Text

Emergency Preparedness Exercise Manual
	ML20118A222
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Site:	Fort Calhoun
Issue date:	08/14/1992
From:	; OMAHA PUBLIC POWER DISTRICT
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Emergency Preparedness Exercise Manual CAUTION: This manual contains confidential exercise information that can r.ot be shared with exercise participants prior to the exercise.

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LUl].E of CONTENTS Tab

1. CONDUCT of EXERCISE

. TABLE of CONTENTS

SCHEDULE of EVENTS

SCOPE and PARTICIPANTS

OBJECTIVES

GUIDELINES and SIMULATIONS

PARTICIPANT GUIDELINES

2. SCENARIO EVENTS

TABLE of CONTEYTS

NARRATIVE

SUMMARY

TIMELINE

MASTER EVENTS

SUMMARY

3. SCENARIO MESSAGES

TABLE of CONTENTS

CONTROLLER MESSAGES - CR/TSC/OSC/ EOF

. 4. OPERATIONAL DATA

TABLE of CONTENTS

- OPERATIONAL DATA SUMMARIES and GRAPHS

CONTROLLER MESSAGES - OPERATIONAL DATA

ERFCS DISPLAYS - OPERATIONAL DATA

5. RADIOLOGICAL DATA

TABLE of CONTENTS

RADIATION MONITORING DATA ~ SUMMARIES

ERFCS DISPLAY - PROCESS MONITORS, PAGE 360

ERFCS DISPLAY - AREA MONITORS, PAGE 361

ONSITE ' PLUME SHINE WHOLEBODY EXPOSURE

! LEVELS

LOOSE SURFACE CONTAMINATION LEVELS -

6. RADIOCIIEMICAL DATA

TABLE of CONTENTS

. REACTOR CORE INVENTORY

ISOTOPICS

!

POST ACCIDENT SAMPLING SYSTEM ANALYSIS

! REPORTS os608atwumcosresT.wr5 i 8/3/92 d

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TAllLE of CONTENTS

7. DOSE ASSESSSIENT DATA and OFFSITE PLUh1E 51APS

TABLE of CONTENTS

METEOROLOGICAL DATA

SUMMARY

ERFCS DISPLAY - MET AND RAD DATA, PAGE 197

VENTILATION STACK RELEASE

PLUME EXPOSURE DATA

8. CONTROLLING and EVALUATING

TABLE of CONTENTS _

CONTROLLER / EVALUATOR ASSIGNMENTS

CONTROLLER / EVALUATOR GUIDELINES

EVALUATION FORMS i

G.\6084 M ANU ADCONTENT,WP5 ii 8/3/92

CONDUCT of EXERCISF TABLE OF CONTENTS

TABLE of CONTENTS 11

SCIIEDULE of EVENTS 12

SCOPE and PARTICIPANTS 14

OBJECTIVES 17

GUIDELINES and SIMULATIONS 1 18

PARTICIPANT GUIDELINES 1 24 G n608M1 ANUCSCHEDUI.E.WF5 11 8/3/92

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CONDUCT of EXERCISE-SCIIEDULE of EVENTS Th'e schedule for all meetings, entrances, briefings, critiques, and exits is provided under this heading.

l G:\6084 3t ANUADSCilEDULE.WPs 1-2 8/3/92

CONDUCT of EXERCISE SCIIEDULE of EVENTS (cont)

Ev ent Attendees Time xation Oct 6 Tue Participant Bnenng Eurcise Participants (Energy Plus) 1430 1630 Energy Plua Oct 7, Wed Oct 8, nur Parucipant Briefing Exertise Participanta (FCS) 0800-1000 FCS Panicipant Briefing Exersiae Participarita (TCS) 1000-1200 FCS Parthipant BricCng Exercise Participanta (FCS) 1230-1430 FCS Oet 9, Fri Ctir/ Eval Bnenng Clln Evals ( AID 0800-1000 FCS Cth' Eval Breakout Session CtirvEvals (A10 1000-1400 FCS Ctir' Eval Walkd,>w n CilrCEvals (Leeds, Selected) 1400-1630 FCS Oet 10, Sat Cilr/ Eval Makeup and Review Citrs/Evals (as needed) 1000-1200 FCS Oct 11, Sun 0.112 Mon NRC Entranet NRC, T.P, OPPD Managsment 1130 1200 FCS NRC GET Training NRC 1300-1500 FCS NRC Eval Brie 0ng NRC 153 > l830 FCS 0.t 13, Tue NRC WalWown of ERFa and Piani NRC,EP 0800 1200 FCS 1300 1500 EOF Oct 14, Wed Exerg ue OPPD Facihty Cntiques Panicipanta (All), Ctira'Evals Post Exercise ERFs Oct 15. Thur Key Pani;ipant' Key Esal Cntique Key PartiSipanta, Key Ctirs.'Evals 0800-1100 FCS Desotop Licensee Critique Key Ctirs'Evals 1100 1600 FCS Oct 16, Fri OPPD Management Cntique OPPD Management, EP 07004830 EOF Licensee Preser,ta Criuque to NRC OPPD Management, NRC 0900-1000 EOF NRC Criuque and Exit OPPD Management, NRC EOF l 1030-1100 ABBREVIATIONS CTLR: Conitoller EVAL: Evaluator NE. Nebraska i EOF: Ernergency Opers. ions Facihty FCS: Fort Calhoun Station NRC: Nuclear Regulatory Commission EP: Emergency Planning ' GET: General Employee Training OPPD: Omaha Public Power Distnet EPZ: Emergency Planning Zone IA: los a QA: Quality Assuranec ERF:- Emergency Response Facility IPZ: Ingestion Pathway Zone TUD: To Be D :rmined I

G.408441 ANU AttSCilEDULE WP5 13 8/3/92

j'- CONDUCT of EXEP.CISE SfDPE and l%RTICIPANTS The scope of the exercise and a listing of participants is provided under this heading. The list of participants is further broken down to utility, state and local facilities and service ngencies-and includes addresses for each.

G"604'M ANUAliSCP&PART WP5 1-4 8/6/92-

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CONDUCT of EXERCISE SCOPE nnd PARTICIPANTS (cont)

KDE As an assurance that the healt h and safety of the general public is r.rotected in the event of an accident at the Fort Calhout station (FCS) the Omaha Public Pov.er District (OPPD) conducts an annual emergency prepcredness exercise. Exercises sirr. alate accident conditions and radiological hazards that require major portions of utility, sute and local emergency response plans and procedures to be implemen:ed. F.mergency re9ases are evaluated by all participants, and the Nuclear Regulatory Commission, Exercise accident sequences, and the severity and characteristics of radiological hazards are held in confidence prior to conducting the exercise.

The exercise scenario is suf6cient to require complete activation of the OPPD emergency response organization for accident mitigation. The accident scenario will require evaluation and decision making on protective :tions for the general public surrounding FCS, Additionally, requirements for an annual communications drill between the utility and states are included in the exercise.

Evaluations of the emergency response to situations presented by thc exercise scenario help provide an assessment of the adequacy of utility, state and loc ' radiological emergency plans and procedures. In addition, conduct of the exercise is valuable in determining whether adequate resources, and trained personnel assigned emergency response responsibilities are available to protect the health and safety of the general public in the event of an emergency at FCS.

PARTICIPMLS The following utility, state and local emergency response facilities and service agencies will participate in 1992 exercise activities.

Omaha Public Power Distriel Control Room (CR) Simulator; Fort Calhoun Station Technical Support Center (TSC); Fort Calhoun Station Operations Support Center (OSC); Fort Calhoun Station Emergency Operations Facility (EOll; North Omaha Station,24th & Craig Ave., Omaha, NE

c. su mNe Atescrar ART wPs 1-5 8/6/92

CONDUCT of EXERCISE SCOPE and PARTICIPANTS (cont)

PARTICIPANTS (cont)

State of Nebraska State Emergency Operations Center'; State Civil Defense Hardened Facility,1300 Military Rd., Lincoln, NE j Washington County Emergency Operations Center'; Basement of12w Enforcement Bldg.,

1535 Colfax St., Blair, NE State of Iowa State Emergency Operations Center'; Level .A, Rm. 29, Hoover State Office Bldg.,1301 E. Walnut St., Des Moines, IA IIarrison County Emergency Operations Center'; County Sheriff's Office,105 S. First Ave., Logan, I A Pottawattamie County Emergency Operations Center'; Basement of Pottawattamie County Courthouse, 227 S. 6th St., Council Bluffs, IA NOTE State and County EOCs will participate to the extent of notifications only.

G sA0hM1 AN U AL\SCP1P ART,WPS 1-6 8/6/92 l

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7. .

CONDUCT of EXERCISE ORIECTIVES Exercise objectives are provided under this heading Objectives provide a basis for scenario development arid a means to evaluate responses by the emergency response organization.

The Omaha Public Power District radiological emergency preparedness exercise objectives for the Fort Calhoun Station are based on Nuclear Regulatory Commission (NRC) requirements provided in 10CFR50.47, " Emergency Plans", and 10CFR50, 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

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of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power 1 Plants", was utilized ia developing the objectives. !

Objectives are grouped according to functional area of emergency response, Additionally, objectives have been cross referenced to major or parent Emergency Plan Implementing Procedures used in demonstrating the objective, and to any related open weaknesses from prior exercises, owu uwumoiuncrrv.wes 1-7 8/3/92

CONDUCT of EXERCISE OILIECTIVES (cont)

Generbi Oblectives:

Accident Assessment. Classification and Mitigation

1. Demonstrate the ability to assess plant conditions.

8NUREG-0654 ref: D.1-2; H.5; I.1 2

Major EPIP ref: OSC-14; RR-10,18,19

' Weakness ref: none

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

2NUREG-0654 ref: D.1-2; H.5; 1.1 2

Major EPIP ref: OSC-1,14; RR-10.18,19

' Weakness ref: 285/9108-03

3. Demonstrate the ability to classify the event per EPIP-OSC-1.

NUREG 0654 ref: D.1-2: H.5; 1.1 2

Major EPIP ref: OSC-1,14; RR-10,18,19 2 Weakness ref: none

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

'NUREG-0654 ref: B.7.a-b 2 Major EPIP ref: TSC-1,8; RR-11,13,84

' Weakness ref: none Notification and Mobilintliga

5. Demonstrate the ability to alert and notify OPPD emergency response personnel in a timely manner, NUREG-0654 ref: A.I.e; B.1,5,7.a; E.2; F.1.e 2

Major EPIP ref: OSC-2 3Weakaess ref: none l

asecuu wu mowtenvuvs 18 8/3/92

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, CONDUCT of EXERCISE

.QHJECTIVES (cont)

Notification and Mobilization (Cont)

J

6. Demonstrate the ability to mobilize OPPD emergency response personnel within the time frames specified in the Emergency Plan.

J.1,4 l

'NUREG-0654'ref:

2 Major EPIP ref: OSC-2 3 Weakness ref: none

7. Demonstrate the ability of OPPD to notify. federal, state and county agencies within the time frames sp cified in the Emergency Plan.

3NUREG-0654 ref: A.I.e; B.4,7.c; E.1-4; F.1; J.7; N 2.a 2 Major EPIP ref: OSC-2; EOF-23,24

' Weakness ref: none

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

NUREG-0654 ref: J.1,4 2 Major EPIP ref: OSC-2 3 Weakness ref: none Einereency Response

9. Demonstrate the ability to direct and coordinaie emergency responses.

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

Major EPIP ref: OSC-14; RR-10,18,19,21

' Weakness ref: none

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

8NUREG-0654 ref: A.1.d; B.3-5 2

Major EPIP ref: EOF-13 3 Weakness ref: none l

G A608GI ANU AUoBJECTIV.WP5 1-9 8/3/92

CONDUCT of EXERCISE OBJECTIVES (cont)

Emercency Response (Cont)

11. Demonstrate the ability to provide initial and continuous accountability of onsite individuals, including search and rescue operations.

'NUREG-0654 ref: J5 2

Major EPIP ref: OSC-9 3 Weakness ref: none

}lmliolocical Assessment and Co111tgj

12. Demonstrate the ability to provide radiological monitoring and decontamination capabilities for < ,nsite non-essential personnel.

'NUREG-0654 ref: J.3-4; K.7 2

Major EPIP ref: EOF-10; RR-87

' Weakness ref: none

13. Demonstrate the ability to provide onsite contamination controls, including decontamination capabilities and area access controls.

NUREG-0654 ref: K.5,6 2

Major EPIP ref: EOF-10; RR-87

'Weakner.s ref: 285/9108-01

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

'NUREG-0654 ref: K.1.a-g,2,3.a-b 2 Major EPIP ref: OSC-9,20; EOF-ll,21; RR-22,87 8 Weakness ref: 285/9108-01

15. Demonstrate the ability to monitor, assess, and correlate onsite radiological-conditions.

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

Major EPIP ref: OSC-20; EOF-6,22; RR-22,87

' Weakness ref: 285/9108-03 I

L ovosotouauosireriv.wr5 1-10 8/3/92

CONDUCT of EXERCISE OlHECTIVFJ (cont)

Radiological Assessment and_Contrg](Cont)

16. Demonstrate the ability to collect, analyze and evaluate simulated radiological samples and surveys.

8NUREG-0654 ref: H.5.b,7; N.2.d,e.1 2

hiajor EPIP ref: OSC 20; TgC-8; EOF-6,11,20,22; RR 22,87 3 Weakness ref: none

17. Demonstrate the ability to assess core damage.

8NUREG-0654 ref: I.3;ht.1 2

hiajor EPIP ref: TSC-8; RR-11,13

' Weakness ref: none

18. Demonstrate the ability to make the decision whether to issue emergency workers radioprotective drugs, KI.

NUREG-0654 ref: J.6.c 2

hiajor EPIP ref: EOF-21; RR-22,24,25 3 Weakness ref: none

19. Demonstrate the ability to determine scurce terms and dose projections, evaluate dose projections against protective action guides and determine appropriate onsite and offsite protective actions.

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

hiajor EPIP ref: EOF-6,7,20,22

' Weakness ref: none

20. Demonstrate the ability to make timely protective action reccmmendations to offsite agencies.

8NUREG-0654 ref: I.5-11, J.7 2

hiajor EPIP ref: EOF-6,7,20,22

' Weakness ref: none l

G n60801 AN U AL\OBJ ECTIV.WP5 1-11 8/3/92 a

_ _ CONDUCT of EXERCISE Q1LIEC.TIVES (cont)

Emulenev Respoibe Fncilltv Soccific Obigthnt

21. Emergency Operations Facility (EOF):

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

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

c. Demonstrate the effectiveness and 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 fashion.

f. Demonstrate the functional adequacy of the EOF.

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

Major EPIP ref: OSC-2,15,21; TSC-1; EOF-1,11,22,23; RR-17,28, RR 65,66,97 3 Weakness ref: none

22. Technical Supnort Center frSch

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

b. Demonstrate the adequacy of communication oetween the OSC, EOF, inplant response teams, and the TSC.

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

d. Demonstrate the adequacy of security access control,

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

f. Demonstrate the functional adequacy of the TSC.

g. Demonstrate the ability to perform core damage assessment and to project core uncovery.

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

-2 OSC-2,15,21; TSC.1; EOF-1,11,22,23; RR-17,28, Major EPIP ref:

- RR-65,66,97 -

3 Weakness ref: none i

cuosatmumonitc riv.wr3 1-12 8/3/92 l

CONDUCT of EXERCISE OlUECTIVI3 (cont)

Onctdency Resoonse Facility Snecific Oblecthis (Cont)

23. Control Room (CB.)

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

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

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

d. Demonstrate the functior'al adequacy of the Control Room.

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

Major EPIP ref: OSC-2,1 .21; TSC-1; EOF 1,11,22,23; RR-17,28,-

RR-65,66,17 3 Weakness ref: none

24. Operations Support Center (OSC):

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

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

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

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

e. Demonstrate the functional adequacy of the OSC.

f. Denionstrate the adequacy of security access control.

g, Demonstrate the adequacy of OSC habitability surveys.

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

Major EPIP ref: OSC-2,15,21; TSC-1; FAF-1,11,22,23; RR-17,28, RR-65,66,97 3 Weakness ref: 285/9108-01 omos4stanuatsoruscriv.wr5 1-13 8/3/92

, CONDUCT of EXERCISF ORIECTIVES (cont)

Scenario

25. Demonstrate the ability to provide an exercise 'cenario and controller organization that permits testing a major portion of the emergency plan and allows for realism and free play.

'NUREG-0654 ref: N.1.a-b 2 Major EPIP ref: none

' Weakness ref; none EVElulltiOD I

26. Demonstrate the ability to conduct a pmt-exercise critique to identify areas requiring additional improvement.

NUREG-0654 ref: N.4,5 2

Major EPIP ref: none

' Weakness ref: none FOOTNOTES

' References related emergency planning objectives provided as guidance -in NUREG-0654/ FEM A-REP-1 Rev.1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of-Nuclear Power Plants" as based-on NRC requirements provided in 10 CFR 50, Appendix E, " Emergency Planning and Preparedness for Production and Utilization Facilities".

2 References major OPPD-FCS Emergency Plan Implementing Procedure (s) used in-demonstrating the objective. Other procedures may be applicable but will generally be referenced by, or N.anched from, the major procedure.

' References applicable open deficiencies from the 1991 exercise as sted in NRC docket 50-285/9108 (see the following for a summary of deficiencies).

Gn608GtANUAL\0NECMVMP3 1-14 8/3/92

CONDUCT of EXERCISE QBJECTIVES (cont)

ELEMENTS NOT TO BE DEMONSTRATED IN 1992

Alternate severe weather scenario (unless actual severe weather exists, i.e.

thunderstorms)

Exceeding emergency worker protective action guidelines (PAGs)

Contaminated / injured personnel response

Offsite fire fighting assistance

Backup communication equipment

Shift changes

Recovery / reentry activities

Use of offsite laboratory analysis

Notification and alerting of the public

Public Information

Protective actions (evacuation,. shelter)

Reception and care

Exposure control (access and traffic control, use of KI, record keeping)

Unannounced Exercise initiation

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Health Physics drill - plant sampling

Participation by state and local governments

Inplant post accident sampling Source term determination - alternate (un-monitored release)

Long term recovery organization

Activation of OPPD NPPD assistance

- Calculations involving total population exposures on6*mAsuruoartenvxr5 1-15 8/3/92

j: CONDUCT of EXERCISE OBJECTIVES (cont) 1991 Exercise Weakness Summary Operations Suonort Center 285/9108 01 Complete habitability surveys, including contamination smears were not performed routinely in the Operations Support Center during an approximate two hour period following indications of core damage and subsequent release to the environs. Even though announcements were made to prevent eating, drinking and smoking, contamination smears were not conducted between 1200 and 1400 hours0.0162 days 0.389 hours 0.00231 weeks 5.327e-4 months to validate habitability requirements of the OSC. Failure to exercise proper radiological controls in the OSC was identified as an exercise weakness.

, Emergency Operations Facility 285/9108 There was one instance of field monitoring teams using an older map containing obsolete - information. The use of maps containing obsolete information to describe a field team's location is considered an exercise weakness. This weakness was corrected by the licensee and closed in NRC Inspection Report 92-08.

-285/9108-03 Failure to accurately detect, asms, and correlate plant conditions with radiological releases and cose assessment functions was identified as an exercise weakness.

Although the containment purge line was correctly assumed as the release path

' due to increasing stack radiation monitor readings, efforts to determine the flow specifics needed for accurate dose projections were ineffective. As a consequence, overly conservative assumptions were used yielding higher than actual dose projections. -!

Contributing factors to this weakness included:

a) Inadequate damage assessment following a simulated short circuit in panel A! 44. This delayed assessment resulted in approximately 40 minutes passing before validation that containment isolation valves PCV-742-C and -

PCV-742-D had opened as a result of the short.

b) Failure to properly identify stack flow rate via available indications in the Control Room. A general determination was made in several locations that since no auxiliary building fans were operating, stack flow was zero.

asosniANUAltORIECTIV.WP5 1-16 8/3/92

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CONDUCT of EXERCISE i OB.IECTIVF4 (cont)

This forced the Dose Assessment Soccialist in the EOF to perform dose assessment using conservative estimated flow rates. This dose assessment '

resulted in overly conservative projections.

c) Lack of stack flow rate data on the Emergency Response Facility Computer System (ERFCS), which would allow- dose assessment personnel in the TSC and EOF direct &ccess to current data, eliminating a communication link, d) In that conservative stack flow was utilized, several refinements to the release rates c cd within the EAGLE system were made based on manipulating the dose program to match known field team survey results.

However, these results were accurate only within an order of magnitude.

A formalized method to use EAGLE to incorporate field data and provide "back calculations" of release rates and/or source terms would provide this function in a more timely and consistent manner.

G36084'M ANUADORIECTIV.WP5 - 1-17 8/3/92

CONDUCT of EXERCISE GUIDELINES and SIMULATIONS Exercise guidelines and simulations are provided under this heading. Guidelines define parameters under which the exercise will be conducted and delineate the extent to which objectives will be demonstrated.

Simulations define the boundaries of emergency responses by participants. Areas where participants will ant be allowed to carry out emergency responses to the fullest extent are indicated under simulations. Limitations in emergency responses are necessary to protec' personnel and the integnty of the operating reactor, and to limit impact to the public while siraulatin;; emergency conditions.

0:\6084alANUAL\GDLNASIM WP5 1-18 8/12/92

. 3 CONDUCT of EXERCISE EUIDELINES and SIMULATION. (cont)

1. The exercise will be conducted on October 14, 1992.

. 2. Personnel necessary for safe reactor operation will be exempt from all exercise activities.

3. Actual operatioral or radiological events or emergencies take precedent over all other activities. If an actual operational or radiological vent should occur, the exercise shall be suspended and players noti 6ed via the controller network. The senior exercise controller shall then consult with management to coordinate resumption of the exercise following resolution of the actual operational or radiological event.

4 Participants will be informed of the exercise date, but will not be informed of the start time.

5. Participants tp.it 4 tot be informed of the scenario events, timelines, or data.

6. Participants will be pre-briefed on limits to responses and on any required actions during responses (see CONDUCT of EXERCISE, PARTICIPANT GUIDELINES for content of brienng).

7. Scenario initial conditions, both operational and meteorological (see SCENARIO EVENTS, INITI AL CONDITIONS for content) will be distributed to participants prior to the start of events through the use of the following routine documents:

Plan of the Day

Routhe shift turnover paperwork

8. Participants will not be pre-staged except for the following:

Participants Location Control Room Staff (Shift Control Room Simulator Supervisor, Senior Reactor Operator, Reactor Operators, Shift Technical Advisor)

Auxiliary and Turbine Building Operators in-plant

Shift Chemist' in-plant

Shift Radiation Protection Personnel in-plant

Initial condition repair personnel repair site (s) 9, Personnel will be notified of emergency conditions through methods normally employed

.in making notifications, i.e. plant alarms, GaiTronic announcements, personnel pagers.

ca60sutwumcouaSRWP5 1 19 8/12/92

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( CONDllCT of EXERCISE GUIDELINES and SINIULATION (cont)

10. Scenario driven plant operations veill be directed from the control room simulator.

Control room communications will be performed using equipment similar to actual control room equipment.

Plant alarm activation will occur under direction of participants in the simulator but will utilize actual control room equipment through use of an intermediary control cell.

Plant wide announcements will be initiated from the simulator via the GaiTronics cross-connect.

Control room briefings and dispatch of auxiliary and turbine building operators will occur under direction of participarits in the simulator but will be conducted onsite through the use of an intermediary in the vicinity of the actual control room.

The simulator will operate " live time." In the event of simulator failure for a protracted period of time, annunciators, indicators of plant parameters, and computer displays may be simulated through the use of hard copy scenario messages. The exercise senior controller shall decide.to continue the exercise using paper hard copy data based on the recommendations of the control room simulator operator.

11. The emergency notificution system (ENS branch of the Federal Telecommunications System) will be used at least once to demonstrate system operability.

12. Selected data normally available through the emergency response facility computer-system (ERFCS) will be simulated through use of either a computer or scenario messages reflecting simulator information.

l

The use of computers to simulate the ERFCS will necessitate additional personnel

in the simulator for monitoring and transmitting the data to the emergency response facilities.

Scenario message data may be required to supplement the limited capabilities of computers to simulate the ERFCS.

on608&MANUADGDLNASIM.%YS 1-20 8/12/92 1

CONDUCT of EXERCISE fd4HELINES and SIMULATION (cont)

13. To the maximum practical extent, participants will be permitted " free play" in emergency responses and accident mitigation. Facility Lead Controllers, after making note of un-anticipated actions, shall inform the exercise senior controller. The exercise senior controller may prohibit certain actions to maintain emergency responses witnin the '

planned scenario timeline. Credit for innovative approaches should be given at the facility critique.

14. Emergency response by participants will be to the fullest extent possible without violating any normal station procedure or good practice.

Participants will obtain permission from the on-shift Shift Supervisor prior to operating the post accident sampling system.

Post accident sampling system data normally obtai may be assessed independently of time required for its operation due to h ario compression.

Personnel accountability will be performed for all personnel within the protected area.

Protected area evacuation will be performed. NO TE: Plant workers not directly involved with the exercise will be permitted to return to work upon the approval of the Site Director.

Site evacuation will be simulated.

Participants contacting outside organizations not specifically listed as a participating organization will perform communication checks only.

15. Some areas of emergency response will be limited to protect personnel and equipment or to lessen the in pact on the public.

Participants will not operate, manipulate or implement repairs on installed pant equipment or valves, without explicit perm:ssion from the on-shift Shift Supervisor.

Actual tag out of equipment and valves will not be performed, however, all required authorizations and paperwork should be completed.

Participants will not make entries into actual High and Very High Radiation Areas with the exception of obtaining actual PASS samples.

G a60801 ANU A13GDLNASIM.WP5 1-21 8/12/92

, CONDUCT of EXERCISE GUIDELINES and SIMULATION (cont)

Appropriate onsite participants will demonstrate the procedure for donning SCBA's once but will not discharge air tanks.

Offsite support will be simulated (i.e. fire or medical support).

Fire hoses will not be charged.

Panicipants will not be administered radioprotective drugs.

Offsite monitoring teams will not wear anti Cs in the field.

Actual decontamination of equipment and vehicles will not be performed.

Participation by non-emergency OPPD personnel will be simulated (i.e.

Transmission and Distribution or System Protection).

16. Offsite monitoring teams shall rendezvous with their controller where their monitoring equipment is obtained.

17. Participants may request and, upon completion of appropriate actions, obtain from controllcrs additionalinformation or data that was not previously available. Controllers shall not freely give out additional information. If, for example, playeis request the results of an internal inspection of a circuit breaker, they must first demonstrate the

. equired tools '6cd techniques,'and the appropriate level of knowledge to perform the inspection. Only then will the controller hand out the results of the inspection.

18. Contingency messages wul be assigned issuance times for reference only and will be issued only if participant actions affect pir.nned scenario events, timelines, or data and only if authorized by the lead facility controller.

19. Controllers will assist in assuring that all communications accessible to the public include "TIIIS IS A DRILL".

L G 360841ANU AUGDURSINIMTs 1-22 8/12/92

CONDllCT of EXERCISE GUIDELINES and SB1ULATION (cont) j AREAS OF EMERGENCY RESPONSE IMPACTED OR DELAYED DUE TO SIMULATIONS

Some actions and communications originating in the simulator control room outside the protected area that must be performed through the onsite control room through the use ofintermediaries, e.g.;

o Sounding of alarms.

o Command and control of onsite, in plant Operators.

o ' Equipment operation or manipulations that require Shift Supervisor approval.

o Communications to the control room that are relayed to the simulator control room.

Control of site access traffic on liighway 75 will be simulated to eliminate the impact to transportation flow on a main thoroughfare.

Non-participating employees may be allowed to return to work efter completing a protected area evacuation.

Analysis of post accident sampling system (PASS) data may be performed prior to operation of the PASS due to a compressed timeline.

a canimumcotusuwes 1-23 8/12/92

CGNDUCT of EXERCISE l'Al[rlCIPANT GUIDELINES Participant guidelines are provided under this heading. These guidelines provide participants a basis and any limits to their emergency response during simulated activities. Participants will be bnefed on these guidelines prior to the start of any simulated activities. These guidelines contain no classified scenario snaterial and are intended to be handed out to participants at the briefing, O.W44 M ANU ALTARTO DLN.WP3 I - 24 NCv b/I3/92

CONDUCT of EXERCISE PARTICIPANT GUIDELINES (Cont)

SIhedule of Events

1. The exercise will be conducted on October 14, 1992.

2. Upon termination of Exercise activities, facility critiques will be conducted in the CR (simulator), TSC, OSC, and EOF. Every participant must complete a participant's critique form and be prepared to discuss any major critique items. Participant critique forms will be handed out after termination of the simulation. The facility manager or director is responsible for collecting the completed critique forms.

3. On October 15, 1992, a key canicioant/ evaluator critiqu will be held in the FCS training center auditorium with the key panicipants from all emergency response facilities and all controllers and evaluators.

4. On October 16, 1992, Omaha Public Power District will present its initial exercise entiqu to the Nucles Regulatory Commission (NRC). This presentation will be conducted prior to the NRC's inspection exit meeting. These activities are scheduled to take place in the conference room of the Emergency Operations Facility.

Scope nnd Partichum15

4. The following emergency response facilities and services will b'e available to participate:

Omaha Public Power District (OPPD)

Control Room (CR) Simulator

Technical Support Ctrter (TSC)

Operations Support Center (OSC)

Emergency Operations Facility (EOF)

State of Nebraska a State Emergency Operations Center'

Washington County EmerSency Operations Center' State of Iowa

State Emergency Operations Center'

Harrison County Emergency Operations Center'

Pottawattamie County Emergency Operations Center'

' State and County facilities will participate to the extent of notifications only, c.esutrsurtteraTaots.wes 1 25 Rev 8/13/92

-. , - . - . - , , , - - . - - . . , _ . _ _ -_-__..~,,m, _.. . - , -

, _ . ,,_ - - , - r - - - y- _ _ - ~

CONDUCT of EXERCISE PARTICIPANT GUIDELINES (Cont) fdtklellnes nnd Simulatiqu$

5. Personnel necessary for safe reactor operation are exempt from all exercise activities.

i 6. Actual operational or radiological events or emergencies take precedent over all other activities, if an actual operational or radiological event should occur, the exercise shall be suspended and players notified via the controller network. The senior exercise controller shall then consult with management to coordinate resumption of the exercise following resolution of the actual operational or radiological event.

7. Scenario initial conditions, both operational and meteorological (see SCENARIO EVENTS, INITI AL CONDITIONS for content) will be distributed to participants prior to the start of events through the use of the following routine documents:

Plan of the Day

Routine shift turnover paperwork

8. Participants must not pre-stage except for the following:

Participants Location Control Room Staff (Shift Control Room Simulator Supervisor, Senior Reactor Operator, Reactor Operators, Shift Technical Advisor

Auxiliary and Turbine Building Operators in-plant

Shift Chemist in-plant

Shift Radiation Protection Personnel in plant

Initial condition repair personnel repair site (s)

9. Personnel will be notified of emergency conditions through methods normally employed in making notifications, i.e. plant alarms, GaiTronic announcements, personnel pagers.

I owsmANUCPArrGDLN.WP$ 1 - 26 Rev 8/13/92 l

l CONDUCT of SXERCISE ;

PARTICIPANT GUIDELINES (Cont) r Guidelines and Simulations (cont) ,

10. Scer'ario driven plant operations will be directed from the control room simulator.

Control room communications will be performed using equipment similar to actual control room equipment.

Plant alarm activation will occur under direction of participants in the simulator but will utilize actual control room equipment through use of an intermediary control cell.

Plant wide announcements will be initiated from the simulator via the GaiTronics cross-connect.

Control room briefings and dispatch of auxiliary and turbine building operators will occur under direction of participants in the simulator but will be conducted onsite through the use of an intermediary in the vicinity of the actual control room.

The simulator will oprate " live time." In the event of simulator failure for a protracted period of ;Ime, annunciators, indicators of plant parameters, and computer displays may be simulated through the use of hard copy scenario ,

mes: ages. The .:xercise senior controller shall decide to continue the exercise using paper hard copy data based on the recommendations of the control room simulator operator.

11. The emergency notification system (ENS branch of the Federal Telecommunications System) will be used at least once to demonstrate system operability.

12. Selected data normally available through the emergency response facility computer system (ERFCS) will be simulated through use of either a computer or scenario messages reflecting simulator information.

The use of computers to simulate the ERFCS will necessitate additional personnel in the simulator for monitoring and transmitting the data to the emergency response facilities.

Scenario message data may be required to supplement the limited capabilities of computers to simulate the ERFCS, a w>smmurtsrARTootre.wes 1 - 27 Rev 8/13/92 l

CONDUCT of EXERCISE i' '

1%IGIC11MNT GUIDELINES (Cont)

Gulddinti.Andlk!1Hla119B5 (cont)

13. To the maximum practical extent, participants will be permitted " free play" in emergency responses and accident mitigation. Facility Lead Controllers, after making note of un-anticipated actions, shall inform the exercise senior controller. The exercise senior controller may prohibit certain actions to maintain emergency responses within the planned scenario and timeline. Credit for innovative approaches should be given at the facility critique.

14. Emergency response by participants will be to the fullest extent possible without violating any normal station procedure or good prtetice.

Participants will obtain permission from the on shift Shift Supervisor prior to operating the post accident nrnpling system.

Post accident sampling system data normally obtained may be assessed inoependently of time required for its operation due to scenario compression.

Personnel accountability will be performed as appropriate.

Protected area evacuation will be performed if required.

Site evacuation will be simulated if required.

Participants contacting outside organizations not specifically listed as a participating organization shall perform communication checks only.

15. Some areas of emergency response will be limited to protect personnel and equipment or to lessen the impact on the public.

Participants ihalln01 operate, manipulate or implement repairs on installed plant equipment or valves.

Actual tag out of equipment and valves will not be performed, however, all requaed authorizations and paperwork should be completed.

Participants shall not make entries into actual liigh and Very liigh Radiation Areas. If the scenario requires entry into such an area, inform your controller, c 4onursurt.rrnicots wes 1 - 28 Rev S/13/92

i-E.

t .

CONDUCT of EXERCISE PARTICIPANT GUIDEl.INES (Cont)

Guidelines and_Sintula110Ds (cont)

Appropriate onsite participants will demonstrate the procedure for donning SC11A's once but will not discharge air tanks.

Offsite support will be simulated (i.e. fire or medical support), if required.

Fire hoses (if required) will not be charged.

Participants will not be administered radioprotective drugs.

