ML20078A946

CNS 1994 Evaluated Exercise Scenario Manual for Emergency Exercise to Be Conducted on 941115

ML20078A946
Person / Time
Site:	Cooper
Issue date:	11/15/1994
From:	NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML19344C673	List: ML20078A944 ML20078A946
References
NUDOCS 9409220008
Download: ML20078A946 (147)

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' COOPER NUCLEAR STATION 1994 EVALUATED EXERCISE SCENARIO MANUAL i i

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t O e CNS 1994 Evtluttsd Exercise TABLE OF CONTENTS E89e. l PART A GENERAL INFORMATION

1. I N T R O D U C TI O N . . .. .. . . . . . . . . . . . . . . . . . . . . . . . . . .. . .. . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . .

2. S C O P E A N D O B J E CTlV E S ... ..... . .. . .... ........ . .. ... .. . . .. ... .. . ........ ..... .......... ... .. . ... . .. 2-1 I 2.1 Scope...............................................................................2-2 -

2.2 Objectives . .. .. ......................................................................2-3

3. EX E R C I S E I N F O R M ATI O N ...... .. . . ... .. .. ..... . .. . ... . . .. . ... ...... .... ...... ....... ... .... . .. . . ...... 3-1

• 3.1 Exercise Participants. . . . . . . . . . . . . . . . . . . . . ......................3-2 3.2 Exercise Organization. . .. . . . . . . . . . . . .............. ..... ... .... 3-2 3.3 Conduct of the Exercise...... ........ . ... ......................................3-4 3.4 Precautions and Limitations.. . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-6 i

4. CONTROLLER / EVALUATOR IN FORM ATION.............................................. 4-1 4.1 General information. . ... ...... .... . .... . . .... .... ... . . . . . . . . . . . . . . . . . .4-2 .

4.2 Controller Instructions.. .. ... ... .....................................4-2 4.3 Evaluator Instructions . .. ..... . .. ... . . . . .............................4-3 4.4 Personnel Assignments.. ... . ... ... .. . .. .. . ... ... ... ..... . . . . . 4-3 4.5 Simulator Instructions . .. ...... .. .. . ...... ... . . . . . . ....... .... . .. ... . . 4-3 Table 4.4-1 Controller Assignments. . . .. ..... ....... .......... ...................4-5 Table 4.4-2 Evaluator Assignments... . . . . . . .. . . . . . . . .. . . . . . . . . . . 4 -7

5. P LAY E R I N F O R M ATI O N . . .. ..... .. . .. .. .. . . . . . . .. .. . .. . .. . . . . . . ... . .... . .. . .. ... .... ....... ... ...... .... 5-1 5.1 General Information .... ..... .... .. . .. . .... ................................5-2 5.2 Player Guidelines.... .. . ..... ... ...... .. . ... .... ........ .. ...................5-3

6. S C H E D U L E O F EV E N TS ... . ....... ........ . .. ...... ...... .. ........ ........... .. . .... .. ................. 6- 1 6.1 Times and Places .. .... . ..... . .. . ..........................................6-2 6.2 Travel Information... .. ... .. .... . .. ... ...... . ...................................6-3 t

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e o CNS 1994 Ev luttsd Ex;rcios Paae PART B CONFIDENTIAL SCENARIO INFORMATION

7. EX E RC I S E S C EN ARIO M ATE RI AL ................................................................. 7-1 I 7.1 S ce n a ri o S umm a ry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7-2 l 7.2 Initial C ondition s . . . . . . . . . . .. . . . . . . . . . . . . . . .. . . . . . .. . .. . .. . . . . . . . . . . . . . .. . . . . . .. . . .. . . . .... . . 7-5 1

7.3 S e q u e n ce oi E ve nt s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7-7 7.4 S im u l a t o r D a t a . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7-9 l

8. STATIO N O P E RATIO N S M ATERI AL .............................................................. 8-1 i l

8.1 S tation M e s sag e s .... ... . ... . . ..... ..... . . ..... ..... ..................................8-2 1 8.2 Operations Data Summary.... . .... . ...... .......... . .. .... .... .... ........... .. 8-24  !

9. RADIOLOGICAL DATA 9.1 Radiological Assumptions. .. .. . . .. .. ... ....... ......... . ..... 9-1 9.2 Messages and Trend Data............. . .. . . . .... .............................9-4 9.3 Count Room Data . .. . . . ..... .... ... . ..... ... . . . . . . . . . . . . . . . . . . . . . . . 9 -9 4 9.4 In-Plant Radiological Data. . ........ .. ... . . ..........................9-10 ,

9.5 Dose Assessment Data. . . . .. .. . . . . . . . . . . . . . . . . . . . . . . . . 9 -4 0 9.6 Plume Phase Environmental Information. .. . .. . . . . . . . . . . . . . . . . . 9 -4 5 t

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CNS 1994 Evtluitsd Exercico e

Section 1 INTRODUCTION h

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a a CNS 1994 Ev lu ted Ex;rcim J. 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 radiologicalincident 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, major portions of the NPPD CNS emergency organization's will be evaluated in the 1994 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 allinformation 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 eve'its. 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 generalinterest, 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 Page 1-2

l CNS 1994 Ev21urted Ex;rcise distribution (Controllers, Evaluators and authorized observers) provides the scenario-  !

specific information and supporting data for the sequence of ovents. Exercise "Plavers" (see Section 3.2) will not have orior access to or know'gdge of any of the i scenario that has been develooed for this Exergig Page 1-3

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l Section 2 SCOPE AND OBJECTIVES 5

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2. SCOPE AND OBJECTIVES 2.1 Scope The 1994 CNS Emergency Preparedness Exercise, to be conducted on November 15,1994, 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 capabilities of the NPPD Emergency Response Organization, and will include activation and participation of all NPPD emergency facilities.

The Exercise 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 government organizations 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 radiological consequences, and activities to minimize the impact of these consequences; notification and mobilization of the emergency response organizations; implementation of in-plant corrective actions;

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activation / operation of emergency response facilities and equipment; Page 2-2

v o CNS 1994 EvIlutted Ex:rcise preparation of adequate :0 cords to document decisions made and actions taken;

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formulation and recommendation of protective actions for personnel within the area; and a termination of and recovery from the emergency condition.

Specific objectives to be demonstrated by the NPPD CNS Emergency Response Organization and Facilities are identified in the following section.

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 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.

Objectives are grouped according to functional area of emergency I response, Additionally, objectives have been cross referenced to major )

or parent Emergency Plan implementing Procedures used in l demonstrating the objective, and to any related open weakness from the j previous years' exercises.

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CNS 1994 Ev"lu:ted Ex: raise l

General Objectives: .

Accident Assessment, Classification and Mitigation

1. Demonstrate the ability to assess plant conditions and classify  ;

emergency events per EPIP 5.7.1..

1NUREG-0654 ref: D.1-2; H.5; i.1 l 2Major EPIP ref: 5.7.1 l 3 Weakness ref: none , )

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

1 NUREG-0654 ref: D.1-2; H.5;l.1 2Major EPIP ref: 5.7.7,5.7.9,5.7.16 3 Weakness ref: none Notification and Mobilization

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

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

2Major EPIP ref: 5.7.6  !

3 Weakness ref: none '

4. Demonstrate the ability to mobilize NPPD emergency response personnel and activate emergency response facilities within the time frames specified in the Emergency Plan.

1NUREG-0654 ref: J.1 2Major EPIP ref: 5.7.7, 5.7.8, 5.7.9 3 Weakness ref: none

5. Demonstrate the ability of NPPD to notify federal, state and county agencies within the time frames specified in the Emergency Plan.

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CNS 1994 Ev luited Ex:rcise 1NUR'EG-0654 ref: A.1.e; B.4,7.c; E.1-4; F.1; J.7; N.2.a 2Major EPIP ref: 5.7.6 .

3 Weakness ref: none

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

1 NUREG-0654 ref: J.1 -

2Major EPIP ref: 5.7.3, 5.7.4, 5.7.10, 5.7.11 3 Weakness ref: none Emergency Response

7. Demonstrate the ability to direct and coordinate emergency responses.

1 NUREG-0654 ref: A.1.d; B.2-6 i 2Major EPIP ref: 5.7.7, 5.7.8, 5.7.9  ;

3 Weakness ref: none

8. Demonstrate the ability to transfer emergency direction from the 1 Control Room (CR), to the TSC, and finally to the EOF, or from the  !

Control Room directly to the EOF.

1 NUREG-0654 ref: A.1.d; B.3-5 2Major EPIP ref: 5.7.7, 5.7.9  !

3 Weakness ref: none

9. Demonstrate the ability to provide initial and continuous accountability of onsite individuals.

1 NUREG-0654 ref: J.5 2Major EPIP ref: 5.7.10 ,

3 Weakness ref: none

10. Demonstrate site recovery /re-entry planning.

1NUREG-0654 ref: M.1-3, B.7.a-b 2Major EPIP ref: 5.7.25 Page 2-5

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CNS 1994 EvIlurted Ex:rcise 3 Weakness ref: none Radiological Assessment and Control

11. Demonstrate the ability to provide radiological monitoring and ,

decontamination capabilities for onsite personnel. l 1NUREG-0654 ref: K.7 2Major EPIP ref: 5.7.13 3 Weakness ref: none i

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12. Demonstrate the ability to provide onsite contamination controls, and area access controls. '

1 NUREG-0654 ref: K.5,6 2Major EPIP ref: 5.7.12,5.7.13 3 Weakness ref: none

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

1 NUREG-0654 ref: K.1.a-g,2,3.a-b 2Major EPIP ref: 5.7.12,5.7.13 3 Weakness ref: 298/9324-01

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14. Demonstrate the ability to monitor, assess, and correlate onsite radiological conditions with plant conditions.

1 NUREG-0654 ref: H.5.b,c,9; i.1-3; N.2.d.e.1 2Major EPIP ref: 5.7.19 3 Weakness ref: none

15. Demonstrate the ability to collect and analyze simulated ,

radiological samples and surveys and evaluate results. l 1 NUREG-0654 ref: H.5.b,7; N.2.d.e.1 2Major EPIP ref: 5.7.18, 5.7.19 3 Weakness ref: none Page 2-6

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16. 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.

1NUREG-0654 ref: H.6a,8; i.3-7,0-10; J.10.m 2Major:EPIP ref: 5.7.16, 5.7.17, C.7.20 ,

3 Weakness ref: none

17. Demonstrate the ability to make timely- protective action '

recommendations to offsite agencies.

1 NUREG-0654 ref: 1.5-10, J.7 2Major EPIP ref: 5.7.20 3 Weakness ref: none Emergency Response Facility-Specific Objectives:

18. Emergency Operations Facility (EOF):

a. Demonstrate the capability of the EOF emergency resonse organization to implement the Emergency Plan and Procedures.

b. Demonstrate the adequacy of communications between the EOF and CR, TSC, government emergency facilities, and field teams.

c. Demonstrate availability of appropriate emergency '

equipment and supplies.

d. Demonstrate the adequacy of security access control.

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

f. Demonstrate the functional adequacy of the EOF facilities.

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- e CNS 1994 Ev~luated Ex:r:;ise 1NUREG-0654 ref: B.5; H.2-3,6-8; J.6.a-c,10.a-b, E.2; F.1,2,3 .

2Major EPIP ref: 5.7.9, 5.7.21, 5.7.22 3 Weakness ref: none

19. Technical Support Center (TSC):

a. Demonstrate the capability of the TSC emergency resonse organization to implement the Emergency Plan and Procedures.

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

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

d. Demonstrate the availability of appropriate emergency equipment and supplies.

e. Demonstrate activation and staffing of the TSC in a timely manner.

f. Demonstrate the functional adequacy of the TSC facilities.

g. Demonstrate the ability to perform core damage j assessment.

1 NUREG-0654 ref: B.5; B.7.a-b,; H.1,6-8,; i.3; J.6.a-c, E.2; F.1,2,3 2Major EPIP ref: 5.7.7, 5.7.17, 5.7.21, 5.7.22 3 Weakness ref: none

20. Control Room (CR)

a. Demonstrate the capability of the Control Room emergency resonse organization to implement the Emergency Plan and Procedures.

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

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

d. Demonstrate the functional adequacy of the Control Room facilities.

1NUREG-0654 ref: B.5; E.2; F.1,2,3; H.6-9,12; J.6.a-c 2Major EPIP ref: 5.7.2, 5.7.3, 5.7.21, 5.7.22 3 Weakness ref: none

21. Operations Support Center (OSC):

a. Demonstrate the capability of the OSC emergency response organization to implement the Emergency Plan and Procedures.

b. Demonstrate the adequacy of communications between the OSC and inplant teams TSC. i l

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

d. Demonstrate activation and staffing of the OSC in a timely manner.

e. Demonstrate the functional adequacy of the OSC facilities.

f. Demonstrate the ability to dispatch OSC repair and/or rescue team personnel.  !

1NUREG-0654 ref: B.5; E.2; F.1,2,3; H.1; J.6.a-c 2Major EPIP ref: 5.7.8,5.7.13,5.7.21, 5.7.22  !

3 Weakness ref: 298/9324-01 l i

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CNS 1994 Evalu ted Ex::rcise Scenario '

22. Develop an exercise scenario and controller organization which supports demonstration and evaluation of a major portion of the emergency plan.

1 NUREG-0654 ref: N.1.a-b 2Major EPIP ref: EPDP 11 3 Weakness ref: none Evaluation

23. Demonstrate the ability to conduct a post-exercise critique to identify weak or deficient areas needing correction.

1NUREG-0654 ref: N 4,5 2Major EPIP ref: EPDP 11 3 Weakness ref: none FOOTNOTES I References related emergency planning objectives provided as guidance in NUREG-0654/ 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 Product;on and Utilization Facilities".

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References major NPPD-CNs 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, 3 References applicable open weakness from the 1993 Exercise as listed in NRc Jocket 50-298/93-24 (see the following for a summary of the weakness).

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CNS 1994 Ev luated Ex:rcise 1993 NRC Exercise Weakness Summarv Ooerations Suncort Center 298/9324-01 Training Program Description 0415, " Respiratory Protection" describes the licensee's requirements for the qualification of personnel who could be required to wear respiratory protection. This TPD requires that OSC maintenance and operator personnel be respirator qualified. The failure to ensure that a response team member was qualified as specified was identified as an exercise weakness.

In addition, an operator was dispatched into the plant even though records available in the OSC showed the individual's respiratory qualifications had expired because the individuals physical had lapsed.

The individual was deemed qualified because he stated that he had completed the physical but the records had not been updated.

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CNS 1994 EvIlutted ExIrcise Section 3 EXERCISE INFORMATION i

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3. EXERCISE INFORMATION l

3.1 Exercise Participants j 3.1.1 The Nebraska Public Power District

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) [for training only)

f. Media Release Center (MRC) [for training only]

3.1.2 Offsite Agencies Emergency response personnel from Nebraska, Missouri and associated counties.

3.2 Exercise Organization P

The organization for this Exercise consists of the Exercise Coordinator, the Lead 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 preparation of a consolidated evaluation package and preparation of a list of identified findings requiring corrective action.

3.2.2 The Lead Exercise Controller l

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 I 1

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• 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 Lead Exercise Controller will also assist with the preparation of a consolidated evaluation package.

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

A Lead 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 report 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. Contingency messages and any other form of prompt will only be delivered by controllers after full discussion with and with the 3 express permission of the Lead Exercise Controller or Exercise l Coordinator. Controllers will submit written observations to the Lead l Controller, who will summarize 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 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.

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1 3.2.5 Observers ,

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i Observers may be authorized, on a limited basis, to participate in the l Exercise for training purposes. j l

3.2.6 Inspectors j

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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.

3.2.7 Players

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Players include station and other utility personnel assigned to perform emergency functions as described in the Emergency Plan and implementing Procedures. Players from offsite organizations and agencies (county, State, and private industry) are also participants in the Exercise. I 3.3 Conduct of the Exercise i The Exercise will simulate a radiological incident at the Cooper Nuclear Station in order to demonstrate the effectiveness of NPPD CNS emergency 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 notifications to agencies not participating will be simulated.

The 1994 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  ;

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software will be available to indicate to the crew the status of systems and equipment, as the operators respond to the scenario. i The capability exists to provide "real time" data to other emergency  ;

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l response facilities (TSC and EOF) using terminals connected to the l 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 i event of a failure of the Simulator computer, the Lead Exercise Controller shall determine whether to continue the exercise, or delay the sequuence of events to recover the simulator or direct that plant indications, parameters and annunciators will be provided to the Control Room operators using message forms and plant data sheets. Sufficient  ;

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. In the event that the Simulator tails to provide operational or radiological data that is consistent with the scenario, and with data previously collected from the simulator and printed in the manual, the exercise controller reserves the right to adjust Simulator output to correspond to the previously generated simulator data in order to maintain the internal consistency of the scenario.

Contingency messages (denoted by an 'x' after the message number) are delivered only when conditions described in the Controller notes have been met. 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 ar9 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 Section 9.0 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 provid9d at a point where it would not be available in a real emergency. Controllers shall deliver ,

allinformation and messages exactly in the time and manner described on the message form. Controllers may interject other information or  !

change a message to ensure that the Exercise progresses as planned, Page 3-5

CNS 1994 Ev::.luated Ex:rcise only with the soecific 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.

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 initiation of the Exercise, pre-exercise briefings will be held to review the entire exercise process with all the Exercise participants.

3.4.1 Actual Emergencies 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. Upon notification of an actual emergency, the Lead Exercise Controller will make a determination whether to continue, temporarily suspend or terminate the Exercise.

3.4.2 Unsafe Conditions SI'ould, 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 maroin of safety in the l Dla01 1

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3.4.3 Operating Equipment .

l All repair activities associated with the scenario 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.

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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 participart not observing this practice, it is the Controller's responsibility to remind the individual of the need to follow this procedure.

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 who is aware of an individual or group of individuals in the immediate vicinity who may have become alarmed or confused ,

about the situation, should approach that individual or group and explain 1 the nature of the Exercise and its intent.

3.4.6 Motor Vehicle Response j l

Any motor vehicie response to this Exercise, whether it be ambulance, l 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 ag.1 be operated on emergency vehicles for the purposes of the Exercise.

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. . 1 CNS 1994 Evnlunted Excrcise r

Section 4 CONTROLLER / EVALUATOR INFORMATION f

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CNS 1994 Evzluated Ex:rcise

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

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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.

l 4.1.5 The evaluation checklists provided. I 4.2 Control:er 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 Facility clocks will have been syncronized with the simulator clock.

Do not change facility clocks. Reset y.Qut watch to facility clock time.

4.2.3 A0 Controllers will comply with instructions from the Lead Exercise Controller.

4.2.4 Each Controller will have copies of the messages controlling the progress of the Exercise scenario. No messaaes shall be delivered out of secuence or other than as written unless soecifically authorized by the Lead Exercise Controller.

4.2.5 Controllers will HQt 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 Page 4-2

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. CNS '1994 Ev lusted Extrcise i

and exercise their own judgement in determining response actions and resolving problems. .

j 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 l questions regarding scenario content.

4.3 Evaluator instructions Each Evaluator will take detailed notes reaarding the oropress of the Exercise and resoonse of the Exercise carticloants at their assigned  ;

locations. Each Evaluator should carefully note the arrival and departure times of participants, 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 prepanng a ,

written evaluation of the Exercise.

l Sheets containing specific emergency facility evaluation criteria are provided in Emergency Preparedness Department Procedure (EPDP) ,

11, Exercise and Drill Evaluation Procedure. These sheets must be completed by each Evaluator and provided to the Exercise Coordinator at the conclusion of the Exercise. For specific evaluation of the exercise  :

objectives, each evaluator shall be provided with objective-based -

exercise evaluation forms, which must be filled out for each facility following the facility critique and provided to the Lead Exercise Controller.

