.o o.1 4.0 2794.7 2o59.1 180.7 1375.5 1.4BE-07 as read (Edos of Pium.) 3" 2.0 2o i

Notes:

• Air sample counts assume a sample volume of 10 cubic ft. and counting etficiency of 3.2 %

for Ludlum 2218, and 0.2% for E-520. Divide counts by 2 for 5 cubic foot samples. l

• Radiological Measurements not incorporated in this section should be given as read.

Abbreviations:

a. LMD = Less than Minimum Detectable c. W.O. = Window Open

b. CPM = Counts per Minute d. W.C. = Window Closed 1

1 I

l l

Of-Site Data andMaps 10-26 G:\6660\93EkY10FFEN1.X1,S i

l 1

> m i_j

! j', l. c __ _I

\ e

's v/,_ _ . . _ . / L ii .?

^\  :

i "* ~ l n I

\'

I ML (J ^ f

'el,,,6ta '

//

/ Ji:s

\

' W ~

~ 3 ,

j - ~

{4, -

/ j ~

7 r

_t,

- 'N I S H.N A3

"" \

TNA

_ . . . . 5/ n

/ ;/

,4 ;I I8 -

I /l /.

] [ '\ (

E NW

)

j M- o .

pn _ T J_,_ I

$/ - y Kis 3'T\ hh M

i i N

\ff 'N/$ .l 2/y 1.

3 1h C5

~ ' ' M(o 6,

"~p N,

_J (i_._

/Ns 1/ [ [ %Mdl,j l

" t f? N

'XI_,_g(YNg

/, / s es El

,i, r

[ [ l' i

\ '

,[j ,

T g a _

ptt -3 g

[7$/bh

~ ~

I (

_U%( M y [ ,3N"%&\i [Sk +

i

' /[

s3 (TfEMP .ET J

., , ]:74W E** ,

s 1  !"# l/ ,

~~

) ,N~N" \ (TN \,,N j

Ph~esub "/ll /^%(/. '

c Ay ' y E i , j ~ _.

W , %, 2 _ I i

L i '

1, '

d _

y .7/ \ g' g\ , / .

s a

i.N _N -

t

~

3 -

L, + I' w -

/ +

\

\g ,- j,,, .

s

\/ll'3 l h i j

kg[ /

$VW g T "

2

-,,,, \ f '"N k h

k

' t.,

%/ A L

~

ydgR f ""