Offsite monitoring teams will not wear anti-Cs in the field.

Actual decontaminati n of equipment and vehicles will be simulated, it required.

Panicipation by non cmergency OPPD personnel will be simulated (i.e.

Transmission and Distribution or System Protection), if required.

Iti. Offsite nionitoring teams shall rendezvous with their controller where their monitoring equipment is obtained.

17. Participants may request and, upon completion of appropriate actions, obtain from controllers additional information or data that was not previously available. Ccatrollers shall not freely give out additional information, if, for example, players request the results of en internal inspetion of a circuit breaker, they must first demonstrate the required tools and techniques, and the appropriate level of knowledge to perform the inspection. Only then will the controller hand out the results of the inspection.

l G A6084 M ANU AL\PARTGDLN WP5 1 - 29 Rev 8/13/92 I

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CONDUCT of EXERCISE 11IEICll%ST_GUID111NES (Coat)

Gmilunlatultlp

18. Three groups of personnel may be in attendance and will function as described below:

Controllers; Controllers are responsible for controlling scenario events and issuing data to participants. Contrellers may initiate certain actions, i.e. issue contingency messages, to assure continuity of cvents. Controllers have evaluator responsibilities as well. Controllers are recognized by red hats and/or badges.

Evaluators: Evaluators are responsible for documenting and evai ig the emergency response. They wve a passive function and do at control .

or impact emergency responses. Evaluators must not interfere with the flow of events. Evaluators may ask questions to clarify theii understanding of actions taken by participants or procedural concerns.

NRC evaluators will also be present.

Observers: Observers are not responsible for participating, controlling, or evaluating. Observers must not interface with participants, or evaluators. Questions from observers should be directed to controllers.

Observers are recognized by yellow badges.

19. Participants must become familiar with the controller and evaluator organizations, especially the controller and evaluator assigned to your location. Identify yourself by name and function to your controller and evaluator, et NRC evaluator (if present).

v

20. All communications which are accessible by the public,} including GaiTronics announcements, outside telephone calls, etc., must begin and end with " Tills IS A DitlLI.". Make sure you repeat the phrase at frequent intervals.

21. Maintain status boards, log books, communication forms, etc., as much a possible.

Document all your actions. Keep your logs accurate and detailed. Ths is very important. Remember, put it in writing and include the note, " Tills IS A DRILL".

22. Participants should actually play out all emergency responses to the fullest extent as possible. Auxiliary and turbine building operators, radiological monitoring teams, search and rescue teams, emergency repair teams, etc., should be deployed as appropriate.

23. Resist over anticipating scenario events. Your actions should be in response to data

! being presented to you.

l osuiwumemoowws ! - 30 Rev 8/13/92

CONDUCT of EXERCISE PARTICIPANT GUIDELINFS (Cont)

Gamumanship (cont)

24. Unless authorized by your controller, you must n01 simulate any of your actions, if authorized to simulate an action, tell your controller or evaluator how and when you would normally perform the simulated action.

Simulation: Simulated play involves identification and explanation of required actions and procedures.

Actual: Actual play involves deployment of resources and physical implementation of procedures.

25. Controllers use time related messages as the mechanism of initiating, orchestrating, modifying, and completing scenario events. Operational and radiological data is also issued through time related messages. Accept these messages immediately. They may contain scenario information essential to your successful performance.

26. Participants are responsible for contacting their controller before 'oeing dispatched into the plant or out into the field. The controller may have data that is vital to scenario events. This is of paramount importance to your success. Offsite monitoring teams may rendezvous with their controllers where their monitoring equipment is obtained,

27. Controllers will act provide information to participants regarding scenario development or resolution of problem areas encountered. Participants are expected to obtain information through their own organizations for use in determining response actions and resolving problems.

28. You may ask your controller for information or clarification of scenario data, examples are:

Initial conditions of the plant and systems including;

system status and availability

valve line ups a reactor coolant chemistry and radio 1c; scal activity

operating history of core

meteorological data, including wind direction, speed, temperatures, and forecasts

Operational parameters and indications

Area radiation data at locations of emergency teams

Airborne data at locations where sampling has been performed

lsotopic data resulting from sample analysis

Data normally obtainable from emergency response facility computers.

On60H M ANU AUPAMODLN3ts 1 - 31 Rev 8/13/92

/ CONDUCT of EXERCISE PARTICIPANT GUIDELINES (Cont)

Gamesmanstth) (cont)

29. You may nej ask the following from the controllers:

Information contained in procedures, drawings or instructions

Judgments as to which procedures should be used

Data not normally available to you o Assistance in carrying out calculations

Ef5ciency of counting equipment

Assistance in activating facilities

Assistance in performing emergency responses

Assistance in repairing, replacing or substituting emergency response equipment, i.e.

telephones, fax machines, etc.

Explanation of scenario events

30. Some participants may insist that certain aspects of the scenario are unrealistic. Scenario events and timelines are designed to permit demonstration of all utility objectives, as well as any state and local objectives.

31. If you disagree with your controller, you may request him/her to reevnsider or seek advise from the facility lead controller. Under no circumstances are you to argue or indulge in theoretical discussions with your controller.

32. Periodically identify your key actions and decisions to the controller and evaluators.

Ensure that controllers and evaluators are aware of when you reference emergency procedures. This may seem artificial but it will assist in the evaluation process and is to your bencSt.

33. You must act accept any data, messages or instructions from evaluators, observers, or visitors, including federal evaluators. If evaluators want to initiate actions, test your abilities, or give you a " surprise", they must work through a controller.

34. If your controller intervenes with your actions, it is for a good reason. Obey your controller's direction at all times. This is essential to the overall success of the simulation, i

l a nsm ANUMAkrGDLN.WP5 1 - 32 Rev 8/13/92

+

CONDUCT of EXERCISE PARTICIPANT GUIDEl.IN13 (Cont)

Gainesmanship (cont)

35. Participants must respond as if any radiation hazards presented by the scenario are actually present. This includes, but is not limited to the following:

Wearing of dosimetry and anti Cs

Observing good radiation protection practices

Minimizing radiation exposures

Responding to failed instruments in the field ~

Reporting radiological hazards to proper personnel

Proper contamination control, i.e. radwaste, eating, smoking, food deliveries, etc.

36. Follow the instructions of individuals in the emergency response organization who are responsible for determining and enforcing good radiological practices.

37. Controllers, evaluators, and observers are not required to respond to simulated radiological hazards. They are exempt. Do not let this confuse you or cause you to act unwisely.

38. All normal station rules and procedures are to be followed when entering actual radiological controlled or radiation areas. H9 Rus, even controllers, evaluators, and observers, are exempt from normal station radiological practices and procedures. ,

39. Respond to controller and evaluator questions. If a question is misdirected to you and you do not know the answer refer them to your supervisor or to the facility. lead controller, if your emergency response is being impacted by questions from evaluators then notify your controller. Observers are not allowed to enter into conversations with Participants.

40. Maintain a professional attitude throughout the simulation. Dead times may arise when scenario events are exercising other areas of emergency preparedness. Use this time to police your facility and work areas. Minimize socializing.

41. Intentional violation of federal, state or local laws is Det permitted. All local traffic laws, especially speed limits, must t.e observed, a womtANU AUPARToDLN WP5 1 - 33 Rev 8/13/92 l

s CONDUCT of EXERCISE i-1%BTICIPANT GUIDEl.INf3 (Cont)

Gamesmansidy (cont)

42. It is not the intent to inconvenience the public during simulated events. Never endanger public or private property. Ensure all communications in public areas begin and end with the phrase " Tills IS A DRILL".

43. Termination of activities will be authorized only by the senior controller.

44. Keep a list of items which you believe will improve emergency plans and procedures.

One of the main purposes of the Exercise is to identify areas requiring improvement to increase the overall effectiveness of emergency preparedness.

45. All logs, journals, worksheets, checklists or other documentation completed during all activities must be retained and turned over to the facility lead controller prior to, or at the facility critiques.

amso,twuwanoow3rs 1 - 34 Rev 8/13/92

i SCENARIO EVENTS TABLE OF CONTENTS l

TABLE OF CONTENTS 2-1

NARRATIVE

SUMMARY

22

TIMELINE 26

MASTER EVENTS

SUMMARY

2 13

MECIIANICAL FAULT AND REPAIR

SUMMARY

1 27 4

D ca6caerxtacisosctwAmo.wr5 1 REV. 8/12/92

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n T' t-- de v g--t't-7't-T' ' ' - +' 'r7 -hh'7w tri*A v'* T19WW 4W*M'Y' N T- **? '4TW -g t c-r e gs-T--Tg

T SCENARIO EVENTS NARRATIVE

SUMMARY

A Narrative Summary of the scenario follows. .,

This narrative summary is intended to present a brief version of the scenario that will unfold '

based on simulais Mdications, and as a result of issuing participants scenario messages, operational data and adiological data contained in this scenario, ,

The plant is operating at 100% power for the last 47 days. Xenon is at equilibrium. The grid is in a high-demand low-reserve situation. The system will not have additional capacity available for at least four more hours (~ 1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months ). A Containment Pressure Reduction is in progress.

All control systems are operating normally in automatic. One new fuel shipment was received ,

_ yesterc'ay. Another is scheduled to be received this morning. A radioactive waste shipment is being prepared for transfer. Chemistry is tracking a suspected leaking fuel pin, indicated by slightly elevated RCS coolant activity levels.

The following plant equipment is out of service or under maintenance:

As a result of a NRC bulletin on experienced incidents of sudden failure of components in the operators of seldom-operated Fisher Controls Class 300 type U and UR valves, the Containment Spray containment isolation valves (HCV 344 and -345) are to undergo --

visual inspection and verification of operation. Since the problem has produced valve operation failure in other plants, Commission direction and approval has been issued for performance of the inspection and verincation at power. HCV-345 was tagged-out for this inspection at Midnight, placing the Unit currently 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months into the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO in ,

accordance with Technical Specifications, Item #2.4.(1).b. The operator of HCV-345 l has been disassembled and is undergoing inspection.- Inspection of the valve internals is in progress. ---The inspection and reassembly process is expected to be completed in 6 I

hours and the testing is anticipated to require an additional 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

VA 3A and -3B containment ventilation fans are running. Control room staff has been tracking an unexplained reduction in fan motor current from 132 to 128 amps over the -

mid watch. - The lowering motor current is suspected to be due to slippage of the adjustable-pitch blades on those fans due' to vibration.

The following plant surveillances are scheduled for today:

Main turbine local vibration test, per request of a visiting _ GE turbine -

representative.

oA6084iEXERC15E\ SCENARIO.WP5 2-2 REV. 8/12/92

i SCENARIO EVENTS

, NARRATIVE SUhth1ARY (Cont)

The #1 Emergency Diesel Generator was scheduled to be placed out of senice for inspection of it's air start system. This Ph10 has been deferred uatil completion of the inspections on 11CV-345 and liCV 344.

The exercise begins with a main turbine trip due to inadvertent impact on a vibration sensor by machinists. Immeditely after the trip, the resulting system pressure spike causes the sudden gross failure of one main steam header of S/G "A" inside containment. The break results in a large release of steam to the containment and the triggering of a Safety Injection Actuation Signal (SIAS), Containment isolation Actuation Signal (CIAS), hiain Steam isolation Signal (htSIS) and Containment Spray Actuation Signal (CSAS). At this point, several simultaneous events occun Upon the CSAS, containment spray valve llCV-344 indicates open, but containment spray flow indicates zero.

liCV-746A (inboard isolation valve for the containment pressure reducuon) fails to shut upon the CIAS.

Containment ventilation fans VA-7C and 7D start and immediately trip.

Containment ventilation fans VA-3A and 3B motor current falls to 120 Amps. (The fan blades have slipped to their zero position and air flow through the fans falls to zero.)

Due to the rapid pressure and temperature transient of the trip and steam generator failure, the leaking fuel pin is further damaged. Approximately 0.4% clad gap inventory is released into the coolant. Containment radiation levels increase.

Containment pressure rises as the steam generator steams down into containment without the suppression effect of containment spray, or ventilation coolers. Operators identify the faulted generator based on loss of level and pressure and focus on rising containment pressure. In an attempt to accelerate the restoration of "A" train Containment Spray, operators may send the auxiliary building operator to open HCV-344 manually. If they try this, the handwheel turns about one turn in the open direction from its neutral position, and then will turn no more. If the turbine building operator inspects the breakers for fans VA-7C and 7D, he will find the breakers in the trip free position. If he is directed to reset the breakers, they will reset and shut, but trip again as soon as the Control Room attempts to start the fans. If maintenance personnel or operators open the cover on the breakers, tney will see that the targets on the Rhts 9 overcurrent devices for overload and short have popped out, hiaintenance is notified of the equipment faults. Chemistry should be directed to start setup for a post trip RCS sample (2 to -

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months post trip).

ovouarscisasemuuoms 2-3 REV 8/12/92 l

SCENARIO EVENTS NARRATIVE SUM 51ARY (Cont)

Containment Pressure reaches a maximum value of approximate'y 34 psig. Containment temperature reaches a maximum of 230*F. The Shift Supervisor should declare an UNUSUAL EVENT per EPIP-OSC-1. EAL 2.1; " Uncontrolled S/G 11 eat Extraction" based on information in EOP-01, Figurc 5-1

Break Identitication Chart". The SS may choose to activate the Emergency Response Organization (optional at NOUE). As the steam generator energy is ,

expended, containment pressure steadies out at ~21 psig (saturation pressure) and begins to decrease very slowly.11 eat and pressure inside containment preclude investigation of the failed open inboard purge valve. Maintenance (or an OSC team, if activated) investigates the failed shut containment spray valve, but it cannot be opened with the handwheel. The valve operator appears open, but the handwheel can be turned only about one turn in the "open" direction from it's neutral position. SS will probably request maintenance team working on llCV-345 to expedite repairs or to shift attention to llCV-344. The only valid success path is restoration of containment spray-via 11CV 344 IICV-345 tagout inside containment cannot be cleared, nor can any of the containment fans be restored. OSC/ Maintenance personnel will likely be directed to remove all or part of the remote air operator from liCV-344 in an effort to free the valve for operation. The primary concern is the restoration of some mode of containment cooling.

Control room operators should throttle SI now when pressurizer level is greater than 45Fo to maintain pressurizer level approximately 50Fv, and use S/G "B" and the MS 292 steam dump to the condenser to control RCS temperature. S/G " A" will boil dry. At some point during this evolution, operators will probably secure the running containment spray pumps. Containment pressure is not within the normal criteria for securing the pumps, but with no spray now and engineering analyses which indicate that recirculation flow is inadequate, the control room is -

expected to secure the pump > to prevent c' . mage and ensure their availability when a spray now path is available.

At EOP-00, Step 15, operators evaluate containment conditions. Elevated containment pressure with no spray now places them in the EOP 00 diagnostic section, which directs them into EOP-

05. In EOP-05, the Shift Technical Advisor (STA) will perform a critical safety function status check. The STA should notify the Shift Supervisor (SS) that containment integrity critical safety function is not met due to high pressure in the containment. This will direct operators into EOP -

20, Functional Recovery Procedures. Since entry into EOP 20 is (by dennition) indicative of a substantial degradation of plant safety, the SS may declare an ALERT, per EPIP-OSC-1, EAL 11.9; " Events in progress which indicate an actual or potential substantial degradation of the level of plant Safety," If notifications for the NOUE are not yet complete, the SS may abort the NOUE and declare the ALERT instead. If the ALERT is declared, TSC and OSC will activate and accountability will be conducted.

Several tubes in S/G "A", weakened by the trip and subsequent transients, fail, resulting in a primary to secondary leak of approximately 75 3pm through the faulted S/G. The rate of containment pressure drop decreases slightly. Operators determine that the leak rate exceeds 40 gpm. Radiation levels begin to increase in the faulted steam generator and inside containment.

owu4 cxrscisescom:uo.wes 24 REV. 8/12/92 k

- - - - ,-,..m _ . . . . _ - . . - ,c, .. -, _ ,

o ~

/ SCENARIO EVENTS NARRATIVE SUSWARY (Cont)

Containment atmosphere samples, if available, confirm the RCS leak into containment via the faulted steam generator. Operators use charging pumps and IIPSI as required per EOP-03 to '

recover and maintain pressurizer level. Three charging pumps and no 11 PSI flow, or fewer charging pumps with some HPSI flow will be sufficient to rnaintain level.

Given these indications of a small break LOCA, and the threat to the containment boundary implied by the failure to meet the containment critical safety function, the SS or Site Director should reclassify the event per EPIP OSC-1, EAL 1.16; "less of Two Fission Product Barriers" and declare a SITE AREA EMERGENCY. In the event that the SS did not previously evaluate the failure to meet the containment critical afety status function check as a threat to the containment bounda.y, the SS would then evaluate the current situation as a failure of the RCS boundary only, reclassify the event per EPIP OSC 1, EAL 1.5; "RCS Leak Rate > 40 gpm" and declare an ALERT. TSC and OSC will activate and accountability will be conducted, if not already done. The EOF may activate as a precautionary measure. Steam Generator "A" and containment radiation levels increase due to the LOCA into the faulted steam generator and from there into containment.

Due to exposure to elevated containment temperatures and pressures, IICV-746B begins to leak by it's shut seat. Containment atmosphere, driven by the ~20 psig containment pressure, i begins to leak to the environment via the exhaust stack RM-060, -061, and -062 (stack effluent monitors) begin to show an increase. In the event that the SS or Site Director did not previously evaluate the failure to meet the containment critical safety status function check as a threat to the containment boundary, based on this evidence of containment leakage, SS or Site Director

.may reclassify the event per EPIP OSC 1, EAL 1.16; " Loss of Two Fission Product Barriers" and may declare a SITE AREA EMERGENCY, if the S AE was not already declared. Operators enter AOP-08, secure Auxiliary Building ventilation supply fans, shut ventilation dampers, and secure one exhaust fan to determine the location of the leak, Continued elevated stack monitor radiation levels with no evidence of elevated radiation or airborne levels in the Auxiliary Building indicates that the leakage path is probabl.v directly from containment into the stack.

Confirmation of the path will be gained by slightly elevated rad 4 tion levels on contact with the containment pressure reduction piping, flow noise, and flow in that pipe indicated on the locally read "annubar" flow indicator. Dose rates at the site boundary increase to a maximum of 0.7 mR/hr over 60 minutes. Operators keep trying to restore containment spray, and continue efforts to cool down the RCS to remove the driving head for the LOCA.

When the HCV-344 operator is opened up, the broken linkage which has prevented valve operation can be cleared. The valve is ready to open with the handwheel. One train of containment spray is restored. Containment spray is started and containment pressure -is reduced, reducing the radiological release rate. The release stops with containment pressure under control and the exercise is subsequently terminated.

omsmucistsemuows 2-5 REV. 8/12/92 l

o -

i l

SCENARIO EVENTS

(

- TIMELINE ,

The Timeline for scenario events follows, This timeline indicates precise times only for those ,

events which occur under the direct control of the exercise controller organization. The times indicated for responses by participants are utimated and allow for " free play" in their emergency response.

Included at the end of the timeline is a summary of potential emergency action levels met by the scenario events and estimated times for t. heir declaration. Also included is a chart summarizing vital equipment lest during the various failures presented by the scenario. Only vital equipment for core ar.d containment cooling are included in this chart.

A list of abbreviations follows the timeline.

N oa6ouuricisnscrMAklO.WP5 26 REV. 8/12/92

SCENARIO EVENTS

(

TIMELINE (Cont) lime T+

0730 -0030 Initial conditions discussed, simulator board walkdowns initiated.

Initial Conditions:

The plant is operating at 100% power for the last 47 days. Xenon is at equilibrium. The grid is in a high-demand low reserve sittuion. The system will not have additional capacity available for at least four more hours (~ 1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months ), A Containment Pressure Reduction (CpR) is in progress per OI VA 1. All control systems are operating normally in abtomatic. One new fuel shipment was received yesterday. Another is scheduled to be received this morning. A radioactive waste shipment is being prepared for transfer.

The following plant equipment is out of service or under maintenance:

As a result of an NRC bulletin on experienced incidents of sudden failure

( of components in the operators of seldom-operated Fisher Controls Class 1 300 type U and UR valves, the containment spray isolation valves (liCV-344 and -345) are to undergo visual inspection and verification of operation. -

Since the problem has produced valve operation failure in other plants, Commission direction and approval has been issued for performance of the inspection and verification at power. Fort Calhoun Station's Plant Review Committee (PRC) has approved this inspection at p]wer. HCV-345 was tagged-out for this inspection at midnight, placing the Unit currently 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months into the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO in accordance with Technical Specifications, Item #2.4.(1).b. The operator of HCV-345 hr.s been disassembled and is undergoing inspection, inspection of the valve internals is in progress,. The inspection and reassembly process is expected to be completed in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and the testing is anticipated to require an additional 6 nours.

VA-3A and -3B containment ventilation fans are running. Control room staff has been tracking an unexplained reduction in fan motos current from 132 to 128 amps over the mid-watch, it is suspected to be a result of the adjustable pitch blades on those fans slipping due to vibration, ovosmrnctsusemARIO WP5 2-7 REV. 8/12/92

, 1 SCENARIO EVENTS IIMEL11E (Cont) {

Ilme T+-

The following plant surveillances are scheduled for today:

Main Turbine local vibration test, per request of a visiting GE Turbine Representative.

The #1 Emergency Diesel Generator was scheduled to be placed 4 out of service for inspection of it's air start system. This PMO has been deferred until completion of the inspections on IICV 345 and IICV-344.

0804 OGJ4 A main turbine high vibration trip occurs due to inadvertent impact on the vibration sensors by a machinist accidently dropping some testing equipment. Immediately after the trip, the resulting system pressure spike causes the sudden gross failure of one main steam header of S/G " A" inside containment. The break results in a large release of steam to the

( containment and the triggering of the SIAS, CIAS, MSIS and CSAS enginected safeguaid signals. At this point, several simultaneous events will occur: ,

Upon the CSAS, liCV-344 indicates open, but containment spray header flow will remain at zero.

Upon the CIAS,11CV-746A fails to shut.

Fans VA-7C and 7D start and immediately trip, and VA 3A and 3D fan blades slip to the zero position. Air flow to the containment air coolers is zero.

Due to the rapid pressure and temperature transient of the trip and steam generator failure, the leaking fuel pin is further damaged.

Approximately 0.4 % clad gap inventory is released into the coolant.

Containment radiation levels begin te increase.

Containment pressure rises as the- steam generator steams down into containment without the suppression effect of containment spray or fans.

Operators identify the faulted generator based on loss of level and pressure.

Operators focus on rising containment' pressure and may attempt to ownerxracur.sconAnto.wes 2-8 REV. 8/12/92

SCENARIO EVENTS

, TIMELINE (Cent)

Jig T+

accelerate the restorr.iion of "A" Train containm:nt spray. Chemistry should be directed to start setup for a post trip RCS ample (2 to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months post trip).

0E05 000$ Containment pressure reaches a maximum value of approximately 34 psig.

Containment temperature reaches a maximum of 230*F. The Shift Supervisor shodd declare c /4 USUAL EVENT per EPIP OSC 1, EAL 2.1; " Uncontrolled S/G IIca' btraction" based on information in EOP-01, Figure 51 " Break Identification Chan" The SS may chnose to activate the Emergency Response Organization (optional at NOUE). As the steam generator energy is expended, containment pressu e steadies out at ~21 psig (saturation pressure) and begins to decrease very slowly. Heat and pressure inside containment preclude investirAtion of the failed open inboard purge valve. Maintenance (or an OSC team, if activated) investigates the failed shut containment spray valve, but it cannot be opened with the handwhccl. The valve operator appears open, but the handwheel 7' can be turned only about one turn in the "open" direction from it's neutral position. SS will probably request maintenance team working on HCV-345 to expedite repairs or to shift over to HCV 344. The only valid success path is restoration of containment spray via HCV-344. HCV-345 tagout inside containment cannot be cleared, nor can any of the containment fans be restored. OSC/ Maintenance personnel will likely be directed to remove all or part of the remote air operator from HCV 344 in an effort to free the valve for operation. The primary concern: restoration of some mode of containment cooling. Control room operators should throttle Si flow when pressurizer level is greater than 45% to maintain pressurizer level approximately 50 %, and use "B" S/G and the MS 292 steam dump to the condenser to control RCS temperature. "A" S/G will boil dry. At some point during this evolution, operators will also likely secure the running containment spray pumps. Containment pressure is not within the normal criteria for securing the pumps, but with no spray now and inadequate recirculation flow, the control room is expected to secure the pumps to prevent damage and ensure their availability when a spray flow path is available.

0820 0020 When operators reach E0P-00 step 15, they will evaluate containment conditions, Elevated containment pressure with no spray flow places them amaracisnsetmouo.wn 2-9 REY. 8/12/92

3

. s SCENARIO EVENTS IIMELINE (Cont)

Iime T+

in the EOP-00 d; agnostic section, which directs them into EOP-05. In '

EOP-05, the $Ta will perform a critical safety function status check. The STA should notify the SS that containment integrity critical safety function is not met due to high pressure in the containment. This will direct operators into EOP 20, Functional Recovery Procedures. Since entry into EOP-20 is indicative of a substantial degradation of plant safety, the SS may declare nn ALERT, per EPIP OSC-1, EAL 11.9; " Events in progress which indicate an actual or potential substar,tlal degradation in the level of sdct; of the plant" If notifications for the NOUE are not yet complete, the SS may abort the NOUE and declare the ALERT instead. If the ALERT is declared TSC and OSC will activate and assembly and accountability will be conducted.

0835 _0035 Several tubes in S/G "A", weakened by the trip and subsequent transients, fail, resulting in a primary to secondary leak of approximately 75 gpm to the faulted S/G. The rate of Containment pressure drop decreases slightly.

Operators determine that the leak rate exceeds 40E pm. Radiation levels begin to increase in the fr.ulted steam generator and inside conti.mment.

0840 0040 Letdown is re-isolated (if re.,tored after the trip).

0842 0042 With pressurizer level continuing to lower and with letdown isolated, operators use charging pumps and HPSI as required per E0P-03 to recover and maintain pressurizer level. Three charging pumps and no HPSI Dow, or fewer charging pumps with some HPSI Dow will be sufficient to maintain level.

0905 0105 Given these indications of a small break LOCA, and the threat to the containment implied by the failore to meet the containment critical safety function check, the SS or Site Director (if the TSC is activated) should

. reclassify the event per EPIP-OSC 1, EAL 1.16; " Loss of Two Fission Product Barriers" and declare a SITE AREA EMERGENCY. In the event that the SS did not previously evaluate the failure to meet the containnant critical safety status function check as a threat to die containment boundary, the SS would then evaluate the current situation as a failure of the RCS boundary only, reclassify the event per EPIP-OSC-1, EAL 1.5; "RCS Leak Rate >40 gpm" and declare an ALERT. TSC and OSC will activate and l assembly and accountability will be conducted, if not already done, The i

l omsorxtscisnsenwuo.wes 2 - 10 REV. 8/12/92

~,

m -

SCEAARIO EVENTS L ELINE (Cont)

Tjmg T+

EOF may activate as a precaution.try measure. Steam Generator "A" and containment radiation levels increase due to the LOCA into the faulted stearn generator and from there into containment. Containment radiation levels continue to increase due to the LOCA into the faulted steam generator and into containment.

0945 0145 Due to exposure to elevated containment temperatures and pressures, HCV.

746B begins to leak by it's shut seat. Containment atmosphere, driven by the ~20 psid containment pressure, begins to leak to the environment via the exhaust stack. RM 060, -061, and -062 increase. TSC/OSC may attempt to shut VA 262, downstream isolation for HCV-746B. If they try, the valve operates stiffly, and will not go fully shut. OSC/ maintenance personnel in the Auxiliary Building may hear the flow noise from the leak and report it to the Control Room.

, 1015 0215 in the event that the SS or Site Director did not prewoosly evaluate the failure to meet the containment critical safety status function check as a thr at to the containment boundary, Site Director'(or Emergency Director, if EOF has already act ivated) may reclassify the event per EPIP OSC 1, EAL 1.16; " Loss of Two F' .::nn Product Barriers" and may declare a SITE AREA EMERGENCY, :f r )t airndy done. Operators keep trying to restore containment spray, and continue efforts to cool down the RCS to remove the driving head for the LOCA. The EOF will activate if not already done.

1115 0315 OSC teams have removed the cover from the actuator of HCV 344 and have cleared the broken linkage that had prevented manual operation of the valve. HCV-344 is ready to open. Operators open HCV 344 manually and start at least one containment spray pump.

1200 0400 Containment pressure is eventually reduced to 3 psig or lese. Containment spray is operated intermittently to cool the containment and keep the pressure at or below 3 psig. Secure from the exercise, ovosaxutcansemuuo.wr5 2-11 REY. 8/13/92

SCENARIO EVENTS VIT AL (OU6PMitif AVAIL ABILITY ST ATU55 Vif A& EQdredtN1 earyghtomy tAf AA gotamgNT UN Ay Ast.A$L3 t'Ju+Vla tv f-t M % * ' ION l'M @ 0130 8 A a+1 ft ( f n Mll'O*t 9 1196 LMtmotNCY Chtatt GtNE8 tat 0R CHAROFNQ PVWPill a+H Patssutt SAf tty rN;tCttON POMPell lHP$ll L OW PAtttsikt SAf tty *N>tCt:0N Puwetti lLPsis cDNT AievutNT 6phAv dCV 346 As to as 3A, .38, 3C We to 'dh 39 30 terwe mornerwwe pee t*e HCV See not esW HCV $44 e eWedi aimJetell NMC WetiN con 1 AmutNt Am Coopho f AN:si <A3Aewas v,mto cetteete Wese Petah

'ess eet va ? A ew 78 ida le egetheei e gJggi con T A:NMtNT Hvt.noctN ANAtvrtm!si

'..ONT AMIN ATED Ant A ViestitAvioN P Ahisi A BBntvi A TiONS A1M ATMOSHERI GF9A CAL 10NS MR MINUTt RCS FEACTOR COOLANT be.?!M AVA. AuxluARY K V' ItiL OVOLT RVtMS FEACTOR Vt6SEL LEVEL DLDO- BUILDING Lt t A: LOCAL LAW (NFORCEMf NT MONIT08tsNG $Y$fiM Cil: CORT (KIT THtHMOCOUKt AGt hCY RX: REACTOR CR CONTROL ROOM LOCA. LO55 OF COOLANT ACCIDENT LLAS: f.AFETY INJLCTION ACTUATION CTMT: CONT AINML N1 USI LOW Nd 55Utt 6AfiTY INJECTKW SAGNAL (CC6- (WRGENCY COff COUuNO 005 OUT OF SERVICE &lf: LAf TTY INJECTION TAMS letAl SY$I(M OSC: OPLRATlONS SUPPORT CtNTtR If4NSF R. TRANSF ORMI R (DA. (Mt ROINCY DsW.L GENERATOR PA$$: POST ACCIDENT SAWbHQ $YlttM 16C f tCHN6 CAL SufPORT CthTtR

[RF CS (WRGENCY Rt6PON5! PRC $$. M48&Uff TUR TVittWNE EACiUTY COWVT[R SYSTIM RAD RADIOLOO? CAL V: YOLT t 07:. (MERGCNCY OPtRAflON5 FACIUTV RCP: RfACTOR COOLANT KMP a q60pxxacisessetnAnto.wn 2 12 REV. 8/12/92

~

l I

I SCENARIO EVENTS 1

h1 ASTER EVENTS

SUMMARY

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

I I

The summary consists of a description of all scenario messages that will be issued to drive simulated events and includes anticipated emergency responses by participants.

Times indicated with a "+" are floating messages that will be issued on or after the indicated time. Times thtt floating messages are issued are dependent on completion of specific responses !

l or actions of participants.

Messages with a "C" following the message number are contingency messages that will only be issued upon meeting the conditions listed in the controller note of the message.

Messages with a "S" l'ollowing the message number are simulator contingency messages that will only be issued in the event the simulator is not available (e.g., simulator computer failure which cannot be corrected in a timely manner).

Key abbreviations used in the master events summary are as follows:

AD Autihry Operstor OOS Out of $vrvka AC Alllead Facility Controllers OSC Operations Support Center CCP Coolant Charging Purry PZR Preamirtxer CEA Control Eternent Assembly ACP Reactor Coolant Pump CEDM Control Element Drise Mechanism RCS Raactor Coolant Sys/ mi CIAS Containment isolauon Actuation Signal RMS Radiation Monitorir.g s> stem CND$ Condensets RPS Reactor Protettive System CO Control Room Operator RWO Rad Wests Operator DO Diewi Generator $1A$ safety trQsstion Actuation Signal ED Emergency Director 50t_ Steam Generator Number (il = ' A'. #2 = *B')

EOF Emergency opustior.s Facility $$ $hift Supervisor KP Xey Players SD site Director g1PS Low /High Presuure safety 1suestion RT Repair Team ovosumCistatsTREvsT.wP5 2 - 13 Rev. 08/12/92

SCENARIO EVESTS M ASTER EVENTS SUM \1 ARY (Omt) .

TIME M SG. FROM TO EVENT / MESSAGE SUMM ARY ANTICIPATED EMERGENCY RESPONSE CM CONTROLLER NOTES WO.

0730 1 AC KP INITIAL CONDITIONS CONTROL ROOM The Plant is operstmg at 100% power for the law Key Players and operators review Plan of the Day inue the nuttal condetams and 47 days. Xenon is at equihhnurn. The grid is m and Shsft Turnover leg. drill plan of the day han&mt a high-demand low reserve situatxm. The system dunng the p evious day to will not have additional capacity available for at Key Players.

least four more hours ( ~ 1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months ). A Issue the Shift Turnover Irg Containment Pressure Reduction (CPR) is in to Control Rami Operators at progress. All control systems are operating 0730.

normally in automatic NOTE: Additional plant Ecuipment out of service nr under maintenance: + .r - n: will be added to the instzal conditwms to Containment Spny containment iwlation valves preclade

prompting" of the (HCV-344 and -345) are to iteergo visual key scenano events.

inspection and verifiestion of operation. HCV-345 was taggede for this inspection at midnight, placmg the Unit currently 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months into the 24 htmr LCO. The opentor of HCV-345 bas been disassembled and is undergoing inspection.

Inspect;on of the valve intemis is in progsss.

The insta1 ion and reasserrbly pn=:ess is expected to be completed in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and the testmg is anticipated to require an addithmal 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l Operators have two tracking VA-3A/B fan uxdor current. Motor current ' for t= 4h fans has decreased funn 132 am;w to 125 am;w over the GWWEXERCtSEMSTREVNT WP5 2 - 14 Rev. 0S/12192

~-- - +

l SCENARIO EVENTS MASTER EVENTS

SUMMARY

(Cont) . ;

I TIME MSG. FROM TO EVENT / MESSAGE

SUMMARY

ANTICIPATED EMERGENCY RESPONSE CM CONTROLLER NOTES NO.