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

i 4.4 Personnel Assignments The personnel assignments for the Controller organization are listed m i Table 4.4-1. Assignments for the Evaluator organization are listed in I Table 4.4-2. i 4.5 Simulator Instructions i

The simulator will be relied on primarily for data generation and plant response interactions with the Control Room crew. Should it malfunction I

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CNS 1994 Evaluated Exercise i

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:

stopping the Exercise and attempting to recover the simulator then resuming play; stopping the Exercise and conducting it the following day (provided Simulator repairs can be performed);

completing the Exercise using the data sheets provided in the {

Exercise Manual; and  ;

l ending the Exercise if most of the objectives have been demonstrated. (Unmet objectives would be re-scheduled for a later date.)

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CNS 1994 Evaluated Exercise CONTROLLER ASSIGNMENTS 4

TABLE 4.4-1 CONTROL ROOM SIMULATOR F

TBD Lead Exercise Controller Robert Hayden -

Control Room Management (Drill Controller)

Wayne McKinzey Control Room Operators Dave VanDerKamp Control Room Operators Duane Shallenberger Instructor Station Operator TBD Instructor Station Operator OPERATIONS SUPPORT CENTER TBD Team Control and Coordination Josh Whisler Mechanical Teams TBD General Teams '

TBD General Teams Cindy Weers Chemistry /HP Activities -

Rodney Fosbinder Electrical Teams Kenton Weeldon Electrical Teams Brad Johnson I&C Teams -

Warren Schwindt I&C Teams i Jeff Bratrsovsky Mechanical Teams '

Larry Corey HP/In-Plant Rad. ,

Pam Delizza HP/in-Plant Rad.

Dave Lewis HP/in-Plant Rad. -

Brad Ackerman Operations Team (s)

Jim Florence Operations Team (s)

TECHNICAL SUPPORT CENTER Mike Estes TSC Management Mick Spencer TSC Engineering EMERGENCY OPERATIONS FACILITY TBD EOF Management Brian Hall Dose Assessment Page 4-5 ,

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CNS 1994 Ev2luited Exercise TBD Field Team Coordination TBD D/W Team #1 .

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TBD D/W Team #2 GENERAL OFFICE EMERGENCY CENTER Bob Wilbur GOEC Management '

MEDIA RELEASE CENTER Alan Dostal MRC Management i 1

• Indicates Lead Facility Controller l

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CNS 1994 Evaluated Exercise EVALUATOR ASSIGNMENTS TABLE 4.4-2 CONTROL ROOM SIMULATOR Dave VanDerKamp Control Room Operator Activities Duane Shallenberger Control Room Operator Activities TECHNICAL SUPPORT CENTER '

Mike Estes TSC Staff Activities EMERGENCY OPERATIONS FACILITY Don Reeves EOF Staff Activities Bob Mcdonald Dose Assessment & DN/ Teams Control GEllERAL OFFICE EMERGENCY CENTER

• Kenneth Almquist GOEC Staff Activities David Whitman Technical MEDIA RELEASE CENTER David Danielson MRC Staff Activities t

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• CNS 1994 Evaluated Exercise Section 5 PLAYER INFORMATION Page 5-1

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5. PLAYER INFORMATION l l

i 5.1 Generalinformation 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, l including "Prscaution and Limitations" in Section 3.4, and the following i information. l The success of the Exercise is largely dependent upon Player reaction, Player knowledge of their appropriate Emergency Plan and l Implementing Procedures, and an understanding of the purpose of the 1 Exercise. Initial conditions which will affect Player action or reaction will be provided to the Players at the appropriate time (depending upon ,

when it is reasonable for that information to have been known) either at the player briefing or when 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 desianed to evaluate the Emeroency Plan. Imolementina Procedures. and the emeroency orecaredness trainino oroaram. Additionally, the Exercise is a training vehicle for NPPD personnel to practice coordination with outside organizations in a simulated emergency 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.

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 messaaes as written. and '

resoond as thouah the deoicted event occurred. If corrective actions are Page 5-2

. 4-CNS 1994 Evaluated Exercise  !

discovered that woidd terminate the emergency, they should be identified to a Controller sc that the Exercise can continue on schedule.

5.2 Player Guidelines 5.2.1 Maintain a serious, professional attitude throughout the Exercise.

5.2.2 Teamwork is essentiall Do your job'and then help other people do theirs. For example, if you know certain information should be 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 oossible 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 i area. Always wear your identification 6 ?dge. ,

5.2.5 If you are entering normal nuclear station radiation areas, {

observe all rules and procedures. No one (including Controllers) is exemot from normal station radioloolcal 'oractices and orocedures. ,

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

5.2.6 Observe all normal security orocedures. All normal security procedures are in effect without exception. If a security condition l arises, obey immediately the directions of Security Guards. 1 5.2.7 initiate actions in accordance with instructions and responsibilities. .

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

5.2.9 Use and demonstrate knowledge of the Emergency Plan and 1 Implementing Procedures. l 5.2.10 No response to an Exercise situation will be simulated without Page 5-3

CNS 1994 Evalur_ted Ex:rcise 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 Controllm/ Evaluator at the end of the Exercise. .

l 5.2.12 Remember, one of the main purposes of an exercise is for you to l assure yourself that you are adequately prepared. Areas for l improvement or lessons learned, when identified, will improve  ;

your overall emergency preparedness.  ;

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CNS 1994 Evaluated Exercise Section 6 SCHEDULE OF EVENTS l

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6. SCHEDULE OF EVENTS 6.1 Times and Places As of 9/14/94 Event Place Time Qa.ta Initial Exercise  : EOF 0900 October 21 -

Controller / Evaluator Briefing Final Exercise EOF 0900 November 10 Controller / Evaluator Briefing Exercise Player Auditorium 1500 November 10 Briefing Conduct of Exercise / Various 05:00-12:00 November 16 Player Critiques Controller Critique EOF 13:00-14:00 November 16 Session Exercise Critique Classroom J 1500 November 17 Presentation to (tenative)

Management Exercise Critique Classroom J 0900 November 18 Presentation to (tenative) the NRC NRC Exit Briefing Classroom J 1000 November 18 (tenative)

Player De-brief Auditorium 1500 November 21 Page 6-2

O O CNS 1994 Evalurted Excrcise 6.2 Travel Information .

For prior arrangements, questions, or permission to observe, contact:

Nebraska Public Power District Cooper Nuclear Station Emergency Preparedness Dept.

Mr. Robert Hayden P.O. Box 98 Brownville, NE 68321 (402) 825-5270 Airoorts

1. Omaha, NE - Approximately 80 miles (Take Rte 73 South, Rte 6 East,1-29 South, Rte 136 West to Brownville, turn south immediately after crossing Misouri river bridge and follow signs to Cooper Nuclear Station)

2. Kansas City, MO - Approximately 90 miles (Take 1-29 North, Rte 136 West to Brownville, turn south immediately after crossing Misouri river bridge 4 follow signs to Cooper Nuclear Station)

Motels

1. Arbor Manor (402) 274-3663 Auburn, NE

2. Rock Port inn (816) 744-6282 Rock Port, MO l

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

4. Auburn inn (402) 274-3143 Auburn, NE i i

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EXERCISE SCENARIO MATERIAL i 1

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7. EXERCISE SCENARIO MATERIAL 7.1 Scenario Summary The date is November 16,1994.

The plant is operating @ 95% power near end of core life having been at power for the previous 280 days. HPCI was placed out of service during the previous g ,

shift for auxiliary oil pump coupling replacement. HPCI is tagged out with its auxiliary oil pump coupling removed and is expected to be returned to service tomorrow. All other plant equipment is in a normal configuration. The ,

operability requirements for RCIC, Core Spray and LPCI were satisfied during the previous shift. The ADS logic operability test is scheduled to be completed on this shift. The plant is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> into a 7 day LCO.

The weather is cloudy and cold with a chance of flurries with winds out of the northeast at six mph.

At elapsed time 0000(0530) the start of the exercise will be announced with initial conditions established.

At elapsed time 0005(0535), the #1/2 jet pump inlet riser fails. Indication of the failed jet pump includes power oscillations, increased recirculation loop flow on the failed side and lower jet pump differential pressure on the failed jet pumps.

Operators will verify indications and may perform a jet pump operability surveillance. Pieces of the riser fall into the jet pump diffuser and become lodged at the inlet of several fuel bundles. The resulting flow obstructions shall cause localized fuel failures.

At elapsed time 0010(0540) the main steam line and offgas radiation levels begin to increase.

At elapsed time 0013(0543) sufficient fuel failures have occurred causing main i steam line and offgas high-high radiation alarms to come in. The offgas  ;

isolation timer is initiated. Various area radiation monitors in areas where i process steam flows indicate elevated area radiation levels. l The operating crew will reduce reactor power in an attempt to reduce offgas activity.

The Shift Supervisor will request Chemistry to take a coolant sample.

At elapsed time 0023(0553) the offgas timer will time out. The offgas system will isolate and condenser vacuum will slowly decay. Per procedure 2.4.7.1, the operating crew will scram the reactor and close the MSIVs.

Air ejector offgas radiation monitors will have exceeded 15,000 mR/hr. Coolant sample results will show a coolant activity in excess of 300 Ci/gm dose ,

equivalent 1-131. Both these conditions are indicative of a loss of the fuel clad l

Page 7-2 l

O A CNS 1994 Ev:luited Ex: rcise boundary. The Shift Supervisor shall declare an Alert based on EAL #2.2.1 (fuel clad loss #1 or #2).  !

Notifications shall be conducted in accordance with EPIP 5.7.6. The TSC and OSC will be activated. Site assembly and accountability will be performed.

By elapsed time 0045(0615) reactor pressure will be controlled by a combination of SRV actuation and operation of RCIC in the test mode. Once reactor pressure is stabilized, a controlled cooldown will be established.

Over the next one hour and 15 minutes, the operating crews will continue to cool down using RCIC. Consideration should be given by both the TSC and operating crew to minimizing potential for spread of fission products throughout process streams and the plant.

At elapsed time 0150(0720) a small recirculation system pipe leak inside the drywell will cause increased drywell temperatures, humidity and pressure.

As the leak rate increases, operators will attempt to maximize containment cooling. Due to the fission products in containment, containment venting will be precluded.

At elapsed time 0200(0730) the reactor coolant leakage will cause drywell pressure to exceed 2.0 psig. Exceeding 2.0 psig in the containment is the threshold for primary coolant boundary loss. The Emergency Director shall declare a Site Area Emergency based on EAL #2.3.3 -loss of any two fission product barriero(primary coolant boundary loss #2 in conjunction with fuel clad loss #1/#2).

The EOF and GOEC/MRC will be activated.

The operating crew will attempt to locate and isolate the source of the leak.

RPV cooldown will proceed in accordance with EOPs.

At elapsed time 0330(0900) the RCIC steam line downstream of RCIC-MO-16  ;

ruptures (Northeast torus area). The resulting steam release results in actuation i of the RCIC isolation logic due to high steam flow and high temperatures on the steam leak detection system. Both steam isolation valves, RCIC-MO-15 and 16 fail to isolate. Following performance of the RCIC operability surveillance conducted on the previous shift, both valves were inadvertently stuck on their  ;

backseats.

1 The unisolable steam leak results in exceeding a loss of primary containment j barrier threshold. The Emergency Director shall declare a General Emergency based on EAL #2.4.1-loss of three fission product barriers (primary containment boundary loss #1 in conjunction with primary coolant boundary loss #2 and fuel l clad loss #1/2).

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CNS 1994 Evtluited Ex::rcis)

The leak also results in a radiological release to the environment. The release path is from the RCIC steam line to the torus area atmosphere to reactor building ventilation and through standby gas treatment to the ERP. Reactor Building area radiation levels increase accordingly. Offsite releases will not be in excess of that which would result in a PAR more severe than the minimum PAR required at a General Emergency.

At elapsed time 0335(0905) the area temperatures in the vicinity of the RCIC steam line break shall exceed the Maximum Safe Operating values specified in the EOPs. Emergency RPV depressurization shall be required. Once RPV pressure has reached the SRV reseat pressure (50 psig), the release rate shall stabilize until action to manually close RCIC-MO-16 have been taken. Once isolated the release shall be terminated (approximate elapsed time of 0355/0925).

By elapsed time 0410(0940) actions to place the plant in shutdown cooling will be discussed. Once the prerequisites for entry into the recovery phase have been met in accordance with EPIP 5.7.25 the emergency will be terminated.

Entry into the recovery phase, elapsed time 0430(1000), wi'l lead to the development of a recovery plan and discussions in accordance with the recovery procedure.

Once all objectives are met, elapsed time 0500(1030) the exercise will be terminated.

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a CNS 1994 Eviluited ExIrcise 7.2 initial Conditions

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7.2.1 Initial Plant Conditions The date is November 16,1994.

The plant is operating @ 95% power near end of core life having been at power for the previous 280 days. HPCI was placed out of service during the previous shift for auxiliary oil pump coupling replacement. HPCI is tagged out with its auxiliary oil pump coupling removed and is expected to be returned to service tomorrow. All other plant equipment is in a normal configuration. The operability requirements for RCIC, Core Spray and LPCI were satisfied during the previous shift. The ADS logic operability test is scheduled to be completed on this shift. The plant is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> into a 7 day LCO.

The weather is cloudy and cold with a chance of flurries with winds out of the norteast at six mph.

At elapsed time 0000(0530) the start of the exercise will be announced with initial conditions established.

7.2.2 Weather Forcasts General:

A changing weather pattern will exist throughout the area. A weak high i pressure zone will move through the region towards the east causing winds to shift to a more westerly direction. Clouds will develop during the afternoon yielding a slight chance of scattered flurries as the unorganized front moves through. Skies will be cleared by tomorrow morning with an area of high .

pressure dominating the region for the next several days.

Detailed:

This evening cloudy with temperatures 35' to 458 Winds from the NE 5 to 10 MPH with gusts of up to 15 MPH. 40% chance of precipitation.

Tonight cloudy and breezy temperatures 25' to 358 Winds from the NE 5 to 10 MPH with gusts of up to 15 MPH. 30% chance of precipitation. l Tomorrow morning sunny with temperatures ranging 258 to 35'F. Winds from the east 10 to 15 MPH with gusts of up to 20 MPH. 20% chance of precipitation.

Tomorrow afternoon increasing clouds with temperatures 35' to 45'. Winds from the east 15 to 20 MPH with gusts of up to 25 MPH. 30% chance of precipitation.

Tomorrow Evening decreasing cloudiness with high temperatures 45' to 558 Winds steady from the ESE 8 to 13 MPH. 20% chance of precipitation.

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CNS 1994 Evilurted Ex rcise ;

Long range forecast clear skies with high temperatures 458 to 55' and low temperatures 25' to 35'. Winds will be steady from the SE 5 to 10 MPH.

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1 e a CNS 1994 Evilurted Excrcise 7.3 Sequence of Events I The date is November 16,1994. The plant is operating @ 95% power having ,

been at power for the previous 280 days. HPCI has been placed out of service '

for auxiliary oil pump coupling replacement. The plant is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> into a 7 day LCO.

The weather is cloudy and cold with a chance of flurries with winds out of the northeast at six mph.

TIME ACTIVITY Elansed/ Clock

-0030/0500 Conduct pre-shift briefing of operating crew. Perform panel walk-down and shift turnover.

0000/0530 Announce start of the 1994 CNS Evaluated Exercise 0005/0535 Indications of jet pump failure and slight power reduction 0010/0540 increasing main steam line radiation as a result of fuel damage caused by localized flow blockages from failed jet pump parts 0013/0543 Main steam line high radiation alarms and increasing offgas radiation. Operators attempt to reduce radiation levels with power reduction. Request Chemistry personnel take coolant sample.

0015/0545 Air ejector radiation in excess of 15,000 mR/hr. Coolant sample results indicate lodine activity of >300 Ci/gm dose equivalent.

ALERT based on loss of 1 fission product barrier - EAL #2.2.1.(fuel clad loss #1 and #2 per Att. 3).

TSC/OSC activated.

0023/0553 Offgas High-High timer times out requiring reactor scram and MSIV closure per Procedure 2.4.7.1.

0045/0615 RCIC controlling pressure and level. Initiate a controlled cooldown per EOPs once RPV pressure is stabilized.

0150/0720 indications provided of increased drywell floor drain leakage along with increased drywell temperatures, humidity and pressure.

0155/0725 Reactor coolant leakage continues to increase as confirmed by ,

indication of increasing drywell temperature, pressure, humidity and radiation. Drywell cooling maximized. Fission product inventory inside containment will preclude containment venting per ESP 5.8.17.

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CNS 1994 Ev;luated Ex:rtise 0200/0730 increasing drywell pressure results in exceeding scram setpoint (>

2.0 psig). ,

SITE AREA EMERGENCY based on loss of 2 fission product barriers  !

- EAL #2.3.3.(primary coolant boundary loss #2 in conjunction with fuel clad loss #1/#2 per Att. 3).

Depressurize RPV to within limit of cooldown rate allowed by EOPs. ]

0225/0755 Establish cooldown rate. EOF and GOEC/MRC activated. )

0330/0900 Piping downstream of RCIC-MO-16 ruptures (Northeast torus area).

RCIC high steam flow and leak detection isolations fail to isolate RCIC steam line. Attempts at manualisolation of RCIC steam line  ;

fail. )

ERP radiation levels increase. Release of fission products to i atmosphere via Reactor Building, Standby Gas Treatment System, i and out the Elevated Release Point (ERP).

GENERAL EMERGENCY based on loss of thres fission product barriers - EAL #2.4.1.(primary containment boundary loss #1 in )

conjunction with primary coolant boundary loss #2 and fuel clad loss l

1. 2 per Att. 3). '

0335/0905 RCIC steam leak results in exceeding Maximum Safe Operating  ;

Values (temperature) in two or more areas. Operators emergency depressurize RPV. j Dose assessment results will not require PAR in excess of those )

required by plant conditions.

0355/0925 Isolation of RCIC steam line (RCIC-MO-16) .  !

Release terminated. l 0410/0940 Recovery discussions begin i 0430/1000 Enter recovery phase 0500/1030 Termination announcement for 1994 Exercise 1

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7.4 Simulator Data  :

IJME ACTIVITY ' SIMULATOR Elaosed/ Clock j

-0030/0500 Conduct pre-shift briefing of operating Initialize simulator to IC-crew. Perform panel walk-down and 99 shift turnover. Batch file: 1hayex Hang RT on HPCI AOP Safety status panel LCO Tracking Book

[ Set remote functions under HV for met. data) 0000/0530 Announce start of the 1994 CNS Simulator in RUN Evaluated Exercise 0005/0535 Indications of jet pump failure and TRG E1 slight power reduction RR18A CR01 10010:00 0010/0540 increasing main steam line radiation as a result of fuel damage caused by localized flow blockages from failed jet pump parts 0013/0543 Main steam line high radiation alarms and increasing offgas radiation.

Operators attempt to reduce radiation levels with power reducion. Request l Chemistry personnel take coolant ,

sample. j 0015/0545 Air ejector radiation in excess of 15,000 mR/hr. Coolant sample results indicate lodine activity > 300 I pCi/gm dose equivalent.

ALERT based on loss of 1 fission product barrier - EAL #2.2.1.(fuel clad loss #1 and #2 per Att. 3).

TSC/OSC activated.

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o o CNS 1994 Ev;lur.ted Ex: raise ;

0023/0553 Offgas High-High timer times out TRG E2  !

requiring reactor scram and MSIV ,

closure per Procedure 2.4.7.1.