l /MLO N _d -Mi= S

' ; U. ," " " - d iioo.o6ir -~~*

[/' \ Time Period 11:15 - 11:30 3000

~~~

o 5000 occo rtti s- ._ ._. -- - -

, , ze

, ,y--f,,--a a- ,#-. - - gw., .,y.-- . . , , aww --w.. - - 2 -- -,.--pa m ,

OFF-SITE INSTRUMENT READIMGS TIME: 11:30- 11:45 Air Samples Air Samples Air Semples (C ont set lodine Smeste Survey Meter E-140 ( CNS ) Ludium 2218 (%esours) E-52o (Nebrasks) C alc.

Nme W.O. W.C. C ertndge Filter Certridge Filter C ertndge Filter Location (mR/hr) (mR/hr) (mR'hr) (mR/hr) (epm) (com) (com) (epm) fuCi/ce) (com) l A. (Centerhne) 3* 15.7 15.7 5.2 18.5 lo831o.6 7980.3 7235.1 53308.1 5.75E.oo esread (Centerkne) 3" 31.4 31.4 A. (Edge of Plumel 3' 1.6 1.6 o.5 18.5 t o831.1 7980.3 723.5 533o.8 5.75E-o7 esread ,

(Fdae of Mume) 3* 3.1 3.1 l

B. (Centerline) 3* 14.5 14.5 1.2 4.2 24824.9 1829.1 1658.3- 12218.3 1.32E oS se reed l (Centerline) 3* 29.o 29.o l B. (Edge of Mume) 3' 1.5 1.5 o.1 4.2 2482.5 1829.1 105.0 1221.8 1.32 E-o7 esreed i (Edos of Mume) 3* 2.9 2.9 Notes:

• Air sample counts assume a sample volume of 10 cubic ft. and counting efficiency of 3.2 %

for Ludlum 2218, and 0.2% for E-520. Divide counts by 2 for 5 cubic foot samples. <

• Radiological Measurements not incorporated in this section should be given as re-d. .

i Abbreviations: I

a. LMD = Less than Minimum Detectable c. W.O. = Window Open

b. CPM = Counts per Minute d. W.C. = Window Closed l

r I

1 i

a b

d Of, Site Data andMaps 10-28 G:\6660\93EX\EXOFFEN1.)[7S i

e

- - - - , a _

3 jy .

_ _. _.x _ _ < m i.

I "

T 1 T ,.g.

o 3' I

\

'i. '

S g .

g,, ; ~

-- _m PDL

/

/ x /' l Y ~~, '

i, .

K / --

'" \ '

M- ii -i / l N IS H.N A3k TNA [

([/ ' ll: '"

\ 'f

&g y

~ \

\ , ,

'"j';]\;

ou7

'] g

(

kf

'T'm

_ L _. /\

g' Q

/'\[ y\

gg ~

g )

q 7; .

N [

y^ ' )K 4 'r s a l )d

' n, 'e ji ' \ g~ ~ T

_\_ ,

4  %-' T-R yg lj z;N f6 ,\ /

'N 7 l\  ; /

I

%)  :

I k -)& 4r4 / 5

(\ 2 _ \ E!h (h

, 5' ,

/ w  !~'

s

\ .'

MP .ET.

( _/ :g g p p ',' \

N ,

jT i

'gMil ; "

I \ \ \- -

j

~4 }, M ,.  ; c x  ;

3 0 __ -

g n\,,

/ i, ,y _: .

~ , .

s

},

r s -

,N - -

, s - /

Ql h kI ~' // f, I q / +

%fW d a g

g - ,,, i Il ,

h _

7 g d

i *

-\w v 9 y y L f kbH M M/ i  %  % e ( k _ 2 N 't '3's J Tj g N G M L ] I l'hc W , -is , 1\- J 'a \i '- -

'\ -

'~

~

se m iin,ooo f 5000

'~ ~' "'

0 50Q0 QOOO FET

'" - ~ ' "

Time Period 11:30 - 11:45 i o i g wts OO OO* *Oh a.eem w hw

.gumamm w g, , , ,

_._m__. ._.__-_ _-_._ __._______-------_------------A. - - - - - - - - - - - - ' - - ' " ' - " " - ^ - - - - - ' - - - - " ^ - - - ~ - - ' ~ " - - - ' " - ' - - - - - ^ - - ^ " - - " ' - - - - - - - ' -~

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

OFF SITE INSTRUMEt3T READINGS TIME: 11 45 12 00 A Semples Air Samples Air Samples (C ont act lodme Smeers Survey Meter E-140 ( CNS ) Ludum 2218 (Messoura E-520 (Netwaska) Calc.

Plume W.O. W.C. Cartndge Filter Cartndge Filter Cartndge Filter L ocation (mR'hr) (mR!hr) (mR!hr) (mR/hr) (epm) (epm) (epm) (epm) (uCi/cc) (com)

A. (Centerhne) 3' 20.8 20.8 8.8 31.5 183999.1 13557.1 12291.0 90560.3 9.77E-06 as reed (Centerime) 3* 41.6 41.6 A. (Edge of Plume) 3' 2.1 2.1 0.9 31.5 18399.9 13557.1 1229.1 9066.0 9.77E-07 as read (Edge of Rumel 3* 42 4.2

8. (Conterfine) 3' 19.9 19.9 4.6 16.5 90210.2 7088.8 6426.8 47352.5 5.11 E-06 as read (Centerline) 3* 39.8 39.8 B. (Edge of Plume) 3' 2.0 2.0 0.5 16.5 9621.0 7088.8 642.7 4735.3 5.11 E-0 7 as reed (Edge of Rume) 3* 4.0 4.0 C. (Centerbne) 3' 13.5 13.5 1.0 3.7 21702.7 1599.1 1449.7 10681.6 1.15E-06 as read (Centerbne) 3* 27.0 27.0 l C. (Edge of Plume) 3' 1.4 1.4 0.1 3.7 2170.3 1599.1 145.0 1068.2 1.15E-07 as reed I (Edge of Mumel 3* 2.7 2.7 Notes:

• Air sample counts assume a sample volume of 10 cubic ft. and counting efficiency of 3.2 %

for Ludlum 2218, and 0.2% for E-520. Divide counts by 2 for 5 cubic foot samples.

• Radiological Measurements not incorporated in this section should be given as read.

Abbreviations:

a. LMD = Less than Minimum Detectable c. W.O. = Window Open

b. CPM = Counts per Minute d. W.C. = Window Closed a

1 i

l OfSste Da:a andMaps 10-30 G:\6660\93EAYXOFFEN1.X2S J

1 l

= -

C , I $  %

N.

A 1

\ ,, / / __\___ t ...

n  ;:

n ~

I 2 . ,.t, uaa,,

'/

/

l 5

b kwd

'%;' ,_ _ n, l

l

, V s

.y hf, -~= . j, p3L g ,,

5

--- .\,

(

! e / - -- .

l'y.Ejlt '  ! ;

k N ' j'!K(

' ' ' =

, 'N ISHN A Bhh x // ,,,

\

K t/,/ I

-  ! i a /

d d ^_]

sta.ng m -

f p r k

/ },'

Q - [ '3. _

,,, l

) 1. h, %

~~i %J,3

\ \l v

(

/

j-  !

/q s

\v/c}\

\l./\[ /t \

l '

d }

NY 2 1

Y -- q . ,

1 ..

ru t) @((< t .

h_

h 't

! s -m dl I.-:2 '

Mf

/>t g =

/ \ i \ .

6 >> T -- '

< vi

!'_ .)

s s ,- " w _

\ 6~.

, / \f "'

A'

,\

R 3'd /

O I

i

' - s nx (\ k

( 0 "" h5/ho f=~l[

$W 'u?

\  ! 5 '

~

\\( \ ^

-l q' f ;i /W>hi i

s

/

f.- >

' ^% a ~l\ N -

/

j UT ,

i , -

'; N. ,+

l; hy'c;f r

+

~

xy"] 4 4 mw -- -

~ , . . - ,  ; ,,

~

JAll

'Y' Y  %'

s f ,N' ll ' kk h &