0730- I mid shift.

. C ont. Cont.

Surveillances schaluted for this shift:

Main Turbine vibration testing.

+ EDGF1 air start system inspection (deferred until con:pletion of HCV-344/-345).

Limitine Conditions for Operatirm

IICV-345, LCO Sectmn F2.4.(1).h 24 lir.

Radiation Work Permi'is:

None.

Maintmance Work Orders iMWO):

hCV-345 Inspection HCV-344 Inspection (following IICV-345)

G:%CM EXERCISGMSTREVNT,WPs 2 - 15 Rev. 08/12/92 w., , -

c+ _ .

SCENARIO EVENTS MASTER EVENTS SUMM Ak( (Omt)

TIM E MSG. FROM TO EVENT / MESSAGE SUMM ARY ANTICIPATED EMERGENCY RESPONSE CM CONTROLLER NOTES N O.

I i

0800 2 CR SS/ Exmise activities are starting. CO_NTROL ROOVs Ensure Contro: Room lead CO Be aware of plant omditums. pervenel have receivest and understand the initia!

canditums.

OSM 3 CR SS *This is hihn D r-hota. Machmists will be CONTROL FOOM This sets up cause for turNne Lead conducting local vibrati<m tesiing on the mam Be aware of plant omditi<ms. trip at ' R(M.

turbine this moming as per request from the GE turbine rep. They are starting to haul their equipment out to the torbine dak. Tley will call l

before startmg work. The paperwo k for this was completed on the mid shift."

0804 4S CR SS/ ANNUNCI ATORS IN CONTROL ROOM CONTROL ROOM Deliver <mly if proper lead CO Reactor Tnp Take immediate actions per EOP4'O, inp all indicekm is n<w available Turbme inp RCPs, transitum to EOP45 Unamtrolled IIcat Lom the simulator.

Generator trip Extraction." Indicathms cf reactor arid SGet Nar Range level ili turbme top mam steam In SG#1 Press leu SS contact Operations Maintenance Liaisin for failure inside amtamment.

DG Start Signal A Act infi rmatum on turbme inp. Turhne tnp was cauwd by DG Start Signal B Act machinists inadvertently thgh Containment Pressure SS direct Aux. Buildmg operator investigste impacting vibratum senwr.

iiigh Omt Sump level amtamment spray valve IICV-344, omtainment 12C (0834) Ensure NOUE is liigh Coni Temp iwism valve IICV-746A and cimtminment '-c'ered.

o warrarncr.rwisTvrVNT WPs 2 - Ifi Rev. 09/12/92

d SCENARIO EVENTS 31 ASTER EVENTS

SUMMARY

(Cont) .

TIME MSG. FROM TO EVENT / MESSAGE SUMM ARY ANTICl"ATED EMERGENCY RESPONSE CM CONTROLLER NOTES 50.

08G1 4S ANNUNCIATORS IN CONTROI ROOM cmling fans VA-7CID.

Cmt. Cont. SIAS CIAS SS declare a NOUE per FPIP-OSC-1, 2.1 MSIS "UncmtroIIed Steam Generator Heat Extracthm.-

VIAS TSC/OSC activation i; optnmal.

CSAS SS may direct AO to shut UCV-746A manual INDICATTONS IN CONTROL ROOM downstream isolation VA-262.

Containment pressure indsates 20 gnig aM rising.

Cont Temp indicates 220'F and rising Steam generator *B* level and pressure on pping rapidly '

All CEAs inserted.

ilCV-344 indicates open IICV-740A indicates open.

VA-7C/D indicate tripped.

Containment Spray Hender hw ialsta^es O.

l o%oserStictscMsTREVST.e 2 - 17 Rev. 08/12/92

SCENARIO EVENTS MASTER EVENTS

SUMMARY

(Cont) ,

TihlE MSG. FROM TO EVENT / MESSAGE SUMM ARY ANTICIPATED EMERGENCY RESPONSE CM CONTROLLER NOTES NO. -

0810 5 CR CR *This is John Drahota. A machinist working on CONTROL ROOM This explains cause for lead SS the local vibration testing on the main turbine Be aware of plant conditions. turbine inp.

impacted the vibration sensor, apparently causing a turbine high vibration trip.*

0810 + 6 OSC A O at IICV-344 Remote Operator appears to be open. AUX. BUILDING Deliver this message when Cont. 11C V- AO report indication to SS. AO reaches the valve.

344 On attempt to manually open llCV-344, the CONTROL If OM handwheel tums about I tern in the "open" SS will probably request maintenance team Cause is broAc rnnote disc. tion, from the neutrul position and then will working on llCV-345 to expedite repairs or to operator linkage jammaf in tum no more. shift over to llCV-344. sufw linlage bonner.

No external indications of fault. Maintenance personnel also cannot open valve manually.

0810 + 7 OSC A O at Upon investigation of VA-/C containment cooling AUX. BUILDING Deliver this message when Cont. VA- fr.n breaker, you find the breaker tripped free. AO report indication to SS. AO reaches the bre=Ners.-

7C/D Upon investigation of VA-7D containment cooling CONTROL ROOM Breakers will reset but trip as Bkr fan breaker, you find *be breaker tripped free. SS notify electiical maintenance to investigate or awm as fans are started. No repair. external indications of fault.

4WC4 EXERCISE 4tSTREVFfLWPs 2 - 18 Rev. 08/12/92 I

SCENARIO EVENTS MASTER EVENTS

SUMMARY

(Cont) .

TIME MSG. FROM TO FVENT / MESSAGE SUMM ARY ANTICIPATED EMERGENCY RESPONSE CM CONTROLLER NOTF' NO.

0820 + 8 OSC Elect. VA-7C and 7D Breakers are tripped. AUX. BUILDING Deliver this message when RT Cont. M sint/ Pop out target for OIL on RMS-9 trip unit are out, RT Inform OSC, OSC inform TSC. reaches the breakers. Isral RTat if checked. inspection reveals no external VA- Breakers and targets will reset, but will trip when (Electrical Maintenance team inform SS). indicaism of fault.

7C/D fans are startal. Megger readings on cables Bkr. No other abnormal extemal indications. and nxors 10,000 0 Fan pour supply cables are grounded out by high containment heat and humidity.

0820 + 9 OSC Mech, Valve ren>te operator indicates open. AUX. BUILDING Deliver when RT reaches the Cont. Maint/ RT report indication to OSC. Maint. report to valve.

RT. at On attempt to manually epen HCV-344, the SS.

H C V- handwheel turns about I tum in the open direction TECIINICAL SUPPORT CENTER Normally, you should be able ,

344 from its neutral position, then contacts the shaft TSC/OSC prionty: opening IICV-344. TSC to turn handwheel ~50 tums.

extending from the actuator inside the h<mnet and recognf2e that the handwheel shaft extending from will tum no more. the actuating lever inside the bcanet should have retracted into the kmnet when the valve openal SS will probably expedite the fact that it did rxd indicates the valve is still inspection by using peramnel shut. Since the actuator indicates open, the fault from HCV-345 inspection.

may be there. Plan to open the kmnet cover / remove operator and operate the valve Linkoge to ball stem frrme manually. remote operator has broken and is jammed inside casing.

f I awccEXERCtSE\MSTREVNT.wr4 2 - 19 Rev. 08/12192

.a

SCENAPIO EVENTS M ASTER EVENTS SUMM ARY (Cont) l TIME MSG. FROM TO EVENT / ME". SAGE SUMM ARY ANTICIPATED EMERGENCY RESPONSE CM CONTROLLER NOTES

. NO.

i 0820 + 10 OSC Elect. VA-3A and 3B breakers are closed. Be aware of plant conditions. Deliver if maintenance Cemt. Maint/ incpects operation of V A-RT at to the Control Room: 3A/B.

VA- Fan rnotor current indicates 120 Amps.

3A/B Megger rendir.gs on cables and rnotors 2,000 MD Adjustable-pit <h fan blades haw slipped to 0*, fans are pwnping no airflow petn the containment awirrs.

0820 + 11 OSC A O at On attempting to close VA-262, valve operates AUX. BUILDING Deliver if CR Shift Supervian Cont. VA- stiffly. The valve handle rotates 4 times in the Be aware of plant conditions. sends operator or repair team 262 shut direction, then will not tum any farther in the TEC11NICAL SUPPORT CENTER to shut VA-262. Valve stem open or shut direction. Evaluate methods to shut VA-262. is slightly bent, and operates stiffly.

SS may elect to shut VA-262 to hack up IICV-746B, since llCV-746A is failed open.

a wm4sExrRCISEiMSTREVffr.WP5 2 - 20 Rev. 0R/12/92

a SCENARIO EVENTS b_f ASTER EVENTS

SUMMARY

(Cont) .

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

0834 12C CR SS Declare an UNUSUAL EVENT per ErlP-OSC-1, CONTROL ROOM fxtiver this message only as lead EAL 2.1; " Uncontrolled Steam Generator lieat Declare a NOUE. directed ' by the Exercise Extrac* ion

based on EOP-05, Figure 5.1

Break Make appropriate notifications. Senior Controller, if the g Identification Chart". NOUE (or ALERT. as SS may elt- t instead to declare an ALERT based described under anticipated on EPIP-OSC-1, EAL i1.9: " Events in progress actions) has not yet been which indicate an actual or potential substantial declared.

degradation of the level of safety of the plant."

0835 13S CR SSI ANNUNCIATORS IN CONTROL ROOM CONTROL ROOM Deliver this message only if lead CO RMS Alarm Isolate letdown if restored after trip. Use proper indicathm is 'not charging pumps and IIPSI as required per EO- available from the Simulator.

INDICATIONS IN CONTROL ROOM to restore / control PZR le el. Start of tule leak in SG#1 s RMS monitor data as per Section 5 Analyze magnitude of leak rate. indicated by lowering PZR PZR Pressure indicates 1330 psig and lowering. level, and increasing PZR level indicates 93.4 and lowering. containment rad levels.

0845 14S CR CO INDICATIONS IN CONTROL ROOM CONTROL ROOM Deliver this message only if lead Cll-1B is running Declare an ALERT per EPIP-OSC-1. EAL 1.5: preper indication is n<w CII-lC is running "RCS Leak rate >40 Epm. available from the simulator.

IIPSI-2A is running Perform plant evacuation, assembly and ilPSI Ileader flow indicates 185 gpm. accountability. So kientinformarkm forleak Pressurizer level indicates 84% and steady. TECIINICAL SUPPORT CENTER rate determinatkm in excess of Charging Ileader Flow indicates 80 gpm. Activate, if not already d<me. 40 gpm.

GWXWEXERCISE\MSTREVNT.WM 2-21 Rev. 08/12/92

SCENARIO EVENTS MASTER EVENTS

SUMMARY

(Cont) ,

r TIME MSG. FROM TU EVENT / MESSAGE SUMM ARY ANTICIPATED EMERGENCY RESPONSE CM CONTROLLER NOTES NO.

0845 14S OPERATIONS SUPPORT CENTER 15C (0915) to ensure ALERT is Cont. Cont. Activate, if not already d<me. declared 0850 Operators stabilize pressurizer level using charging Playe:cs have sufficient pumps and ilPSI as required. Increasing radiation information to diagnose RCS levels in the faulted Steam Generator and inside leak rate greater than 40 gpm.

containment point to the location of the leak. 'Ihey may not identify . the There is no indicati<m of a release to the kration as the faulted Steam environment. Operators may consider sampling Generator. The critical factor the containment atmosphere. to recognize is that the leak is to containment. They sixmid be able to classify the eve it as an ALERT (or SAE, if the i I containment barrier was already declared challenged).

Players should by now have identified the most pn>bable '

success path as restoration of containment spray via IICV-344. Even if IICV-345 were opened, downstream tags inside containment cannot be cleared. Fans VA-3AIB cannot be reached, ' nor can VA-7C/D cables be replaced while containment is at awar_xrJtCESE\MSTR EVNT.WP5 2 - 22 Rev. 08/12/92

. i e

s SCENARIO EVENTS MASTER EVENTS

SUMMARY

(Cont) .

TIM E MSG. FROM TO EVENT / MESSAGE SUMM ARY ANTICIPATED EMERGENCY RESPONSE CM CONTROLLER NOTES NO.

elevated pressures and temperatures. Available means of opening IICV-344 is removal of bonnet cover to free the broken lever arm. -

This will allow the valve to be manually (W l

0915 15C CR SS Declare an ALERT per EPIP/V'C-1, EAL 1.5; CONTROL ROOM Deliver this nwssage only if Lead "RCS Leak Rate > 40 rpm." Declare the ALERT. directed by the Exercise TECilNICAL SUPPORT CENTER Senior Controller, if the Activate if not s'xady done. ALERT has not been declared OPERATIONS SUPPORT CENTER at this time.

Activate if not already done. If SS declared ALERT based EMERGENCY OPERATIONS FACILITY on thrent to Containment FP Precautionary activation of the EOF is optional. barrier (failure to meet containment - CSF status check)c LOCA meets second barrier criteria, and SS may -

now declare SAE per EPIP-OSC-1. EAL 1.16; *Iess of Two Fission Prmluct Barriers" c womEXERCISEntSTREVNT.Wrs

. 2 - 23 Rev. 08/12/92

SCENARIO EVENTS MASTER EVENTS

SUMMARY

(Cont) .

TIME MSG. FROM TO EVENT / MESSAGE

SUMMARY

ANTICIPATED EMERGENCY RESPONSE CM CONTROLLER. NOTES .

NO.

G945 16S CR SS/ ANNUNCIATORS IN CONTROL ROOM CONTROL ROOM Deliver this message tmly if Lead CO RMS Alarms CR informs TSC. proper ' indication is not ,

Isolate Aux. Bldg. ventilation per AOP-08. available from the simulator.

INDICATIONS IN CONTROL ROOM TECHNICAL SUPPORT CENTER Indications of leakage past RM-060 indicates as read in Section 5. TSC directs OSC to send a team to investigate. IICV-746B RM-061 indicates as read in Section 5. Site Director declares a SAE.

RM-062 indicates as read in Section 5. SiterTSC Directors / Engineers, evaluate leakage 18C (1015) Ensure SAE is path. declared AUX. BUILDING Attempt to shut VA-262, if not already tried. _

RADIATION MONITORING TEAM Conduct surveys as directed to omfirm the release.

0945 + 17 OSC RT You hear a high pitched whistling noise, like the AUX. BUILDING Deliver this message to any -

Cont. near flow of air or liquid under pressure. It seems to RT inform OSC. repair teams in the vicinity of 11CV- be getting louder. IICV-746B. .

746B Flow in the pipe indicates valve seal breakdown.

For teams in the area, obtain local area radiation levels from Section 5 " Radiation Monitor Data Summaries" 18C (1015) Ensure SAE is declarai a:wmcEXERCISEWISTREVNT.WP5 2 - 24 Rev. 08/12/92

ci+%

SCENARIO EVENTS MASTER EVENTS

SUMMARY

(Cont) .

TihsE MSG. FROM TO EVENT / MESSAGE

SUMMARY

ANTICIPAND EMERGENCY RESPONSE CM CONTROLLER NOTES NO.

101S 18C TSC SD Declare a SITE AREA EMERGENCY per EPIP- TECIINICAL SUPPORT CENTER Deliver this message only if Irad OSC-1 EAL 1.16; less of Two Fission Prrx!uct Site Director declare the SA8. directed by the exercise senior Barriers." EMERGENCY OPERATIONS FACILITY controller,if the SAE has not Activate the EOF if not already done. been declared at this time.

II10 19 OSC RT at ne bonnet cover has been removed fmm the Inform OSC. Broken piece of rtxl end Cont. IIC V - remote operator of IICV-344. Remove cap screw and hex nut from actuating bearing assembly has 344 He rod end bearing assembly which connects the lever, remove rod end bearing assem'4y to free prevented the manual operator remote operator to the actuating lever on the drive manual operator. from opening the valve.

shaft has broken inside the bonnet and is jammed TSC/CR Coordinate to restore containment spray.

against the bonnet casing.

1115 + 20S CR SS/ INDICATIONS IN CONTROL ROOM Lead CO One containment spray pump is running Containment Spray Flow indicates 2400 gpm.

Containment Pressure indicates 16 psig and d opping.

Containment Temp. indicates 190*F and dropping.

1200 21 AC KP All Exercise activities are terminated. Please Deliver this message only prepare for facility critiques. Participant critique when directed by tne Exerciw forms are being passed out for you to complete. Senior Controller.

Please collect all paperwork and logs generated during the exercise and tum them over to your O WMOEXERCISEWSTREvrfr.WP5 ,2 - 25 Rev. 08/12/92

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SCENARIO EVENTS MECilANICAL FAULT AND REPAIR

SUMMARY

Equipment Mfg 3Model Failure Time / Event Indication Faikire Mode Gnnsp Restoration llCV-344 Fishes Controls Type . Initial conditions: Tagged out Tagged out, dis- Tagged out, dis- Mech. NA. Even if the splveis re-Containment spray V Vec-Ball valve for inspection assembled assembled - mud 4cd, the tagout inside isolation valve containment cannot be cleared, so no flow through the vahr is possible.

IICV-345 Fisher Controls Type Fails shut on CSAS Vaht is shut. Shut. Air operator Mech. Remme air operator or Containment spray V Vee-Ball valve - Ilandwheel will not linkage failed bor net cover. Remove lower isolation valve turn more than Iturn inside bonnet, vaht portion of rod end bearing -

in either direction. manual operator assembly to free manual Vahe air operator jammed. operator. -:

indicates open. 3 lirs to Min.

VA-3A/B Fan blades slip to 0* position . Lowering fan motor . Fan blades at 0* Elect. NA. Electricians may Containment current. Current falls position, fans troubleshoot based on low ventilation fans to minimum after running. Fan motor current, but no trip. motor current 120 electrical fault will be found.

Amps. Air flow through coolers is essentially zero.

Main Turbine 01t04 ' Trips, causing reactor inadstrtent NA NA trip. agitation of turbine vibration sensor.

Main Steam ficader 08.04:10 licader supture inside Doubles:nded NA NA.

No. I containment,- header rupture indicated by inside containment.

containment pressure Approximately 75

- 34 psig, temp 230'F. gpm S/G Tube !. ak

1 S/G level drops - starts at 0835.

rapidly to 0%

4 5 GM08AEXERCIsf4fATRtxxts 2-27 '8/13/92 g

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SCENARIO EVENTS -

a MECIIANICAL FAULT AND REPAIR

SUMMARY

q Equipment Mfg 3Model Failure Time /Esent Indication Failure Mode Group Resecration l RCS / Steam - 08:35- Lowering pressurizer Tube leakage NA NA ,

Generator #I leveland RCS approximately 75 pressure from.. gem.

previously stable conditions.

Containment radiation levels

. nerease.

IICV-746A Fisher Controls, Design Fails open on CIAS Valve indicates open. Mechanical NA NA Containment pressure *A*, Double disk, One vaht indicated . binding. Carmot be 4

reduction inboard . double seat rising stem as not in CIAS corrected from isolation air operated globe valve position; outside the -

pressurized containment.

VA-7C/D Trip aller starting on CIAS. Breakers trip. Reset Power supply cables Elect. NA. Dry cables after Containment - and trip if tried. grounded by steam containment is ,

ventilation fans Megger reading on . inside containment. 4.r-rized.

load side of breakers, 10K ohm.

VA-262, (downstream Dresser 4(ancock type When operated. . Stuck partially open. Corrosion products Mech Attempt to force vahr shut isolation vaht for ' 950 rising stem gate inside vaht body Attemps unsuccessful Stem

, ilCV-7468) vaht, outside stem and cause gate to stick will bend.

yoke. partly open. -

E /ahr leaks by. Mech. ' Izakage is stopp:d only1 c ! ICV-746B - Fisher Controls, Design 09:45 Noise, rising .

p Containment pressure 'A', Double disk, _ radiation areas on Leakage. when containment is reduction outboard double seat rising stem RM-060, -061, -062. determined to be depressurized.:In the isolation air operated globe vahr (also on contact with 2400-2800cc/ min at interim, remost operator and piping). Annubar 60 psig last outage, force stem dowli with flow gage indicates Icakage worsens bearing puller,' l-2 hours.

80scfm. due to eleuted . .

temperateres and pressures. :

owsetxtactsratArarxAu 2-28 8/13/92; 1

SCENARIO MESSAGES TABLE of CONTENTS Eage

TABLE of CONTENTS 3. 1

CONTROLLER MESSAGES - CR/TSC/OSC/ EOF 3. 2 os6084atacistwitssActsws 3-1 8/12/92

SCENARIO EVENTS CONTROLLER MESSAGES - CR/TSC/OSC/ eof Scenario messages are provided under this heading.

Messages are included for the control room simulator (CR), technical support center (TSC),

operations support center (OSC), and the emergency operations center (EOF).

Messages are issued according to scenario time and upon completion of specific emergency responses by participants. Each message heading indicates the participant (s) receiving the message, the origination of the message, and the time frame the message is to be issued.

Message footnotes contain special notes to controllers and expected participant responses to the information contained in the message. Actual messages issued to participants will nel contain the controller notes or expected responses.

Times it.dicated with a "+" are Goating messages that will be issued on or after the indicated time. Times that floating messages are issued are dependent on completion of specific responses or actions of participants.

Messages with a "C" following the message number are contingency messages that will only be issued upon meeting the conditions listed in the controller note of the message.

Messages with a "S" following the message number are contingency messages that will only be issued by specific direction of the exercise senior controller, in the event that the simulator fails during the exercise, and the decision is made to continue the scenario on paper.

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4 SCENARIO MESSAGES:

CONTROLLER MESS AGES - CR/TSC/OSC/ EOF (cont)

[

TO: Key Players NUMBER: 1 P

FROM: Initial' Conditions (All Facility lead TIME: 0730 Controllers ) T-00:30 i

TYPE: Handout Page 1 of 3 DRILL PURPOSE ONLY DO NOT initiate actions affecting normal plant operations.

INITIAL CONDITIONS- .

(See attached exercise plan of the day)

(Simulator participants will also be given operator and shift turnover logs)

(Simulator CR - Telephone 7623 or 7632)

The plant is operating at 100% power for the last 47 days. Xenon is at equilibrium. The grid-. ,

- is in a high-demand low reserve situation. The system will not have additional capacity available for at least four more hours (~ 1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months ). A Containment Pressure Reduction (CPR) is 'in progress per OI-VA-1. All control systems are operating normally.in automatic. One new fuel shipment was received yesterday. Another is scheduled to be received this morning. :A-radioactive waste shipment is being prepared for transfer.

i CONTROLLER NOTFJS:

1. Issue the initial conditions and drill plan of the day handout during the previous day to Key Players.

2. Issue the Shift Turnover Log to Control Room Operators at 0730.-

EXPECTED RESPONSE:

1. Key Players and operators review Plan of the Day and Shift Turnover Log.

O:\6084iEXERCISE%1ESSAGES.WPs - 3 Rev. 8/12/92-

p SCENARIO MESSAGES

. CONTROLLER MESSAGES -'CR/TSC/OSC/ EOF (cont)

TO: Key Players NUMBER: .1 FROM: Initial Conditions (All Facility Lead - TIME: 0730-Controllers ) .T-00:30' TYPE: Handout Page 2 of 3 DRILL PURPOSE ONLY DO NOT initiate actions affecting normal plant operations.

- Key parameters are listed below:

i Reactor Power 100 % :

-RCS Pressure 2110 psia

RCS T, 540 *F Boron Concentration 130 ppm ,

= Pressurizer Level 58.2 .

Steam Generator Levels 65%

Steam Generator Pressures 821 psia All control systems are operating normally in automatic

- The followine olant equipment is out of service or under maintenance:-

As a result of a bulletin on . experienced incidents;of sudden failure of components _ in the-operators of vital air operated valves, the Containment Spray containment isolation valves (HCV-344 and -345) are to ' undergo visual inspection and verification of operation. Since the problem has produced valve operation failure in other plants, Commission direction and approval has . _

been issued for performance of the inspection and verification at power. HCV-345 ws.s tagged-out for this inspection at Midnight, placing the. Unit currently 7. hours into the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO in accordance with Technical Specifications, Item #2.4.(1).b. The operator of HCV-345 has been disassembled and is undergoing inspection. Inspection of the valve internals is in progress. The-inspection and reassembly process is expected to be completed in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and the testing is -

anticipated to require an additional 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

VA-3A and -3B containment ventilation fans are running. Control room staff has'been tracking an unexplained reduction in fan motor current from 132:to 128 amps over the mid watch; Gn608MXERCL5E\ MESSAGES.WP5 3-4 Rev. 8/12/92

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

SCENARIO MESSAGES CONTROLLER MESSAGES - CR/TSC/OSC/ EOF (cont) .

TO: Key Players NUMBER:' 1 FROM: Initial Conditions (All Facility Lead TIME: 0730 Controllers )- T-00:30 TYPE: - Handout Page 3 of 3 DRILL PURPOSE ONLY DO NOT initiate actions affecting normal plant operations-l Surveillances scheduled for this shift:

Main Turbine local vibration test, per request of the GE turbine Representative.

The #1 -Emergency Diesel' Generator was ' scheduled to be placed out of service for

_ inspection of it's air s*. art system. This PMO has been deferred until completion of the inspections on HCV-345 and HCV-344.

Limitine Conditions for Ooeration

HCV-345 tagged out, LCO Section #2.4.(1).b 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Radiation Work Permits: .

.None. s Maintenance Work Orders (MWO):

HCV-345._ Inspection

- HCV-344 Inspection:(following HCV-345) -

- Radiochemical; Daily chemistry report from the mid shift is attached.

u!

, Meteorolocicali

- Clear day with late morning clouds. Temperatures are expected between a low'af 45'F and a high of 80*F. ' Winds are expected to be light from the northwest increasing in to 15_ mph.

' by late morning. A weak cold. front is expected 'to pass through the area in the late morning. .

~

Winds are expected to shift to the southeast. A 30% chance for precipitation is forecast for the late morning. Skies should clear again by mid afternoon.

aa60scEXE.RCISEWESSAGES WP5 3--5 Rev. 8/12/92 p yr- e 4 'svee---

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SCENARIO MESSAGES CONT' TOLLER MESSAGES'- CR/TSC/OSC/ EOF (contF l

- TO: All Control Room Personnel NUMBER:- 2

'FROM: (CR Lead Controller) TIME: 0000 T+00:00 .

TYPE: Handout Page 1 of1 DRILL PURPOSE ONLY DO NOT initiate actions affecting normal plant operations.

Exercise activities are starting.

9 7

4 CONTROLLER NOTES:

1. Ensure Control Room personnel have received and understand the initial conditions.

EXPECTED RESPONSE:

1.Be aware of plant conditions.

GW8f. EXERCISE \ MESSAGES.WP5 3-6 Rev.' 8/12/92 -

- SCENARIO hfESSAGES-CONTROLLER hfESSAGES - CR/TSC/OSC/ EOF (cont)

-TO:- CR Shift Supervisor NUhfBER: - 3

. FROhi: Operations hiaintenance Liaison (CR TIhiE: 0802--

Lead Controller) T+00:02 TYPE: Verbal

- Page 1 of 1 DRILL PURPOSE ONLY DO NOT initiate actions affecting normal plant operations. ,

~

"This is John Drahota. hiachinists will be conducting local vibration testing on the main.

- turbine this morning as per request from the GE turbine rep. They are starting to haul their equipment out to the turbine deck. They will call before starting work. The paperwork for -

this was completed on the mid shift."

4 CONTROLLER NOTES:

1. This sets up cause for turbine trip at 08(M. .

3 EXPECTED RESPONSE:

1. Be aware of plant conditions, ososexonctstwitssaats.wes 3 Rev. 8/12/92 e

y yw=- 1 r v' v- e- a e-w v m>ru-r -r - + -d-f- -W -

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.-.. g-SCENARIO hfESSAGES CONTROLLER h1ESSAGES - CR/TSC/OSC/ EOF (contl TO: Control Room Operators - NUhiBER: 4S FROht: Indication (CR Lead Control!ct) TIhiE: 0804 T+00:04 TYPE: HandoWi Page 1 of 2 -l DRILL PURPOSE ONLY .

DO NOT initiate actions affecting normal plant operations.

ANNUNCIATORS IN CONT; 'L ROOhi ;

Reactor Trip Turbine trip ,

Generator trip SG"A" Nar Range Level Hi SG"A" Press Low DG Start Signal A Act 1

CONTROLLER NOTES:

l. Deliver only if proper indication is not available from the simulator.

2. Indications of reactor and turbine trip, main steam line failure inside containment.

3. Turbine trip was caused by machinists inadvertently impacting vibration sensor.

EXPECTED RESPONSE:

1. Take immediate actions per EOP-00, trip all RCPs, transition to EOP-05 " Uncontrolled Heat Extraction,"

2. SS contact Operations hiaintenance Liaison for information on turbine trip.

3. SS direct Aux. Building operator investigate containment spray valve HCV-344, containment isolation valve HCV-746A and containment cooling fans VA-7C/D.

-4 SS declares a NOUE per EPIP-OSC-1, EAL 2.1; " Uncontrolled Steam Generator ' Heat Extraction." ERO activation is optional.

5. SS direct AO shut HCV-746A manual downstream isolation VA-262.

an6oamERCISEMSSAGE5W5 3-8 Rev. 8/13/92 1

i SCENARIO MESSAGES CONTROLLER MESSAGES - CR/TSC/OSC/ EOF (cont)

TO: Control Room Operators NUMBER: 4S FROM: Indication (CR Lead Controller) TIME: 0804 T+00:04 TYPS: Handout Page 2 of 2 DRILL PURPOSE ONLY D_O NOT initiate actions affecting normal plant operations.

ANNUNCIATORS IN CONTROL ROOM (Cont.)

DG Start Signal B Act High Containment Pressure High Cont Sump Level High Cont Temp SIAS CIAS MSIS VIAS CSAS INDICATIONS IN CONTROL ROOM Containment pressure indicates 20 psig and rising.

Containment temp indicates 220 F and rising Steam Generator "B" level and pressure dropping rapidly All CEAs inserted.

HCV-344 indicates shut HCV-746A indicates open.

VA-7C/D indicate tripped, omsmtaciscurssActs375 3-9 Rev. 8/12/92

SCENARIO MESSAGES CONTROL}J.R MESSAGES - CR/TSC/OSC/ EOF (con 0 TO: CR Shift Supervisor NUMBER: 5 FROM: Operations Maintenance Liaison (CR TIME: 0810 Lead Controller) T+00:10 TYPE: Verbal Page 1 of I DRILL PURPOSE ONLY DO,NOT initiate actions affecting normal plant operations.

"This is John Drahota. A machinist working on the local vibration testing on the main turbine impacted the vibration sensor, which may have caused a turbine high vibration trip."

CONTROLLER NOTES:

1. This explains cause for turbine trip.

EXPECTED RESPONSE:

l 1. Be aware of plant conditions.

ca60strxrscistwir.ssActs.wr5 ' 3 - 10 Rev. 8/12/92

r.

SCENARIO MESSAGES CONTROLLER MESSAGES - CR/TSC/OSC/EQf_(conll TO: Aux. Building AO at HCV-344 NUMBER: 6 FROM: Observation (OSC Controller) TIME: 0810+

T+ 00:10 +

TYPE: Verbal Page 1 of 2 DRILL PURPOSE ONLY D_Q NOT initiate actions affecting normal plant operations.

On attempt to manually open HCV-344, the handwheel turns about I turn in the open direction from its neutral position, and then will turn no more.

CONTROLLER NOTES:

1. Deliver this message when AO reaches the valve.

2, Remote operator linkage has failed inside bonnet Fragment oflinkage still attached to actuator lever has jammed against inside of bonnet. Valve cannot be operated manually until this is cleared.

3. Manual handwheel moves an outer sleeve over a second shaft attached to the opposite end of the same actuator lever. If the valve were actually_open, the handwheel should be able to turn - 50 turns prior to the handwheel shaft contacting the end of the actuator shaft The fact that the wheel will not turn indicates the valve is still shut, despite the-fact that the operator has moved to the open position.

4 Maintenance personnel also cannot open valve manually.

EXPECTED RESIONSE:

1. AO report indication to SS.

2. SS will probably request maintenance team working on HCV-345 to expedite repairs or to shift over to HCV-344 ca60 4tExERCISE' MESSAGES.WP5 3-11 Rev. 8/12/92

- . - - ~ - - . - - - - -. .

g -.. - - ..

G

.. - SCENARIO MESSAGES : '

CONTROLLER MESSAGES - CR/TSC/OSC/ EOF (cont)'

TO: Aux. Building AO at HCV-344 - NUMBER: 6 FROM: Observation (OSC Controller) TIME: 0810+

T+00:10+

TYPE: Verbal $

Page 2 of 2 DRILL PURPOSE ONLY'

_ DO NOT initiate actions affecting r>3rmal plant operations.

Additional Controller Troubleshootine Information - HCV-344 The valve indicates open in the Control Room. Locally, the valve operator appears open,-

since the bellows diaphragm (left) is stretched to near the top of the gage mounted beside it.

The manual handwheel (right) is in the normal neutral position. The ball-lock pin is -

removed. If operators try to turn the handwheel, it will go only about I turn, then stop.- It does not become gradually stiffer, as would be expected if it were binding, it just C_,

will not turn past that point. The handwheel opens the valve by forcing the hard inner - y surface of a sleeve-like outer shaft down onto

~

m the inner shaft, extending from the operating -

l 2-lever. If the valve were actually open, the inner shaft would retract and the handwheel would be free to turn ~ 20 turns, until the outer shaft once again extended to contact the

~)

(.)

inner shaft. The ball lock pin is required only w 'o to manually shut the valve. The pin is inserted p after the manual handwheel is turned all the way'in to align the hole in the retracted inner '

shaft and the outer shaft. The pin locks the two shafts together, and allows the outer shaft to withdraw the inner shaft to_ shut the valve. The pin is not required to manually open the valve, it may be inserted without preventing manual opening. If operators try to insert the

. pin, they will' note that the holes in the' inner and outer shafts are aligned. This is clear-indication that the valve ball is still shut. All.other external indications are normal. . See page 2 of message 19 for internal valve inspection results.

On608AEXEXCISEWESSAGES.WP5 3 - 12 Rev. 8/12/92

e l

L SCENARIO MESSAGES -

CONTROLLER MESS AGES - CR/TSC/OSC/ EOF (cont) '

TO: Aux. Building AO at VA-7C/D Breaker NUMBER: 7:

FROM: Observation (OSC Controller) TIME: 0810+

T+00:10 +

TYPE: Verbal Page 1 of 1 DRILL PURPOSE ONLY DO NOT initiate actions affecting normal plant operations.