CR03 (2) .5 RM02E (3) 53 3:45:00 74.1 l RM02F (3) 52.5  :

3:45:00 74 l

. [ Ramps SJAE RMs to i 1200 mr/hr by 0415)  ;

RM03DD (0:10) 46.8 5

RM03EE (0:05) 47 5 ,

[ Ramps drywell hl rad mon. to 2000 r/hr) 0045/0615 RCIC controlling pressure and level. TRG E3 (Auto)

Initiate a controlled cooldown per RM02A 42.1 EOPs once RPV pressure ,s i stabilized. RM02B 42.15 ,

RM02C 42.0 t RM02D 41.9 (This locks MSL rad ,

mon. @ ~300 mR/hr - ,

prevents from i decaying to 0)  ;

0150/0720 indications provided of increased TRG E4  !

drywell floor drain leakage along with - RR20A 5 3:00 increased drywell temperatures, humidity and pressure.

0155/0725 Reactor coolant leakage continues to I increase as confirmed by indication of increasing drywell temperature,  ;

pressure, humidity and radiation.

Drywell cooling maximized. Fission product inventory inside containment I will preclude containment venting per ESP 5.8.17.  ;

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CNS 1994 Ev;lutted Ex:rcise 0200/0730 Increasing drywell pressure results in exceeding scram setpoint (> 2.0 psig).

SITE AREA EMERGENCY based on loss of 2 fission product barriers - EAL

1. 2.3.3.(primary coolant boundary loss

1. 2 in conjunction with fuel clad loss

1. 1/#2 per Att. 3).

Depressurize RPV to within limit of cooldown rate allowed by EOPs.

0225/0755 Establish cooldown rate. EOF and GOEC/MRC activated.

0330/0900 Piping downstrearn of RCIC-MO-16 TRG E5 ruptures (Northeast torus area). RCIC RC06 50 high steam flow and leak detection I

isolations fail to isolate RCIC steam RC07 line. Attempts at manual isolation of ZDIRCICSWS2 RCIC steam line fail. Open l ERP radiation levels increase. ZDIRCICSWS1 Release of fission products to Open atmosphere via Reactor Building, Standby Gas Treatment System, and RA: MUX 16C069 On out the Elevated Release Point (ERP). RA: MUX 17C061 On l GENERAL EMERGENCY based on

[ sets RCIC valve loss of three fission product barriers - overload ann. 9-4 EAL #2.4.1.(primary containment F-3 for MO-15 & 16]

boundary loss #1 in conjunction with primary coolant boundary loss #2 and RM02L 100 (0:30) fuel clad loss #2 per Att. 3). 8:00 RM02M 73.6 (3:00) l 13:00

[ ramps ERP Kaman to release value) 0335/0905 RCIC steam leak results in exceeding Maximum Safe Operating Values (temperature) in two or more areas.

Operators emergency depressurize RPV.

Dose assessment results will not require PAR in excess of those required by plant conditions.

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Ev;lu ted Ex rcise CNS 1994 0355/0925 Isolation of RCIC steam line (RCIC- TRG E6 MO-16) . - ZDIRCICSWS2 Release terminated. Close (gives closed indication on RCIC-MO-16]

DMF RM02L DMF RM02M

[ deletes ERP kaman malf]

IMF RM02L 210:00 IMF RM02M 0 2:00

[ ramps ERP Kaman to post release value) 0410/0940 Recovery discussions begin 0430/1000 Enter recovery phase 0500/1030 Termination announcement l

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Section 8 1

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51f.S.SO()j- \ .foPPLS111EnJT19L ouT-O F- 4EGLRf AJC.4 ST/? Rf EYI45I-MESSAGE:

OUT-OF-SEQUENCE TO ALL OTHER MESSAGES. MESSAGE WILL CONSIST OF READING THE ' NORMAL' NOTIFICATION MESSAGE (EPIP 5.7.6, ATTACHMENT 1)

TO THE STATE OF MISSOURI DUTY OFFICER FROM A CONTROL CELL. THE NOUE WILL BE ON EMERGENCY ACTION LEVEL 1.1.1:

Uncontrolled, unmonitored radiological release ofliquid to the environment vNch has the potential to exceed Radiological Environmental Technical Soerh m (RETS).

PURIOSE:

THE S.QLE PURPOSE OF THIS MESSAGE IS TO ALLOW OFF-SITE AGENCIES (STATE)

TO DEMONSTRATE REAL-TIME RESPONSE.

-FEMA REGION .Vfj] WILL ALLOW STATE (S) TO EXERCISE THE OI7FION TO MOBILIZE AT A NOUE CLASSIFICATION.

LIMITATIONS:

IN ORDER TO MAINTAIN THE CONFIDENTIALITY OF THE START TIME AND DAi .

OF THE EXERCISE (0500 on 11-16-94) THIS MESSAGE WILL BE "ONE-WAY", THAT IS, NO CALL DACK VERIFICATIONS WILL BE MADE TO THE UTILITY.

THERE IS NO INTENDED RELATIONSHIP BETWEEN THE NOUE EVENTS OR ANY OTHER CLASSIFICATIONS IWENDED BY THE SCENARIO. UTILITY PERSONNEL i WILL NOT EVEN BE AWARE OF A NOUE CLASSIFICATION. ANY REFERENCE TO l A NOUE MADE OR HEARD AFTER UTILITY PLAY BEGINS WILL BE " PURGED" BY CONTROLLER INTERVENTION.

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-- This is a DRILL --

l COOPER NUCLEAR STATION INCIDENT REPORT l ATTACHMENT 1 l Notification Report #  !

Initial Report (Complete Sections 1 - 5) / Follow-Up Re' port (Complete Sections 1 - 8)

1. Current Time: b3Ob Current Date: /[ / /d /k Name: dokn To n9 s Call Back Number: AlcA/r- Do &rr hi

2. MNOUE ALERT SITE AREA GENERAL EMERGENCY Declared At: (Time) O 969 (Date) O / /d / kk EAL No. /, [. /

3. Wind Speed: b mph Wind Direction From: Degrees Stability Class: A B C@E F G Precipitation: Yes

/h

4. There , , ls E No Release Of Radioactive Material

, Was 4, Airborne 1 Will Be ,E t Liquid

5. Recommended Protective Actions None Evacuate Sectors Shelter Sectors 0 - 2 Miles V 2 - 5 Miles /

5 - 10 Miles / _

General Emergency Automatic PAR - Evacuate 2 mi radius /5 mi downwind, Shelter remainder 10 nJ E/Z.

6. Estimated Release Duration: brs Release: Start Time Step Time Release From: Release Height: ft (ERP - 3o0 ft all others 3o ft)

Release Rates: Noble Gas: Ci/sec lodines: Ci/sec Particulates: Ci/sec Projected Dose Rate (rem /hr) Projected Integrated Dose (rem)

TEDE CDE TEDE CDC Site Boundary 2 Miles  ;

5 Miles l 10 Miles

, 7. Prognosis Of Emergency Based On Plant information is:

Stable Unstable At Power Shutdown

8. Remarks: {1A]/710IdIW D kC D Mll&$ F~ nF E Roto A eTr u E LI C Lt t a 70 THE trir s.sn u t' 1 (LLVi L . l 01 s ..I s  :

Emergency Director: b  !/b/ -

qp w - ' vg-PROCEDURE NUMBER 5.7.f' This le n MigIpN.UUMBER 21 PAGE 9 OF 14

. 4 COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FORM MESSAGE NO: SIM-1 ELAPSED TIME: -0030 TO: Control Room Simulator Staff CLOCK TIME:

FROM: Lead Exercise Controller LOCATION: Control Room Simulator '

THIS IS A DRILL PLAYER MESSAGE:

initial Plant Conditions ,

The date is November 16,1994.

The plant is operating @ 95% power near end of core life having been at power for the previous 280 days. HPCI was placed out of service during the previous shift for auxiliary oil pump coupling replacement. HPCI is tagged out with its auxiliary oil pump coupling removed and is expected to be returned to service tomorrow. All other plant equipment is in a normal configuration. The operability requirements on RCIC, Core Spray and LPCI were satisfied during the previous shift. The ADS logic operability test is scheduled to be completed on this shift.

The plant is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> into a 7 day LCO.

The weather is cloudy and cold with a chance of flurries with winds out of the ,

norteast at six mph.

THIS IS A DRILL DO NOT INITIATE ANY ACTIONS THAT MAY AFFECT STATION OPERATION Page 8-2 .

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COOPER NUCLEAR STATION l EMERGENCY EXERCISE CONTROLLER FORM l MESSAGE NO: SIM-1 ELAPSED TIME: -0030 TO: Control Room Simulator Staff OLOCK TIME. i FROM: Lead Exercise Controller i LOCATION: Control Room Simulator  ;

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THIS IS A DRILL ,

CONTROLLER INSTRUCTIONS:  ;

Provide the initial conditions to the participating Plant Operator's assigned to the i exercise. Ensure Players have name tags and a copy of the Exercise Phone j List. Get all operations participants to sign the attendance sheet. Ensure that '

procedure 6.3.11.1 is signed by the real Shift Supervisor, and a Gal-tronics i announcement is made when the Simulator is cross-tied to the Plant Gai-tronics i system. Contact the Shift Supervisor at the real Control Room and tell him that the Exercise is starting and to initiate Message No. SIM-2 at time 1800.

All communications outside the Simulator must include the phrase "This is .!

a drill" l ANTICIPATED PLAYER RESPONSE:

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THIS A DRILL DO NOT ALLOW ANY ACTIONS THAT MAY AFFECT STATION OPERATION Page 8-3

e s COOPER NUCLEAR STATION l EMERGENCY EXERCISE MESSAGE FORM l MESSAGE NO: SIM-2 ELAPSED TIME: 0000 TO: Control Room Staff CLOCK TIME:

FROM: Lead Exercise Controller LOCATION: Control Room Simulator .

1 THIS IS A DRILL PLAYER MESSAGE:

Make the following Gai-tronics announcement when directed by the Lead Exercise Controller:

" ATTENTION ALL PERSONNEL. ATTEffTION ALL PERSONNEL.

THE 1994 EVALUATED EXERCISE IS COMMENCING. ALL ANNOUNCEMENTS PROCEEDED BY 'THISIS A DRILL' ARE FOR PLAYERS ONLY. IF AN ACTUAL EMERGENCY OCCURS, AN ANNOUNCEMENT WILL BE MADE THAT THE EXERCISE HAS BEEN SUSPENDED UNTIL FURTHER NOTICE. ALL PERSONNEL ARE REOUESTED TO MINIMlZE THE USE OF THE GAI-TRONICS UNTIL THE EXERCISE HAS BEEN COMPLETED."

4 THIS IS A DRILL DO NOT INITIATE ANY ACTIONS TH/.T MAY AFFECT STATION OPERATION  :

Pa<je 8-4

. s COOPER NUCLEAR STATION EMERGENCY EXERCISE CONTROLLER FORM MESSAGE NO: SIM-2 ELAPSED TIME: 0000 TO: Control Room Staff CLOCK TIME:

FROM: Lead Exercise Controller LOCATION: Control Room Simulator THIS IS A DRILL CONTROLLER INSTRUCTIONS:

Contact the Shift Su >ervisor in the real control room and inform him of the start of the 1994 Evaluated Exercise, then have the Control Room Simulator Shift Supervisor make the following Gal-tronics announcement.

ANTICIPATED PLAYER RESPONSE:

Start the exercise.

i THIS A DRILL DO NOT ALLOW ANY ACTIONS THAT MAY AFFECT STATION OPERATION Page 8-5

O d COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FORM MESSAGE NO: CHEM-3 ELAPSED TIME: 0040 TO: Chemistry Technician CLOCK TIME:

FROM: Controller LOCATION: Chem lab THIS IS A DRILL PLAYER MESSAGE:

Refer to attached data sheet for coolant chemistry analysis results.

)

l THIS IS A DRILL DO NOT INITIATE ANY ACTIONS THAT MAY AFFECT STATION OPERATION ,

Page 8-6 l

COOPER NUCLEAR STATION EMERGENCY EXERCISE CONTROLLER FORM MESSAGE NO: CHEM-3 ELAPSED TIME: 0040 TO: Chemistry Technician CLOCK TIME:

FROM: Controller LOCATION: Chem lab THIS IS A DRILL CONTROLLER INSTRUCTIONS:

Provide the area radiation and chemistry analysis results appropriate for sample time.

Prior to reactor scram: Data sheet 1 Post reactor scram: Data sheet 2 ANTICIPATED PLAYER RESPONSE:

Report results to Shift Supervisor.

Shift Supervisor declare Alert (EAL 2.2.1.A) if not already declared based on offgas radiation levels.

THIS A DRILL DO NOT ALLOW ANY ACTIONS THAT MAY AFFECT STATION OPERATION Page 8-7

i COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FORM MESSAGE NO: SIM-4X ELAPSED TIME: 0045 TO: Simulator Shift Supervisor CLOCK TIME:

FROM: Lead Exercise Controller LOCATION: Control Room Simulator l

THIS IS A DRILL l l

PLAYER MESSAGE:

Declare an Alert per EAL 2.2.1.A (coolant activity > 300 pCi/gm eg.1-131)

THIS IS A DRILL '

DO NOT INITIATE ANY ACTIONS THAT MAY AFFECT STATION OPERATION  ;

Page 8-8  !

s a COOPER NUCLEAR STATION EMERGENCY EXERCISE CONTROLLER FORM MESSAGE NO: SIM-4X ELAPSED TIME: 0045

'TO: Simulator Shift Supervisor CLOCK TIME:

FROM: Lead Exercise Controller LOCATION: Control Room Simulator l l

l THIS IS A DRILL CONTROLLER INSTRUCTIONS:

Provide this message to the Shift Supervisor only if he has not declared an Alert by this time.

l ANTICIPATED PLAYER RESPONSE:

Declare Alert (EAL 2.2.1.A) if not already declared based on either offgas radiation levels or coolant chemistry.

Implement Procedure 5.7.3 " Alert" and Procedure 5.7.6 " Notification".  !

Activate TSC and OSC.

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THIS A DRILL DO NOT ALLOW ANY ACTIONS THAT MAY AFFECT STATION OPERATION Page 8-9 i

COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FORM MESSAGE NO: TSC-5X ELAPSED TIME: 0230 TO: Emergency Director CLOCK TIME:

FROM: TSC Lead Controller LOCATION: TSC THIS IS A DRILL PLAYER MESSAGE:

Declare a Site Area Emergency per EAL 2.3.3.A & B (coolant activity > 300 Ci/gm eq.1-131 & Drywell pressure > 2.0 psig) l l

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THIS IS A DRILL l DO NOT INITIATE ANY ACTIONS THAT MAY AFFECT STATION OPERATION l Page 8-10 l

COOPER NUCLEAR STATION EMERGENCY EXERCISE CONTROLLER FORM MESSAGE NO: TSC-5X ELAPSED TIME: 0230 TO: Emergency Director CLOCK TIME:

FROM: TSC Lead Controller LOCATION: TSC THIS IS A DRILL CONTROLLER INSTRUCTIONS:

Provide this message to the Shift Supervisor only if he has not declared a Site I Area Emergency by this time.

l ANTICIPATED PLAYER RESPONSE:

Declare Site A'r ea Emergency (EAL 2.3.3.A & B) if not already declared.

Implement Procedure 5.7.4 " Site Area Emergency" and Procedure 5.7.6 ,

" Notification" Activate EOF if not already activated.

I THIS A DRILL DO NOT ALLOW ANY ACTIONS THAT MAY AFFECT STATION OPERATION Page 8-11 l

COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FORM MESSAGE NO: OSC-6 ELAPSED TIME: 0340 TO: RCIC Inspection Team CLOCK TIME:

l FROM: OSC Team Controller LOCATION: RCIC Ouad Intermediate Level THIS IS A DRILL PLAYER MESSAGE:

You hear rushing steam. Sounds like the steam leak may be in the torus area.

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i COOPER NUCLEAR STATION "cMERGENCY EXERCISE CONTROLLER FORM MESSAGE NO: OSC-6 ELAPSED TIME: 0340 TO: RCIC Inspection Team CLOCK TIME:

FROM: OSC Team Controller LOCATION: RCIC Ouad Intermediate Level 4

THIS IS A DRILL CONTROLLER INSTRUCTIONS:

Provide this indication to the OSC team dispatched to investigate the RCIC stream line break. If the team enters the RCIC quad, provide indication of steam flow noise and radiation levels as specified in the inplant radiation data for this area.

ANTICIPATED PLAYER RESPONSE:

Report observations to OSC.

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COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FORM MESSAGE NO: EOF-7X ELAPSED TIME: 0345 TO: Emergency Director CLOCK TIME:

FROM: EOF Lead Controller  ;

LOCATION: EOF THIS IS A DRILL PLAYER MESSAGE:

Declare a General Emergency per EAL 2.4.1.A & B & C (coolant activity > 300 pCi/gm eq.1-131 & Drywell pressure > 2.0 psig & Inability to isolate primary containment) i THIS IS A DRILL DO NOT INITIATE ANY ACTIONS THAT MAY AFFECT STATION OPERATION Page 8-14

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• COOPER NUCLEAR STATION EMERGENCY EXERCISE CONTROLLER FORM -

MESSAGE NO: EOF-7X ELAPSED TIME: 0345 TO: RCIC isolation Team CLOCK TIME:

FROM: OSC Team Controller LOCATION: Main Steam Tunnel THIS IS A DRILL CONTROLLER INSTRUCTIONS:

Provide this message to the Emergency Director only if he has not declared a

• General Emergency by this time.

ANTICIPATED PLAYER RESPONSE:

Declare General Emergency (EAL 2.4.1.A & B &C) if not already declared.

Implement Procedure 5.7 5 " General Emergency" and Procedure 5.7.6

" Notification".

Formulate and issue protective action recommendation per Procedure 5.7.20

" Protective Actions".

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I THIS A DRILL DO NOT ALLOW ANY ACTIONS THAT MAY AFFECT STATION OPERATION Page 8-15 l

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O O COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FORM MESSAGE NO: OSC-8 ELAPSED TIME: 0355 TO: RCIC isolation Team CLOCK TIME:

FROM: OSC Team Controller LOCATION: Main Steam Tunnel THIS IS A DRILL PLAYER MESSAGE:

After exerting heavy force on the manual hand wheel, RCIC-MO-16 breaks off its back seat and can be closed THISIS A DRILL '

DO NOT INITIATE ANY ACTIONS THAT MAY AFFECT STATION OPERATION Page 8-16

.o o COOPER NUCLEAR STATION EMERGENCY EXERCISE CONTROLLER FORM MESSAGE NO: OSC-8 ELAPSED TIME: 0355 TO: RCIC lsolation Team CLOCK TIME:

FROM: OSC Team Controller LOCATION: Main Steam Tunnel THIS IS A DRILL ,

CONTROLLER INSTRUCTIONS:

Provide this indication to the OSC team dispatched to the steam tunnel to attempt closing the 16 valve once action is taken to turn the manual hand wheel.

ANTICIPATED PLAYER RESPONSE:

Report to OSC that the valve has been shut.

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COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FORM MESSAGE NO: EOF-9X ELAPSED TIME: 0410 TO: Emergency Director CLOCK TIME:

FROM: EOF Lead Controller LOCATION: EOF THISIS A DRILL PLAYER MESSAGE:

For demonstration purposes of the Exercise, begin recovery discussions /

downgrading procedures at this time.