kg N

Nfu h & ,_

- - 1 j\

s v .i fI \.}

\

j \ir N

'i

~~.i,._

L n

\

m sc* too.ooo T-3 O O EO N Time Period 11:45 - 12:00 -

L _. 3 L 2 ats

. - . . . - . -h*ee  %,,

-* * *n.o w e .

-~ - . . _ . __

OFF-SITE INSTRUMENT READINGS TIME: 12:00- 12 15 Air Semples Air Samples Air Semples (Contact lodma Smeere Survey PAeter E-140 ( CNS I Ludlum 2218 (Missoun) E-520 (Nebraske) C alc.

Plume W.O. W.C. Certridge Fdter Certndge Filter Cartndge Filter Location (mR/hr) (mR/hr) (mR/hr) (mR/hr) (cpm) (epm) (epm) (cprn) (UCi/ce) (com)

A. (Centerline) 3' 24.0 24.0 12.2 43.7 255626.1 18834.5 17075.7 125813.5 1.36E-05 asread (Centertme) 3* 40.0 48.0 A. (Edge of Plume) 3' 2,4 2.4 1.2 43.7 25562.0 18834.5 1707.6 12581.4 1.36E-06 es reed (Edos of Momet 3* 4.0 4.8

8. (Centerhne) 3' 23.0 23.6 7.8 27.9 163442.8 12042.5 10917.9 80442.9 8.68E-06 asread (Centerline) 3* 47.2 47.2

8. (Edge of Rume) 3' 2.4 2.4 0.8 27.9 16344.3 12042.5 1091.8 8044.3 8.68E-07 asread l (Edos of Rumel 3* 4.7 4.7 41397.0 C. (Centertme) 3' 17.8 17.8 4.0 14.4 84109.8 6197.2 5618.5 4.4 7E-06 esread (Centertme) 3* 35.6 35.0 C. (Edge of Rume) 3' 1.8 1.8 0.4 14.4 8411.0 6197.2 561.8 4139.7 4.47E 07 es read (Edge of Rume) 3* 3.6 3.6 D. (Centerime) 3' 10.8 1 C.8 0.9 3.2 18580.4 1369.0 1241.2 9144.9 9.8 7E-07 esread i (Centertme) 3* 21.0 21.6 D. (Edge of Plume) 3' 1.1 1.1 es read 3.2 1858.0 1369.o 124.1 914.5 9.87E-08 esread (Edoe of Rume) 3* 2.7 2.2 Notes:

• Air semple counts assume a sample volume of 10 cubic ft. and counting efficiency of 3.2 %

for Ludlum 2218, and 0.2% for E-520. Divide counts by 2 for 5 cubic foot samples.

• Radiological Measurements not incorporated in this section should be given as read.

• %breviations:

LMD = Less than Minimum Detectable c. W.O. = Window Open

. , . CPM = Counts per Minute d. W.C. = Window Closed l

.i

+

Of-Site Data ardMaps 1042 G:\6660\93EA%CYOFFEN1.XIS

, ,pg .e-- "

Sp

[*m $

g ' .4 m.

j i , .. . . -

ysf

,qmg N.a l + -, i s

/I ^ E

s. 1 i

c jQf c:

["" '1Syj c{

~

~

4 n wi g _ g _

+y - ./< 7~ -

- i p A 4; a ..

c 1 q & ] b

.r 4--

x -- # or

. 5l )

' ~

_ s i

/~

, u, a t y

[ ]

i \ -  ! \  ; -

~ e ta A is [ g p,  ; ')

z yr J_ LJ g :c (**63 , ' [1 /

4 7/ "

a; r- v.g

' a/ ,c g

e

-g W , A .U ,

p q-

' O fy -j- .

4

~

j -

Q) ' <

i l

p .,

/ .

tgy j: Aeh_

0 x __ f,/ Q 3;3 -}, %Lif

. . n, 2 2

4 Q

s.- .

_. ~

i

.. x. 31 I<

- a M 2 . - "

3,

• s so ,s .=

= -

S [.

d kj \

$ h' 4._- .

t i

fu$.0 sD@ >gn J%K('. ;1 } 'Q b _

y '

. '4 1 7 1 ' x A

___t.g_t_

1

/ - .- --

@D!

J PN

--/ k p 9 1

,x.. A.bj;  :

~

.y r; '

< f tl AP er s  ; -

'

• c n i >-V \\M9 , 6t

+4pM 4y a

3 1 '3 R

. kk/ NAN 1R1 )

E <

=r Z. -. c-L 4,

f

, 1 I ._. t ., N l / 22 s,

, i

~

x , ,*

wy p',,f.... f ,M 4

1~ ,'

4

. ~ .

OFF-SITE INSTRUMEfdT READIMGS TIME: 12:15- 12:30 Atr Samples Air Semples Air Semples (Contact lodine Smeers Survey Meter E.140 ( CNS I Ludlum 2218 (Missouri) E-520 (Nebraska) Cele.

Plum, W.O. W.C. Certridge Filter Certndge Filter Certridge Filter location (mR/hr) (mR/hr) (mR!hr) (mRmr) fepm) (epm) (epm) (com) (uCi/ce) (epm)

A. (Centerline) 3' 19.9 19.9 15.4 55.4 323717.8 23851.5 21624.1 159326.7 1.72E-05 es reed (Centerline) 3* 39.8 39.8 A. (Edge of Rume) 3' 2.0 2.0 1.5 55.4 32371.8 23851.5 2162.4 15932.7 1.72 E.06 esread (Edge of Rum ) 3* 4.0 4.0 B. (Centerline) 3' 19.0 19.0 10.8 38.8 227067.7 16730.4 15168.0 111757.7 1.21 E-05 es read (Centerline) 3* 39.2 39.2 B. (Edge of Plume) 3* 2.0 2.0 1.1 38.8 22706.0 16730.4 1516.8 11175.8 1.21 E-06 es reed (Edge of Rume) 3* 39 39 C. (Centertme) 3' 14.2 14.2 6.8 24.4 142886.5 10527.9 9544.7 70325.6 7.59E-06 esreed (Centerkne) 3* 28.4 28.4 C. (Edge of Plume) 3* 1.4 1.4 0.7 24.4 14288.7 10527,9 954.5 7032.0 7.59E 07 asreed (Edge of Rume) 3* 2.8 2.8

0. (Conterline) 3' 9.0 9.0 3.4 12.3 72009.4 5305.7 4810.2 35441.4 3.83E-06 as reed (Center (ine) 3* 18.0 10.0 ,

D. (Edge of Plume) 3' O.9 0.9 0.3 12.3 7200.9 5305.7 481.0 3544.1 3.83E-07 asreed (Edge of Rume) 3* 1.8 1.8 E. (Centerkne) 3' 7.8 7.8 0.7 2.6 15458.2 1139.0 1032.6 7608.2 8.21 E-07 asread (Centerline) 3* 15.6 15.6 E. (Edge of Rume) 3' O.8 0.8 es reed 2.0 1545.8 1139.0 103.3 760.8 8.21 E-08 esreed ,

(Edge of Rumel 3* 1.6 1.6 Notes:

• Air sample counts assume a sample volume of 10 cubic ft. and counting efficiency of 3.2 %

for Ludlum 2218, and 0.2% for E-520. Divide counts by 2 for 5 cubic foot samples.

• Radiological Measurements not incorporated in this section should be given as read.

Abbreviations:

LMD = Less than Minimum Detectable c. W.O. = Window Open CPM = Counts per Minute d. W.C. = Window Closed Of-Site Data andMaps 10-34 G:\6660t93EX\F10FFENIXLS

r.w 'r, e- .

O o. v e.,:

'%~ *

[ g M' _ I E! J g

"~ .

,, n p .. . -

j# l

, .1 W '

,)

" 3 jj m .. i

'jh. --

3 ai i fi f b I O  ! s#

, . 1

, , , a 0 3

^

I o

[ p J =,9 r.

(

• T I I

e' & d  ! u 4 n s y  ; /1 .

4, H F1

]

~

U/

g3g

_[

1 k l F:

T,r " i s y s

!n,N~

u ,