Upon-investigation of VA-7C containment cooling fan breaker, you find the breaker tripped free. :

Upon investigation of VA-7D containment cooling fan breaker, you find the breaker tripped free.

No external indications of fault.

CONTROLLER NOTES:

1. . Deliver this message when AO reaches the breakers.

= 2. Breakers will reset but trip as soon as fans are started.

EXPECTED RESPONSE:

.1. L AO ' report indicatio_n to SS.

2. SS notify electrical maintenance to investigate or repair.

4 ca60mExtacistwessActs375 3 - 13 Rev. '8/12/92

-f SCENARIO MESSAGES

t- ' CON'IROLLER MESSAGES - CR/TSC/OSC/ EOF (conti TO: Electrical Maintenance / Repair Team NUMBER: 8 (VA-7C/D Breakers)

FROM: Observation (OSC Comroller) TIME: 0820+

T+ 00:20+

TYPE: Verbal Page1 of1 DRILL PURPOSE ONLY DO NOT initiate actions affecting normal plant operations.

VA-7C/D Breakers are tripped.

No other abnormal external indications.

CONTROLLER NOTES:

1. Deliver this message when RT reaches the breakers.

2. Pop out target for O/L on RMS-9 trip unit are out, if checked (see next page).

3. Breakers and targets will reset, but wil: trip when fans are started.

4 Megger readings on cables and motors 10,000 0 phase-to-ground on all three phases.

5. Fan power supply cables are grounded out by high containment heat and humidity.

EXPECTED RESPONSE:

1. RT Inform OSC, OSC inform TSC.

2. Electrical Maintenance team inform SS.

ca60setxtacistsutssAGES.WP5 3 - 14 Rev. 8/12/92

i i SCENARIO MESSAGES CONTROLLER MESSAGES - CR/TSC/OSC/ EOF (cont) 1 TO: Electrical Maintenance / Repair Team NUMBER: 8 (VA-7C/D Breakers)

FROM: Observation (OSC Controller) TIME: 0820+

T+00:20 +

TYPE: Verbal Page 2 of 2 DRILL PURPOSE ONLY DO NOT initiate actions affecting normal plant operations.

Additional Troubleshootine Information - VA7C/D Eans Operators are initially expected to attempt to reset the w eas sm= = = '

' ' #b breakers. If they try this, the breakers will reset. As m54 - N - Pop out soon as the Control Room "Fs to start the fans, the mat 4 Tarset -

~~~ " " ~ ~ ~

breakers will trip again. External inspection of the breakers reveals no indication of the fault. When - - - -

electrical maintenance or OSC personnel arrive, they - _ _

may open the breaker cubicle, If they check the RMS-9 yod /

solid state trip programming unit, they will note the - p "short circuit" mechanical pop-out fault target is out. - - - -

Settings on the unit are c'orrect. If maintenance resets 9/d 0 -

P the' target and the breaker, and watches the Control

~~~

Room try to start the fans, they will see the breaker trip immediately and the "short circuit": mechanical pop-out fault target popped out. The "long time" trip light stays Yk O

\ . _.

~

dark . Maintenance may then inspect the breaker and .

cabling, ' There are no internal indications of breaker fault. If operators megger the power supply cables, they will see 10,000 0 phase to ground on all three phases on-the' load side of the breaker. Acceptable range is greater than 1.5 Meg O. This indicates a short circuit on the load sidc. Operators may inspect the cables leading to the_ fans, but find no indication of the fault between the breaker and the containment penetration.

, 1 On60841 EXERCISE' MESSAGES.WP5 3 - 15 Rev. 8/12/92 x, . . . - . .

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7 . CONTROLLER MESSAGES LCR/TSC/OSC/ EOF (cont):

_ TO: ; Mech. Maint./ Repair Team '(HCV-344) ' NUMBER:- 9; FROM: Observation (OSC Controller) TIME: 0820+

T+00:20 + -

TYPE: Verbal Page 1 of 2

. DRILL PURPOSE ONLY .

DO NOT initiate actions affecting normal plant operations.

Valve indicates shut.

On attempt to manually open HCV-344, the handwheel turns about l' turn in the 'onen direction, from the n'ormal neutral position then stops. The holes for inserting the ball lock pin are almost perfectly aligned. .

9 CONTROLLER NOTES:

~

o 1-. Deliver this message when RT reaches the valve.

~

2. SS will probably expedite inspection by tising personnel froni HCV-345 inspection.

3. -Remote operator linkage has failed inside bonnet. Fragment of linkage still attached to -

actuator lever has jammed against inside of bonnet. Valve cannot be operated manually -

'until this is cleared. ,

4 Manual handwheel moyes an outer sleeve ~over a second shaft attached to the opposite -

n end of the same actuator lever. If the valve were actually_open, the handwheel should

'be able to turn - 50 turns prior to the handwheel shaft contacting the end of the actuator -

shaft. The fact that thei wheel will not turn indicates the. valve is still shut, despite the:

fact that .the operator has moved to the open position, H EXPECTED RESPONSE:-

l ._ RT report indication to OSC. Maint. report to SS.

2. TSC/OSC priority: opening HCV-344. Plan to remove all or part of the operator to free the manual operator to open the valve.

GW8CEXrACISEWESSAGES.WP5 3 Rev. 8/12/92 o

,,~

, ,, , . . , a. , , - ,

l

! SCENARIO hiESSAGES CONTROLLER MESSAGES - CR/TSC/OSC/ EOF (cont)

TO: hicch hiaint./ Repair Team (HCV-344) NUhiBER: 9 FROhi: Observation (OSC Controller) TIhiE: 0820+

T+00:20 +

TYPE: Verbal Page 2 of 2 DRILL PURPOSE ONLY DO NOT initiate actions affecting normal plant operations.

Mditional Controller Trouhleshootine Infonnat]on - IICV-344 The valve indicates open in 'he Control Room. Locally, the valve operator appears open, since the bellows diaphragm (left) is stretched to near the top of the gage mounted beside it.

The manual handwheel (right) is in the normal neutral position. The ball-lock pin'is removed. If operators try to turn the handwheel, it will go only about I turn, then stop, it does not become gradually stiffer, as

~

would be expected if it were binding, it just _

will not turn past that point. The handwheel opens the valve by forcing the hard inner surface of a sleeve-like outer shaft down onto y

\

the inner shaft, extending from the operating d

l / /' << \

j/

lever. If the valve were actually open, the inner shaft would retract and the handwheel

'p//'

sy

,y would be free to turn ~ 20 turns, until the 3 o y outer shaft once again extended to contact the

[ rf>

inner shaft. The ball-lock pin is required only b to manually shut the valve. The pin is inserted ( goej after the manual handwheel is turned all the way in to align the hole in the retracted inner shaft and the outer shaft. The pin locks the two shafts together, and allows the outer shaft to withdraw the inner shaft to shut the valve. The pin is not required to manually open the valve, it may be inserted without prevent'og manual opening. If operatcrs try to insert tt .-

pin, they will note that the holes in the er and outer shafts are aligned. This is clear indication that the valve ball is still s' . other external indications are normal. See l page 2 of message 19 for internal va! jection results.

L an60st axracisttutssaats.wp3 3 - 17 Rev 8/12/92 l

+

SCENARIO htESSAGES CONIl10L11R11ESS AGIL_CRGECIOSClEOLftmin TO: Elec hiaint./RT at VA-3Alli NUhtllER: 10

- FROht: Observation (OSC Controller) TlhiE: 0820 +

T + 00:20 +

TYPE: Verbal Page 1 of I DRll.L PURIOSE ONIN DO NOIinitiate actions affecting normal plant operations, VA-3A/Il breakers are clos-d.

Fan motor current indicates 120 A in the control room.

CONTROLLER NOTES:

1. Deliver if maintenance inspects operation of VA 3A/11.

2. Adjustable pitch fan blades have slipped to 0*, fans are pumping no air flow past the containment coolers.

3. hiegger readings are normal,2,000 hieg 0 phase-to-phase.

EXPECTED RESPONSE:

1. Be aware of plant conditions, a sonrxrscisntr35 AGr.s wn 3 - 18 Rev. 8/12/92

J SCENARIO h1ESSAGES CONTROLLER 51ESSAGES - CR/TSC/OSC/ EOF (cont)

TO: Aux. Operator at VA 262 NUhtBER: 11 FROht: Observation (OSC Controller) Tih1E: 0820+

T+00:20+

TYPE: Verbal Page1of1 DRILL PURPOSE ONLY DO NOT initiate actions affecting normal plant operations.

On attempting to close VA 262, valve operates stiffly. The valve handle rotates a times in the shut direction, then will not turn any farther in the shut direction.

CONTROLLER NOTES:

1. Deliver if CR Shift Supervisor sends operator or repair ' cam to shut VA-262.

2. SS may elect to shut VA 262 to back up HCV-746B, since HCV 746A is failed open.

3. Valve stem is slightly bent, efforts to muscle the valve closed or straighten the stem will only bend it further,

4. After 0945, dose rates on contact with the valve are approximately 5 mR/hr. General area dose rates in the room and airborne surveys indicate normal. Contact dose rates on the pipe return to background upori initiation of containment spray at - 11:15.

EXPECTED RESIONSE:

1. Be aware of plant conditions.

2. Evaluate methods to shut VA 262, omarJtCl$E$tES$ AGES.WP5 3 19 Rev. 8/12/92

SCENARIO MESSAGES CQNTROLLER MESSAGES e CR/TSC/OSC/ EOF (cont)

TO: CR Shift Superviwr NUMBER: 12C FROM: Contingency (CR Jead Controller) TIME: 0834 T+00:34 TYPE: Ilandout Page1 ofI DRILL PURPOSE ONLY DO NOT initiate actions affecting normal plant operations.

Declare an UNUSUAL EVENT per EPIP OSC 1, EAL 2.1; " Uncontrolled Steam Generator lleat Extraction" based on EOP-05, Figure 5.1 " Break identification Chart".

CON'IROLLER NOTES:

1. Deliver this message only as directed by the Exercise Senior Controller, if a NUE has not yet been declared.

2. If operators have entered EOP 20, based on failure to meet containment critical safety function status check in EOP-05, SS may elect to declare an ALERT instead, per EPIP-OSC 111.9. This will supersede the NOUE.

EXPECTED RESPONSE:

1. Declare a NOUE.

2. Make appropriate notifications.

ososmracistur.SSAGU WP5 3 - 20 - Rev. 8/13/92 w -

t SCENARIO hiESSAGES CONTROJ.LER MESSAGES - CR/TSC/OSC/ EOF (coqu e

TO: CR Operators NUh1BER: 13S FROht: Indication (CR Lead Controller) TlhtE: 0835 T+00:35 TYPE: Handout Page 1 of1 DRILL PURPOSE ONLY DO NOT initiate actions affecting normal plant operations.

ANNUNCIATORS IN CONTROL ROOh!

PZR Pressure low PZR Levellow INDICAIlONS IN CONTROL ROOh!

PZR Pressure indicates 1330 psig and lowering.

PZR Level indicates 93.4 and lowering.

CONTROLLER NOTES:

1. Deliver this message only if proper indication is not available from the simulator.

2. Start of tube leak in SG#1 indicated by lowering PZR level, and increasing containment rad levels.

l

! EXPECTED RESPONSE:

1. Isolate letdown if restored after trip. Use charging pumps and HPSI as required per EOPs to restore / control PZR level.

2. Analyze magnitude of leak rate.

an60strxrRC15EWLS$ AGES WP5 3 - 21 Rev. 8/12/92

l l

l SCENARIO h1FSSAGES CONTROLLER A1ESSAGES - CR/TSC/OSC/ EOF kont) ;

TO: CR Operators NUhfBER: 14S FROht: Indication (CR I ead Controller) TIhiE: 0345 T+00:45 TYPE: llandout Page 1 of1 DRILL PURPOSF. ONLY D_O NOT initiate actions affecting termal plant operations.

INDICATIONS IN CONTROL ROOh!

Cll 1B is running CH lC is running IIPSI-i A is running IIPSIIIcader flow indicates 183 gpm.

Pressurizer level indicates 84% and steady.

Charging Header Flow indicates 80 gpm. ,

CONTROLLER NOTES:

1. Deliver this message only if proper indication is not available from the simulator.

2. Sufficient information for leak rate determination in excess of 40 gpm.

' EXPECTED RESPONSE:

1. Declare an ALERT per EPIP-OSC-1, EAL 1.5; "RCS Leak rate > 40 gpm,"

2. TSC/OSC activate, if not already done.

3. Perform plant evacuation, assembly and accountability.

on.osuxtaciscwtssAcu wps 3-22 Rev 8/12/92

SCENARIO MESSAGES CONTI(DLI.ER MESSAGES - CR/TSC/OSC/ EOF (con 11 TO: CR Shift Supervisor NUMBER: 15C FROM: Contingency (CR lead Controller) TIME: 0915 T+ 01:15 TYPl!: llandout Page1 of1 DitlLL PURPOSE ONLY DO NOT initiate actions affecting normal plant operations.

Declare an ALERT per EPIP OSC 1, EAL 1.5; "RCS 1.cak Rate > 40 gpm."

CONTROLLER NOTES:

1. Deliver this message only if directed by the Exercise Senior Controller, if the ALERT has not been declared at this time.

EXPECTED RESPONSE: 1 I-

1. Declare the ALERT.

l 2. Activate the TSC and OSC if not already done.

3. Precautionary activation of the EOF is optional, a muutactsestF35 AGE 5MT5 3 - 23 Rev. 8/12/92

SCENARIO MESSAGES CONTROLLER MESS AGES - CR/TSC/OSC/ EOF (corg)

TO: CR Operators NUMBER: 16S FROM: Indication (CR Lead Controller) TIME: 0945 T+01:45 TYPE: Handout .

Page 1 of 1 DRILL PURPOSE ONLY DO NOT initiate actions affecting normal plant operations.

ANNUNCIATORS IN CONTROL ROOhi RAi-060, RM 061 high alarms INDICATIONS IN CONTROL ROOM RM 060 indicates 1.75 x 10' epm RM-061 indicates 4.37 x 10' cpm RM 062 indicates 2.80 x 10' cpm CONTROLLER NOTES:

1. Indications of leakage past HCV 746B

2. See section 5 for additional RMS data.

EXPECTED RESPONSE:

1. CR inform TSC.

2. TSC direct OSC to send a team to investigate.

l 3. Site Director declare a SAE.

l 4 Attempt to shut VA-262, if not already tried, c asos4.r.uncistwoss Aotssu 3 - 24 Rev. 8/12/92

SCENARIO MESSAGES CONTROLLER MESS AGES - CR/TSC/OSC/ EOF (cont)

TO: RT near HCV-746B NUMBER: 17 FROM: Observation (OSC Controller) TIME: 0945 T+02:15 TYPE: Verbal Page1of1 DRILL PURPOSE ONLY DO NOT initiate actions affecting normal plant operations.

You hear a high pitched whistling noise, like the flow of air or liquid under pressure. It seems to be getting louder. It is coming from the direction of Room 60.

CONTROLLER NOTES:

1. Deliver this message to any repair teams in the vicinity of HCV-746B.

2. If teams move to investigate the noise, indicate increasing noise levels until they reach HCV-764B.

2. Flow in the pipe indicates valve seal breakdown.

3. For teams in the area, obtain local area radiation levels from Section 5, " Radiation Monitor Data Summaries" On contact readings at HCV-746B indicate 5 mR/hr.

EXPECTED RESPONSE:

1.' RT inform OSC.

a460smracistMCS$ AGES WP5 3 - 25 Rev. 8/12/92

_ _ . _ . _._ - _ m _ - . . _ . _ - _ _ _ . _ . _ _

1 SCENARIO hiESSAGES i CONTROLIER Af ESSAGES - CR/TSC/OSC/ EOF (cont) i TO: Site Director NUh1BER: 18C FROht: Contingency (TSC 1. cad Controller) TihfE: 1015 T+02:45 TYPE: Handout Page 1 of I DRILL PURPOSE ONLY DO NOT initiate actions affecting normal plant operations.

Declare a SITE AREA EhiERGENCY per EPIP OSC 1, EAL 1.16; " Loss of Two Fission Product Barriers,"

CONTROLLER NOTES:

1. Deliver this message only if directed by the exercise senior controller, if the S AE has not been declared at this time.

FlPECTED RESPGNSE:

1. Site Director declare the SAE.

2. Activate the EOF if not already done.

3. Perform site evacuation.

ce,60:4ntacismESSAGES.wn 3 - 26 Rev. 8/12/92

SCENARIO MESSAGES CON'11(OLLER MESSAGES - CR/TSC/OSC/ EOF (cnnO TO: RT Leader IICV 344 NUMBER: 19 FROM: Observation (OSC Controller) TIME: 1110 T+03:45 TYPE: Verbal Page 1 of 2 DRILL l'URPOSE ONLY DO NOT initiate actions affecting normal plant operations.

The bonnet cover has been removed from the remote operator of HCV 344.

The rod end bearing assembly which connects the remote operator to the actuating lever on the drive shaft has broken inside the bonnet and is jammed against the bonnet easing.

I CONTROLLER NOTES:

1. Broken piece of rod end bearing assembly has prevented the manual operator from opening the valve.

EXPECTED RESPONSE:

1. Inform OSC.

2.- Remove cap screw and hex nut from actuating lever, remove rod end bearing assembly to free manual operator.

3. TSC/CR Coordinate to restore containment spray.

I ouosmtreisrwrssaatsws 3 - 27 Rev. 8/12/92

7_ _

i i

SCENARIO hfESSAGES I CONTROLLER hf ESS AGES . CR/TSC/OSC/EOl' funil

TO: RT Leader HCV-344 N'UhfBER: 19 .

i FROht: Observation (OSC Controller) TlhiE: 1115 i T+03:45 [

t TYPE: Verbal -

Page 2 of 2 DRILL PURPOSE ONLY i DO NOT initiate actions affecting normal plant operations.

Additional Controller Troubleshootine Information - IICV-344 _

hialntenance/OSC personnel are expected to have recognized that the air oprator is in its-open position and that the valve itself is still closed, based on indications provided in messages 6 and 9. If they do not recognize that the air operator has opened, they may !

attempt to vent the operator. If they try this, they will discover that the operator is already vented. Next, they _

will likely start to disassemble the remote operator from the SW j'

valve. : The diagram at right describes what they will find.

If they remove the neoprene boot, they will find the upper ,

L d

extension of the rod end bearing assembly hanging from ip

- the actuator stem. If they look inside the bonnet, they will .E see the lower part of the rod end bearing assembly jammed- C against the inner surface of the bonnet. They will not be ( /

able to move it from above. They must remove the six cap screws holding the bonnet cover, remove the bonnet cover,

([ , , , , '

[

and un bolt the lower rod end bearing assembly to free the +

lever arm. When this is done, the valve may be opened manually. The team controller needs to pace the progress of the repair to ensure that the valve is not ready to open prior to 11:10. Ensum that players have the proper tools, manuals and materials to do the job.

. ~ ,

O WREXERCISEMS$ AGES.WP3 3

28 Rev. 8/12/92 7

w- < .w 1. , -

c - , - y w. ,r ,. ,. v --, .- ~.w 5,,--

SCENARIO hiESSAGES CONTROLLER MF,SSAGES - CR/TSC/OSC/ EOF (cont)

TO: CR Operators NUhfBER: 20S FROht: Indication (CR Lead Controller) TlhiE: 1115 T+03:15 TYPE: llandout Page 1 of 1 .

DRILL PURPOSE ONLY DO NOT initiate actions affecting normal plant operations.

LNDICATIONS IN CONTROL ROOM One containment spray pump is running.

Containment spray flow indicates 2400 gpm.

Containment pressure indicates 16 psig and dropping.

Containment temperature indicates 1900F and dropping.

Radiological data indicates as read in section 5.

CONTROLLER NOTES:

1. Deliver this message only if proper indication is not available from the simulator, upon initiation of containment spray, EXPECTED RESPONSE:

1. - Maintain spray flow as required to control containment pressure, o.36aa4;txtacistsitssrats.wr5 3 - 29 Rey, 8/12/92

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

e SCENARIO htESSAGES CONTROLLER h1ESS AGES - CR/TSC/OSC/ EOF (cDnD TO: All Players NUbiBER: 21 FROht: (All Facility Lead Controllers) TIhfE: 1200 T+ 04:30 i TYI . Vcrbal Page 1 of 1 DRILL PURPOSE ONLY DO NOT initiate actions affecting normal plant operations.

All Exercise activities are terminated. Please prepare for facility critiques. Participant critique forms are being passed out for you to complete. Please collect all paperwork and logs generated during the exercise and turn them over to your controller with the participant critique forms. Please return all procedures, manuals and drawings to their proper storage locations.

b CONTROLLER NOTES:

1. Deliver this message only when directed by the Exercise Senior Controller.

EXPECTED RESPONSE:

ca60scr.xrmeisexusAcr.s.us 3 - 30 Rev. 8/12/92

n-OPERATIONAL DATA TABLE of CONTENTS A

Page

TAllLE of CONTENTS 4,1

OPERATIONAL DATA SUMMARIES and GRAPIIS 4. 2

CONTROLLER MESSAGES OPERATIONAL DATA 4,26

ERFCS DISPLAY - OPERATIONAL DATA 4,28 STATUS BOARD, PAGE 194 4,29 REACTIVITY CONTROL, PAGE 200 4,30 VITAL AUXILIARIES, PAGE 210 4,31 RCS INVENTORY CONTROL, PAGE 220 4.32 RCS PRESSURE CONTROL, PAGE 230 4,33

- CORE IIEAT REMOVAL, PAGE 240 4.34 RCS IIEAT REMOVAL, PAGE 250 4.35 CONTAINMENT INTEGRITY, PAGE 260 4.36

'onoo 5mNuruTocams . 4-1 Rey, 8/12/92

OPERATIONAL DATA OPERATIONAL DATA SUS 151 ARIES and_GRAl'llS Operational data summaries and graphs are provided under this heading.

Summaries and graphs are for reference by controllers only and will not be issued to panicipants in this form. Participants have complete access to this data through simulator data, or proper inquiry of the emergency response facility computer system (ERFCS) by displaying the following pages:

Status Board Page 194 Reactivity Control Page 200 Vital Auxiliaries Page 210 RCS Inventory Control Page 220 RCS Pressure Control Page 230 Core H6at Removal Page 240 RCS Heat Removal Page 250 Containment Integrity Page 260.

Example of these ERFCS screens are included in this scenario.

NQIfd The examples provided in this scenario submittal are only examples to depict the layout and configuration of the scree.is, The actual volume of screens to be available for the exercise will be produced from the tables of data. The data reflected in the examples enclosed may not necessarily reflect actual exercise data.

owoueurt.mm wrs 4-2 Rev. 8/12/92

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o. 2 x

g . t. W . . _ , _ . _ . . s sss sss sssss OPER ATIONAL DATA I (' ~ ~ 'i 153'15 T+02iiS~ ^ 10l25 ' T+ 02520~ J))[Si>{ j ~ [ STBY g _'STBY ] RUN }. RUN 10:30 ^STBI~ 15:35 T+02:35 ~ ' 0' ~ 1E45~ ~ T+d2 ~ ~ ~ ' i i RUN' RUN ~ RUU~I 56:4 5' ' ~ TA02:45 10:55 T+02:55 5TB I ~ ~' '~ U:00~ TA03:ho STBY ~'5tSY' STBY ' 0' 0_ ]iBY RUN ~SVBV' STBY S TB[ ~~~ STBY 11:10 T+03:10 '11:15 ~iT03:15 1132E' ~TA53do ~ 'ROS STBY bTBY 11:30 T+03:30 . . . _ . . . . - . _ , . _ _ . _ - - - 4 l o. o nnnnnny.x=noa.nnnna'y**n5c.nnnnnn*5== se a se so se a se a se es ao aeeeeeeeeeeee-.o e SUMM ARIES 1992170ltT CAI IIOUN EXERCISE l'LANT DATA SUMM ARY Time i napsed T,m zw A l Cuv B i CCw c j Cont Spray A j CW. Spray B ) Cont. Spray C Cont. Spray twader now g Asr Compressor A { Aw Compressor B [gnrhpressor C t j ! _. 9P" i. j NON 10:10 . . _ ~ .T+02:10 RUN R04 I STBY STBY l ..STBY.. i 0 i RUN '[ STBY j STBY I ~ RUU~ ~ STBY' .iT BY U TBN 0 '~RUN ' ~ l STBY ~~ STB RUN ! ~RUN . UUti li EB ^ STNY ST5Y ~ ~ ~ ' O' I ~~ST5f~ -STBi~ ~ STBY 5 ,]k2i25 %J jUp,' _ [0 - ]~~ ] [ ]5TBY [ ] ] ]St5Y~~] '5Ti{ T+02:30 RNN SW STBY l STBY i 0 ! RUN l STBY STBY Rdff ~ l ' 'RUN~ 'RUN ^I'RUN 'STBY ~7 TBE [ O I STBY STBY ~STBY ST5E~ ' 5TB STB ~~h ~~~V STB STBY RUfE ~5T5 F ~0 '! RUN' R'btf [~~~STBY~~ STBY STBY ! STBY STBY 10:55 '~[TkO2:55 _ RUN , [RUN[ RUS[ . 'STB ' ' i57 } [STBI[' [ 0 lj _ ] TIN } ~ { STBY_. _ STBY _ RUN RUN RUN STBY ST3Y STBY 4 0 RUN 1 STBY STBY ' ~RUN ' ' ~R Uti RUU' ~UT5E ' 0~ 5TBi i~ ~ STBV 115{5 { T 03idd ' ' rut [' RUli N ~RbN ~ ~ ' 5iBi~ ~ 5TBv ~' STB 9' ~ ' RUN RUN RUN STBY STBY '~~~ ~' ~ ~RUN RUN RUN RUN STBY } 'STBY' 2*X5 ~~~ RUS STBf I5TBY~~ 'RUN~ RUN RUN STBY STBY 2480 ~ "SY l SW STBY III25 T+53I25 'RUU NUU~f ~RUN , RUN , 2480 ST5Y ! STBY ~5TBi~ RUN PUN

RUN~I RUE # ~ 5TBY ~ STBY 2480 i STBY 1 STBY STBY UiN ' ~ T+ii3d5 ~ RNN [ RUN Rud~~ RdO~ ~ ~ ~STBY' ~5T BI- ~

' ~ ~ ~ 250~ '~f' STBY l STBY '5TB l'MO -.}83@U1 T+03:45 1RUN1 R k RUN RUN }RU{ RUN ._RUN{ { ]pBf STBY ] STBSTBY { _ _ g~} [STBf)) SW SfBY STBV ~5IB{STBY 11:45 { _ 2480_ , J 11:50 T+03:5a RUN RUN STBY STBY 0 ST _STBY { _ STBY RUN 4.RUN_ _ l _ STBY iiTBY _ STt STBY 11 55 T+0P55 (UN j_RUtQ RUN __._ R,0N 0 l j ] STBY ] 12:03' T + 04.00 RUN t RUN f RUN RUN I STBY i STBY 0 i STB STBY STBY o ne rM errmn;inistaists 4-16 Rev. 8/6/32 , k OPERATIONAL. DATA SUMM ARIES 1992 FOltT CAlllOIIN EXEltCISE l'I. ANT DATA SitMMAltY Tome .l Flapsed Tame .

Asr headef pressure ,j FW4 FW 10 { PPLS j : SlAS { CPHS

.i j CIAS ' CRHS ! VIAS l RAS j STLS l CSAS ; O.3,i Stack flow l _ Reactor .._ _ ,. l Turtnnd j Generator _ pug i i , i ,! ! 1 1 ! cfm ! i ~l 7:00 ' T-0100 + 102 lSTBVi STBY STBY STBY}STBr}STBY STRY STBY f STBY ! STBY STBY ! STBY [ ~482f ~~ ^NT TRIP ~NT TRIP'I ' NT TRIP ~ ' 90I55 i 102 'STBY STBY STRY: STBY i STBY I STBY I STBY i STBV I STBY~ STBY ' STB) STBij^ "4827S Y NT TRIP NT TRIP NT TRfP 7:05 } 7:10 . T-00I50' ~102 SiBY[ STBY l STBI f STB /' STBY STBNISTBY' STBY 5 STBYi 485 T 'NT TRIP ~NT'TRd }~NT TRTP ; 'STBY{S'TBE STBi{LSTBY 7:15 T '00:45 , 102 'S3YIdTBY}STBY I STBY STBY l STBY 3 STB STBY f STBY STBY } STBY l ~ 48285 I NT" TRIP NT TRIP 'IUT TRIP 7:20 . ~ T-00I40 ! 102 - P BY ST BY ' ' STBY STBy~"STBY f ~STBY ! STBY f 'STBY f STBV ! STBE STBY l STBY ~ ~ 48290 f ~ P.T ThiP ' i NT TRIP" f NT TRIP ~ NT TRIPYNT TRIP ~ 7:25 I T-00:35 '} 102 "STBY' STB ( 'STBf STBY STB (! STBY $ STBY } STBf f STBY I STBY i ST8Y 'STBII ^48295~ I" NT TRtP ~ 7:30 T 40:30 I '102 STBf 5TB( STBY ' STBY STB ( f STBY ! STBY) STBiI STBY I STBYj STBY ! STBY 48300 IJTFRid NT ~ TRF [ NT TRIP [ 7:33 T-00:25 [ 103 ~fSTBY STBY STBY $ STBY ' STBf j STBY] STB STBY STBY ; STB,Y j STBY f ST5Y [48300] JT TR!P[ NT TR!P ' ' NT TRIP f 48300 f4T TRIP 7:40 l T-00:20 l 102 , jSTBV STBY_ STBY { ,STBY STB ( I STBY { STBY j STBY STBY ; STBY ; STBY }TBY . } NT TR1P {NT TRIP ; 7: T-00:15 99 5 'STBY STBY.I STBY I STBY j STBf f ,STBY STBYiSTBY STBY ! STBY j STBY^ i STBY j ~ _48300 : NT TRlP i NT TR!P tJT TR:P 45 ij ^ ' T 00do ~ STBY' ST'B Y ST5Y ' STBY l STB fS18Y ' STB ! STBy l STBY f STBi! STBV STBY[~ ~4830E ^ NT TRIP N ' TRIP- N T 'T RtP 7:50 - 1015 ~ . _ 7:55 ~ I-00IOS " 103 STBffSTB[!STBY" ST5Y ! 'STBY f STBY STBYfSTB I'STBY { STBE i STBf 'STBY { 48300 ~ ! NT TRIP' "~NITRIP' i NT TRIP 8:00 'T+00:00 [ 1035 . ' STBE [ STBY i STBY[STBY f STBVSTBY I STBY STBY f STBY STBY STBY j STBY] 48300 _NT TRfP))J ' TRIP NT TR!P 8:05 T+00 05 99 3 ACT ! ACT , ACT ; STBY j ACT jSTBY STBY ACT ! STBYf 4830J I TRIP i TR1P i TRIP !RUN{RUN l ACT " TRIP 8do' T+00i10 'I~ ~ ' 101' ' )RUN dCT' ACT ! STBi~f ACT'i STBY STB [ AdT iSTBY 48300 TRfP~ f ~ T RIP Rufi[I ACT I~ dCTACT]'AUT IRE "~TRM 8:15' ~T+00i15 ~ ~ 102 ' R U'J' 'RUN ~ ' AdT' CT ACTl'STBY STBy j ' ACT l STBIi 48300 ~~ T RIP ~8:20' ' T A00:20 ^ 103 5 ~ ' rut [ RU(I NCT [iQ{ACT NCT]jSTBY STEiY Adi'{ _STBY f STBY j ACT'fSTB, { [ TRIP][TR:P , [ TRIP l 8:25 T+00:25 99 _ RUN RUN_ ACT ACT j _ ACT_j.ACTjSTBY . ACT j STBY l STBY { ACT lSTBY 48300 TR!P] _ TRIP i TRIP 8:30 T+00:30 101 RUN RUfJ _.ACT . ACT. ACT ' ACT STBY ACT lSTBY STBYj~ACTISTBY 48Xio~j~~ _ TRIP_ TRIP I T RIP 8:35 T+00:35 102 RUN ' RUti ' '~ACi ~ AUT ACT ~ ACT I 5TB9 NUT STBY STBYj hCT 5TB ' 48300 l TRIP TRIP ~ f ~TRtP 8:46f T+00:40 I~ 103 5 *~i rut RON' AUT ACT STBY' ' CT ' S'T BI ST B Y 'ACT[ST5E' ~48300"] TRIP ~ 'I ~ TRO ' ~ ! ' TRIP ~ l ' NCT]"' ACT ' TRII i:45' ' T+0dd$ ' 98 8 RUti rut [I~Adi ~ AUI ' ~ AUT {' ACT STBY' ~~ A'CT STBY 5TBY[ ACT' i ST5Y" 48300 ~ ' '~ TRIP ' ~T RIP > '[ RUf4 ~ RUf4 l'ACT' ACT } ' ACT j 5CT' STBY' AUT 'STBY ' STBY I dT I 5TBY ['48306~ l TRtP TRIP ~ 8:50 T+06:56 1005 T RIP ' BI53 T+0dl55[ j ~[10(~ rut ACT Ui] AUf[AdT[ STB _E ~ ~ACT STBV STBY I ACT I5TBVIR3500~~I TR { - 'I RM " T RIP j [RUN(IRUN 9-00 T+01:00 ~ 103 lRUN 5 ACTj'ACT %CT l ACT , STBY YACT STBY { STBY f ACT i STBY 48300[ l TRIP TRIP TRIP 9:03 ~T+d1:05 , 98 5[ ,[RUN STBI 'ACT ' ACI ACT {dUT j ST5E ACT[STBY. ~ i STB f ACT f SiBi{48300[ TR@ [jTRif ' [TR;P