THIS IS A DRILL DO NOT INITIATE ANY ACTIONS THAT MAY AFFECT STATION OPERATION Page 8-18 l

COOPER NUCLEAR STATION ,

EMERGENCY EXERCISE CONTROLLER FORM MESSAGE NO: EOF-9X ELAPSED TIME: 0410 TO: Emergency Director CLOCK TIME:

FROM: EOF Lead Controller LOCATION: EOF THIS IS A DRILL CONTROLLER INSTROCTIONS:

If discussions related to recovery / downgrading procedures have not been initiated by this time, issue this message.

ANTICIPATED PLAYER RESPONSE:

Players should be cognizant of the following conditions in order to consider down grading and entry into recovery phase:

All plant radiation levels are stable or decreasing with time ERP vent radiation monitor readings are back on normal range Plant conditions no longer constitute a hazard to plant personnel Measures have been instituted to correct or compensate for malfunctioning equipment or barriers designed to contain radioactive materials.

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THIS A DRILL DO NOT ALLOW ANY ACTIONS THAT MAY AFFECT STATION OPERATION Page 8-19

COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FORM MESSAGE NO: All-10 ELAPSED TIME: 0500 TO: Facility Managers CLOCK TIME:

FROM: Lead Facility Controllers LOCATION: All Facilities THIS IS A DRILL PLAYER MESSAGE:

Terminate exercise play and notify players located outside the facility to return.

Perform a short critique of the exercise. When complete, perform the following:

1. Gather all facility logs, forms and other documents generated during the exercise and leave them at your station.

2. Return all equipment to appropriate storage locations.

3. Place all chairs, tables and other furniture back in their pre-exercise locations.

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COOPER NUCLEAR STATION EMERGENCY EXERCISE CONTROLLER FORM MESSAGE NO: All-10 ELAPSED TIME: 0500 TO: Facility Managers CLOCK TIME:

FROM: Lead Facility Controllers LOCATION: All Facilities l

THIS IS A DRILL i

CONTROLLER INSTRUCTIONS:

Terminate exercise play and notify all station personnel through the use of Message All-11. Conduct facility critiques and ensure all player comments are documented.

ANTICIPATED PLAYER RESPONSE:

Terminate from exercise.

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i THIS A DRILL DO NOT ALLOW ANY ACTIONS THAT MAY AFFECT STATION OPERATION Page 8-21

COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FORM MESSAGE NO: All ELAPSED TIME: 0500 TO: Control Room Staff CLOCK TIME:

FROM: Lead Exercise Controller LOCATION: Actual Control Room THIS IS A DRILL PLAYER MESSAGE:

Make the following Gai-tronics announcement when directed by the lead exercise controller:

" ATTENTION ALL PERSONNEL ATTENTION ALL PERSONNEL.

THE EXERCISE HAS BEEN TERMINATED NO FURTHER EXERCISE ANNOUNCEMENTS WILL BE MADE.

ALL EXERCISE PARTICIPANTS SHOULD CONDUCT A CRITIQUE IN YOUR EMERGENCY FACILITY" THE EXERCISE HAS BEEN TERMINATED" THIS IS A DRILL DO NOT INITIATE ANY ACTIONS THAT MAY AFFECT STATION OPERATION Page 8-22

COOPER NUCLEAR STATION .

EMERGENCY EXERCISE CONTROLLER FORM i MESSAGE NO: All-11 ELAPSED TIME: 0500 TO: Control Room Staff OLOCK TIME:

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

CONTROLLER INSTRUCTIONS:

Contact the Shift Supervisor in the Control Room and inform him that the exercise is now terminated and to please make the Gal-tronics announcement.

ANTICIPATED PLAYER RESPONSE:

Make termination announcement.

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THIS A DRILL DO NOT ALLOW ANY ACTIONS THAT MAY AFFECT STATION OPERATION Page 8-23

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l COOPER NUCLEAR STATION EMERGENCY EXERCISE MESSAGE FORM l

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SECTION 8.2 OPERATIONS DATA

SUMMARY

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Page 8-24 i t

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l SECTION 8.2 OPERATIONS DATA

SUMMARY

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CNS 1994 Operations Data Summary Evaluated Exerose 00:00 00:05 00:10 00:15 00:20 00:25 00:30 00:45 01:00 ID Nerne units 05:30 05:35 05:40 05:45 05:50 05:55 06:00 06:15 06:30 B000 APRM A Flux Level  % 92 84.1 79.3 59.8 43.6 43.9 0 0 0 j B012 Reactor Total Core Flow Mibm/hr 76.4 65.0 57.8 37.3 30.7 30.8 11.0 11.8 11.2

, B013 Reactor Core Prese-Diff PSD 21.5 16.1 12.2 5.3 3.6 3.6 1.0 0.9 1.0 B025 Reactor Pressure PK3 1020 1000 977 958 947 948 901 808 858 F084 Drywell Pressure PT512A PSG 0.2 0.2 0.2 0.2 0.2 0.2 0.2 0.5 0.5 G038 Drywell Pressure PEE 0.2 0.2 0.2 0.2 0.2 0.2 0.2 0.4 0.5 G039 Torue Pressure PSG 0.2 0.2 0.2 0.2 0.2 0.2 0.2 0.5 0.5 N003 RCIC Fkm G%4 0 0 0 0 0 0 398 330 331 N004 RHR Flow A G%I O O O O O O 7590 7590 7590 N005 RHR Fkm B GM 0 0 0 0 0 0 -0 0 0 N009 Reactor Water Level A (FZ) In. 186 182 174 145 145 144 159 155 151 N011 Reactor Water Level B In. 185 36 37 35 37 35 52 41 40 N013 Reector Pressure A PT1 1020 999 977 958 947 948 901 808 858 N015 Containment Pressure A (WR) PM3 0.2 0.2 0.2 0.2 0.2 0.2 0.2 0.5 0.5 N017 Containment Pressure A (NR) PSG 0.2 0.2 0.2 0.2 0.2 0.2 0.2 0.5 0.5 i N019 Suppreselon Pool Level A in. 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.9 N023 Suppression Pool WTR Temp TE-1 A P 80 80 80 80 80 80 80 83 85 N277 Drywell Zone 2B Area Temp F 121 121 121 120 120 120 120 120 120 N333 Reactor Water levet A (WR) in. 40 40 42 41 43 41 60 52 48 N781 GRP 21 SOL CHAN A 1 1 1 1 1 1 0 0 0 N783 GRP 31 SOL CHAN A 1 1 1 1 1 1 0 0 0 N787 GRP 5 ISOL CHAN A 1 1 1 1 1 1 1 1 1 N789 GRP 6 tSOL CHAN A 1 1 1 1 1 1 1 1 1 N791 GRP 71 SOL CHAN A - 1 1 1 1 1 1 1 1 1 i

I Page 8-25

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

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CNS 1994 Ooerations Data Summarv Evaluated Exercise m

l 01:15 01:30 01:45 01:50 02:00 02:15 02:30 02:45 4 03:00 4

ID Nome unite 06:45 07:00 07:15 07:20 07:30 07:45 08:00 08:15 08:30 B000 APRM A Flux Level  % 0 0 0 0 0 0 0 0 0 B012 Reector Total Core Flow Mlbm/hr 10.2 14.2 13.5 13.5 11.2 11.1 12.5 11.1 11.1 0013 Reactor Core Prese-Diff PSD 1.0 0.8 0.8 0.8 0.6 0.6 0.7 0.6 0.6 8025 Reactor Presouro PSG 970 543 502 506 546 574 542 499 523 F084 Drywell Pressure PT512A PSG 0.5 0.7 0.9 0.8 1.7 2.9 3.7 4.0 4.2 G038 Drywell Pressure PSG 0.5 1.0 0.9 0.9 1.7 2.9 3.7 4.0 4.2 G039 Torus Pressore P33 0.5 0.7 0.9 0.8 1.7 2.0 2.3 3.1 3.4 NOC3 RCIC Fbw (FM 331 415 0 239 0 0 0 314 243 N004 RHR Flow A CRA 7590 7560 7520 7530 7520 0 0 0 0 N005 RHR Flow B CR4 0 7890 7870 7870 7860 0 0 0 0 N009 Reactor Water level A (FZ) In. 150 171 187 183 161 159 167 148 146 N011 Reactor Water Level B in. 45 41 59 55 58 58 60 35 36 N013 Reactor Pressure A PSG 970 543 502 506 546 575 542 499 523 N015 Containment Pressure A (WR) PSG 0.5 0.7 0.9 0.8 1.6 2.8 3.7 4.0 4.2 N017 Containment Pressure A (NR) PSG 0.5 0.7 0.9 0.8 1.7 2.9 3.7 4.0 4.2 NO19 Suppression Pool Level A in. 12.9 13 13.1 13.1 13.2 13.3 13.3 13.4 13.4 NO23 Suppress 6on Pool WTR Temp 1 A P 86 91 93 94 95 95 95 98 100 N277 Drywell Zone 2B Area Temp 7 120 118 116 116 124 140 151 153 156 N333 Reactor Water Level A (WR) In. 51 59 65 65 65 65 65 56 55 N781 GRP 2 tSOL CHAN A 0 0 0 0 0 0 0 0 0 N783 GRP 3 fSOL CHAN A 0 0 0 0 0 0 0 0 0 N787 GRP S ISOL CHAN A 1 1 1 1 1 1 1 1 1 N789 GRP 6 tSOL CHAN A 1 1 1 1 0 0 0 0 0 N791 GRP 7 tSOL CHAN A 1 1 1 1 1 1 1 1 1 Page 8-26

a CNS 1994 Ooerations Data Summary Evaluated Exercise 03:15 03:30 03:45 04:00 04:15 04:30 04:45 05:00 ID Nonie units 08:45 09:00 09:15 09:30 09:45 10:00 10:15 10:30 B000 APRM A Rux Level  % 0 0 0 0 0 0 0 0 B012 Reector Total Core Flow M!bm/hr 11.1 11.1 12.9 14.8 16 7 18.6 20.6 22.5 B013 Reector Core Press-Dtff PSD 0.6 0.6 0.8 1.0 1.3 1.5 1.8 2.0 8025 Reactor Pressure PE 544 571 555 531 506 482 457 433

F084 Drywell Pressure PT512A PE 4.4 4.6 5.2 5.8 6.4 6.9 7.5 8.1 G038 Drywell Pressure PE 4.4 4.6 5.2 5.8 6.4 6.9 7.5 8.1 G039 Torus Pressure PSG 3.5 3.7 4.1 4.9 5.5 6.0 6.5 7.2 N003 RCIC Flow G%4 245 375 134 41 0 0 0 0 N004 RHR Flow A G14 0 0 0 0 0 0 0 0 N005 RHR Flow B GWI O O O O O O O O N009 Reactor Water Level A (FZ) In. 146 145 145 144 143 142 142 141 N011 Reactor Water Level B in. 37 39 53 68 82 97 112 127 N013 Reactor Pressure A PE 544 571 555 531 506 482 457 433 i N015 Containment Pressure A (WR) PE 4.4 4.6 5.2 5.8 6.5 7.1 7.7 8.3 N017 Containment Pressure A (NR) PE 4.4 4.6 5.2 5.8 6.4 6.9 7.5 8.1 N019 Suppression Pool Level A in. 13.4 13.4 13.4 13.4 13.4 13.4 13.4 13.4 N023 Suppression Pool WTR Temp TE-1 A F 100 100 102 104 106 108 110 113 N277 Drywell Zone 29 Area Temp P 158 161 169 177 185 193 201 209 N333 Reactor Water Level A (WR) 5. 56 57 69 82 95 108 121 134 N781 GRP 2 tSOL CHAN A 0 0 0 0 0 0 0 0 N783 GRP 3 tSOL CHAN A 0 0 0 0 0 0 0 0 N787 GRP 5 l SOL CHAN A 1 1 1 1 1 1 1 1 N789 GRP 6 tSOL CHAN A 0 0 0 0 0 0 0 0 N791 GRP 7 tSOL CHAN A 1 1 1 1 1 1 1 1 Page 8-27

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CNS 1994 Evaluated Extrcise Section 9 S

RADIOLOGICAL DATA l

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6 s j CNS 1994 Evaluited Exercise Section 9: RADIOLOGICAL DATA -

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SECTION IIILE PAGE '

9.1 Radiological Ass u m ptions .... ........ ..... .. . ....... . . .... . ... . ...... .... .... . ... ... ... 9-1 Assumptions  ;

Release Rate Curves Table 9.1-1 1 9.2 Massages 'and Trend Data......................... ...................................9-4  ;

National Weather Service Forecast Message i

. Meteorological and Vent Flow Data . Table 9.2-1 & 2 ,

Monitor Trend Data Table 9.2-3 l 9.3 Cou nt Room Da ta . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . 9-9 Reactor Cociant Activity Table 9.3-1 ,

5 9.4 in -Pla nt Ra diologic a I D ata . .. ... .......... ... . .. .. .. . . . . . . .... ... .. . ... ..... ..... ... . . 9-10  ;

Reactor Building (859') Table 9.4-1  !

Reactor Building (881') Table 9.4-2 i Reactor Building (903') Table 9.4-3 l Reactor Building (931') Table 9.4-4  ;

Reactor Building (958') Table 9.4-5  ;

Reactor Building (976') Table 9.4-6 i Reactor Building (1001') Table 9.4-7 l

. Turbine Building (882') Table 9.4-8 i Turbine Building (903') Table 9.4-9  ;

Turbine Building (932') Table 9.4-10 l 9.5 Dose Assessment Da ta . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . .. . . . .. . . . . . . . . . .. . .. . . .. . . .. 9-4 0 l Computer Runs By Scenario Time l

' Total Population Exposure Table 9.5-1  :

9.6 Plume Phans 'dnvironmental Information . .... .......... ........... ...... ... 9-45 Onsite Plume Map l

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Onsite Survey and Sample Data Table 9.6-1 Field Team Data Offsite Plume Map Release Segment Times Table 9.6-2 Closed Window WB Dose Rates Table 9.6-3 'j Open Window WB Dose Rates Table 9.6-4 '

Thyroid Dose Rates Table 9.6-5 l Totallodine Concentration Table 9.6-6 l-131 Concentrations Table 5.6-7 i lodine Cartridge Readings (SAM-II) Table 9.6-8 j lodine Cartridge Readings (E-520) Table 9.6-9 Gross Particulate Concentration Table 9.6-10  !

i Particulate Filter Readings (E-140-N) Table 9.6-11 Particulate Filter Readings (E-520) Table 9.6-12 ,

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I CNS 1994 Evaluated Exercise 1

I Section 9.1  ;

Radiological Assumptions i 1

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6 e CNS 1994 Evaluated Exc: use Assumptions General ~

1. The radiological effluent and process monitor data in this scenario is modeled to be l consistent with the postulated operational sequence of events. Protective action recommendations are based on plant conditions which drive the classification of General Emergency. Initial Area Radiation Monitor data was developed using the CNS simulator. As such, key in-plant radiological conditions have been designed to l allow participants to perform actions consistent with the scenario and may deviate  ;

from the dynamic values generated by the simulator during the evaluated exercise.

2. The release path for this scenario is through the Elevated Release Point originating from inside the Reactor Building from a ruptured RCIC line in the Torus area. Main steam (reactor coolant) noble gas and halogen relative abundance will be consistent with a source activity of approximately 20% cladding failure as calculated using Chemistry Procedure 8.4.1.1, " Estimating Core Damage" in order to provide chemistry results which are consistent with the classification. Radioactive material released to the environment will consist of noble gases and halogens. Isotopic fractions are maintained consistent with a cladding failure. Process reduction factors and hold up times are consistent witn W methodology of NUREG-1228 utilized within the CNS-DOSE code, therefore appropriate credit is taken towards removal of halogen sources by these means. Since the release bypasses the drywell and torus, by a direct release of reactor coolant into the reactor building, no filtration or reduction credit is taken for primary containment.

3. Onsite and field data will be provided to plant teams only when they perform appropriate tasks and request specific information.

Dos 2 Assessment and Environmental Data

1. Stack release concentrations are based upon a ventilation flow rate of 6,400 CFM.

This is consistent with the isolation of the Reactor Building ventilation, initiation of both trains of Stand-By Gas Treatment at 1,350 CFM each, and continued use of Radwaste Building, Off-Gas Building, and Turbine Building (high) fans.

2. The dispersion factors used in dose assessment calculations for the derivation of protective action recommendations and the creation of offsite field data are those contained in the CNS-DOSE computerized dose assessment program, for EPA TEDE, external, and thyroid dose rates.

3. Air sample results are calculated using EPIP 5.7.18, "Offsite and Site Boundary Monitoring," 5.7.19, "Onsite Radiological Surveys," and Health Physics Procedure 9.6.4, "Eberline SAM-2." Airborne concentrations are calculated using an assumed air sample volume of 15 ft3 and a background level of 40 CPM. E-140-N efficiencies are assumed to be 10%

4. Survey results within the plume or other high airborne areas are similar at waist and ground level readings. It is assumed deposition values are insignificant compared to immersion levels while surveys are performed within the plume.

Page 9-1 Revsion 2

s o CNS 1994 Evaluated Exercise '

5. Open window reading are assumed to be approximately 2.3 times greater than closed window readings while immersed in the plume for this isotopic mix.

f

6. E-140-N area reading conversion: 2000 CPM = 1 mR/hr Open Window.

Count Room Data

1. The fractions for the various radionuclides are generated by back calculation from the values utilized by the simulator to drive the events. Core damage assessment  ;

performed using Chemistry Procedure 8.4.1.1, " Estimating Core Damage", assumes  ;

the reactor has been operating at an average power of 100% for 280 days.

2. Dose rates from post-accident samples were calculated using the Radiological Health Handbook rule of thumb:

r B

R/hr at 1 foot 5.64CE where:

C = number of curies E = energy in MeV E is conservatively assumed to be 0.5 MeV for iodine and 0.7 MeV for noble gases.

In-Plant Radiological Data  :

1. The fractions for the various radionuclides are determined as in item 1 above. <

2. Immersion dose rates were developed by calculating a center point dose in a semi-infinite cloud of noble gases, utilizing the formula:

D = EX i* DFi where:

D = gamma air dose Xi = concentration of nuclide i DFi = dose factor for exposure to a semi-infinite cloud of nuclide i. I I

Dose factors were obtained from Regulaiory Guide 1.109, Table B-1, pp.1.109-21.

\

3. Dose rates for in-plant areas are calculated using point, line, and plane source  ;

equations from simulator generated ARM response data. Where appropriate, dose rates from affected plant systems are also calculated using point, line, and plane source equations.

4. Air sample results are calculated in the same manner as the field team air samples described in the dose assessment section above.

l Page 9-2 Revis.on 1 l

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Halogens 09:45 10.00 Table 9.1-1 Scenario 09:05 09:15 09:25 09:35 09:45 10:00 Elapsed 03:35 03:45 03:55 04:05 04:15 04:30 Noble Gases 1.0E+00 2.0E+07 2.5E+07 2.2E+07 1.8E+07 1.0E+00 Halogens 1.0E+00 1.3E+04 1.6E+04 1.4E+04 1.2E+04 1.0E+00 Total 1.0E+00 2.0E+07 2.5E+07 2.2E+07 1.8E+07 1.0E+00 Page 9-3 nevision 2

CNS 1994 Evaluated Exercise l

1 l

Section 9.2 Messages and Trend Data t

i

CNS 1994 Evaluated Exercise I

Section 9.3 Count Room Data

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l l

CNS 1994 Evaluated Exercise j MIDWESTERN ZOiG FORECASTS  !

NATIONAL WEATHER SERViOE, LINCOLN NE.