/ y\s -

=

e- ~

i

,, l. I f_

t

^ Nm /;

d .- _

-\q X r-l-- %g

's i

g, 4 a

'x x &f %j' 5 Jg l c 0 j >7 '4 l&.; l i u /,

~~}&g - _p

- ,i n a

j. _.. .

'N Y[ e mi r

y x,p~; i f 'g s>4 f Le 4a g

m pN m yr g .y k i ,x t

1 e .

n .P  :

my e is -

5:

e l

\ [z

=,

N

-. \ .

q l W* '9 J

! s a qx,S f*hp ' V 'e 7 e. F.,- F & l C f , .

~

JEd N' [\_'

j Jyy K 1%

, . s  : ? .. ., b

7. _

I I

', //

/ 5,' /

F b.

1 ,w

- ,\ . j

&]y N s

,3 i e _ l .- _j ~

- X i s i , v d - L-n s lg'a h)'

~

? z i ~

,v 9" c 4 l

' 9 ,XVNA1$1U  !

?4

- - , c .

^

i -

".  ? g l N , I 4

i

.'y

,Z - u4.,

- d J - . _ .

'_ _,,_ g p o .

l /  : z -

.2.i  !

af m a.... ,- n z- ~ = y L-- - - p , \

('\

7

~

q

,' \ ' I'*

..h,W, &wm*' sissc uai1:fB\r' i h,h l 'Q -

.. L

OFF-SITE INSTRUMENT READINGS TIME: 12:30- 12:45 Air Samples Air Semples Air Samples (Contact lodine Smeers Survey Meter E-140 ( CNS ) Ludlum 2218 (Missount E-520 (Nebraskel Cate.

Rums W.O. W.C. Certridge filter Certridge Filter Cartridge Filter location (mR/hr) (mR/hr) (m R.hr) (mR/hr) (com) (ct)m) (epm) (epm) (uCi/cci (com)

A. (Centeriene) 3' 22.0 22.0 18.t 60.5 388725.5 20041.3 25900.0 191322.1 2.07E-05 as read (Centerline) 3* 45.2 45.2 A. (Edge c'f Rume) 3' 2.3 2.3 1.8 06.5 38872.0 20041.3 2590.7 19132.2 2.07E-00 as read (Edos of Rumel 3* 4.5 4.5

8. (Centertino) 3' 22.2 22.2 13.7 49.2 287552.2 21180.8 19208.3 141520.8 1.53E-05 es reed j (Centerkne) 3* 44.4 - 44.4 B. (Edge of Rume) 3' 2.2 2.2 1.4 49.2 28755.2 21180.8 1920.8 14152.7 1.53E-00 es read (Edoe of Rume) 3* 4.4 4.4 C. (Centerline) 3' 15.0 15.0 9.4 33.9 198509.3 14020.2 13200.3 97701.9 1.05E-05 es read  !

(Centerline) 3* 31.2 31.2 C. (Edge of Mumel 3' 1.0 1.0 0.9 33.9 19850.9 14020.2 1320.0 9770.2 1.05E.00 as read (Edge of Rume) 3* 3.1 3.1 D. (Centerline) 3' 10.2 10.2 5.8 20.9 122330.3 0013.3 8171.0 00208.2 0.50E-00 as read (Centertine) 3* 20.4 20.4 D. (Edge of Rume) 3' 1.0 1.0 0.0 20.9 12233.0 9013.3 817.2 0020.0 6.50E-07 as reed (Edge of Rume) 3* 20 2.0 E. (Centedine) 3' 8.9 8.9 2.8 10.2 59909.0 4414.1 4001.9 29485.9 3.18E-00 se reed I

(Centerline) 3* 17.0 17.8 E. (Edge of Rumel 3' O.9 0.9 0.3 10.2 5990.9 4414.1 400.2 2948.0 3.18E-07 es read ,

^

(Edge of Rumel 3* 1.8 1.8 F, (Centerline) 3' 7.4 7.4 0.0 2.1 12330.0 908.9 824.0 0071.5 0.55E-07 as read (Centerline) 3* 14.8 14.8 F. (Edge of Rume) 3' O.7 0.7 as read 2.1 1233.0 908.9 82.4 007.1 0.55E-08 esread (Edae of Rumel 3" 1.5 1.5  ;

Notes:

• Air sample counts assume a sample volume of 10 cubic f t. and Counting efficiency of 3.2 %

for Ludlum 2218, and 0.2% for E-520. Divide counts by 2 for 5 Cubic f00t samples.

• Radiological Measurements not incorporated in this section should be given as read. ,

Abbreviations:

a. LMD = Less than Minimum Detectable c. W.O. - Window Open .

b. CPM = Counts per Minute d. W.C. = Window Closed l

l l

i l

l i

l Of-Sae Data andMaps 10-36 G:\6660\93EX\DL*0FFEN1.XIS

j

~ ' ' ~ ~ ~

y

= , - ~ . . ~

a,,--

,.,'ll L~i,

/ 3 T ,

I"p

~

7- g/ ~ ,

,, ll' (' y y ,

q' I

'}

I ~

~ ~ .  % "

-w i& fly.,

f,y th' ~ >,,

'/

/ l

'V ~

7 ,y 7 Pb( /r 7' ~~ C ~ iQ_

,/ljlel - s?

N (ys"h--,~/ (I

~~

e

~~

['yisunh; .

u, ,f / ;-

Tug ""

{ \ ;

L,.

'l -

]

b D 1lY'$; iN,f'!p\

I

['/'

4 .

f

(

3

,\:i f

fA =2_ 1fy k

{

q t, L ,

d ,1

)

<& Q -

y rJ- -s,

{,.- J ~. N ,.'[

gs) ll

' ",p" f-

, ~

'q

' ~- ,

f'Wi' .

T

\

A g M. k

/ pw ,

• i \ ~' O/

\

'y ,

I j- [ L

/

l i b\

~ 10

/,f ', ' P m "lC' s (

lw hN Q \T ET -

, W

\ /p eg - /( \ c. x gb, h ss p N

'A h u'ga>&s7

~~ -

i *

'* \.

{ ,T j JC

? w .~ \

E

\\ if 'I y' \</* *

'{

l 9i ~ l2~ ggk 'sy. , - 'f ~

,,7/  :

+

ps.

7.% '  %

! j

'- l 1[

~

x 'd . ' f61 '

Y N';2l,$',_ V, 'g'[/'&*m\'j%

~

~

i l  ?

g <

2"W '

a - p i I

, 4 p'. $ L

>k g ikn}[y Ie

}w\j

- u g

' ~ln ka ADt . ,- -

,~ y y,' '

${

ax%~' ' A Y} o s p<gns.tQ75

~

l't~ .

~,,  ;

a

.ju.ir~~-x.-w i

sc% g,g,ggo

,i ,

=

.,~,,\,

/

Time per;nd 12:39 ' 12:45 g~~  % 'mm rttr L% ~

o

" a 2 kCS 4

OFF-SITE INSTRUMENT READINGS TIME: 12 45- 13:00 Air Samples Air Samples Air Samples (Conteet lodine l Smeers Survey Meter E.140 ( CNS ) Ludlum 2218 (Messouri) E-52o (Nebraskel Celc.

Plume W.O. W.C. Certridge Filter Certndge Filter C ertridge Filter location imR/hrt (mR/hr) imp /hr) (mR/hr) (com) (cpm) (epm) (com) (uCi/cc) (epm)

A. (Centerhne) 3' 25.7 25.7 21.4 77.1 451037.0 33232.4 30129.0 221990.4 2.40E-05 es read (Centerkne) 3* 51.4 51.4 A. (Edge of Rume) 3' 2.6 2.6 2.1 77.1 45103.7 33232.4 3012.9 22199.0 2.40E-06 es read (Edge of Rume) 3* 5.1 5.1 8 ICenterkne) 3' 25.3 25.3 16.4 59.0 345297.3 25441.5 23065.6 169947.7 1.83E-05 as read (Centerhne) 3* 50.6 50.6