TRy j , TRM T Rip 9:10 T+01:10 100 5 RUfJ j STB { {ACT ACT , ACT j ACT_ STBY{ACT , S,T B Y STOY] ACT l STBY{ 48300_;_ _

ACT !ACT, TRIP 102 RUN j STBY l ACT ACT STBY ACT . STBY._ STBYl ACT 1STBYl 48300 j T RIP ~~l" ~TR:P 9:15 { ' T+01:15 'fRUN STUY ~A UI ACT ACT}'ACf '~ STB ~ ~ ~dbT~ STBE 'STBIACT STB /I 48?l06~~ TRIP I' ' TRIP T+0dO' id3 } T RtP ' 9:20 5:25 ~ TE01:25 98 5 ~ Rufi ' STBY ACT' ACi 'ACTi"C STRY 'ACT 'STBYiSTBk' ACT[ STB ^48300 ~ TRIP" TRM TRIP Di3d ~ ' T +IO130 99 9 'RUN' STB {ACT ACT ~ACTi ~CT' STB FACT ' STBh i STBY ACTiSTBi- ~48300~ " I" ' TRIP ' l ~ TRtI f TRIP 9:35 T+01i35 102 ~ 'RUN ACT STBNf CT STBY If STBY ACT' [ STB ' '48300' ' TRIP ' ' TRIP ' ^ ' TRtP t STBY I'ACi f[5dT f ~ ACT i c:40 T+01:40 103 ' RUtii ST3 {lACT ACT1 ACT;ACT STBYj ACT STBY STDI ACT!STBf [48300[ ' f TR@ [][ TRIP TRIP TR!P RUN{STBi_iACT ACT ACT _ ACT j STBY 1 ACT STBY, STBY{'ACT STBf ; 9:45 T+01:45 101 48300 i TRIP TRIP 9:50 T+01:50 99 8 , RUN j STBY } ACT ACT ACT. ,ACT j STBY f ACT j STBY . STBY{ACTiSTBY f 48T0 T RIP {j TRIP T RtP STBYjACTISTBYj 24300 I 9:55 T +01:55 102 RUN !TBY l ACT ACT . ACT ACT j STBY l ACT i STBY ~ TRIP t T RIP ! TRIP 10.00 T+02:00 103 jRUNISTBY ACT 'ACT ACT , ACT ' I STB ( f ACT f STBI STBY [ ACT f STBY 24300 ' TRtP ~I]RtP f [ TRIP 10-05. T +02:05 103 l RUN } STBY ; ACT I ACT 1 ACT1 ACT i JBY I ACT 1 STB ( i STBY l ACT tSTBYt 24300 TR!P 1 Trip i TRtp o mmrutsE ri nNsnt Es 4-17 Rev. 8/G/92 r ]3 OPERATIONAL DATA SUMMARIES ' 1992 FORT CALilOUN EXERCISE l'LANT DATA SUMM ARY Generator .. . Turbene ~ CPHS _ Stack flow. _ _ .__c_r { - ______ T=ne ( SLA Rea to Elapsed Time ,! Air header pressure _ FW4_ . _FW.10 ._ ppt _S_7_,._S . C_IAS i .CRHS _ . . .l VIAS

_. i RAS.. I STL._S l CSAS i OPLS.__._.-

~ RijN jT[~STBh AdT ' 5TB iSTBi(ACTfST5' ~ 3 4300 ' TRIP - ~ TRIP 1'Od0' ._' T+0210[ 99 65 ' STBV _ ACT ACT] AdT TRtP[ ACT, I ACT STBY STBY ACT 10:15 ' T+ 02:15 101 RUN STBY ACT' ACT ACT ACT 24300 TRIP Trip TRIP 16d0 ((T+02:20 102.5 ~ ~ RUE ~5'8 ~ dT 'AC[ "Edf' kCT 'AdT[AC'T STBi- STBf 'ACt{STBY 5T5Y T4360~ ~ " TRIP ( TRtf IRIP TRIP 10:25 T402:25 104 RUN STBY ACT ACT ACT ACT ACT ACT STBY STBY ACT STBY 24300 TRIP TRtP j 35 +k23 3[ ' 99 5 , . _ _ .%N jiU{AdQ AC [_y,I f,[d( , . 'ACT[ ACT . STBy[ST5f{AC_T" _ 5t'B{] 30 6 ] iRIP Trip TRIP, T RIP TRi? - 335 __,T+g2g5_,;, ,y _- ,_Ry .STBf ACT 3Q, pCTj ACT_ . pC{ .ACT STBY STBY ACT _ STBY _ _24300 TRIP TRIP _ 10:40 T+02:40 102 5 RUN STBY ACT. , . ACT ACT ACT ACT ACT STBY STBY ACT STBY 24300 TRIP TRIP 10:45 T+02:45 103 RUN STBY ACT ACT ACT ACT ACT ACT STBY STBY ACT STBY 24300 T RIP TRIP - TRIP +2[ 99 25[ _[_ y[ .y [ [dUil}A]CT[ }dT "(T]CTT ACT STBY StBY ACTjS18Y 24300 TRtP TRIP T rip ACT ACT ACT STBY_ STBY .ACT STBY 24300 TRIP TRIP TRtP 10355 _]+355_ -_ __ , J 01 -_ RUN STBY_ ACT ACT { ACT .1190_. T+03:00 1025 RUN "%Y ACT ACT ACT ACT ACT *CT STBY STBY ACT STBY 24300 TRIP TRIP TRlP 3 _ ACT' STBY_ACT .CT] STB,YfSTBY , STBYj STBY 24300 TRIP TRtP TRIP 11 05 _ ; T+0325 103 _ _ RUN STB _Y ACT ACT ACT[ ACT ACT STBY . STBY STBY STBY 24300 TRtP TRIP TRIP 11:10 T+03:10 99 05 _.RUfJ,_ STBY ACT ACT STBY RUN STBY ACT ACT ACT STBY STBY S_TBY .STBY 24300 TRIP TRtP TRIP 11jt5_ 4 _ T+03:15, _ _, 101 _ STBY_ ACT_ _AC,T _ 11:20 i T+03:20 102.5 _,_ ,RUN STBY STBY STBY_ STBY STBY ACT ACT, STBY STBY 24300 TRIP TRIP TRIP STBY f STBY ~5i5i " dY' '~ $133 f NU5i25^ 103 . RUti li'BT'5T 5Y' 5TBi' '555E' ' 'AUT" ' S BY ~5T5Y STBY STBYI 24300 TRIP T RIP TRIP 11301 T+03:30 103 . RUN STBY STBY STBY STBY STBY ACT ACT STBY STPY STBY STBY 24300 TRIP TRIP TRIP STB,Y STBY STBY STBY STBY, _ACT, ACT STBY STBY 24300 TRIP . TRIP T RIP - 11:35 f ,T403g35 103, _ Ruff _ STBYJ STBY TRfP TRIP { TRIP 11:40 T+03:40 103 RUN STBY STBY STBY STBY STBY . .CT ACT STBY STBY {STBY , STBY 24300 11:45 T+0.i:45 103_ RUN STBY STBY STBY STBY STBY ACT ACT STBY STBY SIB) STBY 24300 TRIP TRIP TRIP 1553~ ~T+03i50 ' 1 03 RUN STBY STBY STBY STBY STBY ACT ACT ,STBY STBY- STBY STBY 24300 TR!P TRIP TRIP - 1h5. T+5h55, [10f_]}~~ yjj dI [STBY ST5y STB 9[ 5TBY 5CT[Adi i5IBY [ST5Y] 'STBY _ 5TBi~2dOOl TRIP TRIP . TRIP 12:00 T+04:00 103 RUN STBYjSTBY STBY STBY STBY ACY ACT l STBY { STBY l STBYSTBY 24300 i TRIP TR;P f TRM (i%UH4 EXf:kCt%ITI.lDIM MXIS 4 -18 Rev. 8/6/92 - OPERATIONAL DATA St 31M ARIES 1992 FOltT CALIlOtIN ENERCISE Pl ANT DATA StiMM ARY Tyne Elapsed Trne Offsde pwr 345 j Off site pwr 161 ~ DC bu_s tj DC bu_s 2 _ _ _. ._ . . . . _ . _ _ . .l. _ . . . . . . _ . . . . . **d'._ .?"ES .{0{_ _, .. _91p0._ g AVAIL AVAfL 129 129 7:05 .. .._ T-00:55. . . l . AVA!L AVAll _ .. 129... - 129 . - . ~ , . . . T b0j45 ] AVAIL , AVdL,! _ _ 29 }[129[ 1 $b_. .J CH35.n . , _3py _, - _ _~ ,@yp%_ , ,,_ _ __,129. .,,} 29 , 7:30.. l_ T-00:30 . .. . _ . AVAll . ._L . _ AVAIL -- ._..129 .. __129 _ ~ 'Ii46~ 'T-06:25' AVAf[ dU'AtL' ~ '129 ~ l ~ 55 ~ i45 ~ T'05:55 ' ~ ~ ~ ~dV IL ' AU I~L '"i5 ' ~ f 125 ~ O. O ~ p,y,[ __ hp(,]. ]29],{_1W .7:55 T-.-00.05.__ . 129. 129 .. . _. %VAll_ _._ .. AVAf L_ _ ... . _ 3:10. . _ . _.... T + 00:10- .. _......t-._.L AVAt 7 AVA! ...._L..._.._ _- 1 _ _29._ .. 12.9 8:15. T+00:15 .. AVAll AVAIL { 129 129 R:20 T+00 20, AVAIL AVAIL _,,_ _ , . _129_ 129 , B:25 AVAIL AVAIL 1 _ 29_ . . .1_29-- . .T+ 00:25 . . - - -. -_ ~ 8:45' . . ' T A0050 .. - . . " _ .- .V IL_ _._- _ UAIL.__ -_7 59~~ ~~i- 12 .. a_ . . .- _. . _. _ . L . _.. _ _ _ . _ . l '29 9:10 .- .. T+01:10 - [ - - . V - . ll .- VAll i _ 529_., _ 9:20 T+01:25 AV^ 8' . AYAll 129 129 9:30 T+01:30 ~ - TAVN ~' dU i '~W~ ~ 1 5' 1 "535' T A01:35 ' ' iS - ~~NVAIL ~ ~ 159~~ I5 ~ l *** AU l[~ ~ ' ~ i25 ~ " I29 9 50 i+0'1540 ~ ~ UAtt~ ~ ~i29~ ~5 ~ O 45 ~ T+01:45 "A % . . 1 ~ hdL ' ' 9:50' T'+ 0150 AV I ' ~ ~ '129~" 129' SiSS ~T+01:SS ~ AVAIL [' ~ ' AV I((' 129 [ i29 10:00 T+02:00 AVAll AVAIL 129 129 10:05 T+02 05 l AVAit ~' ~ ~~AVhlL~ ~~129~ ' 16 " o Wm4 El RCist:T1.11)TSUM 'U 4-19 Re P/6/92 -OPERATIONAL DATA SUMMARIES 1991 l' ORT cal.llOl!N EXERCISE PI, ANT DATA StiMMAltY Tune Elapsed Tame Offsne pwr 345 i Offsste pwr 161 t DC bus 1 DC bus 2 'US 5 _.10:10 . . . _ . _ . .T+ 02:10 AVAfL . _ . . . . AVAIL i I29 '129 _]k{ ' 1[ ,.[ ^ +k2 [ ,.. AV3{ 129 i[, 10j20 ._ T+02:20 j AVAfL _ AVA!L_ _ j_ 129__ 1g5 T+ , ,-_p2:25, , {, ,, ,AVAtt AVAIL _ . _ } , 29 j 129 . 12:30- AVAfl. 129 129 l T+ 02:307 AVA}L _ _ [ _ 10:35 } T+02:35 AVAlL AVAIL - f( 129 j 129 '~ AVAti ' 129 3 ~i[ 10i43' II+h2:40- 'AVAU'~ "1055 I TA02:45' VAit ~ - AYAIL~ ~129' l 129 ' AVA!L _ AVAIL _ _,29 1 _ 1, 29 p5[ 10:55_ T+02:50. T+02:55 ,Iy AVAIL AVAIL , 129 1 129 11:00 T+03:00 AVAll . AVAtt 129~ 35~ 11:05 -.. T+03:05 .~ AVM AVAtt . - - [- 125. ~.- 129 ... ., ..._ . . . ~ . . _ 11:25 T+03:25 AVAIL ~ AVAll b I2i [29~ ~t id6 TidO3:30'~ ~~ ~NVAll ~AV IC I ~ 1U9 ' 129 '~ V II AVA 529 1h35~ Y+03335 f 7 29" . b 3 _._: . _O ._ 7.. .._ . E . . _ I 29__ 11:45 T+03:45 AVAIL AVAtt 129 ; 129 11:50 __ +03:50,, T .A , VAIL , AVAtt _} 129 { 129 11:55. T+03:55 AVAtt AVAtt

129 1 129 1220 T+M:00 AVAIL i AVAIL 129~ " ~ 1UU' warm acistcru n rst a1 xis . 4 -20 Rev. 8/6/92 - .s

e l. x p Containment Pressure (psig) I- 'd - o. , 3 ' g;; g g g g .x 3 x. . 4 7-05 l l $ 7:10 + ; l' A 7 15 i . m .4 720 1 ,

- 7 2$ i '

!C .?-

/ 7.30 ', !?

? 7.35 a , ~~ 7.40 1 ; jO . 7 45 w 750 4 . %): !- 7.55 i . l !C 8 00 ? l '... , !C 8 05 - IZ 8:10 i - - ~ ~ 8:15 4 '5 8.20 4 iN 8 25 +. . Pn 8 30 I 8 35 -- l 3 %__

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4 T. --9

'g 8 55 f , jq O gr 9 00 - 4 C7 l' 'g 9 05 y _ , jK >' 4 910 + .

19 E E

'l 915 y M 9 20 + 3- !Z > 3 k 925 y l Z -i

u. 9 9 30 + ,

'm 7 d l 3 935 4 l4 'A ~3 - 9 40 ? ! l i" O l 9 45 -- 9 50 L l l d3 fy 3 o 9 55 + + O> 3 1000 1 ,' !$ % E 1005 4 ,' F~ -i 10.10 i * !> I2 10 15 l 10 20 l d^ C py 10 25 + ,' el' = . 10.30 ' ; ly 7-10 35 + - jZ O 10 40 j l lC to 45 t , 7 10.50 4 * :M . f-1055 4 - '"A' H 11 00 1 -

m 11,05 1

/ !C" 11:10 i / Id 11:15 1 11:20 1 < 11 25 I .***'.** -

1130 1- l .-

4 1135 +i y L- 11:40 ' - 11 45 l N 11:50 t ,' 11 55 i - 12.00 -. - o g -. -. u y . 8 8 8 b y Containment Temperature (*F) - 7 N A . 0. i

Q Temperature ('F)

, y -E o b N $ b b k o 3 7 00 - 2 > 7M , 7 : 7,10 a, t 2 7 15 , I j ; 7:20 4 9 ! ;f ; 725 4 .d 7 30 + E' l *- 7.35 + e ,yg l. 7 40 m . t " ,' . 7.45 + i

7.50 7 _l

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n .? j p 'j 910 + 'E ,I 915 e re e a t y 9 20 t , jm- ;;.' a i l .*I g' 9 25 1 9 30 i e

C y N j _

e " , 3 -F e lC C i l 9 40 a lT ~ > e f -l 9:35 4 9 45 I 1 id 5

9 50 y I '

!) y l 9 55 a i :g g o 10 00 - l im - j f, 1l 10 05 a 10.10 i iN h !> 2 '#l 10:15 i ! MO l5 ji G 10 20 - l j 10OS y g im ". I 10.30 i g "A O i 10 35 L C ~ ! 1040 1 l i 10d5 e %'

10 50 s h 1055 1' -

d 11.00 h f A 11 05 i e ! 'd 11.10 y e i 11 15 + l I '1'20 1 i i 11 25 i i i 11:30 l 1 11.35 f

1140 1 11,45 i

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S 30 e --f l'> C' . n". 4 8 35 a st~ t : O 8 40 %% - 8 45 ( ~ ~ gy 8 ,; - ig- 8 50 - 17q 8 55 a i ~ *'Z , , 9 00 - lg s, 9 05 + y == {$ 910 + - : 9 15 .- , X-f 'a 9 20 a 4. i } ,') lg i q# g tJ < i { 9 925 30 +- . I y; l 9 35 e ! lZ C l$ 2 h 9 40 a ,' . f3 M 1 - g 45 4 1

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10: t o - , ?- <O 1015 a tr 10 20 - , f =- 10 25 a' - i 1030 1,. }g O ~ 10 35 a N i q!' e to 40 e j g% {j 7 l i 104s + 1050 a 10 55 a I ,m f! l 11.00 4 11.05 a - l 1110 a ,1 11:15 A' 1120 a - 1125 4 1130 a 1135 4 11:40 4 11:45 4 11:50 4 1155 a 12 00 a a cc i-t , OPERATIONAL DATA CONTROLLER MESS AGES - OPERATIONAL DATA An example of a controller message containing operational data is included under this heading. These controller messages will be issued to participants only upon simulator failure. A complete set of messages will be issued at the controller briefing. These data sheets are not intended to represent any specific ERFCS screens. The data presented here is a compilation of critical parameters of operator interest, drawn from several different ERFCS screens. NOTE: The examples provided in this scenario submittal are only examples to depict the layout and con 5guration of the screens. The actual volume of screens to be available for the exercise will be produced from the tables of data. The data reflected in the examples enclosed may not necessarily reflect actual exercise data. G:\6085\MANUAliTOC#4.WP5 4 - 26 Rev. 8/12/92 - . =_ _ CONTitOLLEll MESSAGES - OPERATIONAL DATA (cont) REAL TIME 7:30 ELAPSED TIME 0:26-lRCS Parameters l

1. PZR Pressure 0- PSIA 2 PZR Level (Lt 101X) 00 %

3 PZR Liq T(mp' Steam Temp 0 0 DEGF. 4 PZR Heaters off S. RVL MS 0 % 6 CET A<e O DEG F 7 CET Hi 0 DEG F

8. Subcooled Margin 00 DEG F 9 Letdown Flow 0.0 GPM 10 CEA's Not Fullin 0

11. WR NI Pwr. 00 %

l LOOP 1 .l l- LOOP 2.. l l Loop Pararneters A B C D l

1. T Hot (DEG F) 0 0 T Cold (DEG F) 0 0 0 0 3 RCP Status 0 0 0 0 4 SeG Press (PSIA) 0 v

5. S!G levet (NR) ~ 00 00 6 S/G Level M'R) 0 0 7 Steam Flow (MLB HR) 00 00

& Feed Flow (MLB/HR) 00 00 9 MSIV Status 0 0 10 AFW Ficw(GPM) 0 0 l Engineered Safeguards Features l 1, Containment Pressure 00 PSIG Temperature O ~DEGF Dewpoint 0 DEGF Hyarogen Conc 0 %> Cont. Sun.; Lvl (NR) 00 IN Cent Sump Lvt(WR) 0 FT

2. VCT Level 00 %

3. SIRWT Level 0 IN.

4. Equipment Status irain A Train B Train C (Is Bus) Total Flow / Pres.

DG D1 0 .D2 0 CHRG CHIA 0 CH1B 0 ~ CH1C 0 0- GPM HPSI SI2A 0 Sl2B 0 Sl2C 0 26 GPM LPSI S!1 A 0 $110 0 20 - GPM ~ CCW AC3A 0 AC3B 0 AC3C 0 CS Pumps S13A 0 Si3B 0 Si3C 0 0 GPM Air Comp CA1A 0 CA1B 0 CA1C 0 0- PSIG -

6. AFW FW 6 0 FW-10 0 l

6. Safeguard Signals PPLS 0 VIAS 0- 7. Plar.t Sinck Flowrate O CFM SIAS 0 RAS O l CPHS. O STLS 0 l CIAS 0 CSAS 0 CRHS 0 OPLS STBY lMaior Equipment Electric Plant l Reactor 0

- Turbine -0 Ctfsite Power AVAIL AVA:L Generator 0 DC Busses 0 0 Voits i l G 60M EXLRCISE PLTDATPG XI.S 4 - 27 Rev. S/6/92 se e OPERATIONAL DATA ERFCS DISPLAYS - OPERATIONAL DATA Examples of the emergency response facility computer system (ERFCS) operational displays are provided under this heading. The following displays are included: Status Board Page 194 Reactivity Control Page 200 Vital Auxiliaries Page 210 RCS Inventory Control Page 220 RCS Pressure Control Page 230 Core Heat Removal Page 240 RCS Heat Removal Page 250 Containment Integrity Page 260, h0Tfd The examples provided in this scenario submittal are only examples to depict the layout and configuration of the screens. The actual volume of screens to be available for the exercise will be produced from the tables of data. The data reflected in the examples enclosed may not necessarily reflect actual exercise data. A complete set of displays is included in a controller packet to be issued during the controller briefing. Displays are included for each time period included in the " Operational Data Summaries" Displays are to be issued to participants only upon proper inquiry of the ERFCS and must not be issued to participants before the time indicated on the sheet, ca60ssanuwcrocn.wr5 4 - 28 Rev. 8/12/92 s~s,

1. POWE R t E Vf L 15. CONT f LOOR LEVEL 0O rT A 102 00 8 101 536 %

C 101 920 D 802 617 % 16. CONT . PRE SS. - W1DE ( AVO 10 PStG . N AR. ( AVO 1.0 PStG 2.HOTtfG t OOP1 591 DEG F . L OOP2 591 DEGF 17. CONT. HYDROGEN 00 % 00 *r

3. COLD LEG LOOP 1 A 540 DEG F LOOP 18 540 DEG F 18.'A'S.G. LEVEL 19.9 79 9 %

L OOP2 A 540 DEG F

A* S G. FW FLOW 3,3 MLB/HR LOOP 2B 540 DEG F

A* S G. AUX FW FLOW O.0 GPM 4 SUBCOOttNGtSUPERHE AT O DEG F 19. "B' S.G . LEVEL 79.9 79.9 %

~B' S.G. FW FLOW 3.3 ML B/HR S. CET AVERAGE 586 DEG F "B" 5.C. AUX TW FLOW O.O GPM 6_ PRESSunr2ER LEVEL S8.6 % 20 ' A' S G. PRESSURE SO6 800 PSIA

7. PZR PRESSURE 2110 2110 PSIA 21. ~B* S G. PRESSURE 806 806 PSI A

8. RVLMS 100 100 % 22. BUS 1 A1 4160 VOL TS

9. # OF RCPS RUNNING 4 23. BUS 1 A 2 4140 VOLTS

10. LPSI FLOW O GPM 24. BUS 1 A3 4240 VOLTS

11. HpSt FLOW O GPfA 25. BUS 1 A4 4220 VOLTS

12. CONT. SPR AY FLOW O GPM 26. DC BUS 1 129 VOLTS

13. SIRWT LEVEL 189 IN 27. DC BUS 2 129 VOLTS

14. CONT SUMP LEVEL 14 IN 28. DG 1 O KW DG-2 O KW STATUS BOARD PAGE 194 S AFEGUARD StGN ALS l RX l lVAXl l 8 l l P l _

PPLS SfAS l Dr.51 14 OCT 92 CPHS C1AS DAS2 CRHS SMAS SS1 lCHRl l RCS l l Cl l' l pot l MODE SELECTION OS : 00 : 00 RAS STLS SS2 1 AUT OM ATIC CSAS O eext!Ni R(. !sISNt!!M1L194 NIS 4-29 ND2 , 1 ERFCS DISPLAYS ' JRATIONAL (cont) Reactivity Control, Page 200 PAGE DRAWING , RE ACTOR POWER DECREAstNG .= 300 CHEMICAL AND (# OF CHAN DEC) VOLUVE CONTROL 0 1 2 3 4 _301 BORIC ACID . " ELF START UP RATE (DPM)~ O 00 Fi2 _302 CONTROL RCD 0 1 3 5 7 POSITION ' TRtPPABLE CE A*S 303 'INCORE (* NOT Futt (N) DETECTORS 44 il5KM[IZI5iE'?CCiCIIIII!IEMEQ 10 20 30 4G _201 REACTIVITY CONTROL ALARMS REACTOR POWER (% POWER) EME.RGE NCY 102. lll BORATION -5 -3 -1 1 2 IN PROGRESS (LOG SCALE) YES REACTIVITY CONTROL PAGE 200 SAFEGUARD SIGNALS I Rx 1 IVAXl l t l' l P'l PPLS SIAS Dh1 MODE 1 14 OCT 92 CPHS CIAS DAS2 CRHS VIAS SS1 lCHRl l RCS l . [ Cl l' l l. MODE SELECTION 08 :00 :00 RAS STLS SS2 AUTOMAT!C CSAS (i 's.0x4 iM frCISLTAtit.2ta1XIS 4-30 8/6/92 S' . ERFCS DISPLAYS OPER+ JN AL (cont) Vital Aunifiaries. Page 210 AC POWER (VOLTSi 1 BUS 1 A1 4100 !!!!bli!E;Idisil@Ci$$ii!E Ql3],$2ECEli$Il!$$Z2!@lEfff[ETEQUj!?% PAGE. DR AWING BUS 1 A2 4140 Nili53RRElIJjiME];fdMiiETdd3$@ijTiCIEN'iffilyM?iP""M BUS 1A3 4240- $$$$ETEEdiMil!I3idM!MDMlI!$@$i33?"jiMSM1!DERE,iD!l , . 310 EME RGENCY POWER BUS i A4 4220 I!$dl!EU,E!iE!NEMETEj!!!llilIIES$$ETj!!Q!E!CIME!O3lUll0!OMiff,is!@D$ - (4160VI 3250 3500 3750 4000 4250 _311 EMERGENCY POWER (480V) 1 DC POWER _3I2 BUS 1 29 sigFgssgiE"$!!T15mEE!!T2n9CTjEr:32Mm3?R,1!:?.!srjirJ2E!!!!!!T5!!? BUS 2 129 Os$i!M!!!G!3EEipsIEE93@I!33335!!EIil53IE!!iEJili!!IITETWJsEH4 313 DC INTERNAL POWER 25 50 75 100 125 .150

314 COMPRESSED AIR *NSTRUMENT AIR (PSIG) 315 RAW WATER 104 UEif,GSE!$!!N!7lC$$iGMlj$!$$25lM!$siSES"EM";!71 25 50 75 100 125 150

. 316 COMPONENT COOLING ,317 CONTROL ROOM HVAC CCW PUMFS RUNNING 318 AUXILLARY BUILDING HVAC 1 lie @@@@SM 1 2 3 _319 SPENT FUEL POOL COOLING CCW CYSTEM 211 VA ALARMS . PRESS (PSIG) SS 3!!iIE!EilI2!!ECEUNil!!I!!3SEElil!3!IlC!%%MCEUSCE!EI2 25 50 75 100 175 150-VITAL AUXILIAlllES PAGE 210 SAFEGUARDS SIGNALS l RX l lVAXl l t l .l P l PPLS STAS DAS1 MODE .1 14 OCT 92 CPHS CIAS DAS2 CRHS VIAS SSI lCHRl l rcd ] l Cf l l l . MODE SELECTION 08:00:00 RAS STLS SS2 AUTOMATIC CSAS O % ORT l XI RCINIKTAt ;[:2l03f S 4 .3 I 8[b/N N- - S ei . w . M , . r a o. MM O pg g $ b$

r. , r= cIf4ls-a 5 4 O O O M

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J O OT ON P S EM RO N O 4 J

T HR E B C U R 4 F CLA M M T T T iW C CI X E A l l G X S _ A A A A OP U R l MR O S E A C A R E E F EO OA U P R V R P O R R R C C N T CM I l ? S A U E P T I C R A R E t \ H l l f 4 M F G 0 4 1 2 1 E x R ) 4 4 4 A 3 R R H C w P 3_ 3_ 2_ O l 0 I C EHFCS DISPLAYS OPERATIO _(cont) HCS Heat HemOvat. Page 250 SG LEVEL (% WRt PAGE DR AWlNG RC 2 A 79.9 Clis@@%DEayijliECEfj$iT2KIOD0"ICQEjTMi3!$E;Qii, TCMM T RC 2 A 79.9 $UUliCiTj%CICISIEti$ilIEE$EiES!!$TTCH3!$E0!300!$EGEihEEE M AIN STE AM RC 28 79.9 !!Ci30!ZEi$$$GUQdijil%7i![2!!$f%i$$iE5$$!!!ij2iFRf%Z[Q$ili;$ '350 RC-28 79 9 [iNEMIEE7CZj$i'U@ij$$y!!?is"C$'!OiE@Ij!!$$fj[jf@@$$l[EEC 20 40 00 80 100 351 SECONDARY STE AM 1 SG PRESSURE (PSIA) 352 5ECOND ARY STE AM 2 RC 2A 806 CSE!!![QiiiEf"[iME@ilIEZjCij$$((2!!U:@i!Q$iEQUll RC 2A 806 $!!!!3fdE*!MiMlIl@M"Mi%, % TE[$$Ci3i77E"djU'23!!CCE! RC-2B 306 tiiGi$$iPiRE!GE!!iliSE!$$3EEZ3%3$2KRT!Id!Ed!M CONDENSATE AND RC-29 806 [iffC"i!!!!S!!EPiii!25!!?!'E!EES'i"5"j2!!0GE!?E$liEI!'li"!ICi!E!EMI ~353 FEEDWATER 300 600 900 12N) MAIN FW _354 AUX:tlARY FEEDWATER FLOW (MLB/HR) RC- 2 A3.290 33iii$37@2i31!E!!!!33!$3s!Tji%!I@$'!MJEH3"!$i!1%# ~355 CIRCULATING WATER RC-2B3.295 GTd5Ei!$IC2EEEGEMiET!EifEZE1;ill!GMEsl 1 2 3 4 356 CONDENSER EVACUATION AUX!LIARY FEEDWATER FLOW (GPM) 251 RCS HEAT REMOVAL RC-2 A _O ALARMS RC 28 .O 50 100 150 200 250 300 T-COLD (DEG F) 475 500 525 550 575 ECO LOOP 1 LOOP 2 LOOPS 40 20$$$2$$@M[l$l$igiiE@iikEdEi!!ill!liCQj$$MZD$ilIQ3 HOT LEG HOT LEG LOOPS 40 LTffiliMiiiDMEEKjiji@23I!!]!$$il}.YG'Qi3ll"li@i@Iff0 MENS (DEG F) (DEG Fl LOOP S40 kj35lE?$MEli[i@$$5$Ei!E%$$35S@ST13f;2iEE2 591 591 LOOP S40 !!@s$$i$M$i$3SDZMEM@!RDil2$$ESSTll"IETMM 475 500 525 550 575 600 RCS HEAT REMOVAL PAGE 250 SAFEGUARDS SIGN ALS l RX l lVAXl l 1 l l P l PPLS SIAS DAS1 MODE 1 14 OCT 92 CPHS CIAS DAS2 CRHS VIAS SS1 lCHRl l RCS j l Cl l l l MODE SELECTION 08 :00 :00 RAS STLS SS2 AUTOMATIC CSAS G %0st131 Retst;1*Nirl50 NIS 4-35 8/602 h 4 ERFCS DISPLAYS OPE. IONAL (cont) Containment integrity. Page 260 CONTAINVENT SUNtP LE VEL PAGE DR A WING (AVE IN H2Of 13 9 E CiE!E M EiCl!.T.IG 7i 10 20 30 40 ~360 FROCESS MCNITORS CONT A!NMENT 361 AREA MONITORS ARE A RADIATION MONITORS (#1 362 CONT AINMENT SPR AY IN ALARM O

N ALERT O ,

363 CONTAINMENT HVAC 2 4 6 8 _364 CON T A'NMENT CONTAINMENT ATM R ADI ATION _261 CONT AINMENT INTEGRITY MONITORS (#1 AL ARM SETPOINTS IN ALARM O !N ALERT O 1 2 3 4 5 SECONDARY RADIATION MONITORS (*) N'JMBER OF CONTAINMENT IN ALARM O VALVES NOT PRESSURE WIDE IN ALERT O IN CI AS R ANGE (PStG) i 2 3 0 1.0 CONTA!NMENT CONTAINMENT CONT AINMENT. PRESSURE SPRAY F342 SPR AY F343 (HI PSIG) (GPM) (GPM) 0.98 MH!!%7!73MiiTE%%!!Ilf"2GEMEZEUM O.0 0.0 -2 0 3 5 COMTAINMENT MAIN 1TE AM CCNi A:NMENT AVE TEMP RAD. MON, HYDROGEN (DEG F) RMO64 (CPM) (MAX %) 109.0 1.2OOE + 01 0.0 ? 4 6 8 10 CONTAINMENT INTEGRITY PAGE 260 SAFEGUARDS SIGNALS l RX l lVAXl l 8 l l t l PFLS STAS DAS1 MODE 1 14 OCT 92 CpHS CtAS DAS? CRHS VtAS SS1 _ lCHRl l RCS l l Cl l l l MODE SELECTION 08 :00 :00 RAS S'LS SS2 AUTOMATIC CSAS o wxi 3.xt acisicP,u;r.2c.ox,s 4-36 8/6/92 1-J - RADIOLOGICAL DATA - TABLE of CONTENTS , Page

TABLE of CONTENTS 5.1

RADIATION MONITORING DATA SUMMARIES 5.2 PROCESS RADIATION MONITORS 5.3-FING RADIATION MONITORS 5.7.