A changing weather pattern will exist throughout the area. A weak high pressure zone will move through the region towards the east causir g winds to shift to a more westerly direction. Clouds will develop during the afternoon yie.iding a slight chance of scattered flurries a.s the unorganized front moves through. Skies will be cleared by tomorrow morning with an area of high pressure dominating the r0gion for the next several days.

MISSOURI RIVER AREA NEBRASKA CITY AND SOUTHEASTERN NE.

This morning will be partly cloudy with temperatures 30 to 40 . Winds steady from the NE 3 to 8 MPH. 20% chance of precipitation.

This afternoon will be partly cloudy with temperatures 40 to 50 . Winds picking up from the NE 5 to 10 MPH with gusts of up to 15 MPH. 30% chance of precipitation.

This evening will be cloudy with temperatures 35 to 45 . Winds from the NE 5 to 10 MPH with gusts of up to 15 MPH. 40% chance of precipitation.

Tonight, cloudy and breezy temperatures 25 to 35 . Winds from the NE 5 to 10 MPH with gusts of up to 15 MPH. 30% chance of precipitation.

Tomorrow morning will be sunny with temperatures ranging 25 to 35 F. Winds from the east 10 tc 15 MPH with gusts of up to 20 MPH. 20% chance of precipitation.

Tomorrow afternoon will have increasing clouds with temperatures 35 to 45 Winds from the east 15 to 20 MPH with gusts of up to 25 MPH. 30% chance of precipitation.

Tomorrow Evening will have decreasing cloudiness with high temperatures 45 to 55" Winds steady from the ESE 8 to 13 MPH. 20% chance of precipitation.

Long range forecast; clear skies with high temperatures 45 to 55 and low temperatures 25 to 35 . Winds will be steady from the SE 5 to 10 MPH.

Page 9-4 Revtsion 1

e CNS 1994 Evaluated Exercise

• Meteorological Vent and Fiow Data Wind Direction (*From) Wind Speed (MPS, Stability SBGT RBV ERP ~ TB Vent Elapsed Scenario 100m 60m 10m 100m 60m 10m Class 'F CFM CFM CFM CFM 00:00 05:30 058 057 055 4.8 4.7 4.5 C 23 ISOLATED 70,000 3,000 152,000 C~

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00:15 05:45 057 ~656~ 054 ~56- - 4 ~T 77- 2i- ISOLATED ~f0 000 .

3,000 i52,000 00:30 06:00 058 057 055 5.4 5.3 5.1 C 24 2,700 ISOLATED 4,400 152,000 00 45 06:15 057 056 054 5.2 5.1 4.9 C 24 2,700 ISOLATED 4,400 152,000 01:00 06:30 057 056 054 5.3 5.2 5.0 C 24 2,700 ISOLATED 4,400 152,000 01:15 06:45 057 056 054 5.5 5.4 5.2 C 24 2,700 ISOLATED 4,400 152,000 01:30 07:00 058 057 055 5.6 5.5 5.3 C 24 2,700 ISOLATED 4,400 152,000 01:45 07:15 - 058 057 055 5.8 5.7 5.5 C 25 2,700 ISOLATED 4,400 152,000 02:00 07:30 057 056 054 5.7 5.6 5.4 C 25 2,700 ISOLATED 4,400 152,000 02:15 07:45 057 056 054 5.5 5.4 5.2 C 26 2.,700 ISOLATED 4,400 152,000 02:30 08:00 057 056 054 5.8 5.7 5.5 C 26 2,700 ISOLATED 4,400 152,000 02:45 08:15 057 056 054 6.0 5.9 5.7 C 27 2,700 ISOLATED 4,400 152,000 03:00 08:30 057 056 054 6.1 6.0 5.8 C 28 2,700 ISOLATED 4,400 152,000 03:15 08:45 057 056 054 6.0 5.9 5.7 C 29 2,700 ISOLATED 4,400- 152,000 03:30 09:00 056 055 053 6.2 6.1 5.9 C 29 2,700 ISOLATED 4,400 152,000-03:45 09:15 056 -055 - ~655- ~6.T ~ 5?6~ ~ 5.8 ' ~ ~C~ ~30 ~ ~5,706- ISOllt5D 4,400 15~,660 04:00 09:30 056 055 053 6.0 5.9 5.7 C 31 2.700 ISOLATED 4,400 152,000 04:15 09:45 057 056 054 7.3 7.2 7.0 C 32 2.700 ISOLATED 4,400 152,000 04:30 10:00 057 056 054 8.0 7.9 7.7 C 33 2,700 ISOLATED 4,400 152,000 04:45 10:15 054 9.0 8.9 8.7 C 34 2,700 lSOLATED 4,400 _

057_ _056_. }5[666~

_C 05:00 10:30 _ 055 . 057 _055 10.0 , 9.9. 9.7 . 35 ,2,700_ ISOLATED 4,400 152,000 Table 9.2-1 Table 9.2-2 s

i Page 9-5 n yi. ion i  ;

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CNS 1994 Monitor Trend Data Evaluated Exercise Table 9.2-3 00:00 00:05 00:10 00:15 00:20 00:25 00:30 00:45 01:00 ID Name units 05:30 05:35 05:40 05:45 05:50 05:55 06:00 06:15 06:30 N091 ARM-1 Fuel Pool Area (Refueling) RMA mR/hr 210 210 210 210 210 210 210 210 210 N092 ARM-2 Fuel Pool Area mR/hr 1.93 1.97 2.12 2.27 2.27 2.27 3.77 3.77 3.77 N093 ARM-3 New Fuel Area mR/hr 0.04 0.05 0.08 0.11 0.11 0.11 0.41 0.41 0.41 N094 ARM-4 RWCU Precoat Area mR/hr 7.3 11.5 18.5 26.3 26.0 26.0 101.0 101.0 101.0 N095 ARM-5 RWCU Sludge /Precoat Area mR/hr 1.0 1.2 1.9 2.7 2.7 2.7 10.2 10.2 10.2 N096 ARM-6 Tip System index Area mR/hr 26.2 28.0 35.4 43 0 43.0 43.0 118.0 118.0 118.0 N097 ARM-7 Tip System Drive Area mR/hr 1.86 1.86 1.87 1.89 1.89 1.89 - 2.04 2.04 2.04 N098 ARM-8 CRD/HCU Equip Area-South mR/hr 0.73 0.90 1.64 2.40 2.40 2.40 9.90 9.90 9.90 N099 ARM-9 CRD/HCU Equip Area-North mR/hr 4.74 5.08 6.56 8.09 8.09 8.09 23.10 23.10 23.10 .

N100 ARM-10 HPCI Pump Room mR/hr 0.92 0.71 0.71 0.E6 0.91 0.86 2.36 2.36 2.36 N101 ARM-11 RHR Pump Room-SW mR/hr 4.10 4.62 6.84 9.12 9.12 9.12 31.60 31.60 31.60 N102 ARM-12 RHR Pump Room-NW mR/hr 16.80. 17.70 21.40 25.20 25.20 25.20 62.70 62.70 62.70 N103 ARM-13 RCIC/CS Pump Room-NE mR/hr 2.62 2.65 2.73 2.81 2.80 2.80 56.60 51.00 53.90 N104 ARM-14 CS Pump Room-SE mR/hr 2.55 2 56 2.64 2.71 2.71 2.71 4.74 3.59 3.57 N105 ARM-15 Turb Front Standard mR/hr 118.0 123 0 306.0 493.0 499.0 499.0 22.8 19.9 15.2 N106 ARM-16 Turb Mez Control Corr mR/hr 0.09 0.12 0.11 OSH OSH OSH OSH OSH OSH N107 ARM-17 Turb Bsmt Control Corr mR/hr 0.06 0.06 0.06 33.04 38.08 59.36 71.96 63.28 55.16 N108 ARM-18 Reactor Feed Pump Area mR/hr 9.36 10.10 215.00 5460.00 6270.00 9780.00 7590.00 6630.00 5790.00 N109 ARM-19 Condensate Pump Area mR/hr 0.10 0.11 0.10 0.09 0.08 0.08 0.06 0.06 0.06 N111 ARM-21 Grade Level Control Corndor mR/hr 0.25 0.25 0.25 0.25 0.25 0.25 0.25 0.24 0.23 N079 ERP Normal Range pCi/sec 1 1 2 2 2 2 2 1 1 N078 ERP High Range pCi/sec DS DS DS DS DS DS DS DS DS N303 MS Line A Radiation Monitor mR/hr 265 419 620 749 712 713 336 336 336 N082 SJAE A Radiation Monitor mR/hr 4 4 1500 11800 13600 21200 25700 22600 19700 N083 SJAE B Radiation Monitor mR/hr 6 6 2310 18200 20900 32600 25300 22100 19300 N064 HR Drywell Ladder ARM RMA R/hr 5 11 19 29 29 29 1920 2000 1976 Page 9-6 nevision 2 l

l L__--________._. - . - - _ _ __ _ _ . _. _ _ _ _ _ _ _ - - _ . - _ _ _ _ _ _ - - - - -

CNS 1994 Evaluated Exercise' Monitor Trend Qata ,

Table 9.2-3

~

01:15 01:30 01:45 02:00 02:15 02:30 02:45 03:00 03:15 ID Name units 06:45 07:00 07:15 07:30 07:45 08:00 08:15 08:30 08:45 N091 ARM-1 Fuel Pool Area (Refuehng) RMA mR/hr 210 210 210 210 210 210 210 210 210 I N092 ARM-2 Fuel Pool Area mR/hr 3.77 3.77 3.77 3.77 3.77 3.77 3.77 3.77 3.77 N093 ARM-3 New Fuel Area mR/hr 0.41 0.41 0.41 0.41 0 41 0.41 0.41 0.41 0.41 N094 ARM-4 RWCU Precoat Area mR/hr 101.0 101.0 101.0 101.0 101.0 101.0 101.0 101.0 101.0 N095 ARM-5 RWCU Sludge /Precoat Area mR/hr 10.2 10.2 10.2 10.2 10.2 10.2 10.2 10.2 10.2 l N096 ARM-6 Tip System Index Area mR/hr 118.0 118.0 118.0 118.0 118.0 118.0 118.0 118.0 118.0 N097 ARM-7 Tip System Drive Area mR/hr 2.04 2.04 2.04 2.04 2.04 2.04 - 2.04 2.04 2.04 N098 ARM-8 CRD/HCU Equip Area-South mR/hr 9.90 9.90 9.90 9.90 9.90 9.90 9.90 9.90 9.90 N099 ARM-9 CRD/HCU Equip Area-North mR/hr 23.10 23 10 23 10 23.10 23.10 23.10 23.10 23.10 23.10 N100 ARM-10 HPCI Pump Room mR/hr 2.36 2.36 2.36 2.36 2.36 2.36 2.36 2.36 2.36 I N101 ARM-11 RHR Pump Room-SW mR/hr 31.60 31.60 31.60 31.60 31.60 31.60 31.60 31.60 31.60 N102 ARM-12 RHR Pump Room-NW mR/hr 62.70 62.70 62.70 62.70 62.70 62.70 62.70 62.70 62.70 N103 ARM-13 RCIC/CS Pump Room-NE mR/hr 60.30 36.00 25.20 29.80 26.60 20.70 32.80 34.10 35.30 N104 ARM-14 CS Pump Room-SE mR/hr 3.57 3.57 3.57 3.57 3.57 3.57 3.57 3.57 3.57 N105 ARM-15 Turb Front Standard mR/hr 12.2 10.2 8.6 7.8 7.5 7.2 6.9 6.7 6.5 N106 ARM-16 Turb Mez Control Corr mR/hr OSH OSH OSH OSH OSH OSH OSH OSH OSH N107 ARM-17 Turb Bsmt Control Corr mR/hr 48.44 42.28 35.84 31.36 29.68 27.52 26.01 24.56 23.21 N108 ARM-18 Reactor Feed Pump Area mR/hr 5040.00 4380.00 3690 00 3240.00 3060.00 2817.00 2655.00 2505.00 2361.00 N109 ARM-19 Condensate Pump Area mR/hr 0.06 0.06 0.06 0.06 0.06 0.06 0.06 0.06 -

0.06 N111 ARM-21 Grade Level Control Comdor mR/hr 0.23 0.22 0.22 0.21 0.21 0.21 0.21 0.20 0.20 N079 ERP Normal Range pCi/sec 1 1 2 2 2 2 2 1 1 N078 ERP High Range pCi/sec DS DS DS DS DS DS DS DS DS N303 MS Line A Radiation Monitor mR/hr 336 336 336 336 336 336 336 336 336 N082 SJAE A Radiation Monitor mR/hr 17300 15100 12800 11200 10600 9830 9290 8770 8290 N083 SJAE B Radiation Monitor mR/hr 16800 14600 12300 10800 10200 9390 8850 8350 7870 N064 HR Drywell Ladder ARM RMA R/hr 1953 1929 1906 1882 1859 1835 1812 1788 1765 Page 9-7 noi.% 2

CNS 1994 ylonjtor Trand_D_ata Evaluated Exercise Table 9,2-3 03:30 03:45 04:00 ' 04:15 04:30 05:00 ID Name units 09:00 09:15 09:30 09:45 10:00 10:30 N091 ARM-1 Fuel Pool Area (Refueling) RMA mR/hr 210 210 210 210 210 210 N092 ARM-2 Fuel Pool Area mR/hr 3.77 3.77 3.77 3.77 3.77 3.77 N093 ARM-3 New Fuel Area mR/hr 0.41 0.41 0.41 0.41 0.41 0.41 N094 ARM-4 RWCU Precoat Area mR/hr 101.0 101.0 101.0 101.0 101.0 101.0 N095 ARM-5 RWCU Studge/Precoat Area mR/hr 10.2 10.2 10.2 10.2 10.2 10.2 N096 ARM-6 Tip System Index Area mR/hr 118.0 118.0 118.0 118.0 118.0 118.0 N097 ARM-7 Tip System Drive Area mR/hr 2.04 2.04 2.04 2.04 2.04 2.04 N098 ARM-8 CRD/HCU Equip Area-South mR/hr 9.90 9.90 9.90 9.90 9.90 9.90 N099 ARM-9 CRD/HCU Equip Area-North mR/hr 23.10 23.10 23.10 23.10 23.10 23.10 N100 ARM-10 HPCI Pump Room mR/hr 2.36 2.36 2.36 2.36 2.36 2.36 N101 ARM-11 RHR Pump Room-SW mR/hr 31.60 31.60 31.60 31.60 31.60 31.60 N102 ARM-12 RHR Pump Room-NW mR/hr 62.70 62.70 62.70 62.70 62.70 62.70 N103 ARM-13 RCIC/CS Pump Room-NE mR/hr 36.70 37.45 37.49 37.54 37.58 37.66 N104 ARM-14 CS Pump Room-SE mR/hr 3.57 3.57 3.57 3.57 3.57 3.57 N105 ARM-15 Turb Front Standard mR/hr 6.3 5.6 4.9 4.2 3.5 2.1 N106 ARM-16 Turb Mez Control Corr mR/hr OSH OSH OSH OSH OSH OSH N107 ARM-17 Turb Bsmt Control Corr mR/hr 21.50 15.93 10.42 4.92 4.62 3.92 N108 ARM-18 Reactor Feed Pump Area mR/hr 2184.00 1599.91 1022.63 445.34 420.00 360.00 N109 ARM-19 Condensate Pump Area mR/hr 0.06 0.06 0.06 0.06 0.06 0.06 N111 ARM-21 Grade Level Control Corridor mR/hr 0.20 0.20 0.20 0.20 0.20 0.20 N079 ERP Normal Range pC /sec OSH OSH OSH 100 48 15 N078 ERP High Range pCi/sec 20000000 23000000 18000000 DS DS DS N303 MS Line A Radiation Monitor mR/hr 336 336 336 336 336 336 N082 SJAE A Radiation Monitor mR/hr 7680 5690 3723 1756 1650 1400 N083 SJAE B Radiation Monitor mR/hr 7280 5333 3409 1484 1400 1200 l N064 HR Drywell Ladder ARM RMA R/hr 1741 1718 1694 1671 1647 1600 l

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l Page 9-8 Resen 2

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CNS 1994 Evaluated Exercise l Reactor' Coolant Activity l

Table 9.41 l Elapsed 00:10 01:00 02:00 03:00 04:00 05:00 l Scenano 05:40 06:30 07:30 08:30 09:30 10:30 Nome _Gassas_ruci/cc)

Xe-133 1.92E+02 1.92E+02 1.91E+02 1.89E+02 1.88E+02 1.87E+02 Xe-135 1.16E+00 1.11 E+00 1.03E+00 9.53E-01 8.83E-01 8.18E-01 Kr-85m 4.42 E+00 4.04E+00 3.46E+00 2.96E+00 2.54E+00 2.17E+00 Kr-85 7.39E-0" 7.39E-02 7.39E-02 7.39E-02 7.39E-02 7.39E-02 Kr-87 4.48E+00 3.26E+ 00 1.89E+00 1.09E+00 6.33E-01 3.67E-01 Kr-88 9.52E+00 8.26E+00 6.47E+00 5.07E+00 3.97E+00 3.11E+00 Total 2.12E+02 2.08E+02 2.03E+02 2.00E+02 1.97E+02 1.94E+02 lodJnes (uCl/cc) l-131 3.00E+02 2.99E+02 2.98E+02 2.97E+02 2.96E+02 2.95E+02 1-132 3.82E+01 3.20E+01 2.36E+01 1.74E+01 1.29E+01 9.48E+00 1-133 2.06E+02 2.02E+02 1.95E+02 1.89E+02 1.83E+02 1.77E+02 1-134 4 66E+01 2.94E+01 1.33E+01 6.02E+00 2.73E+00 1.24E+00 1-135 1.10E+02 1.03E+02 9.28E+01 8.35E+01 7.51 E+01 6.75E+01 DEI 3.67E+02 3.64E+02 3.60E+02 3.56E+02 3.53E+02 3.49E+02 P_atticulaterducil.ctd Cs-134 1.70E+01 1.70E+01 1.70E+01 1.70E+01 1.70E+01 1.70E+01 Cs-137 7.72E+00 7.72E+00 7.72E+00 7.72E+00 7.72E+00 7.72E+00 Cs-138 4.32E+02 3.16E+02 1.85E+02 1.08E+02 6.31 E+01 3.69E+01 Te-132 6.72E-01 6.69E-01 6.63E-01 6.57E-01 6.51 E-01 6.45E-01 Sr-91 5.60E-03 5.37E-03 4.99E-03 4.64E-03 4.31 E-03 4.01E-03 Sr-92 5.98E-03 5.15E-03 3.99E-03 3.09E-03 2.39E-03 1.85E-03 Ba-140 8.44E-03 8.43E-03 8.41 E-03 8.39E-03 8.37E-03 8.35E-03 Total 4.57E+02 3.41 E+02 2.10E+02 1.33E+02 8.86E+01 6.23E+01 Samole Exposure Rates (mR/hr) 10 ml Samole Volume On Contact No Shield 2946.67 2916.77 2872.81 2835.30 2802.22 2772.33 2" Pb Shield 294.67 291.68 287.28 283.53 280.22 277.23 4" Pb Shield 29.47 29.17 28.73 28.35 28.02 27.72 1.Eco!

No Shield 20.46 20.26 19.95 19.69 19 46 19.25 2" Pb Shield 2.05 2.03 2.00 1.97 1.95 1.93 4" Pb Shield 0.20 0.20 0.20 0.20 0.19 0.19 0.1 ml Samole Volume QD_CQntact No Shield 29.47 29.17 28.73 28.35 28.02 27.72 2" Pb Shield 2.95 2.92 2.87 2.84 2.80 2.77  :

4" Pb Shield 0.29 0.29 0.29 0.28 0.28 0.28 1 Foot -

No Shield 0.20 0.20 0.20 0.20 0.19 0.19 2" Pb Shield 0.02 0.02 0.02 0.02 0.02 0.02 >

4" Pb Shield 0.00 0.00 0.00 0.00 0.00 0.00 Page 9-9 Revision 1

o .