8. (Edge of Rume) 3' 2.5 2.5 1.6 59.0 34529.7 25441.5 2306.6 16994.8 1.83E-06 es read (Edge of Rumel 3* 5.1 5.1 C. (Centerkne) 3' 18.5 18.5 12.0 43.0 251386.7 18522.2 16792.5 123726.9 1.34E-05 esreed (Centerknel 3" 37.0 37.0 C. (Edge of Plume) 3' 1.9 1.9 1.2 43.0 25138.7 18522.2 1679.2 12372.7 1.34E 06 as read (Edge of Plume) 3* 3.7 3.7 D. (Centerhne) 3' 11.6 11.6 8.1 29.1 169950.9 12522.0 11352.6 83646.1 9.03E-06 as read (Centerline) 3* 23.2 23.2 D. (Edge of Plume) 3' 1.2 1.2 0.8 29.1 16995.1 12522.0 1135.3 8364.0 9.03E-07 as read (Edge of Plume) 3* 2.3 2.3 E. (Center (ine) 3' 9.3 9.3 4.8 17.4 101774.0 7498.7 6798.4 50090.9 5.41 E-06 as read (Centerknel 3" 18.6 18.6 E. (Edge of Plume) 3' O.9 0.9 0.5 17.4 10177.4 7498.7 679.8 5009.1 5.41 E-07 as read (Edge of Plumel 3* 1.9 1.9 F. (Centerhne) 3' 8.0 8.0 2.3 8.2 47808.6 3522.5 3193.6 23530.3 2.54E-06 as read (Centerline) 3* 16.1 16.1 F. (Edge of Plume) 3' O.8 0.8 0.2 8.2 4780.9 3522.5 319.4 2353.0 2.54E-07 as read (Edge of Plume) 3* 1.6 1.6 G. (Centerhne) 3' 6.8 6.8 0.4 1.6 9213.7 678.9 615.5 4534.8 4.89E-07 as reed (Centerhne) 3" 13.6 13.6 Edge of Plume) 3' O.7 0.7 as read 1.6 921.4 678.9 61.5 453.5 4.89 E-08 as read (Edge of Plumet 3* 1.4 1.4 Notes: Air sample counts assume a sample volume of 10 cubic ft and countino efficiency of 3.2 %

for Ludlum 2218, and 0.2% for E-520. Divide counts by 2 for 5 cubic foot samples.

• Radiological Measurements not incorporated in this section should be given as read.

Abbreviations:

a. LMD = Less than Minimum Detectable c. W.O. = Window Open

b. CPM = Counts per Minute d. W.C. = Window Closed Of.Sae Data andMaps 10J8 G:\6660\93EDEXOFFEN!.k72

QS

- ~

/ **

[\l'NI 1 \  ! rl i j L

Ii.sia Yk niili ].T .t hij 11."f.

E I

I 4 l

@[

8,, e err .

a .. a h I ;- '*

lI fL gy \ "! v o.i I

t

r. ) g { . I i A 7

~

%s#

~

a ' l I E

,5- ..

-l c {} _I .

ll, l _ _ .-

B

.g.

F-v l O l 7 j' #o o ,

i

. a i / L <

. 1 ,

)  :

T A

/

/

r / {g ; '

. I I lI I

Y  % ,

f f 1

.IN ,  !

.\ - 7

(\

5 y , [

\

~m' ' ot

" u 7

j ggg cvsv >

jT

~

s 's l' V 1

_v $

\'gg #/ W 8 g .

y: x 'NN

" ',g  % O,.

J ~ ~, \

9 ,

' -[

I  : ,

/ 'QA Q~

? -

\ +r / .

s " nn a, -/ , n -

p, ,. , ' Rg3,  ?

fn / \,,, /i f>. .;,

p ',

l i j ,. 3 j }

n;]fQl_{ ? \ g hl'

.~

- ' 7. *

[

H- -

./-m S Q q. Vf g%g. g8 ~

(. '

\ v-- s j l

s .-

' l t J I , J Y,. \lNyQ'b,/ / fP i.

j J g l P.# ls N 4 "

j%

' )I .

" , .t,': j,- ,

j-'I 3 l

. - . /s s/ -s p, ~ , 'w/78

\ l, '/

y,/ %K -

. n /((]

p .

-l-

/

/

8/

/ Tg!! ( p , gg:g  :

____ I J ><

z

- 43fy8

.#' s g E

/y\ i/;x >\'m x yj.:qq 7  ;

s

/~ -r ,

.; ~

.) _

l

! Nf '. m l

.$ /

._ l

\,

~

- - . . - - - - 'y $

t (3 l --

z.

/ \ j -]}&

f g,;;- _

e gis t jjR J -

t

• 4 i

g,D

/4, '

k k -

• D'T _ \. ! . e

OFF-SITE lalSTRUMENT READINGS TIME: 13:00- 13:15 Air Samples Air Samples Air Semples (Cont act lodme Smeers Survey Meter E-140 ( CNS ) Ludlum 2218 (Missount E-520 (Nebroska) C elc .

Plume W.O. W.C . C ertridge Filter C artridge Fetter C ertndge Filter t.ncstion (mR/hr) (mRIhr) (mR/hr) (mR/hr) (com) (com) (com) (com) (uCi/ce) (epm)

A. (Centertane) 3* 10.2 10.2 11.1 40.0 234179.2 17254.3 15043.0 115257.0 1.2 4 E-05 esreed (Centertmel 3* 32.4 32.4 A. (Edge of Rume) 3' 1.0 1.0 1.1 40.0 23417.9 17254.3 1504.3 11525.8 1.24E-00 asread (Edae of Rume) 3* 3.2 3.2 _.

8. (Centerlinel 3' 27.7 27.7 19.1 08.5 400047.4 29519.7 20703.0 197189.8 2.13E-05 asread (Centerline) 3* 55.4 55.4

8. (Edge of Rume) 3' 2.8 2.8 1.9 08.5 40004.7 29519.7 2070.3 19719.0 2.13E-00 seread (Edge of Rume) 3* 55 5.5 C. (Centertine) 3' 20.2 20.2 14.4 51.0 301809.1 22241.7 20104.7 148573.3 1.00E-05 esread (Center!ine) 3* 40.4 40.4 C. (Edge of Rume) 3' 2.0 2.0 1.4 51.0 30180.9 22241.7 2010.5 14857.3 1.00E-00 seread ,

(Edge of Rumel 3" 4.0 4.0 0, (Centerline) 3' 12.7 12.7 10.2 30.0 215221.1 15857.5 14370.0 105927.1 1.14E-05 as reed (Centerline) 3* 25.4 25.4

0. (Edge of Rumel 3' 1.3 1.3 1.0 30.8 21522.1 15857.5 1437.7 10592.7 1.14E-00 asread (Edoe of Rume) 3* 2.5 2.5 E. (Centerime) 3' 11.1 11.1 0.7 24.2 141392.5 10417.8 9444.9 09590.3 7.51 E-00 esread (Centerline) 3* 22.2 22.2 E. (Edge of Plume) 3' 1.1 1.1 0.7 24.2 14139.3 10417.8 944.5 0959.0 7.51 E-07 es read (Edge of Rume) 3* 2.2 2.2 F. (Centerline) 3' 9.4 9.4 3.9 13.9 81217.7 5984.1 5425.3 39973.0 4.31 E-00 se read (Centerline) 3' 18.0 18.8 F. (Edge of Rume) 3' O.9 0.9 0.4 13.9 8121.8 5984.1 542.5 3997.4 4.31 E-07 asreed (Edos of Plume) 3* 1.9 1.9 G. (Centertine) 3' 7.8 7.0 1.7 0.1 35708.2 2031.0 2385.3 17574.0 190E-00 enread (Centerline) 3* 15.0 15.0 Edge of Plume) 3' O.B 0.8 0.2 0.1 3570.0 2031.0 238.5 1757.5 1.90E-07 asreed (Edoe of Rume) 3* 1.0 1.0 H. (Centerime) 3' O.2 0.2 0.3 1.0 0091.5 448.8 400.9 2998.1 3.24E-07 as read (Centerfirw) 3* 12.3 12.3 H. (Edge of Plurne) 3' O.0 0.0 as reed 1.0 009.1 448.8 40.7 299.8 3.24 E-08 es read (Edge of Rume) 3* 1.2 1.2 Notes:

• Air sample counts assume a sample volume of 10 cubic ft. and counting efficiency of 3.2 %

for Ludlum 2218, and 0.2% for ES20. Divide counts by 2 for 5 cubic f00t sarnples.

• • Radiological Measurements not incorporated in this section should be given as read.

. Abbreviations:

a. LMD = Less than Minimum Detectable c. W.O. = Window Open