AREA RADIATION MONITORS - 5.10 - RADIATION MONITOR LOCATION MAPS 5.14-

DISPLAY - PROCESS MONITORS, PAGE 360 - .5.26

. ERFCS DISPLAY - AREA MONITORS,- PAGE 361 5,28

ONSITE PLUME SilINE WIIOLEBODY EXPOSURE LEVELS 5.30 ONSITE PLUME SIIINE SECTOR MAP 5.33

LOOSE SURFACE CONTAMINATION LEVELS 5.34 LOOSE SURFACE CONTAMINAT1GN SECTOR MAP 5.37-ca6on.txtactstioocsvroc5375 5-1 - REV. 8/13/92

.- . ._ _ ~ - - - - -- .. - -. - .- -. , . . - A q RADIOLOGICAL DATAE .- RADIATION MONITORING DATA SUMMARIES Radiation monitoring data summaries are provided under this heading. These summaries are for use by controllers as a reference only. Participants have acces's to all-this data through the emergency response facility computer system (ERFCS) on . screens 360 and . -361. Examples of these screens is included in this scenario. - The :,ummaries are divided into orocess radiation monitors, PING radiation monitors, and area radiation monitors. A' set of maps is provided that depict the locations of the pre:ess and area - radiation monitors. The summaries include data for background levels, ALERT and HIGH alarm setpoints, and the setpoints at which the ERFCS considers level as being INVALID LO or INVALID Hl. These various setpoints are depicted in the summaries utilizing the following scheme: - INVALID LO - indicated with " 7": i.e. 0.00E+00 ?.- ALERT indicated with "* ": i.e. 0.00E+00

HIGH indicated with "" ": i.e. 0.00E+00 "

INVALID HI indicatec with "**?": i.e. 0.00E+00 "? Out of Service indicated with "OOS" - The three- RM-063 process monitors, RM-063L, RM-063M, and RM 063H, each share a > common sample _line and are designed to switch b( . ween the three monitors as certain setpoints . are reached.- When not sampling, the monitors are in standby mode. This'is indicated with? " standby" in the summaries. Iodine and pan ulate calculations have been calculated under the assumption that all charcoal cartridges and particulate filters were replaced and are new as of 0730. _ Cumulative buildup , of iodine is presented in the radiation monitor summaries _'(travel time for moving particulate (filter paper is taken into account in the calculation); If participants replace filters at anyl time-during the scenario the activity buildup on the new filter starts at background at the time 'of replacement. Example: Participants replace the iodine cartridge'on RM-063 at-1100'and again at 1400. What is the iodine activity on the cartridges? , Solution: Actl100 (activity @ 1100) = Actl100 - Act0730 - Solution: Actl400 (activity @ 1400) = Act1400 - Actl100,- ca60amEnctsstoocssToc5.wr5 5-2 REV. 8/12/92 8*" RADIATION MONITORING DATA SUMMARIES PROCESS RADIATION MONITORS <rm Process Radiation Monitors RM-050.RM-05I RM ese RM 45I ILM 492 RM053 RM 454 A ILM 444B tat +e

- epen etum etsu es== egen epen

_8k E *d_ 3 J2E + 01_. 48%E+07 6_90E + 0i 3 50E + 03 1.58E+02_J 44E + 02_ . . is,14 I mE + 01 ? I onE+0i 7 1.00E + 0i ? IamE+017 1.mE+01? IME+01? , , N .\_ 9 , Y Alert 3 5AE+04* 7.17E + M* 2.50E + 01* 1 66E + 04* t onE+05* 1 10E + 01* {, . Y . High S ME + 05** 8 00E + 05** 1.NE+ 06** 2 97E + 04** 1 27E + 0l** 1.46E + 01** im* m -- I , Ili ivwsE4 M **t I onE + M**? I imE + 06**1 100E + 06*" l 5mE + 06**? 8 00E + M***

p+> wg i + M*4 w) R.M &O 7.30 7 41 3.21 E + 01 122E + 01 4 #9E + 02 4 89E + 02 6 90E +0!

6 90E+0i 3.50E + 0) 3 ME+01 1.5M E + 02 1.5tE + 02 3 44E+ 02 3.44 E4 02 i a, + et p)M ^w # ~ o - . ~ I M+NM"J ; - RM(Mt 8 00 3 22E 4 01 4 89E + 02 6 90E + 0i 350E+01 I .5 AE + 02 3 44E+02 8:15 3 *2E + 01 4.89E + 02 6 90E + 0i 1.50E + 03 1.5tE + 02 3 44 E + 02 8 10 . 3 22E + 0! 4 99E + 02 6 WE+01 3.50E + 05 1.5#E + 02 3 44E+02 .- 8 45 , ' N *C 3 ML + 04*_ 7. 27E,+ 02_ 600E+DI 150E+0) .I SIE+ 02 3.44 E + 02 _ 9 l'4 2 29E 4 04 9 64 E + 02 6 00E 4 01 3.50E + 01 1 SSE + 02 3 44E+02 .- 9 15 t 02E+05* l 20E+03 6 ME + 0i 350E+01 1.Ss E + 02 3.44E+ 02 t erw.m - 9 40 3. 39E + 04 't.41E+03 6 90E+ 0s 3.50E + 01 1 5sE + 02 3 44 E + 02 7. m se e, ,e ,e lee so lo ne n:e 2m s:.le 9 45 1 42E + 05* I 67E+ 01 690E+0i 3.50E + 04 8 59E 4 02 3 44E+ 02 to Oo i2NN 04* I 90E+01 6Mii+T150E + 01 1.5NT02~i UEis cra Process Radiation Monitors RM-052.RM-053 10 15 I 71E+ 05* 2.11E + 03 6 90E+01 3.50E + 01 13RE+02 3 44 E + 02 10 30 5 01 E + 0s* 2.ME + 01 6.90E + 0! 3.50E + 01 15AE + 02 3.44E + 02 , ,4 .,7 10 45 2 05E+ 05* 2SRE+03 6enE+0! 350E+04 1 SEE+02 3?'E+02 11 00 $84E+o4* I 88E401 6 90E + 01 - 3 SOE4 01 I 58E+02 3 44E+02 t am.m II- 5 5 I OnE+04 5 54E+02 6 90E + 01 3 50E+01 1.5 A E + 02 3.44 E + 0? i at .as -] , il 10 129E + 01 5 OR E+ 02 6 90E + 01 3.50E+ C3 5 58E+02 3 44E+02 ' il 45 3 42E + 01 4 91E + 02 E90E+0i 3 ME+03 1 59 E + 02 3 44E + 02 12 in 12-15 1.29E + 03 142E+04

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g_f4 g._ "I g4 Q4 - 12.10 3 29E+ 01 428E+02 6.90E + 0! 3 50E+01 1.5M E + 02 3 44E+02 ; _ 12 45 3 4?E+ pt 4 tRE + ff2 6 90E +01 3 59E+ 01 I $nF+02 144 E + e2 g ent .e? cy 5777 7 yf g y t . .t I I- I I I: I I l.. 1 16 se SW em 9M 19e 96 W 11 6 81 18 32 6 12 18 crm Process Radia: ion Monitors RM-054 A.RM 054B IRE +m i - e I RE + 07 j1 t nW +416 t SE 481 O RM &4A 1 eE +04 i .w RM &48 ,__________j.__-_______s 1 .e, , y ,g g i at .c2 MJJJJm%%%%%%%%%"Js N%%) ' - ~' ' - ~ - - RM C50 cima aim part R M C53 component ce=6ng water , , , , , RM 0$t came atm gas R M -054 A 5/G A blowdown RM 042 stad ree R M 4M4 R 5/G B blowdown t est .m . _- ,L.. . _,- - _d_ _

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G:Wm4\ EX E RCIS B R AD D AT\ R AD PCS I . X LS 5-3 Rev. 8/I3/92 2 ,u - RADIATION MONITORING DATA SUMMARIES PROCESS RADI ATION MONITORS cpm Process Radiation Monitors RM-055,RM-055A RM 455 RM455A RM4%4 RMe%B RM457 RMe*9 s ea +es . . - - D"" epen egen evue epen egen t =,sh'~s2.=C==# r== m,4 ), km=ke,=fe,,(M.(=.A N= sh erem Rk 5 ME + 04 5.16E + 01 5 SliE+02 5 30E + 04 3 70E + 0i 129E+02 ~~ l - d ; .. I . ~le,gnd ! . Im I 00E + 0! ? 100E + 01 7 1.00E+0! ? I 00E+ 0! ? 100E401 ? I onE+ 01 ? at .os Alert 6.70E + 04* 500E+04* 4 40E4 03* 8 10E + 04* 4 00E +0i' l .69E + 01* jPjPP~W* * .W W Iligh 7 ME + 04" 6 55E+04" 5. 50E + 03 ** 900E+n4" 3 60E+04" 3 05E+ 01" lav Ili I emE + 06*** I mF + rm**7 I onE + 06**7 1 00E + M*** I ME + C6*** I OnE + M**' 8 " * '3 -"' P O gM.o5$ 7:30 5 Mii+ 04 5.16E + 01 - 55AE+02 530E + 04 3.70E + 0i 3.29E + 02 4 f ~ 7.45 5 35F +04 5.16E + 03 5.5t E + 02 5.30E 4 04 3.70E + 0i 129E + 02 RM455A 8 00 5.35E + 04 Sl6E+01 5 58E+02 5. 30E + 04 3.70E + 0I 3.29E + 02 n- 15 5 ME +04 5.16E + 09 5 58E+02 5 30E+04 3 70E + 0i 3 29E +02 ' ' 8 30 535E+04 5.16E + 03 5 58E+02 5 30E+04 3.70E + 01 3.2*E + 02 ,,g.,, __ 8 45 5 ME+ 04 5.16E + 03 5 SRE+02 5. 30E + 04 3.7eE + 08 3 29E + 02 9 00 5.ME + 04 5.16E + Cl 55sE+02 5 30E+04 3.70E + 0i 329E+02 ' 9 IS 535E+04 516E+ 01 53aE+02 530E+04 3 70E+08 3.29E+ 02 I anr +as - 9 10 5. 3 5E + 04 5.16E+ 03 5 5tE+02 530E+04 3.70E + 01 3 29E + 02 9, se sw ,e , , ,,e ,, e ,ge g,.m i;m 3 2. . 9 45 5 ME + 0a $ 16E + 03 5 58E+02 5. 30E + 04 3 70E + 01 3 29E + 02 10 00 515E+04 5.16E + 03 5 58E+02 530E+04 3.70E + 08 3 29E + 02 rem Process Radiation Monitors RM-056A,RM456B 10 15 5 35E+ 04 5.16E + 03 5 5tE+02 530E + 04 3.70E + 01 3.29E+02 10 30 535E+04 5.16E + 01 5 5sE402 530E+04 3 70E+01 3.29E+ 02 , , , .. , , 10 45 5 35E+04 516E +01 55tE+02 530E+04 3.70E + 01 3.29E + 02 11-00 535E+04 5.16E + 01 5.58E + 02 5 30E+04 $;70E+ 01 3_29E + 02 l aw .e6 18.85 535E+04 5,16E + 03 5.58E + 02 5. 30E + 04 3.70E + 01 3 29E + 02 .f _ j- ; j ;_ . u 8 8* **5 1930 535E+04 516E+03 5 58E+02 530E+04 3 7DE+0! 3 29E + 02 ,,,,,y,,,,,;_ g 9g,,,,,I: 4 II45 5 ME+04 5.16E+03 5 5tE+02 530E+04 3.70E + 0i 3 29E + 02 c+I ' ;_l ' ~

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'I I ,,,,,x 12 00 5 ME+04 5.16E + 03 5.5AE + 02 530E+04 3.70E+ 0! 3 29E+02 RA44%B 12 15 5 35E+04 5.16E + 03 5 54E+02 530E + 04 3.76 + 01 3.29E+ 02 s am .es ' 12.30 535E+04 516E+01 5.58E + 02 55AE+02 5 3GE+04 5 30E+04 370E + 01 3.29E + 02 3 79E+ 02 t mE +e2 WMQ X j N K"*dW M 12 45 i ME + 04 5.16E + 01 3 70E + 08 , l: tMWem + 7.10 Se 8 10 +e 9W tem t# W tte II:D 12 6 12- 2 ' ccm Process Radiation Monitors RM-057,RM-059 iee.= I at +e7 1 1. - . -. . . . . . . t me +.s RM457 i t0 _ _ _. RM C50 - t at +el -w , m. ,- i M nie.e twriss i : t ant .e2 efM , (~f ,~ ~ > ( ~ ,"< , ; [j > f y . T-- ~f~ '~ ' ~ ' N M 055 werkarif headcr RM 4568 raw water , T-RM OSS A overbord header RM 057 cewmfemer RM 046A raw water RM C50 waste ca.ncerdrat<w t ans .as - . t TW se s us em *w tem te m sie ti w f2e 12..es d G:\6084\ EX ERCIS E\ R AD D AT\R A D PCS2.X LS 5-4 Rev. 8/13/92 -m r ' l , N Y _ - N, g l. - - m !, Iw, su k k ~ (- "3 g s x a u = - t u () < J J n . . E y - g C [ y m s y- , - -- -- -- .- -- a _ _ , j ~Y gh Uk f { , j O -. _-, y ! 3 , ; -- ) I. O' /y.p . - N ,e ,I y 4 g :: m g y- - ,-

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BBB9BBBB. + +++!++ + iil. iii:iiiiiiiii . . .l7 7 7 i'}7 7 7 7 +l+ + + +v+ + + + + + + + y }, n U x I6k N;5 9 W W s, If$ $ k h $ $ $ W ;W ;W W W'W W W WiW W W W i * ** W m 9exc e e r e - e;e r r a; ;ss w a g a r. E ss; x - . O _ -,----.:---m j m aau w s l l - Y h f$ $ $ R $tb b BIO b$E F tj<=j k$~~l'.$$Re = =je + e ej* t *:: $j00": } E i ! , o do RALIATION MONITORING DATA SUMMARIES PROCESS R ADIATION MONITORS cpm Pn= cess Radiation Mostors RM-0631,RM-06_tP RM 4438 ItM463 P R.M h4 ( A) ILM 4h5 Eto214-1 RO?!4-2 g ag .co , W - G. _ }; Tame l. e s== e s== tram e s== es== < r== Baged t 00E 04 I 00E 04 1.2eE + 0i j 8 00E+01 I tml + 05 346E+05 , ~lme Im N/A N/A 1 UnE + 01 7 1.00E+ 01 7 1.(stE + 0t 7 I 00L + 01 7 : a+ et . Aleet N/A N/A N/A $ OnE + 02* 2.9wE + 05* 9 20E+ 01* Itegh N/A N/A N/A I 19E+ 01** 9 196 + 05** 3 20E + 04** Inw fli N/A N/A I 00F + 06"' I tmE + 06**7 I fmE + 06**? I (Nt!' + 06"7 IM ' - ~~~ ~ ] gy g3g 7 10 100E 04 I WWe4 120E+ 01 8 toe +01 1. 57E + 04 1R6E+01 7 45 100E 04 10nE 04 120E+ 0! 8 00E + 01 1.57E + G4 I *^E + 01 _. _p_ RM m3p 8.00 1 00E 04 1 OnE44 1.20E + 01 8 00E + 01 157E+04 186E+01 :.g. j 8:15 I (ME nd 100E 04 1.20E + 0! 8.31E + 0i 6 18 E + 06**7 8 20E +0$** S il9E+06"? 8.16E + 05" l_ 8 10 11eE04 t onE ue I f.0E + 0 t 8 000+ 01 , ,a yg g . .. gggggg 8 45 100E 04 1 OnE 04 t 17E+01 8 fu)E+0s 5 57E+(4**7 t8.IIE4 05" l. { . 9.00 I sufE 04 100E 64 1 51E + 01 8 onE +0i 514E+ 06"? 8 07E + 05" {' - l 9 I$ 1 (CE 04 100E-04 I 70E+ 03 8 00E + 01 5. I7E+ 06"? 8 04E+ 05** i me a; I 1 ' 9:10 t onE 04 100E 04 8.86E + 01 8 00E+03 5 04E+ 06**7 a 00E+ 0$** Tw em te em *w tem sa w sta sLe s2m 12 m 9 45 1 OnE 04 i OnE.04 202E+01 8 00E+t . 4 94E+ 06"? 7 96E+ 05" 10 00 i etE 04 100E-04 2. t BE + 0! 800E+01 4 87E+06"7 7.91!;+ 05" (Pm Process Radiation Monitors RM-064 (A).RM-065 4 S I E+ 06**' 7.90F + 05" I0 15 I c0E 04 100604 2.34 E + 0! 8 00E + 01 ! : }' ' 4 77E+06"7 7. 87E+ 05" 30 lo 1 n0E 04 100E44 2 50E+0! 8 00E + 01 , eg .,y 10 45 1 (W.1F-04 100E 04 2 66E+ 0! 8 ODE +0! 4.71E + 06"? 784E+05" ' ~ ~ 11 00 100E-04 5.DeE-04 28tE+08 8 00E + 01 4.70E+ 06"7 7 81 E+ 05" e as +es 100E 04 100E-04 132E+0i 8 0nE+ 0i 4 68E + 06"7 7.78E + 05** :} 11:15 . _ . _. 100E 04 100E04 1.26E + 01 8 00E+0I 4 66E + 06**? 7.75 E + 05" an'.es _ I130 11 45 100E 04 100E 04 5 76E+01 8 00E+0! 4 64E 4 06**7 7.71E + 05" W 12 00 1.00E04 3.00E04 1.26E + 01 8 00E+0i 4 62E+ 06**7 7.70E + 0$" 4 6tE4 06-*? 7 67E + 05* Y UM !? 15 I 00E 04 1.00E 04 1.26E + 01 8 00E+01 , mg . ,, 12 30 100E 04 3 00E04 1.26E + 0! 8.00E + 08 4.ME+ 06**? 7 65E+05" l.

_,i 17 45 t #mE-04 1 tmE 04 126E + til 8 OnE + 0! 4 in E + 06"? 7 62E 4 0%" i aE.c2 ,, .,y y M i.,y - y g.,,,.L M o<k 11I ,

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None RM tw.4 emhnge are for genernene A enemi ecem he der only. Mesi iram traternwa e . _ , .

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RM M31 statk i = fine cartndge RM M5 contnit n=wn L= tine { , R M udP stack pa t filter RO214-1 failed fuel, gamma RM /64 ( A) snsin wesm RO214 2 feited fuel. Mne i ras .m - .- l - -- - tm .. == .. ,= iem ie n uw n.= um uw G:4084\ EXERCISE \RADDAT RADFCS4.XLS 5-6 Rev. 8/13/92 J- 'd RADIATION MONITORING DATA SUMMARlES PING RADIATION MONITORS -- cpm Ping Radiation Monitors RM-067NG RM-0671 RM ae7NG RMeen RMea7r ' teas Rm.Sr; vest Ret Vees Rmr a mE +e)

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_Fkgs4 I OnE + 02 1.25E + 02 1.2SE + 0? 2 50E+ 01 { 8.50E + 01 650E+02 In* Em NtA N/A N/A N/A N/A N/A

Alert 3 00E+ 02* 2 0nE +03* 2.00E + 01* 5.70E + 02* 2 DIE + 02* 148 E 4 01* . . A s __ a tigh 4.10E+02" 3 00E+03" 3. 5 5E + 01" 3.83E+ 01** s30E+02" 3.28E + 03*. 1 mE +02 kW 'M

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ime !!! N/A N/A N/A NtA N/A N/A u RM O67NG ~ 7 to . I tut + 02 3 2SE+02 1.25E+ 02 2.50E + 0! l 8 50E + 01 6.NE+02 _ 7 45 ' I 00E +02 125E+ 02 1.25E + 02 _2.50E + 01 18 50E + 01_ 650E+02_ . ^ RM4671 . 8 00 1.00E +>32 1.25E + 02 1.25E + 02 2.50E + 01 8 50E + 01 6 50E+02 , _ 8.15 t OUE+02 125E + 02 1.25E + 02 2.50E &of a 50E + 0! 6 50E

02 8.30 - 100E + 02 1.25E + 02 125E + 02 2.50E + 01 8.28i+ 0! 6 50E + 02 - -

8 45 100E + 02 125E + #2 1.25E+ 02 2.50E 4 01 8 50E + 0i ' 6.50E + 02 9 00 3 OnE+ 02 125E + 0? 12SE + 02 2 50E + 01 S ME+ 01 6 50E + 0? 9-15 10nE+02 1.25E + 02 1.25 E + 02 250E+01 8.50E + 0! 4. 50E + 02 g en en , 9 30 100E+02 1.2S E + 62 1.25 E + 02 2.50E + 01 8 50E+01 6 50E + 02 ,, ,, ,, ,e ,e nom ne w lies iN t2m t2_e 945 1.00E + 02 1.25E + 02 1.25E + 02 2 50E + 01 8.50E + 01 6 50E+02 10 00 tone +02 1.25E+ 02 1.25 E + 02 2.50E + 0! 8 50E+0! 6.50E + 02 erm Ping Radirtion Monitors RM-067P, Vent Rm-NG 10 15 I OnE+02 1.2SE + 0? 1.2SE+ 02 2.50E + 0! 8 ME+0! 6.50E + 02 ' Fj 8 50E+0! 10:50 I .OnE + 02 1.25E + 02 1.25E+ 02 2.50E +01 6.50E + 02 , g . ,, to 45 3 00E4 02 1.25E + 0? t.25E 4 02 2 50E+01 8 50E + 01 6.50E + 02_ !! 00 I AW)E + 02 1.25 E + 02 1.25 E + 02 2.50E + 0! 8.50E + 01 6. 50E + 02 r aw *as , a1:15 100E+02 1.25E+ 02 1.25E + 02 2.50E +0! 8 50E+01 6.50E+ 02 l, _ . . 11.30 100E + 02 3.25E+ 02 12SE + 02 2.50E + 01 8 50E+0! 6 50E+02 s aw +os n ~ 18 45 100E + 02 1.25E+ 02 1.25E + 02 2.50E + 0! 8.50E + 01 6 50E+ 02 - - 12 fl0 3 OHE + 0? 1.25E + 02 ~ I .25E + 02 2.50E + 01 8.50E + 01 6 50E+ 02 12:15 l ooE+02 1.25 E + 02 t.2S E +02 2.50E+0 8 5cE+01 6 50E+02 ' ~ ~ Y8 E* NU 3 ,g .,, .__ 124d 100E + 02 1.25E + 02 1.25E + 02 2.%E+01 8 50E +0! 6.50E + 02 _. . .. . .. . 'q #O[ .~ -- '- 12 45 100E + 02 3 25 E + 02 125E 402 2. S+ 0i 8 50fi+0! 6 VtE + 0? ImE

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s. -- g e. I. ' w. n.- .s.y-s.E.- w.iW w ? . W.s I..nS. w f. W n. W . I. Ww 's. . . .. $ - G , *. f ~~ ~ (it 22 < O () y= , *~ $. 3. %. *s g. *g ). gg;*U.999999999.E. gyg*WW W W W.W.W. E.898.l69999 W. W. W.;W W. W. h ww ,te3s# c w__ ~~ ~ .. W_ W_ W W yyy e . __ _ .. .... .... 3 , , g a 10 t IJ 4s@55[ yj e . ? Ew $ 5Esissseg4Ess5545545 l 5$E 5" k w . $. $. 5 . d. e. 9.9 c. 5. W. 9;d. W. e. $ W E..5 5 e.1_e. , ,@, . .3 } . .. ._ - .i.. ...... . 3 ,3,y, g J l 6l ,].3 ;j ) =$3 i f as s ,- .8 :... s e. s.ECR. 2 seea B:8s! RE l de ] g y., g I . PROCESS AND AREA MONITOR LOCATIONS s mt - Tsc q sotiri J L I ( i L J t= ma l n d r r-Q l l e __ , ff F 1 a, ; 1 U 1 w:1L,:tsr. en:uzzzuens.r. l n 1 L,,, m l twm2_ . _, _ = = = - - - , .. an.+ ^ d n... _ /-PM-093 V-em E".u. ,A M.C" l / l l~ AN j 'N l } 'RM -067 RM-067 . PING L RM-093 : AREA MONITOR 7 o *su1 APHUMAU J1 APS WP5 d

~~14 REV, S/ 6'92~~

PROCESS AND AREA MONITOR LOCATIONS AUXILIARY DU!LDING (ELEY. 089'-0") j snt - hopiq c (DVEkHL A!O ~ - .s- - - Vw . . . -_ -01 sa Q'c----f Q Rv-CSLL4 TL i , l r ][ -' QRW-079 r - 4 P " m d.' ._ [~ ;j p ; I- <", d O\s\. l! l ]a pi.- // rf F ,- < O'.. VN s % . / e .- tu-C70 "Q ~; F u-078 . /j/ O gik \, i x _-i j' - \ '~ ,, , , 'Q- O O D f' l \ C lp) y 'r l orju <- t t(v s m i \ ' ~J O x O C~ sw_oS53; _ i0 // O -, ci _ Fu-055 d cr" r- ~ \ s'. s q{ J r'h [# j -/ // l C., ~D ~ \x i p /, l NN QL j)//' ,/ f&f l j l 05 - RW-07 7 $f% N wf f _lt d_- b I ^^ _ _.i J]f i 2 u l l I .I .h ? ~~ '~ !u-076 R ' ' '- I rt. n n n % r RM-055 . OVER BOARD DISCHARGE HEADER RM-070 ARCA MONITOR FM-055 A . OVER DOARD DISCHARGE HEADER RM-076 : ARCA MONITOR PM-056 A - RAW WATER HEACER RM-077 : AREA MONITOR FM-0550 : RAW WATER HEADER RM-078 : ARCA MON 170R RM-079 : AREA MONITOR O M4 M APflLES;ALLJ1APS WPs 5 - 15 REV. S/ 6/92 PROCESS AND AREA MONITOR LOCATIONS , AUXiUARY BUILDING (ELEV. 1007'-0" & 1013'- 0') A . Mil m hent 4 p T y2 ,q.,_a WT_.v- u g- _ _ % s I i I -_ a s i FW-063L & * ., I- { m ,. - - # j- RM- 0$ 3 h } .; ry. / a- c= w l 1,0. rtg - , .b O-(rw-cow .. F W-Ct3H p. g i I Jd f-- -. s.,,, f l g -]l " c. 'J- s *c'[-9 o '5Pv-0720*NQ 0%N s'. - l i r a l,: s- s I l L__rf i _ pu.on / -N. x ~~ , . 'A\b_!j _) _ ,_j - . ,o \ __._, / g d lb y'= ' _____; c I f /. j - H _ dl - pu-071 I l , , g Ru-2t4 \ \ '- l ( , ) J 1- "' [ O .l C - ' / C , , r. h-6 -q.p~w \x ; v ,/ ,/ H Itw-Ot44/9 // } l' \\y {Q- , p /j/ ; r, ANN [j / ,, - ~ ~ < o _L4 ' O ?.sc"te.xv iocr_ tr > l N_ # [ ! "h_1_ l $ i i Il hw-082 0-I C" _ _ _ ; 1 l e av.opQ Ru-oeo O b - t OF L m b wq ,___, , ta t_ __ , r, PM-053 , COMPONENT POOLING RM-214 : RCS ACTIVITY MONITOR RM-054A : STEAM GENERATOR BLOWDOWN Ru-057 : PING RM-0549 , STCAM GENERATOR BLOWDOWN RM-071 . AREA MONITOR RM-081 . AREA MONITOR RM-003l STACK AS NORMAL RM-072 . AREA MONITOR RM- 082 . AREA MONITOR RM-0639 , STACK As MEDIUM ACCIDENT RM-030 AREA MONlIOR RM-OS4 AREA MONITOH RM-063h ' STACK AS HIGH ACC! DENT a m mn n.usruyt An wn 5 - 16 REV. 8/ 6/92 i PIl0 CESS AND AREA MONITOR LOCATIONS , AUXILIARY DUILblNG (ELEY. 1025'-0") r-_- !El m N041H _a -___.-_s, _ _ , . , _ . _ - _ . . , , y i NmmmA 7- - / ~ 'U ,9 ,' 6 DQ3GN,N, U . //O t N s, p== ==m==r-- a e __,. l KW-060 Q , /:. O,\s p H w -ot,1 / .-- s \xg __ __.J p! ! k u - 0 62 ,' / ,' C \\ Qs x q s 'l ~ ( 'b c ?,< (%' b {O -, E, ir?- !N 210'. 11 7 ku-oso ,< ; 3 \p S $ &' a ' " ~ =g // e)),g-if kv-051' \n*](. ~7 l ** ' // l O6 I:Sd=I // p\ RH-088 $ \.Q ? cy},/ 6 \ lN O ,/,/ kke dl 1113 \Nk_ bgy/ {j -] N RW -Ce 6 " -f 4) i i l l t A ~ Aw-067 Q l 1 q _. rw-oeso- -- l n rt... L ._.n n n r RM-0$0 : CONTAINMENT PARTICULATE PM-085 : AREA MONITOR RM-051 : CONTAINMENT CAS FH-036 : AREA MONITOR RM-060 STACK (lODINC GAS) PM-087 : AREA MONITOR RM-061 STACK PARTICULATE FM-088 : AREA MONITOft FM-06 STACK CAS G- Mikht APMUT ARJt APS WPs 5 - 17 REY. 8/ 6/92 Pl;OCESS AND AltEA MONIT01< LOCA*Il0NS . AUXILIARY IJUILDING (ELEY. 1030'- U" ) y_ 9'r NC41H Q --. -r - - u_,_, ---- p - , e u m _ ] g ==- + l -l"r- - l y ,e -; ,/ *RW-0(4 ',-', ll ~ l (TL'kblNE 0U110!% Eltz 1036'-0') , ,,< '- (SOUTH FIDE TtlF 0lNE rc - D'3:ho Ettv 8 035'-(') OL N W-06L m ~ cu=Yn.w= - sk, m .) < , pW-DE9 l [ ' * ,,. - I=_f <-h~. - ,-D; j s .- # W-09 t A },- # / . ,a N' \ 9 ,/', RW-0?4Q ' i }' h ~ ( jl /[ 7y q , %so;o;y ; F, tUXATED IN TTACK) ~-e: oi1)l i \ '%O f ' C ] . .. . . .- __ . Y 4, ,]y ,y I f/ k u - o . 5 -- ' 'N ,j l d '? , ,he o;',' .; j 'NNQ' f,, ' i_ _ _ 4M-0910 Qs - / 9 -d r ] [.) LJ" L.I 5 fw ,g t u_- -- r- -' _ .,. ._..q l _. n. FLjt__._.D n n p r R4-052 . STACh C AS RM-0918 . CONTAINMENT HIC}l RM-057 . CONDENSER Off-CAS RANCE MONITOR RM-064 POST ACCIDENT MAIN STEAM MONITOR RM-074 . AREA MONITOR RM-06S : POST ACCIDENT CONTROL ROOM !ODINE RM-075 : Af1EA MONITOR RW-091 A

CONTAINMENT illGil f4NCE MONITOR RM-CSD: AEEA MON 110R G w*4 M APilLES'.ALLJ1 APs WP5 5 - 18 REV. 8/ 6/92

( PROCESS AND AIEA MONITOR LOCATIONS RAD WASTE DUILDING ) A "' E e = = = = _ _ _ _ . --- __ - _J i[TTpi~ 1101 044?S stop act pu.ogs ; , y g~ teetR - R ADiO* C th e [ UN,N RV-041 : CARP /kWPD EXilAUST j rtt4AlloH (PARTJCULATC) & ion t ec.uwcr RV-04: : CARP /HWPD EXHAUST noctSS NO (IODINE) 'I I DV-043 : CARP /EWPil EXilAUST i~ (NOBLE GAS) I ,,l$P,$7 _ RV-09b ARCA MONITOR waitk e;. RV-096 : AREA MONITOH S'0"

~~M,jf o RV-097 :- ARCA MONITOR a c_._.;~~

d RM-098 : AhEA MONITOR p .___ ._. - -_y [ ~ TO H,A 0T 1N CORRIDOR 4' 6 ] n..'lif_ n! l m ...___.s _ n J li! Rv-047 RM-042 l!I c== - Touce ' RM-043 i n F n,eou "y' [o Uy-F M -09 6 , y' ARCA MONITOR

~~g. , y FM-09,/ y 0 ,~~

ALAliM PANEL ^ ~~ ~~ -^ ^ ^^ ' .n t.crITSc l 7. ~~~ ~ ~ qll % rp J:--] '~ a HtPA l %[~ ,_ ] SUPP Y FANS d } _, ._ orrier l ORu-osa ' - 1 4 g . . - - - - - - , , Lg 510cA nt p.y @j E Ori tct H5 , ^=ra ,,t, - I costr erHct @ *$,TC n_j orner ^RLA s)l[% 5] [j2 g dj t - GE= GROUND FLOOR LEVEL MEZZANINE LEVEL c, m uarntos.Au.yiars.m 5 - 19 REV, 8/ 6/92 1 l>ROCESS AND AREA MONITOR LOCATIONS TURUINE UUILDING BASEMENT {%.-- M] ~~5$=g~~L, ~{ i

~~e. F k.J L.J 1~~

jl{ (D o o 0] l0CDOl l000Ol 7 i i W E .) s 0 y ]' p=r=:==1 .. - t j t [ t=n i ,ryy U ] ! th a ~ ! O v.na 3 1 ! {] L4 il ,_; _ i 1 ! I i_-.., ,_ s I 1 s1 1 1 L !b ~~ l .J "'l ', ~l-l[) ; E )) l 1 pj~ ' g i j h_, , ' a : rr 1r i i0 E ,! 7-- ..,

~~-.c y~~

1 l 1 [t, p ~ li" g=/) -f l _ J 9 ?1 f_ l , O' l't ) L-i i i[ <t 1 D b1 * ? o h a E2 = - rn Udj c. ~-- [l a 1~%'~^ n - ] 1 ri 0 t Gmam F- ' ' l ll l I 4 0 I d h l[ [9l! i L1 o IllJ is XI - y l o -<.ou uoritrs' Attates wn 5 20 REV. 8/ 6!92 l l PROCESS AND AFEA MONITOR ITCATICNS SERVICE DUILDING [1HST l'L0t AND f TURBINE BUILDING TRUCK DOCK LEVUL , n .. = dr dr & v- - C1, - m' x ' *- 7 / -qc ,p-l } o 6 , i e/ ^ 3 l .\ .h(( ;. [vf i e; x l . / u=. > .. _ , H i i / ;R r" r- .r, , ?. i i @q qr Lp e- ] o l C; - Co r L f i 1 _,,.! r--] J 1 [ '. ^' C,.s i . . , E ' r- J!3 En ! r"" a i L_ ~~tlQ -- m by \ ' j t - , s _! n ;(~] ) ........8 f j L :-. ...4- .. . ,a,, .a 3 1 1( ]! 1 I b * -- --~;) u ) .l -d t ((=- q j - g - j 7 u! t _, ' l

r ,-.r*(1 6 p ===ne e m = m ,un'

-. a ! -H l*~~Fr:, i i r- --m i r e l L. 'J g : : i p w= =, mmm... _ .m _ r 1 ' = ' i F j l p > 2 i p ~g] y !, F( n - l4

~~r. +x, l~~

' . ~ T T m r m . - -I-lisMF cwu menun ujurswes 5 - 21 REY. 8/ 6/92 PROCESS AND AREA MONITOR LOCA' huns [ SERVICE DUILDING SECOND FLOOR AND f TURBINE DUILDING MEZZANINE LEVEL y ; 1 2 -5[ or-)J ;e t /- % 3,e O b '- f """."" , f I , ) () i .k Pg i , . i . \ l' R c'~)_ A * ** ' r 9 f.. b (x o _( c)) ) ,- o~~ ij, O.w. , _ 'm ( e so e i s._) } p , -(, {__.b, (y;- wJ t - Mcf 5 m nh x i ('w g B'[m g..j.:,i Ef l p M () ,, -l j _ l jolp E SE "- : ___E __e ']i i i ,y o - ,. , l ,. EO -11 ,L' l el {..,ag e ._,. IN _~ i x A C [l5FTJ! .n - L 1. _ m h- l ./ i (J ,.g r - p_1 - [g lA m /\s u y.- S I i i - u ,w J = umrs;: , . M '] ,X. = ,::gl - (*- , [l- r2 t-o

k. c . ,_ bl ,d n

o. m u w riorstA u.>iArs w rs 5 - 22 REV 8/ 6/92

l ( PROCESS AND AREA MONJTOP LOCATIONS l SERVICE BUILDING TillRD FLOCR AND f ; j TURBlNE BUl! DING TURDINE DECK LEVEL , l g' g;;;- _ \ Nl l 7- &{ lq 1 i ~ '

~~t. , i~~

.__._. _ _ _ _ _ . _ . _ , l [sIl , , - , .. o. I ! { oo j w y g- -n A -,___==_. . . _ _ ; i e n oo I i L_I f ._ !' .- P -.-- g ]', [ ;ll RM-064f I 7 / / (ld'1 o c lh p o e y o 6 : O - M 7 - 0 ,_1 1 , 5 O C j~ lo 'l ['u o o deD Job = o o q o o - a "U .,. m [' ~ - rRV-057 i 1 -- y y / i < g Fe ' -1 i { F g i + C ! e ~y l [ l la!2 n-. . .*% (' ! X l l CT-* M l o rm. rw . . . 1 1 .J M ! .a RM-057 : CONDENSER OFF CAS RM-064 : POST ACCIDENT MA!N STEAM MONITOR l o w.u tuntrsuttat es wr5 5 - 23 REV. 8/ 6/92 1 t PROCESS AND AREA MONITOR LOCATIONS MAINTENANCE SHOP j GROUND FLOOR . > c- - -g N TRUCK - BAY a i i - I SHOP AREA lj u n -=_m m, .=> l{ ; fa 3 L% = 4 ij J, + ==7[ c===g TOOL g u == ==,1 ' i ROOM ; OFFICE L_ f , i AREA t i - L.J 0ll .q _, ._ __ mm m: _ _a r_}g g J, - ,e r y=== n I _I n i, l OC - m ng1h. h 1 - j = gu t[ __._!. l n, ! lq L g; c___ _ __ _ , i - _.J l -- b,] o muurnus,AuftArswes 5 24 REY. 8/ 6/92 l i' l i;l ,I , li ll \11li1 ! l l. _. ^g q 8l1,'gghl-S - N O I T A ii t; V ,U ?Pllt C 1li!u

~~m. .N !. t' i~~

O L E S CA I R F E FR OO P )C OA ,P:0:. F S [ F H N S (O A E , OEL R A. J_ MCE NV P A A LE rIl - O ' H E N E S ~ R T R C ,- AN E P 7i' I AP ,,- D MU N l A = S ~ S 'jm E j .u p$ C - j.}- miij O R 7 o , P 1,9ir j j *(. gp > [. fj'a r - i-o $i>p_ E:'r4w E# u, ,$ ? c.2tJ r , ' ! Il l RADIOI.OGICAL DATA l ERFCS IllSfLAY - Pl[OCICSS MONITORS. PAGE_369 e An example of the ernergency respont.e facility computer system (ERFCS) display, " Process Monitors", Page 360, is provided under this heading. Displays renect the summaries provided in the ' PROCESS RADIATION MONITORS" section of this scenario. A complete set of displays is included in a participant mesuge packet to be issued during the controller briefing. This data is intended to be issued to participants only if the simulator or the computer link between the simuletor and the emergency response facilities falls. NOIEi The examp?cs provided in this scenario submittal are only examples to depict the !ayout and configuration of the screens. The actual volume of screens to be available for the exercise will be produced from the tables of data. The data renected in the examples enclosed may not necessarily reDect actual exercise data. l c 036084;f31.RCl5DDOCstTOC).Wie 5 - 26 REY. 8/12/92 -. . . - .~.. - .. . . - - _ . . ~ . . . - . -- q A _. 4 MontTOR VALUE WCNtTOR VALUE MONITOR VALUE (CPM 3 (CN1 ,ICN RM050 3.230E + 03 RM055A 6.000E + 03 RM062 3.7'OOE + 01 1 RMO51 4.970E + O2 RM056A 5.580E + O2 RM063H 2.OOOE + O2 RM052 G900E+01 RM056B 5.300E + 04 RM063M O.OOOE + 00 RM053 3.490E + 03 RM057 8.300E + 01 RM063L 2.OOOE + 01 RM054A 1.580E v 02 RMO59 3.290E + 02 RM064 1.200E + 01 l RM054B 3.440E + O2 RM060 1.550E + O2 RM066 2.500E + 00 RM055 5.3OOE + 04 RM061- 8.400E + 01 R0214 2.010E + 04 i PROCESS MONITORS PAGE 360 1 . SAFEGUARD SCNALS

- ' l Rx l IvAxl .I i l 1e I j FT'tS STAS DAST i MODE 1 14 OCT 92 CPHS C1AS DAS2 7' .