CNS 1994 Evaluated Exercise Section 9.4 in-Plant Radiation Data i

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Page 9-10

CNS 1994

~

in-Picnt Radictinn Data Evtluated Exercise Reactor Building (859') Table 9.4-1 00:00 00:05 00:10 00:15 00:20 00:25 00:30 00:45 01:00 01:15 01:30 01:45 Area 05:30 05:35 05:40 05:45 05:50 05:55 06:00 06:15 06:30 06:45 07:00 07:15 Ambient Radiation Levels (mRIhr)

A 18.48 19.47 23.54 27.72 27.72 27.72 68.97 68.97 68.97 68.97 68.97 68.97 U . __ ,96 2 2@9 3 08 M8 . _3.1g ,_ _ __ 3 16 63.96 57.63 60.91 68.14 40 68 28 48

__ C_

2.75 2.76 2.85 2.93 2.93 2.93 5.12 3.88 3.86 3.86 3.86 3.86 D 4.72 5.31 7.87 10.49 10.49 10.49 36.34 36.34 36.34 36.34 36.34 36.34 E 15.71 16.55 20 01 23.56 23 56 23.56 58.62 85.00 112.00 139.00 166.00 193.00 ARMS 11 4.1 4.6 6.8 9.1 9.1 9.1 31 6 31.6' 31.6 31.6 31.6 31.6 12 16.8 17.7 21.4 25.2 25.2 25.2 62.7 62.7 62.7 62.7 62.7 62.7 13 2.6 2.7 2.7 2.8 2.8 2.8 56.6 51.0 53.9 60.3 36.0 25.2 14 2.6_

2.6 2.6 2.7 _ _2.7 _ _

2.7 _ . _ _

4.7 . _ . .

3.6 _

3.6 3.6 3.6 3.6 Contamination Levels (CPM 1100 cm2)

A BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD B BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD D BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD E BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD Airborne Sample Levels (CPM /CF where 2000 CPM = 1mrlhr)

-~ -

~5fGD ~ 5kKdD BKGD BKGD BKGD BKGD BKGD ~ BKGD BKGD BKGD BKGD BKGD B BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD D BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD i E BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD  !

Notes:

Blank or zero value cells reported "As Read".

In high airborne areas OW=CW x 2.3, otherwise OW=CW.

Page 9-11 nomion 3

CNS 1994 In-Plant Radiation Data Evtluated Exercise Reactor Building (859') - Table 9.4-1 02:00 02:15 02:30 02:45 03:00 03:15 03:30 03:45 04:00 04:15 04:30 05:00

. Area 07:30 07:45 08:00 08:15 08:30 08:45 09:00 09:15 09:30 09:45 10:00 10:30 Amp!gnt gapation [ eye!s (mR/hr) _ _ _ _ _

_A 68.97 68.97 _68.97 68.97 68.97 68.97 68.97 68 97 68.97 68.97 68.97 68.97_

8 _

3367_

30 06 __

23 39 _

37.06 38.53 _

39.89 41.47 42.32 42.37 _

42.41 _ __

42.46 __

42.56 C _

3.86 3.86 3.86 3.86 3.86 3.86 i 56 3 86 3.86 3.86 _ _ _ _ 3.86 3.86 D_ 36.34 _ _ _ _36.34 36.34 36.34 36 34 36.34 36.34 36 34 36.34 __ 36.34 36.34 __36.34 E 220.00 247.00 274.00 301.00 328.00 350.00 2000 00 2000 00 2000.00 890.00 420.00 350.00 ARMS 11 31.6 31.6 31.6 31.6 31.6 31.6 31.6 31.6 31.6 31.6 31.6 31.6 12 62.7 62.7 62.7 62.7 62.7 62.7 62.7 62.7 62.7 62.7 62.7 62.7 2 . _ _

26 _

2 __

3 __ , _ _ _

35 ___

37 _

37. __

3 _3 __

3 3 Contamination Levels (CPM /100 cm2)

__~ BRd~b { BKGD ~~BKGd g_b ~ 5KGD BKGD BKGD [ _[BRGD ]B@dd sKdD B BKGD BKGD _ BKGD BKGD _ BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD

__C _ _.BKGD _BKGD BKGD __ BKGD _ BKGD __ BKGD BKGD BKGD __BKGD BKGD __BKGD _BKGD D BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD E BKGD BKGD BKGD BKGD BKGD BKGD 5.00E+05 3.80E+06 2.10E+07 2.30E+07 2.00E+07 8.80E+06

~ Airborne Sample Levels (CPMICF where 2000 CPM = 1mr/hr)

- ~~

A ~ ~5ifGD'~~BKd6 'sKGD ~-BKGD ~ ~ilfd E F ' ~BRdD ~"~ BKGD BKGD ~~ BKdD ~ ~BKGD sKGD BKGD B BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD D BKGD_

BKGD _ BKGD _

BKGD BKGD BKGD BKGD BKGD __

BKGD __

BKGD BKGD BKGD

_E_ _

__ BKGD __ BKGD BKGD BKGD _BKGD __ BKGD 9.60E+05 9.30E+05 6.90E+05[ 4.80E+03 _.2.20E+02 _ __6.00E+01 NoteE Blank or zero value cells reported "As Read".

In high airbome areas OW=CW x 2.3, otherwise OW=CW.

Page 9-12 n m ni

CNS 1994 Ev:lur.ted Exerci;o Raactor Building (881')

STAIRS e ARn13 A

O 3 2

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5 CAM Hs * o AR414 Page 9-13 l

CNS 1994 in-Plant Rcdiation Drta Evaluated Exercise -

Reactor Building (881') Table 9.4-2 ,

00:00 00:05 00:10 00:15 00:20 00:25 00:30 00:45 01:00 01:15 01:30 Ot45 Area 05:30 05:35 05:40 05:45 05:50 05:55 06:00 06:15 06:30 06:45 07:00 07:15 Ambient Radiation Levels (mRlhr)

A 10.90 11.49 13.89 16.35 16.35 16.35 40.69 40.69 40.69 40.69 40.69 40.69 B 1.51 1.53 1.57 1.62 1.61 1.61 32.62 29.39 31.06 34.75 20.75 14.52 C 1.46 1.47 1.51 1.55 1.55 1.55 2.71 2.05 2.04 2.04 2.04 2.04

,_ D_ _2.59 _

2.92 4.33 5.77 _ , _ _

5 77 _ _ 5._77 , 19.99 _.

19.99 19 99 19.99 ,

19.99 19.99 Contamination Levels (CPMI100 cm2)

A_ BKGD BKGD BKGD_

BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD B __ BKGD BKGD _ BKGD BKGD __.BKGD BKGD __ BKGD _. BKGD BKGD BKGD BKGD BKGD C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD D _ BKG_D BKGD BKGD _ _GD BK _

BKGD; _ BKGD _ BKGD BKGD BKGD BKGD BKGD BKGD Airborne Sample Levels (CPMICF where 2000 CPM = 1mrlhr)

A BKGD BKGD BKGD BKGD ~ ~ B'KGDI ~~ BKGD BKGD BKGD BKGD BKGD BKGD BKGD B BKGD BKGD BKGD BKGD BKGG I BKGD BKGD BKGD BKGD BKGD BKGD BKGD C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD D BKGD BKGD .

BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD UoteE -

Blank or zero value cells reported "As Read". In high airborne areas OW=CW x 2.3, otherwise OW=CW.

Page 9-14 nemsen i

CNS 1994 gn_ plant Radiation Data Evt.luated Exercise Reactor Building (881') Table 9.4-2

• 02:00 02:15 02:30 02:45 03:00 03:15 03:30 03:45 04:00 04:15 04:30 05:00 Area 07:30 07:45 08:00 08:15 08:30 08:45 09:00 09:15 09:30 09:45 10:00 10:30 Ambient Radiation Levels (mRlhr)

A 40.69 40.69 40.69 40.69 40.69 40.69 40.69 40.69 40.69 40.69 40.69 40.69 B 17.17 15.33 11.93 18.90 19.65 20.34 21.15 21.58 21.61 21.63 21.66 21.71 C 2.04 2.04 2.04 2.04 2.04 ~

2.04 2.04 2.04 2.04 2.04 2.04 2.04 D 19.99 19.99 19.99 19.99 19.99 ~ 19 99 19.99 19.99 19.99 19 99 19.99 19.99 I

Contamination Levels (CPM /100 cm2)

A BKGD BKGD BKGD BKGD _ BKGD __BKGD BKGD _ BKGD _BKGD BKGD BKGD BKGD B BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD D BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD Airborne Sample Levels (CPMICF where 2000 CPM = 1mr/hr) l A -

BKGD- . . .

BKGD -.

BKGD --.

BKGD BKGD -

BKGD __

BKGD _-

BKGD - -.

BKGD BKGD .

BKGD .

BKGD C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD D

BKGD _ BKGD _ BKGD __

BKGD BKGD _

BKGD BKGD BKGD BKGD BKGD _BKGD BKGD l

Noter .

Blank or zero value cells reported "As Read". In high airborne areas OW=CW x 2.3, otherwise OW=CW.

l Page 9-15 nev%n i

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CNS 1994 in-Plant Radiation Data Ev;Iu.-ted Exercisa Reactor Building (903') Table 9.4-3 .

00:00 00:05 00:10 00:15 00:20 00:25 00:30 00:45 01:00 01:15 01:30 01:45 Area 05:30 05:35 05:40 05:45 05:50 05:55 06:00 06:15 06:30 06:45 07:00 07:15 Ambient Radiation Levels (mR/hr)

A _ 0.33 0.33 0.33 0.33 0.33 0.33 0.33 0.31 __0.30 0.30_ _ _ _ _ _ _0.29 0.29 B 5 12 5.49 7.08 14.98 14.24 14.26 6.72 6.72 6.72 6.72 6.72 6.72 C 286 20 452.52 669.60 808.92 768.96 770.04 362.88 362.88 362.88 362.88 362.88 362.88 2.01 2.01 2.02 2.04 2.04 2.04

__D _

20.66 _. 21.77 26.32 __ 31 00 , 31 00 31.00 2.20 2.20 __

2.20 2.20 _ 2.20 _

2 20

.._ E ___ _ _. _

77.12 77.12 77.12 _ _ _ _ _77.12 77.12 _ _ _ _77 12 ARMS

~ -~ ~

6 ~ ~~ ~26T2 ~~~~28l6 ~ 353 -~ 43l0 43LO 4 350 118.0 118.0 ~~118Td ~ II810 '~ I8 D ~ ~T1TD 1

7

1.9 ~ ~

1.9 ~~

1.9 1.9 1.9 1.9 2.0 2.0 2.0 2.0 2.0 2.0 8^ ~0.7 .9 1.6 2.4 24 24 9.9 9.9

~~

9.9 ~ ~ ~ ~9.9 ~ ~ ~ ~ 99 ~ ~ I5 9 9 4.7 5.1 6.6 8.1 8.1 8.1 23.1 23.1 23.1 23.1 23.1 23.1

~

'~ 03 ~ ~ ~ .3

~~

21 0:3 0.3 0l3 0.3 ' O.3 0.2 ~~0. 2 ~ ' ~ ~0.2 ~~~0.2 ' O.2 Contamination Levels (CPM /100 cm2)

A BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD B BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD

_BKGD _BKGD

._.C_ BKGD BKGD _.BKGD __ BKGD BKGD BKGD BKGD BKGD _ BKGD BKGD BKGD __BKGD D BKGD ._BKGD _ BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD __BKGD _ BKGD E _ _ BKGD BKGD BKGD ._ BKGD . BKGD _ BKGD _ BKGD BKGD _ BKGD _ _ _BKGD BKGD .BKGD Airborne Sample Levels (CPMICF where 2000 CPM = 1mr/hr)

A .

BKGD BKGD _

BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD _ BKGD BKGD B BKGD BKGD BKGD BKGD BKGD _BKGD BKGD BKGD . BKGD BKGD _ BKGO __BKGD C _ BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD _BKGD _ BKGD ,BKGD BKGD D BKGD BKGD _ BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD _BKGD E BKGD _

BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD NoteE Blank or zero value cells reported "As Read".

In high airborne areas OW=CW x 2.3, otherwise OW=CW.

Page 9-17 noi..on i

=

CNS 1994 Ev:Iuated Exercise in-Plent Rcdiation Data Reactor Building (503') Table 9.4-3 .,

02:00 02:15 02:30 02:45 03:00 03:15 03:30 03:45 04:00 04:15 04:30 05:00 Area 07:30 07:45 08:00 08:15 08:30 08:45 09:00 09:15 09:30 09:45 10:00 10:30 Ambient Radiation Levels (mR/hr)

A 3.07 3.07 3.07 3.07 3.07 3.07 3.07 3.07 3.07 3.07 3.07 3.07 B 6.72 6.72 6.72 6.72 6.72 6.72 6.72 6.72 6.72 6.72 6.72 6.72 C 362.88 362.88 362.88 362.88 362.88 362.88 362.88 362.88 362.88 362.88 362.88 362.88 D 2.20 2.20 2.20 2.20 2.20 2.20 2.20 2.20 2.20 2.20 2.20 2.20 E 77.12 77.12 77.12 77.12 77.12 77.12 77.12 77.12 77.12 77.12 77.12 77.12 ARMS 6 118.0 118.0 118.0 118.0 118.0 118.0 t 18.0 118.0 118.0 11b.0 118.0 118.0 7 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 8 9.9 9.9 9.9 9.9 9.9 9.9 9.9 9.9 9.9 9.9 9.9 9.9 9 23.1 23.1 23.1 23.1 23.1 23.1 23.1 23.1 23.1 23.1 23.1 23.1

. - _21- 2.4 2.4 2.4 _ _ -

2.4 2.4 .__- --

2.4 ---. -

2.4 2.4 2.4 2.4 2.4 2.4 Contamination Levels (CPM 1100 cm2)

A BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD B BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD C_ BKGD _ BKGD __BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD D_ ___ BKGD BKGD BKGD _ BKGD __ BKGD ..BKGD . _ _BKGD BKGD _ BKGD _BKGD _BKGD BKGD E _ _ _ _ _

BKGD BKGD BKGD __BKGDl ~~BKGb ~~BKGD ~ ~ ~ ~BKGD BKG ~~BKGD BKGU BRG6 BK5 Airborne Sample Levels (CPM /CF where 2000 CPM = 1mrlhr)

A BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD B BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD D BKGD BKGD _BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD E _BKGD BKGD . _ ,

BKGD BKGD BKGD BKGD BKGD BKGD BKGD _. BKGD __BKGD

_BKGD_

Notes Blank or zero value cells reported "As Read".

In high airborne areas OW=CW x 2.3, otherwise OW=CW.

Page 9-18 neve i

CNS 1994 Evtlutt:d Ex:rciss

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Reactor Buildina (931') O - -- -

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Page 9-19

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

CNS 1994 in-Plant Radiation Data Ev luated Exercise Reactor Building (931') Table 9.4-4

• 00:00 00:05 00:10 00:15 00:20 00:25 00:30 00:45 01:00 01:15 01:30 01:45 Area 05:30 05:35 05:40 05:45 05:50 05:55 06:00 06:15 06:30 06:45 07:00 07:15 Ambient Radiation Levels (mR/hr)

A 0.36 0.36 0.36 0.36 0.36 0.36 0.36 0.34 0.33 0.33 0.31 0.31 B 0.39 0.39 0.39 0.39 0.39 0.39 0.39 0.38 0.36 0.36 0.35 0.35 C 0.31 0.31 0.31 0.31 0.31 0.31 0 31 0.30 0.29 0.29 0.27 0.27 D 0.33 0.33 0.33 0.33 0.33 0.33 0.33 0.32 0.30 0.30 0.29 0.29 ARMS

.. _. 5_ _l- 76l{l.il__1.9{))j.7l E7l~ ~2.7l~~ 10.2] , 10 2l T'_]Ql 16.5l 1d~2{ 10.2l Contamination Levels (CPM /100 cm2)

A BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD 8 BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD D _BKGD _ BKGD _ _

BKGD BKGD _ BKGD _ BKGD _ BKGD_ _

BKGD _

BKGD BKGD BKGD BKGD Airborne Sample Levels (CPMICF where 2000 CPM = 1mr/hr)

A BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD B BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD D BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD *BKGD NoicE Blank or zero value cells reported "As Read".

In high airborne areas OW=CW x 2.3, otherwise OW=CW.

Page 9-20 nv%ni

CNS 1994 Evaluated Exercise In-Plant Radiation Data Reactor Building (931') Table 9.4-4 02:00 02:15 02:30 02:45 03:00 03:15 03:30 03:45 04:00 04:15 04:30 05:00 Area 07:30 07:45 08:00 08:15 08:30 08:45 09:00 09:15 09:30 09:45 10:00 10:30 Ambient Radiation Levels (mR/hr)

^ N

~

N _ ._j37 ~ ~ j37

~

3137 '3.37 [ ~3.37 3.37 ] 3737 - ~ ~ ~ ~3.37 ~137 3.37

._ 3.71 B_ 3.71 3.71 3.71 3.71 _ 3.71 3.71 3.71 3.71 3.71 3.71 3.71 C 2.95 2.95 2.95 2.95 2.95 2.95 2.95 2.95 2.95 2.95 2.95 2.95 D 3.13 3.13 3.13 3.13 3.13 3.13 3.13 3.13 3.13 3.13 3.13 3.13 ARMS ~- ~

]5 _l i f2l 10 2l- 10.2l - ~10 2l _ 10.2l ~ ~ ~103l_~]0 2l } 10 2l _ iO4 ~ ~ 1.0.2l _ iiiR 10]l Contamination Levels (CPM /100 cm2)

A BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD B BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD D BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD Airborne Sample Levels (CPMICF where 2000 CPM = 1mr/hr)

~ -

~ ~ B'KUD [DK56 - ~[BRGD' ~ "d{G[6'] BKGD _ BKGQ BKGD ~BKG6 ] 5~KGD ~ '-~BR5D

_" B))~{5RdD BKGD _ BKGD BKGD _ BKGD BKGD _,BKGD BKGD BKGD

_BKGD BKGD BKGD BKGD BKGD

_. C__ __BKGD BKGD BKGD BKGD __BKGD BKGD _ BKGD BKGD _ BKGD BKGD BKGD BKGD D BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD NoteE Blank or zerc value cells reported "As Read *.

In high airbome areas OW=CW x 2.3, otherwise OW=CW.

Page 9-21 a.m;on i

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

O i CNS 1994 Evaluated Exercise Reactor Buildina (958')

ll STAIRS l [-~

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@ ARM-Sensor l STAIRS l e ARM-Indicator ECAM Page 9-22 -

CNS 1994 In-Plant Radiation Data Eviluated Exercise Reactor Building (958*) Table 9.4-5

• 00:00 00:05 00:10 00:15 00:20 00:25 00:30 00:45 01:00 01:15 01:30 01:45 Area 05:30 05:35 05:40 05:45 05:50 05:55 06:00 06:15 06:30 06:45 07:00 07:15 Ambient Radiation Levels (mR/hr)

A 0.10 0.10 0.10 0.10 0.10 0.10 0.10 0.10 0.10 0.10 0.10

~

0.10 B'

~ 634

~

.34 ~ ~~ ~0.34 ~~ ~ 634 ~0.34 ~'- ~ ~ 6 34 ~ 6.34 0 33 ~ ~ ~ 632 6 32 630 6T56 C - -.