b. CPM = Counts per Minute d. W.C. = Window Closed h

OfSite Data andMaps 10-40 G:\6660\93EX\EXOFFEN1.173 r

w

, . ,s

~&

/ Np l '

1 '"

/

y' t

s l >> l ~g a

- I.. n,.

~

~. i.  ?

3'

/ ,- i i

Q l;. u l Lm, d*4

' .J x r -

,t

'Y,f(fc

in a t g /

m ,

}

(Q, ll  ;

~. '

ry K~T K, /  ::

f t, ~

Q HN p, s s, Ag "n x i

=. s i ,  ; ~j ~ '

x.. i "a

)j Q ,

n

- t. ' ' t &

8

/

7 )

.y, \\, y t; +i .

a l N.7ibh

) ']e ,,

f: h @,

.~

~ e

]e\+v.-

.g

~

2'~

m J , y/

/s '

9 .-

q pji e

'y b N ,l' ,, x s& \

e X' )- 1, g)p y, fg)'l IW f 2 .m- - 9pj t, u

r) L yb N,  ?

th'3

_R r

N:s~

l '*' ~

q /-

y g, - ,g ~q ee x .

y

~

C y

,/'

s ,+.e7px s r c9t s 1,y,%  :-;P" Q> .. ' f~

~

< g, YN K ,. @. % nR 't y :

aug\,' 3ilj. f 3 >',.t/ # x; W3 y

"- ,hp%_

s

gf.k,{$ m

%l

}w70 4'x & 3 ; glh 6.b:

5_

p ??Mt...pxygg 3:l(; &L h ki '

.n

g. W y... i  ?

i

~ '

c 5,

gW g

%wyq j~~h e

c nN4.>r m y s

2 t

\  !

L gJ

~

sq,, y ,,,

~

\! _-

7

~ ,,.

, m k ~

,i / q '

+s'~ ~

,a, S -n l' -(.,

. ~. ,_ i . . L i

?

• toi,000

~

'\-

'~

Time Pering ,a:00 ,13:15 5000

% -, , ,0 5000  % rttr

' ' ~ _

- ~ . ,_ --- ~ ..

g o t M rs

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

L' !-,,. ...,. ., ' 'N+ - - .

~ . ~

_ _ . _______A_.--- __ _-

OFF-SITE INSTRUMENT READINGS TIME: 13 15 13:30 Air Semples Aer Semples Air Semples (C ont act lodme Smeers Survey Meter E-140 ( CNS ) Ludlum 2218 (Missouril E.52o (Nebreake) Caic.

Nume W.O. W.C. C ertridge Filter Certridge Filter Certridge Filter L ocation (mR/hr) (mR/he) (mR/hr) (mR/hr) (cpm) (cpm) (epm) (epm) (uCi/cc) (epm)

A. (Centerkne) 3' O.2 0.2 0.4 1.0 9390.1 092.3 027.7 4024.5 4.99E-07 esreed (Centerhne) 3* o.4 0.4 A. (Edge of Mume) 3' asread esreed esread 1.0 939.0 092.3 02.8 402.5 4.99E-08 seread (Edge est Rume) 3* esreed sereed

8. (Centertine) 3' 11.0 11.0 9.9 35.0 208010.8 15320.7 13895.4 102381.2 1.11 E-05 esreed (Centerkne) 3* 22.0 22.0 B. (Edge of Rume) 3' 1.1 1.1 1.0 35.0 20801.7 15320.7 1389.5 10238.1 1.11E 00 as reed (Edge of Mumen 3* 2.2 2.2 C. (Centerhne) 3' 21.5 21.5 10.7 b9.9 350257.8 25007.0 23397.0 172389.1 1.80E-05 as read (Centerkne) 3* 43.0 43.0 C. (Edge of Rume) 3' 2.2 2.2 1.7 59.9 35025.8 25807.0 2339.7 17238.9 1.00E.00 eeread (Edge of Rumel 3* 4.3 4.3 D. (Centerkne) 3' 13.5 13.5 12.3 44.2 258440.9 19041.9 17203.7 127198.9 1.37E-05 esread (Centerline) 3' 27.0 27.0 D. (Edge of Rume) 3' 1.4 1.4 1.2 44.2 25844.1 19041.9 1720.4 12719.9 1.37E-00 es reed (Edoe of Rume) 3* 2.7 2.7 E. (Centerkne) 3' 11.8 11.0 8.5 30.0 179055.5 13192.8 11900.8 88127.2 9.51 E-00 asreed (Conterhnel 3* 23.0 23.0 E. (Edge of Rume) 3' 1.2 1.2 0.9 30.0 17905.0 13192.8 1190.1 8812.7 9.51 E-07 esreed (Edge of Rume) 3* 2.4 2.4 F. (Centerline) 3' 10.0 10.0 5.4 19.3 112834.1 8313.0 7537.2 55534.5 5.99E-06 sereed (Centerime) 3* 20.0 20.0 F. (Edge of Mume) 3' 1.0 1.0 0.5 19.3 11283.4 8313.0 753.7 5553.4 5.99E-07 as read (Fdoe of Rume) 3* 2.0 2O G. (Centerline) 3' 8.3 8.3 2.9 10.4 00001.5 4409.5 4052.1 29850.2 3.22E-00 se reed (Centertme) 3* 10.0 10.0 i Edge of Mume) 3' o.8 0.8 0.3 1 o.4 0000.1 4409.5 405.2 2985.0 3.22E-07 enread l ledge of Rume) 3" 1.7 1.7

]

H. (Centerhne) 3' O.5 0.5 1,1 4.0 23007.8 1739.4 1577.0 11019.2 1.25E-00 esreed I (Centerline) 3* 13.1 13.1 H. (Edge of Mume) 3' O.7 0.7 0.1 4.0 2300.8 1739.4 157.7 1101.9 1.25E-07 esread (Fdae of Rume) 3* 1.3 1.3 ,

1 Notes: Air sample counts assume a sample volume of 10 cubic ft. and counting efficiency of 3.2 %

for Ludlum 2218, and 0.2% for E-520. Divide counts by 2 for 5 cubic foot samples.

• Radiological Measurements not incorporated in this section should be given as read.

Abbreviations:

a. LMD = Less than Minimum Detectable c. W.O. = Window Open

b. CPM = Counts per Minute d. W.C. = Window Closed l

l 1

I OfS%te Data andMaps 10-0 G:\6660\93EDFXOFFEN1.X25

g m,9 - . .

,y, e W N' F ,kl I "W

I { I i k

E "j

,,/!p'JE s lM3 [%- (', m

+

I....,,-

l-[

w.: ,

/I

.' i A ae i7 .. q

!N "

3 fj *

.itivirz- ! s'i i g

a

, ,e _!.! -

I - i_

s g -g i .

( -----.-

--f H  :

., , _J. #o 7 o

7

($ __

_. i .'s  : -

g

( \ -\

g e

< ~

w m xw.

- Qg ngm .

ww, _ e - 7 _

i n j

~

h

,- ~y 5 . Ahh p h k, w

\o g % N

p ...,,ig. d. , 'o w

= x y ': g 9 ; g 4 %< g r T ' /

c c a

n a Qd a , -

,,gg  : ~, -

g / e_h d .%(y . ;df*4g8E k, s j4 f  ; i

'q p -

s 7

y a l

5l -~. '41l g d, g a ; ,j, b f ju 8 .

i- ,

p. i e

'e 'p ,[

.I i h% 2 I "' ' C

] ,a '{k j hg s* ) g  !

&zA)$%g' d j 'I .?h * \

AQp M Jat-o ? .

.. t ,

e_.! M MV V J i s .

a1 9- yMs o?

ys %mqdth 1

c~ l w

g -

i

< f~ I /_An g; i _ _.

\

j s )/x . p )\ g. m e, Il gl/ %rgv Vg

/ ,;gump- J

~

t, l"z

/ ,9

.- ,.m

_ r m s .. <

L ___ E I

g kl i Z ._. N. - ( ,

4

- - - . ~ 1- , 6UN , g g

1 l = =

y "

/

3 LJ{

7 V

f.

/\

..gsf fP T e at w

T"'

f'.= giss on 'h \j,es-;

E r; & f p

j/ '

OFF-SITE INSTRUMENT READINGS TIM E: 13:30 13:45 Air Samples Air Samples Air Semples (Contact lodene Smeers  !