CRHS V1AS $$1 lCHRl l RCS l ' l CI l l l MODE SELECTION 03 :00 :00 RAS STts S$2 AUTOMATTC CSAS G wm4TMRC1SFf,v'3L%c.X15 - 5-27 8/7/92 RADIOLOGICAL DATA l ERFCS DISPLAY - AREA MONITORS. PAGE 361 l l An example ni .e emergency response facility computer system (ERFCS) display, " Area Monitors", Page 361, is provided under this heading. Displays redect tne summaries provided in the " AREA RADIATION MONITORS" section of this scenario. A complete set of displays is included in a participant message packet to be issued during the controller briefing. This data is intended to be issued to participants only if the simulator or the computer link between the simulator and the emergency response facilities fails. NOTE: The examples provided in this scenario submittal are only examples to depict the layout and configuration of the screens. The actual volume of screens to be i available for the exercise will be produced from the tables of data. The data reDected in the examples enclosed may not necesarily reflect actual exercise data, omtxracistwesaoc3.wes 5 - 28 REV. 8/12/92 - - - - - - ~ , , -, ,y e ,-r..---n.,-ws_e, - - - - - - - - - < - - - .->,-.m-e.-; -_. _.. - . --.-.e w .---- m - --. _ m . -__ _ ---- i ,.4 M ' MONITOR VALUE MO*Jf T OR V ALUE MONITOR VALUE (MR THR) (MRMR) pHR) ,{- . RMO70 2.870E + O2 RM077 5.000E-01 RM084 2.OOOE-01 RM071 9.550E + 01 RMO78 2.000E-01 RM085 7.500E + 01 4. RM072 3.960E + 02 RM079 1.790E + 00 RM086 2.OOOE-01 RMO73 1.960E + O2 RM080 6.000E + 00 RM087 1.OOOE + 00 RMO74 2.960E + O2 RM081 3.000E + 00 RM088 2.OOOE-01

~~RM075 2.550E + 01 RM082 2.OOOE-01 RM089 2.OOOE-01~~

, RMO76 1.OOOE + 00 -- (RHRt (8tNR) - RM091A 1.000E-02. RMO918 7.010E-03 4 i e AREA MONITORS PAGE 361 SAFEGUARD SIGNALS inh lVAXl l t l l P l , PFLS SIAS DAS1 MODE 1 14 OCi 92 CPHS CIAS DA52 I' CRMS V1AS SS1 lCHRl l RCS l - l Cl l h MODE SELECTtO*2 08:00:00 RAS STLS SS2 AUTOMATtC CSAS o verni netseruatv.uis 5-29 s/7/92 i t . . . , , _ __ __ . . . _ - - ~ _ . _ . _ _ _ - _ _ _ _ _ . ~ . - - RADIOLOGICAL DATA 4 QNSITE PLUME SIIINE WilOLEBODY EXPOSURE LEVELS Onsite plume shine wholebody exposure levels are provided under this heading. Wholebody exposure levels that result from plume shine are summarized for indoor various onsite buildings and for outside onsite areas. The plume touches ground at approximately 0.25 miles from the point of release. The boundary of the map provided in this section is approximately at the 0.25 mile mark. Exposure levels indicated take into account direct view of the auxiliary building ventilation stack where the radiological effluents are released during this scenario. Sectors P and Q are in direct line of sight of the stack and hence view not only the plume but also radiological deposition in the stack. s O.40841XERC15E'DOCSiTOC$.MT5 5 - 30 REV. 8/12/92 1 a b m s P q w ! - 90 Y ,f ~ s s w . g , m u u u a 3 .N m A .g. A ' I g = g

~~e. le u 8 g ,8 g~~

-~ ' O N. n o* c$ c 6 su ~ R = =x = P 8 8" _ ,! = . = = I R E ! ' R9 R

g +g 1o E $ Ib -

t = sa e b w ,c x g i R . ,A R . N . 'W d i

~~e g c5 g~~

a g :s } e4 , g<p , _ . _ _ af I 8 { oE ax - y R 8 s 9<cw jg ~ 7"A08 E' a' g [E 86 qV g 1k t 1g' t am - 1 - - oW QC (E $ ilEI4E3sf45448i IEE3iE33E $ J- I]l, gjg tls t rit t e r tit tit t rlit t t a Uxr;;;; ;;;;;; ;;;;;; ;;; a. ) i I k kIkI kk"Ikk kkIkkk kk# t 'l k 8 a . 8 C

~~w ( 5 84 565? ss s k345 3 834 D~~

f k 8 k kk k E E 8I $ w ; ;; ;;;; ;;;;;; ;;;;;; ;;t n o s ~ A gi js 5 55" WEE 5js455 54 h j SI BI $ $I I$I IIIIII N$ g . ; ;; ;;;; ;;;;;; ;;;;;; ;;; o I; a 433lgiss sgjisig?sR8E sss < J W - fissWfi ls.Elssfilii tt! @ i ; ;; ;;;; ;;;;;; ;;;;;; ;;; g ~ e .- o e .--g .- ,- e- ,- ,- . .- ., --, , .- ,- G 4 e ge m j0 $ $ ~d I$$IIIa$$$ IINI$$ $$I h i ; ;; ;;;; ;;;;;; ;;;;;; ;;; w x W l R --..O.$. 0RO.IEI $ SiO R I I ; E. ; I $ I. I h - - .. eee e=====;=c= 7 6 -- ~ . - - . _ t = y s u a = 4 *

~~i. .~~

t e. . a 2 ' %, W A I h U. 4 e 4 j - J z m 1 1 1 a o , o I a $ "LI @: I i _, a u y y' ' . . . A-I 3,1. , '7g ' f2: I .I f,- c

r,

.s_ J' R ~_ s ss l' a. 1 7 u 8 ~a j i i ~ .a r :: = y g. e 3;; .<_ _ -::c.7. - -s , .' . e.- = - A" =, 4_i y = .o / .__) ,,__b g$c-:::::"#~~~~< 8= gy g -. 8 R y = g i i a l a y};=

~~e. - -~~

l E w - -AS- f . ;i 8d _.1 1J 1 a' g W w _,i . 2 x 1 2d

p

- } o 6) v. . w p u ;,e ,. a, w _. . <Ww $s . $ - 8$ s

~~J, nk~~

_

R om . . ,

<,38 8 . .i > q: w: , g o : + , a (9 s E 5 y s A *u 5 ,e + a- ,s. c &. E. E. 5 9 4( s.--- 9

~~s. 8 5 e . L$ $, y g~~
~~w O_ws g g g ; s g g g g s a~~

e, . - - - - - . - <0 u- sjss,ssss ssB888 885s55s5 ? J Q i G g 9 ! = rit!ltrii { qtvicccc ffs:si t;;!:: ::vvvv vc; sitittrir a , s'; ; -.gs 5 s. a. 5- s,, w . ,- - sss.s.s.s. a 2 }a

8. 8 6. 8 . 8 8 . g y y y y g . $,8 s 5 s p ; ;; ggg gg,4,4o,s.,Agg* g**

~~d a .g a. ,w a s v s s v ,s a~~

~~e. . .s s. s. s. s. -. ..~~

... --wurg s. s...s. r s a _t. sm s . x $ I ~ 70 UUUU UUbbh? e* U UUU j e m _ w ; < 5 ~s ,45ssssssB 3 U E .s s E ss, ;; h h i 4 ; ;; ;ctvv;;::- 5:f-cccccc p O 5 I s w sl5s&ss .yyy3 s U. s % B ssy ++ - s s 5 5 5' l O g W j S' 5.. Y 75 h N Y 5kN9"s>"+g+d{NU57l7I{ 5 sa $4g!4 ', < f- $ A A A 8 8 j@ k II fE E9Yk!EIk ik EfI h 5 e l'!!'888$lak.jjgdg.IsEl;ial ciculvvv;cca2-+.-;cccic;c d .l ]' 'N S ,gy i c t " A_ t ' \ i m/l@ E /t n e u* X \ w N t n q a w w u j, s - .s=h - \ \ \ r' n b E - a s/A/ [. . g I 3 2 s 1 g ds / 1 u% I . 'I . / j I x'e$,89" \ .N j. r. y i l 2 i e e / s 2 ;{ , t '" ' f@ j ,I - ~ i,ga

s.

/; =j t ~ s ,z ) , 7 7 = <; , N 8 5 2 CN = < c$sg = U = a j $[ O s2 w s '[ s u H . n . e e a i L 2 @ O) i CAN -c O x I f T / RT -A 7 7 ow , OT 2 3 1 [ 5 2 FS 9 1 1 ,s ; R R G l ,,4 3 j g" , e - gw ' . ;: - !;l- Lli RADIOLOGICAL DATA LOOSE SURFACE CONTAMINATION LEVEI4 Loose surface contamination levels are provided under this heading. Surface contamination levels that result from plume passage are summarized for alllevels of the auxiliary building, Control Room, Technical Support Center, and the Operations Support Center. Additionally, data is provided for levels outside onsite areas. The plume touches ground at approximately 0.25 miles from the point of release. The boundary of the map provided in this section is approximately at the 0.25 mile mark. loose surface contamination levels are provided per 100 cm ,2 the size of an average smear taken during a survey. os,6onnrscistmcs1Tocs.wes 5 - 34 REV 8/12/92 I N N 5,' - g m m E C ~ -2 5 " f

~~n 4~~
~~h. e.~~

- h 1 "g 2 . m 9 u , o - ~ h R e T 3 u . 3 m w I U m - a 4 i 3 } ;] .- .u - = .i 2_ el 3 g 2 , ~ $ i 1% '@ ' - $ , g i > ! .. j 3 :O 8 5 8 ' ~ - f Rg s. a u 2 s *s s - i , M ,h g R a > .a ,a x2 a j .5 ~ s, _ _. x 5 , < .2 4 O 8 $ ~~-~ a < Ey .)_ ' 7 i RT R g s' " ^ W 9 gs - is v ' I8 8 O iG i li. I }s' E.S > e ks ~ O. 4'3' OE ye ..

~~s i s!?sEs 4554ss Wdsssi vs.~~

E hY I ~ f $$lTUIN$ IIIILIII$$$$ $$$ j 1 ; ;;v;;; ;;;;;; ;;;;;; ;;; 7 Was'sssavss , s, ssssss Y Y Y Y Y Y h ;;,c;;;;; eevi;;;eet ;;; 1 vsva 5 vv ess 3 }t$i{l' h sgveghhfiVWh,,shth!! is tis evece; !El . x 1 c ov et;; v;;; ev; i - x. I

~~I Is sisssEs~Is sjIf5s Ifs gIj g~~

8 588 88% k6k "! h t' M ; ;; ;;;; ;;ttt; t;;;;; ;tv {' ~ s Ljg g j, r ;; s- s,-- ,- se; <- 1rI , s s J !@ { !!!!hhi !!hhsk i hlkssg ffs fit i- .$. 1 3 s j s!s y s s - ss-- - asva sas 'i Si fyl%Ekva$$hhv l hhfils $$5 s .l E E l. ug Q 1 . .. .. . . .. .. . .. g J w I jj [ A sF!:Es Ps82Rs8ER.9808; I g a < -- j---.8 +.+sts s = = :: : = c :: l g e. O i i -w.rm,.: w. , ,. .g ----i ,. , - . . - , y . - , ----v.- - o . m. 2d2 RADIOLOGICAL DATA Loose Surface Contamination Levels dpm/ KE.k m2 {;wre Suf face Contaminate *m Leve:s, Onsite Sectols. G.HJ.K Immee Sarfare Ceed enessmesse teels 1.NE+ 07 4 y p - . opentf(Aw2 i dpm/imh m2 ! dem/f rmn? dren/Ifnw? i opw/t tnm7 l 'i.e. opm/ t <%=. - ---- - sedert.6 Ell J.E j l.M N.P Q B R D.A.R I mE +fra ! - - - - -- j _ _ _ _ . . 1 {- ~f Aree ouedoor out$aos mundour ausdaos outioor ound<=er {- "y I ME + 05 -f. ~ ' $4 ' r 7dwww., me w'w M N* W M ? to < l mF-01 < l tmE 01 < 1 m>E01 <l onE<01 < t toe 08 < I tmL el < 1 mE 01 < I .fm0 01 ' IN 7 45 < 1 tmE 08 < l toe of (I 00E of < 100E01 1 Di E+W e-- ,- < 1 coE 0t J 8 (m) < 1 tmE 01 < l OnE 01 < I OnE c1 < 1 cme 01 < 100E 01 < t mE O! < l onE 01 s $ 15 < ! ME 01 < l OnE 01 (l 00E 01 < 100E45 a 10 < l DOE 01 < l 00E-01 < l .w, pl < l DOE 01 < l ME cl < 1 DiLot I fee + 04 i- f-. - - - ,--- -- < 1 tmE01 < 1 OuE48 < t mEGI < 1 (mE O! 8 45 9 00 < l 00E 01 < l 00E05 < l 00E-Oi < 100E 01 { < l (mE41 :1 imE Of < 1000 01 < t onE 01 ' M

~~f. h 9 35 < 3 tmE of <l 00E41 < 1 OnE01 < 13508 < l 00fiel < l wilICI' I 00E + 02 <~~

9 30 < IDE-01 < 100E41 <1onE01 < lime 41 <l.00E01 < 1 coE 05 7. sm 3 30 9 se 9 so 30 0010 30 33 00 Il to 12 0012.30 9 45 2.57E + 04 2A6E+05 < l 00F-01 < 100E45 < 100E45 < l ME 01 6 2tE+03 < l 00E01 < l 00E05 mse Surface Contamination level 4, Onsite Secton L,M.N P 10 00 5 65E+04 585E+04 4. 20E + 04 I.99E + 01 < l 00E01 < I onE of < I .00E41 I mE4 07 ; to 15 : 5 85E +04 8 27E +04 42?E+04 s 100E-01 < 1 00E-01 < I 00E-Of l 10 30 5 85E +p4 853E+04 884E+04 2. 54E + 01 < 1 ouE 01 < 1 OnE 01 to 45 f- f ' 5 $$E+ 04 8.51E+04 912E+04 5 5tE+04 2stE+0) < l wfE-01 1 OnE + 06 l 11 00 l 585E+04 s$1E+04 9 3 2E+04 5 31E +04 292E+01 < l onE Of 11 15 11 10 5 85E + 04 8 51E + M 912E + 04 531E+04 2s2E+03 <l00E 01 I WE + 05 ~ } - g}- o- W -q ^ ' Ly II 45 595E+04 8.5? E + 04 912E+04 5 34E+04 281E+03 < lone 45 #. ! 289E+01 <!tmE41 ' }

12 00 5 85E +04 851E+04 912E+04 5.34E + 04 '

N.P I 2 96E+01 < f onE 01 [ 12 15 5 85E + 04 8. 51E + 04 912E+04 5. 34 E + 04 g ggg,94 , __ _f___ . j 585E+04 8 51E+ M 912E+04 5.34E + 44 102E + 33 < 100E01 12 to c. a 3 09F + 01 < l onF 01 3 g I? 45 5 R5F + 04 9 54E+04 912f +04 5 44E 4 04 I OrtE + 01 - 1 OnE + 02 7.30 8 00 4 30 9 689 9 30 10 00 10101100 II 3012 em 12.30 -mm2 I2""e Surface Contamination I.evels. On<ite Sectors QB.C.D.A.R W 06 1 l .ME . 05 - y 1.mE + 04 - ^ f B.C.D.A.R (-va a<w +,@ _ g mE 4 0s . -.. N,d e. All; contamenatuen levels res=?t frons overhem] plume degmeewe ~ - -+-- 1-I foe + 02 + - - -- -- -

~~7. le s 00 3 to 9 m 9 30 10 see 30 30 II 00113012 0012 to l~~

5-36 Rev. 8/13/92 G:\6084TEXERCISETRADDAT\SURFCNU .(LS [ _ _ _ _ _ _ _ RADIOLOGICAL DATA LOOSE SURFACE CONTAMINATION SECTOR MAE -( .. n g 3, = -- n g-0 ~ h , E $2 5 i , ? VISSOURL RIVE N ? 3)_ /\ # ^ /g .. N _ _\ pi _f a-- - - / / :(a a/ v _ :; a\ , % b , E N E s:: gqy: \ 9l3\g// / n e 1 : '+MM - ', / /F" e , n E wg ] jF%KWI ' _~2~ h$ N , y"" 7'"i . p 3@e ~

~~k - ~ ~~ l N 5 P' l OLD wa#fHouSC -~~

l :h :::C ) I' .. N = f - 0 5! - Nm J $ I! :--- @ gt>'[p k C 8 - o! O a R it n Z " i A n 0 %c ~ ggO / >==4 b h . \ {,'g (f*/ .o p 4 - - g ki.n _ / G36084\EXERCl3E\ DOCS', TOC 5 WP5 37 REV. 8/ 6/92 RADIOCHEMICAL DATA TABLE of CONTENTS Page. * . TABLE of CONTENTS 6.1

REACTOR CORE INVENTORY 6. 2

ISOTOPICS 6.3 a

~~REACTOR COOLANT SYSTEM ISOTOPIC 6. 4~~

CONTAINMENT BUILDING SUMP ISOTOPIC 6, 8 -

CONTAINMENT BUILDING ATMOSPIIERE ISOTOPIC 6.12

VENTILATION STACK ISOTOPIC 6.16

POST ACCIDENT SAMPLING SYSTEM ANALYSIS REPORTS 6.20

.i - o*osaxtacistoocssToc6.wr5 6-1 8/13/92 7 j RADIOCliEMICAL DATA i ',, REACTOR CORE INVENTORY Values for 100% core activity and release fractions were taken from document EA FC-91-001, " Fort Calhoun Coolant Activity". Fuel damage is indicated as 0.4% clad gap activity,0% fuel pellet over-temperature, and 0% fuel cladding oxidation. No hydrogen will be produced, since there is no clad oxidation. L i 1 l i an6cs4ctacisceocsiroc6.wes 6-2 8/12/92 ' RADIOCHEMICAL DATA 1 , ISOTOPICS Isotopic summaries are provided under this heading. Isotopic summaries are for controller reference only. Participants will be issued isotopic data through the use of post accident analysis system (PASS) reports. ' An example of a PASS report is included in this scenario. Isotopics are included for the following systems: Reactor Coolant System Containment Building Sump Containment Building Atmosphere Ventilation Stack Isotopic Isotopics take into account decays from reactor trip. Activities less than 1.00E-12 are indicated as less than the lower limit of detection (< LLD) in the isompic summaries, c a60scrxtacisasoocsvroce.wes 6-3 8/12/92 L L RADIOCHEMICAL DATA i*" 'I Reactor Coolant System isotopic (uCi/cc) ; i e9tg Mie seat enne tolg teie I to4g t ties . e7te e744 l Ouno e4t5 evie 1 0445 l 9*ne ! l t i Kr*% 5.25E.01 5.25E el 525E.01 5.41E41 5.20E41 5 01E41 482E4l 4 61Ect 4 46E Cl 419E41 4.15E41 3.97ESI 3.82E41 3 67E41 331E4i %hae same. KeM5 < 11D < LID < UD < IJ D < 11D < IID < fl.D < 11D < IID <UD < llD < 11D <UD =<UD <UD Keg 7 1. 81E M t.11E M t.llE4C 2 76E41 2.411141 2.10E-ol IR3E4I s wit!41 3 40E45 122E4R 1.06E 01 929P42 s.110 42 7.0R E 42 6.1*E4C Bleks < t LD < LL D < LLD 8.83E411 830E 0 B 7.SI E41 7 35E 01 6 9 t E-01 630E41 6.12E ol 5.75E c t $ 4tE41 5 04E41 4.790 4I 430E43 Kr ar9 <UD <tJD <!JD 5.79041 < LLD < IJD < IID < UD < tJD < TID < 11D < tJD < uD <tJD < IJD Xel3 h < UD < IJD < UD < LLD < 11 D < LLD < LLD < ( LD < t.tD < Lt D < flD < LL D < tid < LLD < LI D Xel33 2.85E42 2 s58 42 1.170 + tc t . 37E + 02 1.1739 02 1 17E + 02 I .3 7E + 02 L t7E + 02 1. tee + 02 1.16E +1C 1.t SE + tc 1. 96E + tc 1 16E + 02 1 16E + 02 2 85E 02 Xel3% 4 4004C 4 40E42 4 40E42 430E 4C 2.18t #2 1.10E 42 5.60E D1 284E41 1.44 E 4 <3 7.29E 44 3.70E44 3.n7E44 9.5nE 45 4 .E45 2 44E45 Xef 35 4.2 t E4C 42t E42 4 2tE4f2 2,16E +00 2.12E+00 2 tmE + m 2.04E + 00 2 mE + H* 196E + 00 E.91E + m i s9E + mi i n5E+m i t:E + m 1.7kE + N 1.75E +(c ' Xet37 <IJD < IID < UD 2.t#E + 00 1.45E41 9.65E 01 6 41E44 4.2S E45 254E46 190E47 126E4m S.42 E. t o S.6 t E. I t 3.74E-12 < LLD Xe13s < tid < I1D < LLD R.16E 42 389E42 t.RAE-02 S R4F 01 422E41 2.01 F oi 9 99Eo4 4.57E44 2.1# E44 e 104E nd 4 9%F45 '2 hF 09 Twat 1.4 S E-e t 14E01 1. 45 F,08 124 E + 02 1.21 E + 02 121 E + 02 1.21 E + 02 E.20ta 02 1.2"E + e2 8 201 + 02 8.19E + 02 119E+02 I .190 + 02 1 19E+ 02 1.t#E+e2 I talagen. It31 < LLD <LLD < LLD 2.97E + 01 8.96E + 0 n.95E + 0! s.95E + ot s .94E + 01 8.93E + 01 8 92E + 0i 9 9tE+0! R .91 E + 01 8 90E + 0I 889E+01 88tE+08 1132 2 74E4C 2.74E4C 2.74E42 1 <52 E + 00 1.41 E + tn 13tE+00 1.22E + no 1.13E+ 00 t 0$E + 00 9.7pE4I 901E4R 834E41 7.74E41 7.ISE41 6 66E et , till 2.19E4C 2.19E 4C 2.19E42 1.96E + 0I t.94E + 01 1.91E + 0i t .* l E + 01 190E + 01 1 RAE+0 1.R6E + 01 1.4%E + 0! 1.R1E + 01 3.R2E + 01 180E + 0! 8.79E + 01

34 5.26t 42 5.26E42 5.26E42 7.8vE-01. 6.47E et 53 t E411 436E41 337E41 2.91E 41 2.41Ec1 1.97E41 162E41 131E41 149E411 8.94E42 3135 3.77E 42 3.77E 42 3 77E42 5.72E + 00 5 57E + 00 5 41E + 00 . 5 29E + 00 5.15E + 00 5 (CP + m) 429E+fn 4 76E +00 4 64E + m 4 92E +tn 4 40E + mi 4 29F + m I

Td.E 1.42F,41 142E-01 E42E41 1 57E +02 1 17E + 02 I 16E+02 1.16E + 02 1.15E+ 02 1 14 E + 02 3.14 E + 02 1.13E + 02 1. 3 5 E + 02 1.13 E + 02 1.12E+ 02 f.I2E + 02 MLah mesals Coll 4 <UD <UD < llD 1.t tE + 0! 1. IRE + 01 I.18 E + 01 1.t aE 4 01 1.tRE+0! t.1RE + 01 1. t#E + 0! 1. IRE + 01 1.12E +01 t.it E + 01 1.1*E + 01 1.1tE+ 0i Cet37* < 11D <UD < UD 7.60E + no 7.60E + tn 7.6nE + 00 7.60E + tn 7.60E + 00 7.ME + tn 760E+N) 7 60E + m) 7ME + 00 7.60E + 31 ' TME + tU 7ME + 31 Cet 34 607E4e 6 07E 02 6 07E 42 6RRE+01 4.9xE + 0i ' 3 6 t E + 01 2 61E + 0! 1.89E + 01 1 17F + nt 9 9tE+tn 7 tRE + 00 5 2cP + fn 176E + 00 2 72E + no 3.97E+vn i T s at 6 07E 02 6 07L-02 60TE42 882E+01 6 92E+ 01 5. 55E + 01 4.55E + 0B St1E+0! 3 3tt+01 2 93E *01 2 66E + 01 2 46E + 01 2. 32E +01 2 21E +0! 2.14 E + 0i i Rh,sh,Te p eds < LLD < t LD < LLD 405E+00' 226E+00 1.26E + 00 7.02E 01 3 92E41 2.1RE 411 1.22E-DI 6.79E 42 3.78E42 < LLD < IJ.D < Ltb R td* 1.70E42

~~70E 02 1,70E4e 9.56E41 4.a7E41 2.49E4 t 1.27E*1 6.46E42 333E4C 1.6aE4C 8 57E41 < LLD < LLD < UD < UD -~~

Tet29 <IJD < IlD < IJ D 312E + 00 3.22E + 00 322E+oo 3.22E + 00 3.22E + oo 3.22E + 00 3.22E + 00 322E+no 3.2 t E + 00 32tE+00 321E + 00 3.2 t E + m Tet32 < IJD < IID <IJD 1.44E + 01 1.44 E + 01 1.44E + 01 1.43 E + 01 1.41E + 01 1.43E + 01 1.42E +01 8.42E + 0i 1.42E + 0! t.41 E + 01 3 4tE+0! t41E+08 Tel34 <tJD '<UD < tJD I 141 + 01 1.04 E + 0 t 811E + 91 6 1119 0) 4 95E+ no 3 R$F + m 10t E + 00 23SE + 00 t stE+m 1 41E +ts) I.IIF + m - R.6A F 41 Tammi 3.8 2 E.02 392E42 3.8 2E-02 3 6t h+01 304E+0I 2.72E + 0 2 47E+0i 2.29E + 01 255E+01 20hE+01 198E + 01 I.9?E+0i I RRE +0t 3.95E + 01 I n2E +of m annererthe %+t9 < IID < IJD < UD <IJD <UD < tJD <UD < IJD < IJD < tJD < tJD < 11D < tJD <IJD < tJD I M98 < TID < tJD <UD <UD < TID < tJ D < UD < TID < tJL < tJD < 1JD <UD <GD' < t2D < tJD T9B < 12D < 8JD <IJD < 11D < IJD <9 <IJD < LID <UD < IJD <IJD < 11D < 11D < 11D < UD , Ete* ae < t3D < t3D < t1D < tJD < 11 D < t1D < t3D < t3 D <1JD < t1D < t3D < tJD <UD < t1D < tJD " Tas et < IID < IJD <UD <UD <UD < IID < IJD < IJD <IJD <UD <UD < 11D < UD <UD <IJD pnee eenth. Nh95 < tJD < flD <UD <IJD <UD < IJD < IID <UD < tJD <UD <IJD (UD < LJD < UD <UD L95 <IJD < IID < tJ D < IJD <IJD <UD < IJD <UD < IID <UD <IJD < IlD <UD < IJD < LED %** <IJD < 11D < IID < IJD < IJD < 1]D <UD <UD <UD ( IJD < IJD <LJD < IJD <UD < UD talde. < 11D < IJD <IJD < IJD < IJD <IJD < IJD <UD < IJD < UD <IJD <UD < tJD <UD <UD Enan4 <IJD <(JD < tJD <IJD <UD < 11D < tJD < 11D < 11D <SJD < tJD <UD < 11D < UD <UD Rute3 < l1D < 11D < 11 D < 13 D < 11D < 11D < l1D < 11D < t3D < 11D < 31D <UD < t3D < 13 D < 11D 7 ue nt < 13 D < 11D < 11D <(JD < ISD < E1D < I1D l < 1tD l < E1D l < 11D < 11 D 1 <IJD 1 <tip t < ISD , < 11 D , G:%0841 EXERCISE \RADDA'nRCS.XLS 6-4 Rev. 8/1232 .~ _ ~ RADIOCHEMICAL DATA 2 14 Reactor Coolant System Isotopic (uCi/ce) IIIs Ilie 1145 12ee 1215 12M 1245 %hle genre Krfl5m 3.40E-01 3.27E41 3.15E 41 3.03E41 2.91 E-O L 2.80E41 2.70E41 . Ersts < IlD < IJD < ll.D < IID < llD < llD < llD Krfr7 5.40842 4.71 E 02 4. IIE42 3.59E-02 3.13 EM 2.73E 42 2.39E42 s Ermil 4.24 E41 3.98E-O L 3.75E41 3.5 sE41 3.322 4I 3.12E41 2 93E41 K rW9 <UD < UD < 11D < llD <!JD < llD < UD %eID= < LLD < LLD < LLD < ll.D < LED < LLD < LLD XeIJ3 E.16E + 02 1.15E + 02 1.15E + 02 8.15E + 02 1.15E + 1C I.15E + 02 1.15E + 02 Xel35am 1.24E45 6.27E46 3.18EM 1.61E46 8.16E47 4.14E47 2.10E.07 Xel35 1.72E + 00 1.69E + 00 1.65E + 00 1.02E + 00 1.59E + 00 1.56E + 00 1.53 E + 00 . Xel37 < !1D <UD <UD <UD < llD <UD (UD Xel38 1.13 f'41 5.17E46 2.56E 46 1.22E.06 582E47 2.77E 47 132E 47 Tasal 1.18E + 02 1.18E

02 1. i s E + 02 1.17E+02 1.17E + 02 E .17E + 02 1.17E + 02 Italagens II31 8.87E 4 01 8.87E + 0! 8.868 + 01 8.85E + 01 8.84E + 0! 8.83E + 0! 8.83E + 0 E 1132 617E-01 5.73E-01 5.31E-01 4 93E41 4.57E-01 4.24E41 3 93E41 1I33 1.77E + 01 1.76E + 0E 1.74E + 01 1.73 E + 01 f.72E + 01 1.70E + 01 /9E+01 El34 7.33 E42 6 02E42 4.94E42 4.05E42 3.32E42 2.73E.02 2.24E42 El35 4.18E + 00 4 07E + 00 3.97E + 00 3.86E + 00 3.76E + 00 3 67E + 00 3.57E + 00 Tasma i IIE+0? I.IIE + 02 1. IIE + 02 E.10E+ 02 1.10E + 02 1.09E + 02 I(ME+02 Anali smeant. Cel34 1.18E + 01 1.18E + 0 E I.18E + 0i 1.18 E + 01 1.t8E + 01 1.18E + 01 1.18 E + 01 C.137* 7.60E + 00 7.60E + 00 7.60E + 00 7.60E + 00 - 7.60E + 00 7 ME + 00 7.60E + 00 Cel38 f .43 E + 00 1.03 E + 00 7.49E41 5.4?E41 3.92E41 284E41 2.rME41 Tasal 2 08 E + 01 2.04E + 0! 2.0l E + 01 f .99E + 01 1.vsE +01 197E + 0! 1.9AE + 01 ih, Sh, Te Rh8dl < LLD < IID < 11D < UD < IJD <IJD < llD RhM9 < llD < llD < UD < 11D . < llD < 11D < llD Tel19 3.2 t E + 00 3.2 E E + 00 - 3.2 t E + 00 3.2 t E + 00 3,2 t E + 00 1.211! + 00 3.21E + 00 Tel32 1.4 ] E + 01 1.40E + 01 E.40E + 01 1.40E + 01 1.39E + 01 E.39E + 0 E I.39E + 01 Tel34 6 T7E-01 5.28 E-01 4.12E41 3.21 E41 15aE41 1.95E41 1.52E.ol Total I 79E+0E I.7EE+ct 1.76E + 01 1.73E + 01 1.74 E + 01 1.73 E + 01 1.72E+ 01 (Ikahme eerike SrW9 < IlD < llD < UD < llD < IlD < IID

< IID Se41 <UD < 11D < llD < IID < 11D <UD < 11D Y91 <UD < llD <IJD < UD <IJD < UD < llD sal 40 < 11D < flD < 11D < I1D < 11D < 11D < llD Tan al < IID < llD < llD < llD <llD- < 11D < llD 2cer earth. Nh95 < 11D < 11D <UD < IID < llD < llD < llD Zn+5 < UD < llD < llD < 11D <UD < UD < UD klae* ' < l1D < l1D < l1D <UD < UD < llD < llD lasso < UD <UD <11D < llD < 11D . < 11D ~ ' < 11D Bend <IJD < 11D < UD < llD < IID < IJD < IID Rele3 < 11D < 11D < 11D < 11D < 11 D < 11D < ISD Tan al < 12D < IS D < 11D f < 13 D < 11D < 11D < I1D G:\6084\ EXERCISE \RADDA~nRCS.XLS 6-5 Rev. 8/12/92 ' UEE +++ 08980 g www + + 4 + + - 52; e w 8 Ii I, w w e8 < -e+ ~ g i eoa oe n i A- - R ~ R n 955 x 0 U U ( < +++ - E. E.+9 +8 5 ~ g wwwww - w$w1 - 3 .m .F .E..R E t. x t o o ., EEE +++ BEBEE +++++ . gww wwwww . A0 EERSE -6< oc a oa ev, s w BEE EBESE +++++ +++ . e - WW$ SN. '-.a-1 R WWyWw 55e 5e -e< , oo-oe UEE +++ . i: > , 8 8. +E+I 8 I- rWW9 ~ r. i -r- .' k WWWWW ee.e. - e r~ . eo-oo &EE ! v,.,! i EEBEE +++++ v + ++ . { $"We ^ .-.4 R WWwWW -, n. = . J, ,,, , .a o-c R .e .e O i ,, q~ - i BEE 3 : 588E8 +++++ $ +++ e WWg ** . y .. - I WWWWw b "" 5 5$$5$ Q O I- E. e- [te . O C - oC 3 ,,w" <9 - . B. 5 8 J" o 5. S. E. S. E. s *o g Wa =he

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-. ; - E WwWWr Shm 5w < C. l' a e' - U ooseo O@ - 1 - 1 ,h a = r sssse ( "a aEs +++ # + + + + .+ www S - 9 mwwew 5:d ,ug :3 y ( . 5 E 8 s. & 8 oo-ao 9 y7 _ J, j , w- - a _' l' =y V EEU +++

~~e ; 888i3~~

+++++ .L e wwwW w E I www m w e ' E e8A85 Q -x E . A. ~S - .o-o ' , + ;! E BEE ++ + 88888 +4 + *+ o 5 $$$ no-I $$$$$ co-so (: E. E. 9 8. E.