0.32 0.32 0.32 ._ .

0.32 0.32 0.32 0.32 0.31 0.30 0.30 0.28 0.28 ARMS

_14 j

~

2

~I6[ 2.6l id({ ~2.7l __].7{~~'~2.7l_ 4.7l} 3.6l ~ 16[ 66l-~ ~i6l_, 3.6l Contamination Levels (CPM 1100 cm2)

A BKGD BKGD BKGD BKGD ___.BKGD BKGD __ BKGD BKGD BKGD BKGD BKGD_

BKGD B BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD D BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD Airborne Sample Levels (CPM /CF where 2000 CPM = 1mr/hr)

A BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD B ~ BKd ~~ BKGb ~ BK5b -~BKGb ~ BNGD ~~BKGb ~ BRdb ~~ BKd6 BRd6 BKGD BKGU BRdb C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD D BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD 'BKGD UoleS:

Blank or zero value cells reported "As Read".

In high airbome areas OW=CW x 2.3, otherwise OW=CW.

Page 9-23 p..en 5

CNS 1994 in-Plant Radiation Data Eniuated Exerciss Reactor Building (958*) Table 9.4-5 ,

02:00 02:15 02:30 02:45 03:00 03:15 03:30 03:45 04:00 04:15 94:30 05:00 Area 07:30' 67:45 ~ ~UsiOO~ Ds:is 08:3 ' ~ 68i45 ~ 0956d 09:15 ~ 9556^ ~~69745~

~

18:00~ 10h30' Ambient Radiation Levels (mRlhr)

A 0.10 0.10 0.10 0.10 0.10 0.10 0.10 0.10 0.10 0.10 0.10 0.10 B 3.25 3.25 3.25 3.25 3.25 3.25 3.25 3.25 3.25 3.25 3.25 3.25 C 3.04 3.04 3.04 3.04 3.04 3.04 3.04 3.04 3.04 3.04 3.04 3.04 D 3.16 3.16 3.16 3.16 3.16 3.16 3.16 3.16 3.16 3.16 3.16 3.16 ARMS 14 l_ 3.6l ~3T5[-~ ~~3 6[ } 3.6l 55l~] 3 6l[ _iL6l _ 316l ' ~ ~ ~~3 ~6l_[3'6l ~ j5l___ _ _ 3.6l Contamination Levels (CPM /100 cm2)

A BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD B BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD D BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD

_Airpoge A

Sampje BKGD Levels (CPM BKGD __BKGD /CF where BKGD BKGD 2000 CPM = 1mr/hr)_

BKGD _BKGD

_ . BKGD BKGD __BKGD BKGD BKGD___

B BKGD BKGD __BKGD BKGD BKGD BKGD BKGD BKGD BKGD _BKGD __BKGD _ BKGD

__ C_ BKGD __BKGD BKGD ._ BKGD BKGD __ BKGD __ BKGD BKGD __BKGD BKGD BKGD BKGD D BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD Noles; Blank or zero value cells reported "As Read".

In high airborne areas OW=CW x 2.3, otherwise OW-CW.

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CNS 1994 In-Plant Radiation Data Evaluated Exercise Reactor Building (976') Table 9.4-6

• 00:00 00:05 00:10 00:15 00:20 00:25 00:30 00:45 01:00 01:15 01:30 01:45 Area 05:30 05:35 05:40 05:45 05:50 05:55 06:00 06:15 06:30 06:45 07:00 07:15 Ambient Radiation Levels (mR/hr)

A 0.33 0.33 0.33 0.33 --

0.33 - . - - -

0.33 -

0.33 -_

0.31 -.

0.30 -

0.30 -

0.29 0.29 C 0.34 0.34 0.34 0.34 0.34 0.34 0.34 0.32 0.31 0.31 0.30 0.30 Contamination Levels (CPM /100 cm2)

~ ~ ~

A ~~~~R55 B BR5U' BK55 BR5 ~ BK5D ~ ~BK5b -~BI(GD ~ BKG6 BKGD BKGD BKG6 BKGD B BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD Airborne Sample Levels (CPM /CF where 2000 CPM = 1mr/hr)

BKGD___

,A BKGD BKGD BKGD BKGD _BKGD BKGD BKGD . BKGD BKGD_ BKGD BKGD B BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD Notes Blank or zero value cells reported "As Read".

In high airbome areas OW=CW x 2.3, otherwise OW=CW.

Page 9-26 n %i

Eviluated Exercise CNS 1994 in-Plant Radiation Data Table 9.4-6

• Reactor Building (976')

02:00 02:15 02:30 02:45 03:00 03:15 03:30 03:45 04:00 04:15 04:30 05:00 Area 07:30 07:45 08:00 08:15 08:30 08:45 09:00 09:15 09:30 09:45 10:00 10:30 Ambient Radiation Levels (mRlhr)

A 3.07 3.07 3.07 3.07 3.07 3.07 3.07 3.07 3.07 3.07 3.07 3.07 B 2.98 2.98 2.98 2.98 2.98 2.98 2.98 2.98 2.98 2.98 2.98 2.98 C 3.19 3.19 3.19 3.19 3 19 3.19 3.19 3.19 3.19 3.19 3.19 3.19 Contamination Levels (CPM /100 cm2)

A BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD B EKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD C ~ RdD B BR5b sR5b BKGD ~ ~ BRdD 5k5d sRG6 ~~BKGb ' sKGD BKUD sR5U BK5 Airborne Sample Levels (CPMICF where 2000 CPM = 1mr/hr)

A BKGD BKGD BKGD BKGD _ BKGD BKGD _.BKGD __ BKGD_ _ . BKGD BKGD BKGD_ BKGD B BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD NOLeE Blank or zero value cells reported "As Read".

In high airborne areas OW=CW x 2.3, otherwise OW=CW.

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Page 9-27 n % ni l -- - __ __ ___ _ _____ _-____ _

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CNS 1994 In-Plant Radiation Data Eiraluated Eweise Reactor Building (1001') Table 9.4-7 00:00 00:05 00:10 00:15 00:20 00:25 00:30 00:45 01:00 01:15 01:30 01:45 Area 05:30 05:35 05:40 05:45 05:50 05:55 06:00 06:15 06:30 06:45 07:00 07:15 Ambient Radiation Levels (mR/hr)

~

I55

~

B 2.5A ~ ' ~2.55 257 - ~~2.75 2.75 1 75 ~

~ ~ ~155 4 55 ~ ~ ~ ~ M 55 4.55 1 55

~C~ -~1.89 ~~2.04

~

1'.85 '^~ 2.18 2.18 ~2.18 ~3.52 3.62 ~ ~ ' 3.52 5~55 ~ 5.'62 ~-~ ~152 D 1.97 2.01 2.16 2.32 2.32 2.32 3.85 3.85 3.85 3.85 3.85 3.85 ApMs_ _ __ _ __, _ . . _ _ _ __ _ __ _ . _ . _ _ _.

2 1.9 2.0 2.1 2.3 2.3 2.3 3.8 3.8 3.8 3.8 3.8 3.8 Contamination Levels (CPM /100 cm2)

A BKGD _ BKGD BKGD __ BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD

_BKGD B. . BKGD __BKGD _ BKGD .

BKGD ..BKGD _ BKGD __ BKGD BKGD BKGD BKGD ___BKGD C . _ . BKGD BKGD _ BKGD _. BKGD _.BKGD . BKGD _ BKGD BKGD _ BKGD BKGD BKGD _ _ _ _BKGD D BKGD __

BKGD BKGD _.

BKGD BKGD BKGD BKGD BKGD _

BKGD _

BKGD _

BKGD __

BKGD

. . _ _ . Airborne Sample Levels (CPMICF where 2000 CPM = 1mr/hr)

-~5[Gd ~ 5K56 ~Bkd6

_ ~

B ~ ~BR56

~ KGb BR5D ~BMGb 'BKGb BkGD B BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD D BKGD BKGD _

BKGD ,

BKGD BKGD BKGD ,

BKGD BKGD ,

BKGD ._

BKGD ._

BKGD _

BKGD Notes; Blank or zero value cells reported "As Read".

l In high airborne areas OW=CW x 2.3, otherwise OW=CW.

l l

Page 9-29 a. men i

Ev;Iuated Exercise CNS 1994 in-Plant Radiation Data Reactor Building (1001') Table 9.4-7 +

02:00 l 02:15 02:30 02:45 03:00 03:15 03:30 03:45 04:00 04:15 04:30 05:00 Area 07:30 07:45 08:00 08:15 08:30 08:45 09:00 09:15 09:30 09:45 10:00 10:30 Ambient Radiation Levels (mR/hr)

A 4.15 4.15 4.15 4.15 4.15 4.15 4.15 4.15 4.15 4.15 4.15 4.15 B 4.56 4.56 4.56 4.56 4.56 4 56 4.56 4.56 4.56 4.56 4.56 4.56 C 3.62 3.62 3.62 3 62 3.62 3.62 3.62 3.62 3.62 3.62 3.62 3.62 3.85 3.85 3.85

.__9_1_ _ 3 85 3 85

. 3.85 _ 3.85 _

3.85 _ 3._85 . _ 3 85 _

3.85 _

3 85 _

ARMS 1 210.0 210O! 210.0 210.0 210.0 210.0 210.0 210.0 210.0 210.0 210.0 210.0

~~ 2 ~ 15 3.8 3.8 3.8 3.8 3.8 '3.8 3.8 3.8 3.8 3.8 3 8l Contamination Levels (CPM /100 cm2)

A BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD B BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD _ BKGD BKGD BKGD BKGD BKGD BKGD BKGD

__E_ _.BKGD _ _

Airborne A

Sample Levels (CPM BKGD__ BKGD BKGD/CF where BKGD 2000 BKGDCPM = 1mrlhr) _BKGD

__BKGD .BKGD BKGD BKGD BKGD BKGD_

B BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD D BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD Noter Blank or zero value cells reported "As Read".

In high airborne areas OW=CW x 2.3, otherwise OW=CW.

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CNS 1994 In-Plant Radiation Data Evituated Exercise Turbine Building (882') Table 9.4-8 .

00:00 00:05 00:10 00:15 00:20 00:25 00:30 00:45 01:00 01:15 - 01:30 01:45 Area 05:30 05:35 05:40 05:45 05:50 05:55 06:00 06:15 06:30 06:45 07:00 07:15

_ _ _ . _ _ . Ambient Radiation Levels (mR/hr)

_ g ,,

gq. g 9 B 0.91 0.85 344.10 2711.07 3113.26 4856.10 3768.69 3292.02 2874.93 2502.53 2174.82 1832.21 C 0.01 0.01 0 01 0.01 0.01 0.01 0.01 0.01 0 01 0 01 0.01 0.01

__ 0.69 __0.64 __258.72 _2038.40

_. .D . 2340.80 3651.20 _2833.60 2475.20 , 2161.60 ._1881.60 _1635.20 __1377.60 3 s _ _ ____ __ __ _ - _ _ __ _ _ _ _. _ _ _ _ __ _

N -

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Contamination Levels (CPM /100 cm2)

A BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD B BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD D BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD Airborne Sample Levels (CPMICF where 2000 CPM = 1mrlhr)

A BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD B BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD D BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD Noter Blank or zem value cells reported "As Read".

In high airbome areas OW=CW x 2.3, otherwise OW=CW.

Page 9-32 noyi. ion 3

Evaluated Exercise CNS 1994 in-Plant Radiation Data Turbine Building (882*) Table 9.4-8 02:00 02:15 02:30 02:45 03:00 03:15 03:30 03:45 04:00 04:15 04:30 05:00 Area 07:30 07:45 08:00 08:15 08:30 08:45 09:00 09:15 09:30 09:45 10:00 10:30 Ambient Radiation Levels (mR/hr)

! A 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 B 1608.77 1519.39 1398.73 1318.30 1243.82 1172.32 1084.43 794.41 507.77 221.13 208.54 178.75 C 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 D 1209.60 1142.40 1051.68 991.20 935.20 881.44 815.36 597.30 381.78 166.26 156.80 134.40 l

ARMS  ;

10.4 .4.9 4.6 3.9 17 31.4 29.7 27.5 26.0 24.6 23.2 21.5 15.91

)

18 3240.0 3060.0 2817.0 2655.0 2505.0 2361.0 2184.0 1599.9 1022.6 445.3 420.0 360.0 l j

19 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 l j Contamination Levels (CPM 1100 cm2)

A BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD l B BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD D BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD i

Airborne Sample Levels (CPM /CF where 2000 CPM = 1mrlhr)

A BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD B BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD *BKGD C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD _ BKGD

__ D _ _ _ _ . BKGD _,BKGD _ BKG_D I'

Notes Blank or zero value cells reported "As Read".

In high airborne areas OW=CW x 2.3, otherwise OW=CW.

l Page 9-33  %,m

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CNS 1994 in-Plant Radiction Data Evaluated Exercise Turbine Building (903') Table 9.4-9 .

00:00 00:05 00:9 l 0C:15 l 0. M l 00:25 00:30 00:45 01:00 01:15 01:30 01:45 Area 05:30 05:35 id:AC !

~ ~ -.a 05-14 k' $* . /~l 05:55 06:00 06:15 06:30 06:45 07:00 07:15 Ambient Radiation Levels (aSeih6 A 0.01 0.01 O!r , ).01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 B 0.51 0.48 e d ..J. 15 M.20 1743.43 2719.41 2110.47 1843.53 1609.96 1401.42 1217.90 1026.04 C 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 D 0M __ 0.77 _ 313.05 , 2466.46 2832.37 _

_ _ _4417.95 . 3428.66 ._

2994.99 26,15.54 2276.74 1978.59 1666.90 ARMS 16 _l- 0.1] . 0.1[~ 0.1l OSHl 05N(-'D5ilj 05S F 05H[ OSHl OSHl OSH] OSSl Contamination Levels (CPM /100 cm2)

- ~ ~

[A B E

ifGD __ BKGD BKGD BKGD BKGD _ _ _BKGD BKGD BKGD

-BK6D' ~lKGD BKFJ BKGD

~~~~Bi(GD BKGD

[B'KG6 BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD C BKGD BKGD BKGD BKGD B'sGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD D BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD Airborne Sample Levels (CPM /CF where 2000 CPM = 1mr/hr)

A BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD 3 BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD C _ . - _ _ .

BKGD _ BKGD ._._ B K G D _ BKGD _ BKGD BKGD . _ - .

BKGD _ BKGD ___BKGD _ BKGD BKGD BKGD Notes.

Blank or zero value cells reported "As Read".

In high airbome areas OW=CW x 2.3, otherwise OW=CW.

Page 9-35 noem

CNS 1994 in-Plant Radiation Data Evaluated Exercise Turbine Building (903') Table 9.4-9 .

02:00 02:15 02:30 02:45 03:00 03:15 03:30 03:45 04:00 04:15 04:30 05:00 Area 07:30 07:45 08:00 08:15 08:30 08:45 09:00 09:15 09:30 09:45 10:00 10:30 Ambient Radiation Levels (mR/hr)

A 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 B 900.91 850.86 783.29 738.25 696.54 656.50 607.28 444.87 284.35 123.83 116.78 100.10 C 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01

__D_ 1463.62 ,1382.30 1272.53 1199.35 1131.59 1066.54 986.59 722.73

_ , 461.96 201

_ _ _ .18 _

189.73 162.62 ARMS

_ ._ 16 _l[D'5ilj DsH[ 'D5Iil~~ OSHl' [O5Hl]_ DSHl[ [OSH[ _

OSHl _ _OSHl))SH[ ~-~ SH[ OSHl Contamination Levels (CPM /100 cm2)

A BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKG'T BKGD 8KGD B BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD C BKGD BKGD BKGD BKGD BKGD BKGD 9KGD BKGD BKGD BKGD BKGD BKGD b -' sRDD sRdD BRDD 5KGD ~~BKGb BkGD 5KCb sKGb ~ BKGb ~ BKdb sKDb BkGb Airborne Sample Levels (CPMICF where 2000 CPM = 1mrlhr)

A BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD

. B _,, ____ B KGD _ BKGD BKGD BKGD BKGD __BKGD _ BKGD BKGD _ BKGD BKGD .BKGD __ BKGD BKGD BKGD _ BKGD C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD D BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD[ j BKGD Noter Blank or zero value cells reported "As Read".

l In high airborne areas OW=CW x 2.3, otherwise OW=CW.

l l

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Page 9-36 a.vism l

CNS 1994 Ev:.lunted Exercisa MTINGHOUEE ,

Turbine Buildina (932') IT m m i CRANE g N STADIS 70 DOC. CONTROL IIATCI]

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! Page 9-37 r

l CNS 1994 in-Plant Radiation Data Evaluated Emlu .

Turbine Building (932*) Table 9.4-10

• 00:00 00:05 00:10 00:15 00:20 00:25 00:30 00:45 01:00 01:15 01:30 01:45 l- Area 05:30 05:35 05:40 05:45 05:50 05:55 06:00 06:15 06:30 06:45 07:00 07:15 l Ambient Radiation Levels (mRIhr)

^ _ _ . . 64 pg _ 67p _ _ 168.30 271.15 274.45 274.45 12.54 10.95 _

8.36 6.71 5.61 4.74

_ _ _B __ 15.34 15.99 39.78 64.09 64.87 64.87 2.96 ___ 2.59 1.98 1.59 1.33 1.12 l

C 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0 01 0.01 0.01 0.01 0.01 l

D 0.01 0.01 0.01 0.01 0.01 _ 0.01 0.01 0.01 0.01 0.01 0.01 0.01 ARMS ~

_ 15[l~ 118.0l 123.0l 306.0l 493.0l ~ 4595l~~ 499.0l 22.8l ~~ 19'9l 15.5[ 12.2l 10.2l 8.6l Contamination Levels (CPMI100 cm2)

A BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD B BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD D BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD Airborne Sample Levels (CPMICF where 2000 CPM = 1mr/hr)

BEGD - ~ 6fd 5 ~ ~~BI M D

-~ ~ - ~~

A ~~ BKsIj ~~5fK5U BKGD E ~ ' ~ ~BKGD BKGD ~~BK56 BKGD BKGD BKGD B BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD D BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD 'BKGD Nokt Blank or zero value cells reported "As Read".

In high airbome areas OW=CW x 2.3, otherwise OW=CW.

Page 9-38 nowe

Evaluated Exercise CNS 1994 In-Plant Radiation Data Turbine Building (932') Table 9.4-10 .

02:00 02:15 02:30 02:45 03:00 03:15 03:30 03:45 04:00 04:15 04:30 05:00 Area 07:30 07:45 08:00 08:15 08:30 08:45 09:00 09:15 09:30 09:45 10:00 10:30

__ Ambient Radiation Levels (mRlhr). _ _

~ ~

~~ o.85

_ _ _ - _ . ~

g ~ ^ ~ ~o.93 o.90 0.87 h.52 ~ ~ ~o 73 0.64 0.55 o.4s 0:28 c o.01 0.01 0.01 0.01 0.01 0.01 o 01 0.01 0.01 0.01 0.01 0.01 D 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 ARMS

~i5~l_ 7.8l 7.5l 7.2l 69l - 1 7l _ 15l ] _ ] 6 [ ~__ _ }6l 5. . T5l .,4.2[ 3.5] 2.1]

Contamination Levels (CPM /100 cm2)

A BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD 6K7D BKGD BKGD B BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD D BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD

_BKGD _ _ _ _ _ _

Airborne Sample Levels (CPMICF where 2000 CPM = 1mr/hr)

_BKGD A BKGD BKGD BKGD BKGD BKGD BKGD BKGD_ __ _ _ _ _ _BKGD BKGD BKGD _BKGD B BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD C BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD D BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD BKGD Noter Diank or zero value cells reported "As Read".

In high airborne areas OW=CW x 2.3, otherwise OW=CW.

Page 9-39  %%n s

CNS 1994 Evaluated Exercise Section 9.5 Dose Assessment 9

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CNS 1994 Evaluated Exercise Total Population Dose Time of Release TEDE (Dose in REM) THYROID (Dose in REM)

From-To 1.0 2.0 5.0 10.0 1.0 2.0 5.0 10.0 03:45 to 03:55 0.003 0.001 0.000 0.000 0.006 0.002 0.001 0.000 03:55 to 04:05 0.003 0.001 0.000 0.000 0.007 0.003 0.001 0.000 04:05 to 04:15 0.003 0.001 0.000 0.000 0.006 0.002 0.001 0.000 04:15 to 04:30 0.004 0.001 0.000 0.000 0.007 0.003 0.001 0.000 Total 0.013 0.005 0.001 0.001 0.026 0.010 0.003 0.001_

Table 9.5-1 l

i I

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! Page 9-44 n.vis % i

CNS 1994 Evaluated Exercise Section 9.6 Environmental Data l

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y CNS 1994 Ev;1unted Exercise Onsite Survey and Sample Data '

Table 9.6-1 05:30 06:00 09:15 09:25 09:35 09:45 10:00 10:15 10:30 10:45 11:00 11:15 Area 00:00 1 00:30 03:45 03:55 04:05 04:15 04:30 04:45 05:00 05:15 05:30 05:45 Closed Window Levels (mR/hr)

A ~ {dII~] ~ [0T'~'i.53EIUI

_ 8__ < 0.1 YU45+U1 1.[795+0T ~1.47EA0I <0.f] <0[1 ._ 7d'.i- <0.1 <0.1 <0.1

< 0.1 _ < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 < 0.1

~ ~ ~ ~ 'Open Window Levels (mR/hr)

<0;1

~

A B

< 0.1 1.705+01 2.12E+ I T85E+01 ~1.5

~~~3 5ib f ~ < 0.1 ~ ~ ~ ~ ~<01 W1~ < 0.i' < 0.1 ~ < 0.1

< 0.1 < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 Airborne Sample Levels (CPM /CF where 2000 CPM = 1mr/hr)

A < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 I

< 0. < 0.1 < 0.1 < 0.1 B < 0.1 < 0.1 < 0.1 < 0,1 < 0.1 < 0.1 < 0.1 < 0.1 e 0.1 < 0.1 < 0.1 < 0.1 Page 9-46 Revision 2

s.