Survey Meter E-140 t CNS ) Ludlum 2218 (%ssourd E-520 (Nebraska) Calc.

Rume W.O. W. C . C artndge Filter Certridge Filter Certridge Filter '

L ocation fmRhr) ImR/hr) (mR/hr) (mR/hr) (epm) (cpred (com) (com) fuCi/cci (com)  ;

A. (Centerkne) 3' as read es reed as read esreed 55.7 4.1 3.7 27.4 2.90E-09 as read (Centerline) 3* esread asread A. (Edge of Rume) 3' asread asread esread as read 5.0 4.1 as reed 2.7 2.90E-10 esread (Edge of Rume) 3* esreed as read B. (Centerknel 3' esread as read 0.4 1.4 8340.4 015.0 557.5 4107,9 4.43E-07 as read (Centerline) 3* es read as reed O. (Edge of Plume) 3' as read as read as reed 1.4 834.0 015.0 55.8 410.8 4.43E-08 as read (Edoe of Rum ) 3* asreed asreed

• C. (Centerline) 3' 10.2 10.2 8.0 31.1 181854.4 13399.0 12147.8 89504.7 9.00E-00 asread (Centerhne) 3* 20.4 20.4 [

C. (Edge of Rome) 3' 1.0 1.0 0.9 31.1 18185.4 13399.0 1214.8 8950.5 9.00E-07 as reed (Edge of Rume) 3* 2.0 2.0 D. (Centedene) 3' 14.3 14.3 14.3 51.3 299808.2 22094.3 20031.0 147588.5 1.59E-05 as read ;

(Centerhne) 3* 28.0 28.0 D. (Edge of Plume) 3' 1.4 1.4 1.4 51.3 29980.0 22094,3 2003.1 14758.8 1.59E.00 as read (Edge of Rume) 3* 2.9 29 E. (Centedine) 3' 12.4 12.4 10.2 30.8 215012.8 15842.1 14362.7 105824.5 1.14E-05 se read (Centerline) 3* 24.8 24.8 E. (Edge of Plume) 3* 1.2 1.2 1.0 30.8 21501.3 15842.1 1430.3 10582.5 1.14E-oS es read (Edge of Rumel 3* 2.5 2.5 F. (Centechne) 3' 10.0 10.0 0.8 24.4 142890.0 10528.1 9545.0 70327.3 7.59E-00 as read (Centerline) 3* 21.2 21.2 F. (Edge of Plume) 3' 1.1 1.1 0.7 24.4 14289.0 10528.1 954.5 7032.7 7.59E-07 asread (Edos of Rume) 3* 2.1 2.1 G. (Centerline) 3' 8.7 8.7 4.0 14.4 84275.7 0209.4 5029.0 41478.0 4.4BE-00 as read (Centerline) 3* 17.4 17.4  !

(Edge of Rume) 3' O.9 0.9 0.4 14.4 8427.0 0209.4 503.0 4147.9 4.48E-07 asread [

Edge of Rume) 3* 1.7 1.7 '

(Centerkne) 3' O9 0.9 1.9 S.9 40105.2 2955.0 2079.0 19738.9 2.13E-00 sereed ,

(Centerline) 3* 13.8 13.8 H. (Edge of Plumel 3' O.7 0.7 0.2 0.9 4010.5 2955.0 207.9 1973.9 2.13E-07 as reed (Edge of Rumet 3* 1.4 1.4 Notes: Air sample counts assume a sample volume of 10 cubic f t. and counting efficiency of 3.2 %  ;

for Ludlum 2218, and 0.2% for E-520. Divide counts by 2 for 5 cubic f00t samples. l

• • Radiological Measurements not incorporated in this section should be given as read.  !

Abbreviations-

a. LMD = Less than Minimum Detectable c. W.O. = Window Open l

b. CPM = Counts per Minute d. W.C. = Window Closed l l

l l

OfSite Data andMaps 10-44 G:\6660\93EX\EXOFFEN1.XIS i

r- -

s y'* a y d' Ty '

y 1 e  %

i

- l- i l

..,,= e". ... 7r srei h; i 3[--\ t, l + ,

e a1 g-

/I A sg 1

s

,e. t W f (1 f a'.4>ieb :% kkk'. s 5Nk ]

j M $$$ 'MW !E

~

4%$  %#4h a  % ' '

a

. :n

- 'kg6

, 4p;,y#%g;,>4 &g x o

N

%../

4 Is'/ .:

,.< . m 1 r b:

B a / _3- N

/ 4 _- J h\s}..

l

p. .gg o

L o y, ,

" Y A l ,a>g \f .e ..y gy%ly.

s N

s

.s gl r g U B

,e M~N, 'r_ %'" N* 4 ' W . A f e- c i . .

a

! I .

a 7 ,  ;

pi g s'e xp su ,s.. , s!s .

N 7g- e e

h )\

,s N

fi4 h ~

[

-\ p A pse /p /_i > .

. .ag R [\-

V Ll b I .

^

~

fik c-g A: 9 'yy/N A- - Pt spr+;M r r _

, [ z g )Ah t a

,~

J ,

~

/m '

.4 ,dm l L ,y

< _2 z 7, [. 4H x _

O

, N; z ~-

.h m

= ,

.x-- i z

+ .-

/ \ '

p"

.s s,

= S RJ Y '

M

[ ..g,MjkI' cTR/MA[\ l ' ./1ffIR J

OFF SITE INSTRUMENT READINGS TIME: 13 45- 14 00 Air semples Air Samples Air Samples (Conteet lodine Smeers Survey Meter E.140 ( CNS ) Ludlum 2218 (Mieeouril F.520 (Nebraskel C ole.

Plume W.o. W.C. Cartridge Filter Certridge Filter Certridge Filter location (mRhrt (mR/hr) (mR/hr) (mRrbr) (epm 1 (com) (epm) (epm) (uCi/cc) (epm)

A. (Conterkne) 3' as read as read asread as road 9.3 esreed as read 4.0 4.93E.10 as read 1 (Centerlme) 3* esread as read A. (Edg< af Rume) 3' es reed as read as reed as reed as read asread as read asreed 4.93E-11 as read (Edos of Plume) 3* as read as read B. (Centerkne) 3' esread as reed asreed asread 49.5 3.6 3.3 24.3 2.63E-09 as read (Centerkne) 3* esread as read B. (Edge of Plumel 3' as read as read esreed asread 4.9 3.6 as read 2.4 2.63E-10 as read (Edge of Plume) 3* as read as reed C. (Centernnel 3' as read as read 0.3 1.2 7296.6 537.6 487.4 3591.2 3.88E-07 as read (Centerkne) 3* enreed as read C. (Edge of Plume) 3' as read as read as read 1.2 729.7 537.6 48.7 359.1 3.88E-08 esreed (fdge of Plume) 3* asreed as read D. (Centerline) 3' 9.6 9.6 7.4 26.6 155692.1 11471.4 10400.1 76028.2 8.27E-06 esread (Centechne) 3" 19.2 19.2 O. (Edge of Mume) 3' 1.0 1.0 0.7 26.0 15569.2 11471.4 1040.0 7602.8 8.27E.07 es read (Edge of Plume) 3* 1.9 1.9 E. (Centerkne) 3' 12.4 12.4 11.9 42.7 249478.6 18301.6 16665.0 122787.8 1.33E-05 as read (Centerkne) 3* 24.8 24.8 E. (Edge of Plume) 3' 1.2 1.2 1.2 42.7 24947.9 18381.6 1666.5 12278.8 1.33E-06 as read (Edge of Rumet 3* 2.5 2.5  !

F. (Centechne) 3' 10.6 10.6 8.2 29.3 171584.6 12642.4 11461.7 04450.1 9.12E-oo esreed (Centerhne) 3* 21.2 21.2 F. (Edge of Plume) 3' 1.1 1.1 0.8 29.3 17158.5 12642.4 1146.2 8445.0 9.12E-07 as read (Edge of Mumel 3* 2.1 2.1 G. (Centerline) 3' 8.7 8.7 5.1 18.2 106724.4 7863.5 7129.1 52527.4 5.67E-06 as read (Centertine) 3* 17.4 17.4

'Ed9e of Plume) 3' O.9 0.9 0.5 18.2 10672.4 7863.5 712.9 5252.7 5.67E-07 es read Idge of Plume) 3* 1.7 1.7 (Centechne) 3' 6.9 6.9 2.6 9.5 55717.3 4105.3 3721.9 27422.8 2.96E-06 seread (Conterhnel 3* 13.8 13.8 H. (Edge of Plume) 3' O.7 0.7 0.3 9.5 5571.7 4105.3 372.2 2742.3 2.96E-07 as reed ,

(Edos of Plume) 3* 1.4 1.4 fJotes:

• Air sample counts assume a sampic volume of 10 Cubic ft. and counting efficiency of 3.2 %

for Ludium 2218, and 0.2% for E 520. Divide counts by 2 for 5 Cubic foot samples.

• Radiological Measurements not incorporated in this section should be given as read.

Abbreviations:

a. LMD = Less than Minimum Detectable c. W.O. - Window Open

b. CPM = Counts per Minute d. W.C. = Window Closed l

0,fTsite Data andMaps 10-46 G:\6660\93EMXOFFEN1.A72

, l

)

• %f% (" \ 54 4 % V$___ :6 9' .t\ g  !,

W g, ,

? 's /< .

&y _L Eyn >I wca l ' '" ~

.f*h' , . . ,j,  %

• IYhIjf8Ehh h iLN N ,

,z rp;yr sw eswqg<, e w- ag , ,

' I I *I p_ 3 ,

z z ,

[  %; q  ;  : /,/,' .y, %g', ,,

w[g..

a

]q$ R3-a-i I'N x ..

'k n~ gi

!fh

.~

, . _/

i x

-e R.; >

.,. . c A "" p f

a.

y

\_ ,

Nys%

\\ ;a -( ,

g. .em.r. . . .a.,., ~

. i

^ ' * ~

. Y

,g  ??7 m

x 6 -

+

s,. . .

m: .

.p 9g,; 1 e

l i.st q .W; 9x% :s; r-o -u  ;

a i.

=

/ _

\,

+ .

m .-

'i t l f*

> f.b y

~ -

k w ?' y*_I ,t.

j/Ht g/ :

r i \.

x y A

• N

, m t .c' g I le

' -j \ _-*f j D, ,,iX,>%

N. .

g c:

a t ,,

s p /\ 3s -

s . , (SMA ,

\ al l' r '

l

', x ' -

- i j

f 2g . ._Nh I > '

(N %.yg> g k N!  ! i h !p ,

o "-

ci. -

%y I 3

c'3-) b J , J, -

I b m5 /ll

- -l I

o wgj %y -\nig;.;.

we , ) w ,, t 9

r; s

< s/ 4._ne. -si '

.k,...

y Mg

< . , z -'

k.__

m R'tM86LL

~

i /1^

O<

z m -

l i

m E __

1"jw

s ' m 7 4 - -

_ _ . F ,

q*

l / 2 Z ._l -

1

._2 p,[x 7 iy g t qp=wA,,,J f s.

< /

qj ru t

I ,,f,M M T -M ,L %'l ' '

X '

l

l OFF-SITE INSTRUMENT READINGS i

TIME: 1400'ON l l

Aar Samples Air Samples Air Samples lodme Smeere Survey 9Aeter E.140-N /RO-2 ]

Ludlum 2218 (Missourel E 520 (Nebreake) C ele. i Plume W.O. W. C . C ertridge Filter C ertridge Falter C ertndge Filter location (mR/hr) (mR/hr) (epm) (cpm) (com) (epm) (epm) (epm) (uCi/cc) (epm)

ALL AS READ AS READ AS READ es read AS f tEAD as read AS READ seread LMD es reed AS READ AS READ AS READ es read AS READ es read AS READ se read LMD es read l l

l l

Notes: Air sample counts assume a sample volume of 10 cubic ft. and counting efficiency of 3.2 %

for Ludlum 2218, and 0.2% for E-520. Divide counts by 2 for 5 cubic foot samples.

Radiological Measurements not incorporated in this section should be given as read.

Abbreviations:

a. LMD = Less than Minimum Detectable c. W.O. = Window Open i

b. CPM = Counts per Minute d. W.C. = Window Closed '

t a

Of-Site Data andMaps 10-48 G:\666063FXEYOFFEN).A73 4

1 Section 11 PUBLIC INFORMATION MATERIAL 6

i I

l l

=_

i i

11. PUBLIC INFORMATION MATERIAL l Public information material includes information that can be used to initiate response by  ;

players at the General Office Emergency Center (GOEC) and the Media Release Center (MRC).

Pre-scripted messages provide a basis for a minimum number of calls to be made during the  :

exercise. It is permissible for a control cell controller responsible for delivering the pre-scripted messages to initiate additional messages as the exercise progresses. Any additional i messages must be documented on the Free-Play Message Form provided Controllers should  ;

ensure that any new messages created are realistic, credible, and consistent with previous messages. If in doubt, check with you Control Cell Lead Controller.

Controllers are permitted to make up names for callers, and can simulate being members of the public or of the news media. local news agencies which may be used include: l

• KMTV - Omaha, Ne

• KCOE Radio - Auburn, Ne

• KTRX Radio - Tarkio, Mo

• KFAB Radio - Omaha, Ne

• WOWT - Omaha, Ne

• KOLN TV - Lincoln, Ne ,

I

• Omaha World Herald

• KlGO Radio - St. Joseph, Mo i

• KQTV - St. Joseph, Mo

• KOTD Radio - Plattsmouth, Ne j

• KNCY Radio - Nebraska City 9

l Public Irtfonnation Material Page 11-1 c:sssow3Exutcn-11.wes

n 4 m-, e-4 -+ -- s- e-3A4- i M- # , Ae d 224 L hi .-6 4

.4 6

Y

.i 6

I h

r N

t e

t t

i I

i i

h

?

O SECTION 11.1 CORPORATE MESSAGES i

.i w

z I

e J

.I

)

t

.I 7

S f

s

?

1 0

i i

l l

1 a

1 l

, .i

A W- U & H m *-&-- + +3 km 4 4 l,kkn e 4 e

-e

+

9 i

s I

' it f

i i

i 6

s 6

s I

o I

6

?

i SECTION 11.2 PUBLIC ASSISTANCE MESSAGES I 4

1 0

m 4

I h

i I

I l

I 1

e

A A & a m

.M_f. A e a -e- - = + ,

1 I

f t

t i

3 i

i l

6

)

.4 e

i i

.6 9

]

I t

F 1

-t t

SECTION 11.3  ;

-i TELEPIIONE CONTROLLER MESSAGES t

f i r I

r 1

I i

5 i

f 1

i 4

i D

'^

o i

s w-- -.

-,, , -e ._s , -