CNS 1994 Elume Phass Environmental Information Evalunted Ex:rcisa i

3 -

Release Segment Times Table 9.6-2 Scenario / Elapsed Time Downwind 09:15 09:25 09:35 09:45 10:00 10:15 l 10:30 10:45 11:00 11:15 Distance 03:45 03:55 04:05 04:15 04:30 04:45 05:00 05:15 05:30 05:45 '

O.5 miles 03:45 03:55 04:05 04:15 I 1.0 miles 03:45 03:55 04:05 04:15 1.5 miles 03:45 03:55 04:05  !

2.0 miles 03:45 03:55 04:05 2.5 miles 03:45 03:55 04:15 3.0 miles 03:45 03:55 04:15 t 3.5 miles 03:45 04:05 4.0 miles 03:45 04:05 -

4.5 miles 03:55 04:15 5.0 miles 03:55 04:15 5.5 miles 03:45 04:05 6.0 miles 03:45 04:05 6.5 miles 03:55 04:15 7.0 miles 03:55 04:15 7.5 miles 03:45 04:05 8.0 miles 03:45 04:05 8.5 miles 03:55 04:15 9.0 miles 03:55 04:15 9.5 miles 03:45 04:05 10 miles 03:45 04:05 Page 9-48 Revision 2

w

, CNS 1994 Plume Phas1Environmsntal Infolination Evtlu .ted Ex;;rci;a Closed Window External Dose Rates (mR/hr) Table 9.6-3 Scenario / Elapsed Time Downwind 09:15 09:25 09:35 09:45 10:00 10:15 10:30 10:45 11:00 11:15 Dbtance 03:45 03:55 04:05 04:15 04:30 04:45 05:00 05:15 05:30 05:45 0.5 miles O.16 0.20 0.18 0.15 1.0 miles 16.30 20.40 17.90 14.70 1.5 miles 10.17 12.72 11.18 2.0 miles 6.35 7.93 6.98 2.5 miles 5.07 6.33 4.56 3.0 miles 4.05 5.06 3.64 3.5 miles 3.24 3.55 4.0 miles 2.59 2.64 4.5 miles 2.58 1.85 5.0 miles 2.06 1.48 ,

5.5 miles 1.50 1.65 6.0 miles 1.36 1.50 6.5 miles 1.55 1.11 7.0 miles 1.41 1.01 7.5 miles 1.03 1.13 8.0 miles 0.93 1.03 8.5 miles 1.06 0.76 9.0 miles 0.96 0.69 9.5 miles 0.70 0.77 10 miles 0.64 0.70

• Notes:

Survey results at 3' will be the same at 6" when inside the plume.

Page 949 m2

. - . - -- .,v. - _ , . . . - - - ww -. = ~ - - . -=or -..<3 w- -

--c -.<v-. v- w---..- - + _ _ uv-- .ww-- ww . --er m ,. - * , = -wre--- -w=.,-m- - - - - - --- - _ _ - - - -

CNS 1994 Plumo Phtse Environmsntal IDf9EnaliOD Evtluited Ex;rcise i

Open Window External Dose Rates (wR/hr) Table 9.64

~

i Scenario / Elapsed Time Downwind 09:15 09:25 09:35 09:45 10:00 10:15 10:30 10:45 11:00 11:15 Distance 03:45 03:55 04:05 04:15 04:30 04:45 05:00 05:15 05:30 05:45 0.5 miles 0.37 0.47 0.41 0.34 1.0 miles 37.49 46.92 41.17 33.81 1.5 miles 23.40 29.25 25.71 2.0 miles 14.61 18.24 16.05 '

2.5 miles 11.67 14.57 10.49 3.0 miles 9.32 11.64 8.37 -

3.5 miles 7.44 8.18 4.0 miles 5.95 6.53 4.5 miles S.93 4.26 5.0 miles 4.74 3.40  !

5.5 miles 3.45 3.79 6.0 miles 3.14 3.45 6.5 miles 3.56 2.56 7.0 miles 3.24 2.33  ;

7.5 miles 2.36 2.59 8.0 miles 2.15 2.36 i 8.5 miles 2.44 1.75 [

9.0 miles 2.22 1.59 9.5 miles 1.62 1.78 10 miles 1.47 1.62 Notes Survey results at 3' will be the same at 6" when inside the plume.

l l

Page 9-50 a. vision 2

. _ _ _ ____.m___.m.___-- _ _ . _ _ , _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ .

. , , . , , w.,,,,.. m.. ,. , .. , . . . , , , , _ . .m ,m_. - ._ .,_,,_,g..,,.

e CNS 1994 Elum9_Ehase Envirqumental informatioll Evaluated Exercise Thyroid Dose Rates (mrem /hr) Table 9.6-5 L Scenario / Elapsed Time Downwind 09:15 09:25 09:35 09:45 10:00 10:15 10:30 10:45 11:00 11:15 i Distance 03:45 03:55 04:05 04:15 04:30 04:45 05:00 05:15 05:30 05:45 0.5 miles 3.30E-01 4.12E-01 3.63E-01 2.97E-01

1.0 miles 3.30E+01 4.12E+01 3.63E+01 2.97E+01 1.5 miles 2.06E+01 2.57E+01 2.26E+01 2.0 miles 1.28E+01 1.60E+01 1.41 E+01 2.5 miles 1.02E+01 1.28E+01 9.19E+00 3.0 miles 8.17E+00 1.02E+01 7.34E+00 -

3.5 miles 6.53E+00 7.18E+00 4.0 miles 5 22E+00 5.74E+00 4.5 miles 5.21 E+00 3.74E+00 5.0 miles 4.16E+00 2.99E+00 5.5 miles 3.03E+00 3.33E+00 6.0 miles 2.75E+00 3.03E+00 6.5 miles 3.13E+00 2.25E+0_L 7.0 miles 2.85E+00 2.05Em .

'7.5-miles

2.07E+00 2.?ef; ~,0 ,

8.0 miles 1.89E+00 7 TE+00 8.5 miles y.14E+00 1.r4E+00 9.0 miles 95E+00 *40E+00 9.5 miles i 12E+"3 1.56E+00 10 miles 1.29t-+00 1.42E+00 Page 9-51 n. vision 2

e-CNS 1994 Evclutted Exerci:o Pluma Phasn Environm3ntal Information i

Total lodine Concentration (pCi/cc) Table 9.6-6 Scenario / Elapsed Time Downwind 09:15 09:25 09:35 09:45 10:00 10:15 10:30 10:45 11:00 11:15 Distance 03:45 03:55 04:05 04:15 04:30 04:45 05:00 05:15 05:30 05:45 0.5 miles 1.49E-07 1.86E-07 1.64E-07 1.34E-07 1.0 miles 1.49E-05 1.86E-05 1.64E-05 1.34E-05 l 1.5 miles 9.28E-06 1.16E-05 1.02E-05 2.0 miles 5.78E-06 7.23E-06 6.36E-06 2.5 miles 4.62E-06 5.78E-06 4.16E-06 3.0 miles 3.69E-06 4.61 E-06 3.32E-06 3.5 miles 2.94E-06 3.24E-06 4.0 miles 2.35E-06 2.59E-06 4.5 miles 2.35E-06 1.69E-06 5.0 miles 1.88E-06 1.35E-06 5.5 miles 1.36E-06 1.50E-06 6.0 miles 1.24E-06 1.37E-06 6.5 miles 1.41 E-06 1.02E-06 7.0 miles 1.29E-06 9.25E-07 7.5 miles ' ' '

'9 34Ef07 1.03E-06 8.0 miles 8.50E-07 9.36E-07 8.5 miles 9.68E-07 6.96E-07 9.0 miles 8.80E-07 6.33E-07 9.5 miles 6.40E-07 7.05E-07 10 miles ' 5.82E-07 6.41 E-07 Page 9-52 a.=-m2

- _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ . I

d CNS 1994 Elumo Phasn Environmrntal Information Evaluated Ex!rcise 2

Iodine I-131 Concentration (pCi/cc) Table 9.6-7 Scenario / Elapsed Time Downwind 09:15 09:25 09:35 09:45 10:00 10:15 10:30 10:45 11:00 11:15 Distance 03:45 03:55 04:05 04:15 04:30 04:45 05:00 05:15 05:30 05:45 0.5 miles 6.41 E-08 8.00E-08 7.05E-08 5.76E-08 1.0 miles 6.41 E-06 8.00E-06 7.05E-06 5.76E-06 1.5 miles 3.99E-06 4 99E-06 4.39E-06 2.0 miles 2.49E-06 3.11 E-06 2.73E-06 2.5 miles 1.98E-06 2.48E-06 1.79E-06 [

3.0 miles 1.59E-06 1.98E-06 1.43E-06 3.5 miles 1.27E-06 1.39E-06 4.0 miles 1.01E-06 1.11 E-06 4.5 miles 1.01E-06 7.27E-07 5.0 miles 8.08E-07 5.81E-07 5.5 miles 5.87E-07 6.45E-07 6.0 miles 5.34E-07 5.87E-07 6.5 miles 6.08E-07 4.37E-07 7.0 miles 5.53E-07 3.98E-07 7.5 miles 4.02E-07 4.42E-07 8.0 miles 3.65E-07 4.02E-07 8.5 miles 4.16E-07 2.99E-07 9.0 miles 3.78E-07 2.72E-07 9.5 miles 2.75E-07 3.03E-07 10 miles 2.50E-07 2.76E-07 Page 9-53 n,% 2

2 CNS 1994 P_lume Phase Environmental Information Evaluated Exercise 1

Iodine Cartridge Readings (Net Sample CPM using SAM-II) Table 9.6-8 Scenario / Elapsed Time Downwind 09:15 09:25 09:35 09:45 10:00 10:15 10:30 10:45 11:00 11:15 Distance 03:45 03:55 04:05 04:15 04:30 04:45 05:00 05:15 05:30 05:45 0.5 miles ,

5138 6413 5655 4620 1.0 miles 513769 641349 565491 462047 1.5 miles 319992 399859 352153 2.0 miles 199301 249299 219300 2.5 miles 159173 199170 143439 3.0 miles 127125 159121 114530 3.5 miles 101529 111700 4.0 miles 81087 89205 4.5 miles 81140 58300 5.0 miles 64825 46550 5.5 miles 47050 51761 6.0 miles 42800 47091 6.5 miles 48768 35044 7.0 miles 44354 31880 7.5 miles 32217 35461 8.0 miles 29307 32262 8.5 miles 33367 24000 9.0 miles 30347 21833 9.5 miles 22061 24294 10 miles 20068 22102 Molem Assume sample volume as 15 cubic feet.

Assume SAM-Il effeciency of 0.085.

Page 9-54 Revision 2

J CNS 1994 Plumo Phasa EnvironmnntaLinformation Eve.lutted Ex;rcise Iodine Cartridge Readings (Net Sample CPM using E-520) Table 9.6-9 Scenario / Elapsed Time Downwind 09:15 09:25 09:35 09:45 10:00 10:15 10:30 10:45 11:00 11:15 Distance 03:45 03:55 04:05 04:15 04:30 04:45 05:00 05:15 05:30 05:45 0.5 miles 150 187 165 135 1.0 miles 14988 18710 16497 13479 1.5 miles 9335 11665 10273 2.0 miles 5814 7273 6398 2.5 miles 4644 5810 4185 3.0 miles 3709 4642 3341 -

3.5 miles 2962 3259 4.0 miles 2366 2602 4.5 miles 2367 1701 5.0 miles 1891 1358 5.5 miles 1373 1510 >

6.0 miles 1249 1374 i 6.5 miles 1423 1022 7.0 miles 1294 930

7.5 miles 940 1035  ;

! 8.0 miles 855 941 8.5 miles 973 700  !

9.0 miles 885 637 l 9.5 miles 644 709  ;

10 miles 585 645 l

l Notet l Assume sample volume as 10 cubic feet.

1 l Assume E-520 contact effeciency of 0.0016.  !

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L Page 9-55 Revision 2

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3 CNS 1994 Elume Phase Environmentallnfonnation Evaluated Exercise I

Gross Particulate Concentration (pCi/cc) Table 9.6-10 Scenario / Elapsed Time  ;

Downwind 09:1.5 09:25 09:35 09:45 10:00 10:15 10:30 10:45 11:00 11:15 Distance 03:45 03:55 04:05 04:15 04:30 04:45 05:00 05:15 05:30 05:45 0.5 miles 9.69E-09 1.21E-08 1.07E-08 8.71E-09 ,

1.0 miles 9.69E-07 1.21 E-06 1.07E-06 8.71E-07 1.5 miles 6.03E-07 7.54E-07 6.64E-07 2.0 miles 3.76E-07 4.70E-07 4.13E-07 2.5 miles 3.00E-07 3.75E-07 2.70E-07 3.0 miles 2.40E-07 3.00E-07 2.16E-07 -

, 3.5 miles 1.91E-07 2.11 E-07 4.0 miles 1.53E-07 1.68E-07 4.5 miles 1.53E-07 1.10E-07 5.0 miles 1.22E-07 8.78E-08 5.5 miles 8.87E-08 9.76E-08 6.0 miles 8.07E-08 8.88E-08 6.5 miles 9.19E-08 6.61E-08 4

7.0 miles 8.36E-08 6.01 E-08 ,

7.5 miles 6.07E-08 6.68E-08 8.0 miles 5.52E-08 6.08E-08 8.5 miles 6.29E-08 4.52E-08 9.0 miles 5.72E-08 4.12E-08 9.5 miles 4.16E-08 4.58E-08 10 miles 3.78E-08 4.17E-08 I

e Page 9-56 ama

s 3-CNS 1994 Plume Phnse Environmental _.lDf0RDAliGD Evaluated Exercise 4-Gross Particulate Activity (Net Sample mR/hr using E-140-N) Table 9.6-11 Scenario / Elapsed Time l

Downwind .09:15 09:25 09:35 09:45 10:00 10:15 10:30 10:45 11:00 11:15 '

Distance 03:45 03:55 04:05 04:15 04:30 04:45 05:00 05:15 05:30 05:46 0.5 miles 6.30E-01 7.86E-01 6.93E-01 5.66E-01 1.0 miles 6.30E+01 7.86E+01 6.93E+01 5.66E+01 1.5 miles 3.92E+01 4.90E+01 4.31E+01 2.0 miles 2.44E+01 3.05E+01 2.69E+01 2.5 miles 1.95E+01 2.44E+01 1.76E+01 3.0 miles 1.56E+01 1.95E+01 1.40E+01 -

3.5 miles 1.24E+01 1.37E+01 4.0 miles 9.94E+00 1.09E+01 4.5 miles 9.94E+00 7.14E+00 5.0 miles 7.94E+00 5.70E+00 5.5 miles 5.77E+00 6.34E+00 6.0 miles 5.24E+00 5.77E+00 6.5 miles 5.98E+00 4.29E+00 7.0 miles 5.43E+00 3.91 E+00 7.5 miles 3.95E+00 4.35E+00 8.0 miles 3.59E+00 3.95E+00 8.5 miles 4.09E+00 2.94E+00 9.0 miles 3.72E+00 2.68E+00 9.5 miles 2.70E+00 2.98E+00 10 miles 2.46E+00 2.71E+00 NDLeE Assume sample volume as 10 cubic feet.

Assume background count rate as 0.02 mR/hr.

Page 9-57 Re2

4 CNS 1994 Plume Phnsa Environmnntalinformation -

Evclu;ted Ex;rci;;a 1

Particulate Activity (Net Sample CPM using E-520) Table 9.6-12 Scenario / Elapsed Time Downwind 09:15 09:25 09:35 09:45 10:00 10:15 10:30 10:45 11:00 11:15 Distance 03:45 03:55 04:05 04:15 04:30 04:45 05:00 05:15 05:30 05:45 0.5 miles 1.83E+03 2.28E+03 2.01 E+03 1.64E+03 1.0 miles 1.83E+05 2.28E+05 2.01 E+05 1.64E+05 1.5 miles 1.14E+05 1.42E+05 1.25E+05 2.0 miles 7.09E+04 8.86E+04 7.80E+04 2.5 miles 5.66E+04 7.08E+04 5.10E+ 04 3.0 miles 4.52E+04 5.66E+04 4.07E+04 3.5 miles 3.61 E+04 3.97E+04 4.0 miles 2.88E+04 3.17E+04 4.5 miles 2.88E+04 2.07E+04 5.0 miles 2.30E+04 1.66E+04 5.5 miles 1.67E+04 1.84E+04 6.0 miles 1.52E+04 1.67E+04 6.5 miles 1.73E+04 1.25E+04 7.0 miles 1.58E+04 1.13E+04 7.5 miles 1.15E+04 1.26E+04 8.0 miles 1.04E+04 1.15E+04 8.5 miles 1.19E+04 8.53E+03 9.0 miles 1.08E+04 7.76E+03 9.5 miles 7.84E+03 8.64E+03 10 miles 7.14E+03 7.86E+03 Notes Assume sample volume as 10 cubic feet.

Assume E-520 contact effeciency of 0.3.

Page 9-58 nem 2

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