~~8. h.s,., s W~~

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~~. h, h h oab e[ y .i g*- ! >- l1 mg~ga X r +~~

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[ $ "f ,,:' 1: & - -+ p o WwwWW 5835s oc aoo U x n*

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+ w + w + w s y e g g ; CE E E. E ., - ; 8888E o. p 8+EE =- - - - +++++ o S $ n** oo-oo M w d u ,f r r 57lg e *_; - x w 2 X x :;; , w Y cc i ? - =f c. E -g7 l3, e Ei ' 1 Jgi_ r - ,,. . . ~ - - RADIOCHEMICAL DATA **** Reactor Coolant Sy:::em Isotopic (uCi/cc) tats flM 1845 { 1208 1215 11 4 1245 i 1,56E + 02

Fgdralends Xel3% 1.59E+ 02 134E + 02 1.52E + 02 1.50E +02 1.4 t E + 02 3.47E + 02 II31sq , 9. I 7E + 0i 9.15 E + 01 9.14E + 0i 911E+0! 9.12E+ 01 9. I I E + 01 ,

~~Cal 37m 5 06E + 01 ! 9.t 6E + 01 4 87E+0! 4.71E4 01 4 61E+01 4 %E + 01 4 50E + 01 4 46E+0B~~

g enen Vehane tant) 0 00E +00 0 00E+00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0 00E+00 (ee) 0 00E+ 00 0 00E + 00 0 00E + 00 0 00E+00 0 00E+00 0 0nE + 00 0.00E+00 (Bereal (ppum) 1.30E + 02 3.30E + 02 1.30E + 02 1.30E+02 0.00E + 0G 0.00E+00' O.00E + 00 toweidel appm) 0 00E + 00 0.00E + 00 0 00E+00 0.00E + 00 0 00E+ 00 0 00E +00 0.00E + 00 plydel teethg) 000E+00 0 OriE+ 00 ' 0 00E+no eenE+00 0 00E+ 00 e imE + 00 e c0E + 00 Gn6084\ EXERCISE \RADDNRRCS.XLS 6-7 Rev. 8/12/92

m _ b 1*" RADIOCHEMICAL DATA Containment Building Sump Isotopic (uCi/cc) ene I e745 e=oo est5 me eu$ e=co 0915 ) ene i ende j sono ? tets lo w I se49 itse Wide rnem Kr#4em < UD < IID < IJD < flD < IJD 4 WE45 839E45 1.4 tE *4 197F 44 230E44 2.99EJ4 3 27E44 3,57E os 3.271!44 418F 44 K rM5 <tJD <UD < IJD <UD < lid <tJD < IJD < eld < tlD <11D < 11D <llD < tJD ' <UD < tJD Krt7 <IJD < uD <nD < t1D <IJD 1 A4E45 3.43E45 5 3tE 05 6 94E45 a 4tE45 96AE45 103E44 I .oeE 44, ,1.15E 64 1.20E 44 Krun < tJD <llD < tJD <UD < tJD <IJD < t1D < llD < tlD < IlD < TID <tJD < t1D ' < UD <UD krue < tlD < UD <UD <tJD <UD <tJD < UD < UD < tJD < !JD < tJD < t1D < TID < UD < UD Xet 33ai < tJD < llD < IJD < IJD < IID < IJD <IJD < UD < IID < UD <IJD <UD < I.1D <UD < 11D Xel33 < 11D < IJD <WD < tJD <UD I O9E-02 2.24E4C 3Jt E42 5lAE42 6.7 t E4C R.17E*C 9 (CE4C 9 99E42 1. toe 45 1.2 t E 41 %el3*as <tJD < tlD < llD < tJD <tJD 8.63 E 47 1.4 t E 46 1.74E W 19t E4m 2.OnEm 2.04EM 2A*Edm 2.0hE M 2.07E 4m 2 07E4m LI35 < tJD < tJD < tJD <tJD <UD I.83 E 44 4 04E 04 6.65E44 9.19E44 1.18 E-01 1.42E43 13hE43 1.72E43 1.RRE 41 2.09E43 XeI J7 <IJD <UD < llD <UD < 11D 7.54E417 A.17E 07 8.22E47 s.22E 47 8 221 07 s 22E47 822E*7 912E47 822E47 8.22E47 Xel34 < tJD < tJ D < IJD <UD < tJD 145E46 23tE46 2RIE44 3n4E4% 9 tht W 'ItE4w 321P4% 3 24F 4n 3 24E M 324r4m Tw el < llD < TID < UD < UD < llD 1.nibc2 2 3tE 02 3.81602 5 35E 02 6 92E 02 3 42E-02 830E42 199E 01 1. 3 3 E-01 1.24E 01 Italagen. 1138 <IJD < !JD < IJD <UD <IJD 9 33Ecl 2.10E + 00 3.4951 + 0n 4A9E+00 '634E+a) ' 73E + t10 s.54E + m 9.47E + 00 104E + 01 1.14E + 0 L !!32 <UD < TID < UD < tJD < TID 137E42 2.95 E.02 431E40 635EC2 7.92E42 9,33E '72 1.01E 41 1.09F41 1.16E*1 1.24E41 1l33 < tJD < tlD < tJD <UD <tJD 2.01 E41 4 50E 01 7.46E41 144E + 00 134E+00 1.61E + 03 t _20E + 00 1.99E + 00 2. t # E + 00 238E+00 1134 < IJD < UD < IJD < llD < UD 5.531'43 1.12E4C 1.cAE 02 2.14P S2 2.53 E42 2 84E42 2.92E4C 3.12E4C 3.24E4C 334E42 : Il35 < IID < IJD < IJD < IJD <UD 566E4C 124E41 20nE4B 254Fel 164P41 41 TEM 4 40E at SlTF48 5 74E41 6 24F48 Twel <UD < !1D < UD < !lD <UD 1.2t E+ M 2 7t E+ 00 4 5tE+00 630E + 00 p t5E+00 9.92E + 00 1 tcE+01 12 t E + 01 131E+0E t #E + 0! Alkan enesel. C 134 < 13D < IID < 11D < IJD < ISD 1.23 E4I 236E41 4 60E of 6 41E41 836E41 102E + 00 1.13 E + 00 1.25E + 00 137E + 00 1.5 t E +00 ' Ces37* < IID < tlD < tlD < tlh < tJD 7.92 E 42 IJ2 E-01 2.97E41 4.16E41 539E41 6.53 E41 7.27E41 8 06E48 S S6E41 9.74E41 C.138 <IJD < IJD < 11D <tJD ^< IJ D 3 36E-01 716E41 1.01E 4 00 122E 4 pn I .19F + m I WE 4 00 !.5SE + fwt - 3.5AP + 00 1.6tE + 00 t 64r +m ; Twel < tJD < tJD < tJD < 11D < UD 5.79E41 1.17E + 00 1.77E + 00 2 2*E + 00 2.76E + 00 3. I B E + m 3 40E+0D 3 64E + 00 3 87E+00 4. 3 2E + 00 - Rh.Sh.Te Rowca <UD < IJD <UD < 11D <UD <UD 2.55E4C 3.29E 82 334E42 4 04E v2 4.22E4C 429E42 436E4C 44tE 42 4.45E4C j nhne < TID <UD <nD <llD <UD < uD <uD < llD <UD < llD < tlD <UD < tJD <Up < tlD l Tet29 < tlD < TID <tJD < t1D < tlD 335E42 754E42 1.26E41 IJ6E41 22nE41 231E41 3.0RE 41 3.418i41 3J5E41 4.12E41 Tel32 < UD <UD <IJD <UD <UD t.50E-O n 3 36Eml 3 60E41 733E41 1.01 E +00 I .24E + 00 1.46E + 00 '.3,5+8m f .eAE + 00 1.82E + 00 i Tel34 <tJD < 11D -<tJD <IJD < tJD R 4WE42 16A E41 2 41E41 3 01E41 1.54E 41 3 9tE45 4 0RE ct 4.22E41 414E41 4 44E45 l Td et < UD < llD < IID <UD <IJD 2.85E-On 6 09E01 9 69E 01 1 3 l E + 00 1 64 E + 00 1.9%E + 00 2.19 E + 00 2 33E+00 232E + 00 233E +00 ! t Alkabne eertha S,we < IID < IID <UD < IJ D <IJD <UD < IlD < IID < UD < IID <UD <UD < IJD < 11D < UD %s91 <IJD < IJD < (JD < 11D <UD < UD ' < 11D < llD < IlD <UD <UD < LID < UD < tlD < EJD I %91 < llD <11D < UD < llD <UD < 11D <UD <IJD < 11D < 11D < IlD <UD <UD < IJD <UD Be14G < l3D < tJD < 13D < 11D <IJD < (JD < IJD < EJD <EJD <IJD < tJD <UD < tJD <UD < 11D l Tw el < IJD < 11D <UD <UD <IJD < EJD < tJD <UD < IJD < 11D < tlD < IJD < ilD < 11D <IJD [ Rem ennho NIW'S < tJD < ilD <UD <UD <IJD < IJD < tJD < IJD < IJD < llD < IJD < IID < IID < llD < IlD j 7t+5 < tJD < TID < IJD < IlD < IJD <IJD <IJD <UD <IJD < 11D < UD < SJD <IJD < 81D < UD y Ma** <IJD <IJD <IJD <UD <IJD < IJ D < IJD < IlD < IJD < UD < IJD <UD < 11D <UD < tJD 12840 < 11D <(JD <UD <UD <UD < IJD <UD < tJD <IJD < 11D < UD < 11D <nD <UD < EJD Eene < 11D < IJD <UD < 11D <UD <IJD < EJD < tJD < KJD < t1D < tJD < IJD <UD <IJD < tJD u Rot 03 <SJD < IJ D < 11D < 81D < IJD < 13D < 1331 < tJD < 11 D < 11 D < 121) ' < tJ D <tJD < lJ D < 11 D Tw el <IJD < tJ D t < EJD ! <IJD f <IJD < IJD ! < IJD i < EJD t <IJD I <UD f < IJD <IJD t <IJD l < 1JD < IJ D t G:%084 \ EX E RCIS E\ R ADD ABCONTSM P. X LS 6-8 Rev. 8/12/92 t sw m 2d*' . RADIOCHEMICAL DATA Containment Building Sump Isotopic (uCi/cc) tels I 11 4 II45 4 t2ae 1215 t23e 5245 %ble sasee .Kr h . 4.41E44 4.54E45 9.64E4n 1.62E4W l.18E46 l 09E 06 1.05E416 Ksts < 11D < EJD < 11D < 11D < UD < UD <UD e Kr#7 1.24E44 1.26E-05 1.40E46 2.6t E47 1.12E-07 1.06E47 9.13 E4s KrM4 < IJD < UD < 11D < 11D < 11D < UD <UD ' Kr** <UD < UD < IJD < IJD < IlD < IJD < 11D Xel33m <UD <UD < 11D < llD < !JD < UD < TID Xet33 1.29E41 1.34E42 1.75EM 5.93E44 4.76E44 4.64E44 4 62E44 Xel39 m g 2 07E-06 2.07E47 2.07E44 2.04E49 2.10E.10 224E.I t 2.95E-12 Xel35 2. tS E43 2.25E-04 . 2.88E-05 9.05E46 6.97E 06 6.67E46 6.54E46 Xel37 8.22E47 8.22E45 8.22E49 8.22E-10 8.22E 11 8.22E.12 < LLD Xel34 3.24E44 3.24E47 - 3.24E4m 3.25E49 3.27E-to 3.36E.I l 3 8 t E.12 2da' l.35E-01 1.39602 1.80E03 6.07E04 4 87E44 4.74E04 4.72E.04 tialagene 1831 1.23E + 01 1.272 + 00 1.67E48 5.66E 42 4.56E42 4.44E42 4.43E42 5132 5.34E-01 1.33 E42 1.57E43 3.79E-04 2.44844 2.15E44 1.99 E-04 1833 2.55E + 00 2.63 E41 3.42E42 1.12E42 8 86E43 8.56E43 8.47E43 It34 . 3.4 t E42 3.44E43 3.66E44 5.49E45 2.05E-05 1.43E45 1.15E.45 It35 6 64E-01 6.82E 42 - 8 6tE43 2 60E43 1.96E43 f.85E43 f .80E43 Tarat I.37E+0! 1.62E + 00 2.12E4R 7.09602 5.66FA2 5.50E42 5 47E42 Ukas aweal. Cel34 1.62E + 00 1.68E48 2.21E-02 7.53 E43 6 07E43 5.92E43 5.91E-03 Cet37* 1.0$E + 00 1.08E45 1.42E42 4 85E-03 < LLD < LLD < LLD Cst 3s 164E+00 t 61E41 f.69E42 f 93E-03 3. PnE44 1.65E 44 f .09E44 Tan =I 4.32E + 00 4.4 t E01 5.321542 n.41E42 3.04bO2 9.9t E43 98)E45 Oh,sb.Te ahmt 4.53E42 < LLD - < LLD < LIE < LLD < LLD < LLD RhM9 < IJD < UD < IJE < llD <UD < UD <UD Tet29 4 41E41 4.582 42 6.02E.43 2.0$E43 1.65E43 1.61E43 1.61E43 Te132 1.96E + 00 2.02E48 2.65E42 S.95E43 7.18E43 6.99E43 6.95E43 Tel34 4.51E41 4.53E42 < t.LD < LLD < LID < Lt.D < I.I.D Twel 2.90E+ 00 2.99E01 3.79E02 1.18E 02 9 091543 8.79E05 8 72E43 Athahme eenho ses* <11D < 11D < 11D ' < UE <<UD < llD < IID % 91 < UD < IJE < IID < IID < UD < 13D < UD Yet < IJE < 11D < 11D <UD < llD < 11D < 11D - Batee < IJD < tJD <UD <IJD <IJD <IJD <IJD Tesat <11D < Ilb < UD < IID < IID < IJ E < UD 2see eerth. Nis*S <IJD < I1D < 11D <US < UD . < IID < IJD Tres < llD < UD < UD < UD <IJD < UD < 11D Ma** < llD < 11D < IJD <UD < 11D < 11D < 11D tales <IJD < IJD < IJD < IJD < 11D < 11D <UD nrne <UD <IJD < llD - < IJD <UD < UD < 11D RulU < IJD < 11D < 11D < 11D < 11D < DJD < (JD Tee nt < (JD < 11D f < 1JD f <IJD < EJD f < 11D <IJD G:\6084\EX E RCISE\R ADD ABCONTS M P.X LS 6-9 Rev. 8/12/92 3 ' RADIOCHEMICAL DATA Containment Building Sump 1sotopic (uCi/cc) e7w em ewe esis em eus no j is ww ! e j i n. i sei, , . . . sus ii Eg .sem. Lthq 0 ME+ 00 0 00E +06 0 ME+ 00 0 00E+ 00 0 fu E + no I 61l>32 355E42 5E3E42 8 05E42 101E41 123F el I 37E-cl 1.51E41

1.ME 41 17'E4t Il3teq 0 00E + m O mE+00 O n0E+m 0 0nE + 00 O ME+00 9 67E 01 g 2.17L + 00 3 62E + te S e7E+00 6 57E + tui 9 01E + 00 885E+00 980E+on 1,.0a E + 01 1_18 E + 01 Cel37eq 0 enF + m O ME + m 0 onE+0rt c onE+00 0 00E + m - 2IBE+0n 4ItE+00 6MF+m 3 c?E +00 9 4tr +00 107E + 01 1 19 E + Cf 1 teF +01 t ?iF + 01 I 1?f'+ 01 oci/cc Contamment Building Sump Equivalents (uCi/cc) 100E + 02 y--- -

1 1.00E + 0 ! ,c) -HW - . fIff ' ' I ME + 00 I,. Xel3J eq ' s~~ ~ 3.00E e t 'gM 0 1131 eq . . . . . . .%; y ~ 1 .. .. .) u M_. A ^> Cs!37 eq t .00E 02 - j -. - _ - . _ . h. ;,wm -..)

~~Oon.oe .~~

0730 0*C Oftl e puoD c930 30,9 1040 Ilm 1130 I200 1210 G:\6084\ EX ERCIS E\ R A D D ATTCONTSM P.X LS 6-10 Rev. 8!!2M2 .. m - *A' 8 RADIOCHEMICAL DATA Containment Building Sump Isotopic (uCi/cc) Itt$ IIM 1141 1200 1219 12M 1245 F@niemse Xel3 hg 1.9t E41 1.97E42 251E43 80lE44 622E44 5 97E44 599E44 II31m 1.27E 4 01 ' 1 31 E + 00 1.73E-01 S 35E-02 4 70E42 4.SS E42 4.57E 02 , A Cel 37.q t %E + 01 f .19E + 0D ' s ME41 170E42 2.44F 02 2 2SFE2 2 ME 0? I a t N l G:\6084\ EXERCISE \RADDAT\CONTSMP.XLS 6-11 Rev. 8/1252. 4 m % u 4 m. , _Y ,' RADIOCHEMICAL DATA ! Containment Building Atmosphere isotopic (uCi/cc) e73e M45 ) ches eats earte ones esse **ts e**e emot tese sets 1 tow tes* Ites %bte enaam - Krt%e 4.08E47 4.CSE-07 . 4 0RE47 4 0sE47 4 0NE47 . 7.34E415 3.4t E 04 2.03E-04 2.6tE44 3.13E44 3 61E44 4.05E44 4,45E 04 . 4.82E44 itSE44 Kr e5 e < IID <(LD- <UD <UD < 11D 7.67EM i33E 05 230E45 3.07E 45 3,84E45 4 60E45 5.%E45 6.12E45

6.8sE45 ' 7.64E45 Krs7 < LLD < LLD < LLD < LLD < LLD . 3.0 tE45 126E45 6.8AE45 8.cIEM 8.74E45 9.14E45 930E45 9.27E45 9.10E45 8.82E45

?.Ato - < LLD < LLD < LLD <LLD . < LLD . t.12E44 2.tlE44 2.97E44 3.73E44 438E44 4 94E44 5 42E44 5 82E4# ' 6.tSE44 6.43E44 KrW9 <11D- < 11D < llD < 11D < IlE ' E.14E-07 8.49E457 4.72E-10 234E-11 1.DRE-12 < 11D <UD <UD < IlD < eld XeI33m 866E M SMEM ' 8.66E4>> 8e6E46 R ME46 4.71EM 8.56EM t.24E44 1.62E 44 2.01E04 .239E44 2.77E44 . 3.tSE 04 332E44 3.90PA4 Xel33 3.95E 04 3.95E44 - 3 95E44 3.95E44 3.95E44 194E42 3.6tE42 142E42 7.20E42 8.97E42 107E43 1.25f48 1.42E-Ot 1.60E-et 3.77E41 i Xe135m ' < LLD ' < LLD . < LLD < LLD < tLD I.58E4M t.6tEJM I.22E4% . 8.25E47 5.23E47 3.18E47 3.8nE47 1.U*E-07 6.19E M 3.88E-06 . Xet35 9.63E4% 9.63E-06 9 63E44 9.63 EM 9.63E46 3.36 E04 6.5 t E44 934E44 1.25E-03 IJ3E43 180E41 2.03E43 230243' 234E43 17FE43 Xel37 < UD . < llD <UD <UD < 11D . 138E06 1.84E47 3.84E49 L64E49 136E 10 1.0*E-S t < LLD < IlD ' < 11D <UD Xel3s <1LD < LLD < 11D < t1D < LID 2 66E-06 2.54E46 1a1E44 1.15EJM 6 87E47 3 91E47 2.18E 47 1.19E-07 6.17EJ1R - 317Ec4 , Tasna 4.14E04 4.14E04 4.14EOs 4.84F 44 414E04 t M E07, - 3.75E02 158602 7.42E42 9.24 h02 1,10E41 I.29E-01 3.46E41 1.64E41 - 1.82E45 Italerene It31 2L62E-t t ' 2.62E-13 2.62E It 2 6aE-E t 262611 2.57E-05 it3E 05 ' 7.69E45 1.02E04 1.28E-04 133E44 IJsE44 2.03 E44 2.29E44 234E44 It32 < LLD < LLD < LLD < LLD < LLD 3.NE47 6.97E47 930E-07 1.20EM 1,39E46 1.55E M t.67E4M 1.77E M 1.85E4% .1.90E44 l .It33 ? < LLD < LLD < LLD . < LLD < LLD 5.53E44 1.10E45 1.63E45 2.16* 45 2 67E45 3.1sE45 3 67E-05 4.t6E45 4.63E45 110E45 ID4 < LLD < LLD <LLD < LLD . < tLD 1.52E47 2.50E 07 3.06B47 3.36E47 3.45E47 339E47 3.24E47 3.04E47 2.90E.07 235E47

D35 < LLD ^ < LLD < LID ' '<11D < LLD 1.56E M 3.03E4% - 4.43EM S76E M 701EJM 8.tAEJM 9.2*E4W 1.01E45 111E45 f.22E44 Total 2.62E l l ' 2 62E18 2 62 Ell 2 62Eli 2 62 bit 3 33E05 t 661605 9 89E05 13tE44 t e1E04 f.95E44 2.2eE.04 2.57E.04 2 88E04 3.19E44 '

Alkali masals Cel34 < LLD < LLD < ll.D < LLD < LLD 338E44 636E46 1.01E45 135E-05 169E-05 2.03E-05 236E41 2J0E 05 3.0' EM 336E45 ' Cat 37' <LLD < LLD < LLD ' < LLD <tLD 2.18EM 436E46 L54E46 8 72E M t .09E45 131E45 3.52E45 I.74E45 1.95E45 2.1?E45 Cot 35 < IID ' < IID <UD' < 11D < IID 1.01E45 1.50E45 ' I 61E45 1.57E45 142E41 1.23E45 f.04E49 S ME in 7 00E4m 56tE M Tasal < t1D < ub < t1D <WD < t1D 1.59E45 2.6t E45 3.29E05 3391.~.45 4 20E45 4.5AE05 4 9?E45 5.29E-05 5.asE45 610EOS Ib.56 Te Rbm4 1.55E-0A L55E 08 1.55E45 lJ5E-08 -1.55E44 4.04E47 4.64E47 4,12E47 331E47 2.5AE-07 2 02E47 I.62E-07 1.35E47 E.17E47 I.06E47 Shmt IJ0E.10 130E-10 IJ0E-10 IJOE!0 IJOE-10 7.14E44 734E48 5 64E4s 3.86E41s 2.49848 536E48 9.59E49 194E49 3.77E49 2.50E49 T,s 29 <UD' < 11D ' < 11D 2< UD < 11D 9 23E47 1.85E46 2.77EM 3 69E4w 4.6t E44 5.52E M 6.44EM 735E46 8.26E46 9.17E44 Tel32 132Et2 132612 L32E-12 132E-12 132E-12 ' 4.12EM 8.22E44 1.23E45 1.64E45 2.04E45 2.44E-05 2.84E45 3.23 E-05 3.63E-05 4.02E45 Tei34 < t1D < TID ' < t3D < t1D < t1D 234EM 364E44 4.26E M 4 41EM 432EJM 4.01PM 367PJM 127E.0F f 2.26EM isnF M ' Tasa! 1.57E06 157E08 1.57E*8 1.57E46 1.57E45 7.86E-06 1.43E45 S.99E45 2 49E45 2.96E45 3.42E 05 3.87E05 43 tE45 434E-05 5 20E 05 . Alkahme enribe Sr## < 11D ' < 11D < 11D < 11D - < UD <UD < IID < IID < IID ' < IID < 11D' < 11D < 11D < IID < 11D Ss9s < ILD < 11D ' < LID < 11D < 11D <tLD < UD < E1D < E1D < 11D < UD <UD < UD < t1D < t1D Yet < t1D . < 11D ' < LED < LED <UD < 11D . < 11D <UD <11D' < tif) < UD < 11D < 11D < t1D < 11D Rasse - < UD < 11D <UD < 11D ' <UD < t1D - < 11D < 31D < 11D < 11D < t1D < 11D < 11D < 11D - < 11D Tanal < t1D < 11D ' < IID < 11D < 11D < llD < 11D < 11D < UD < ilD < 11D < UD < 11D <UD l < ilD - Raes earske Nkos <UD' < 11D < 11D < 11D < UD < 11D . < LID <UD < UD < 11D < I1D < 11D < 11D < 11D < UD Er+5 - < UD - < 11D ' < 11D <UD' <UD < 11D < UD < ELD < t1D ' <LLD <UD <UD <UD < t1D <UD-Mae9 ' < 11D < 11D . <UD - < IID <ILD <UD < 11D < (1D < til' <UD < 11D <UD- < 11D < 11D <UD tatte < UD l < UD . < ilD . _ < 11D < ISD ,< 11D <UD < i1D < IID . l _ <11D < 11D '<11D' < UD .- < UD . <UD Brss < $1D : . < 11D " <UD < LID < UD . <UD < 11D < 11D ' < t1D <UD <UD . < 11D < 11D <UD <11D' 8ete3 < 11 D ' < 11D < 31D <UD : e UD < 11D < 1]D ' < 11 D < 13 D h < 11D <UD <UD < IID ' <UD <

~~ID Ten al < l1D < E1D <1D < 11D < $1D - < 11 D 1~~

< l1D < 11D f < ISD l < ISD f < 11D a < 11D ' <UD < 11D < 11D L Gn6084) EXERCISE \RADDABCONTATMS.XLS 6-12 Rev. 8/12/92 : :1 J 4 . .. . . s. . . ._ ~ _ , _, _ , _. .- RADIOCHEMICAL DATA g2w4; Containment Building Atmosphere Isotopic (uCi/cc) tit $ It3e i 1945 i 12ee 1215 1130 1245 %ble ge '- KrRL9e '- 3.67E45 1.67E-05 1.6tE45 1.55E45 1.49E45 1.43E45 1.3*E-05 Krus 5.65E46 2ME44 2MEM 2.66E44 2.66EM 2ME46 2ME44 * ~ KrW7 -530E44 234EM 2.04E44 - 8.78EM I.56E46 136E44 I.19E44 Kres 4.47E45 1.98E45 t.86E45 IJ5E45 1.65E45 1.55E45 : I.46E-05 t Kane < l.1D - < 11D < 12D . < UD : <UD <UD < 11D Ket De . 2.86E45 1.33E45 1.33E45 1.33E45 133E45 133E45 133E45 , ' %el33 13tE42 - 6.14E43 6.13E43 - 6.12E43 6.12E43 . 6. l l E-03 6. toe 43 %et35m ' i t.3 tE 09 3.IIE-10 1.58E.10 8.00E.i t 4.06E.I t 2.06E-Il 1.04E-It Xel35 2.02 E44 93RE-05 9.22E45 9 06E45 8.9 f E45 836E45 8.62E45 Kes37 < E1D < 11D < 11D < 11D < 11D <UD < 11D %eI3a 1.19E49 - 2 67E.10 1.27E. t o 6 f43-It 2.89E.11 1.12 E.11 6.57E 12 Twel 3.34602- 6.29E05 6.2tLO3 6.27FAI 6.26E43 . 6.24E 01 6.23 E 03 flalagar 1831 - 1.87E45 8.88E44 -8.80E44 8.79E46 839E44 8.78 E44 8.7'E44 . 1532 130E47 5.69E48 ' 5.28E48 4.89E-08 4.54E45 ' 4.2 t E48 3.90E48 1833 334E44 135E44 1.73E46 f,72E44 IJ0E46 3.69E-06 f .68E44 . 1834 1.15E4M 5.98E49 4.90E49 ' 4.02E49 330E49 23tE49 2.22E49 1835 882E47 4 04E47 3 94E47 3.84E47 3.74E47 3 64E47 ~ - 3.55E47 Td al 235605 1.30645 ' l.10E 45 1.09Ee5 1.99E45 1.09E45 iOR605 Alkali mdals . Osl34 ' 2.49E46 . 1.17E46 1.17E46 1.17E-06 't.17E44 t.17E46 1.37E46 C.837*. I .60E44 7.55E-07 7.55E47 7.55E47 7.55E47 7.55E47 7.55E47 Cel3e 3 02E47 1.01247 7.44E4R ' 5.39E42 3.90E42 2 82E48 2.04E4m 4.40FA4 1.95606 ' Tasat 2.03E44 2 00E44 - 1.9AE06 1.97E44 1.95E4M-Ib,Sb,Te RtJW l.90E418 - 1.62E48 t.61E48 f.6tE45 1.60E.08 1.60E4m I.60E4m BlJee~~ 2.58E.10 ' t.9013 30 1.83E.10 . tJ9E-10 1.77E.10 136E-10 I "soE.10 Tet29 638E47 ~3.19E47 3.19E47 3.19E.07 ' 3.19E47 3.19E47 3.19E47 !' Tel31 2.97E46 1.39E44 1.39E44 1.39E46 - I.38E44 . 1.38E46 138EM Tel34 ' I 43E47 5.25E48 4 09E44 3.19E418 2.49E48 1.94E42 1.5tE4m Tas al 3.81606 1.78E44 1.77L06 1.75E46 I,74 E06 1.74IA6 - 1.73E46 4thanne e.,the srwe < 11D < UD <UD' <UD- <UD <UD < IlD sees <11D ~ <UD < tib < 11D < UD < 11D ' < UD wt < 11D : < 11D <UD < UD < 11D '<11D < 11D nette ' < 11D ' . <UD' < (JD < 11D < 11D <UD < 11D Tenan ' < 11D ' < 11D <UD" ; < UD < 11D . < 11D < 11D inte earthe Nbe5 ' < UD < 11D < UD < 11D <UD- < 11D <UD - 1s+5 < 11D < 11D ' < 11D - < 11D .<UD < 11D < 11D 14ee - < 11D . < t1D < IID i<11D. . < 11D <UD < t1D Baite : < 11D <UD' . < 11D ~<UD ; < 11D < 11D . < t1D hree -- < 11 D . . <UD <UD . < 11D : < IID <UD < 11D trese3 : '<UD < 11D < (JD < 11D < 11D < t1D < 11D 7en al < 11D < t1D e t3D < 11D < (JD < 11D I ' < I SD ' G:4084\ EXERCISE \RADDATTCONTATMS.XLS ' 6-13' Rev. 8/12/92 L i , .~t - ,. . , , ,,e .m _ . - ... ._-. . . , . . _ .. . . . _ _ . _ _ 3 *'

RADIOCilEMICAL DATA Containment Building Atmosphere Isotopic (uCi/cc) em ms i m i 0 is em i eus i - ! ms i n i ed. , ion. i i.i. . . . i su. ii 4 67E.04 4 67E 04 4 67E44 4 67E 04 4 67E44 2 95E 02 5 7tE42 9 35E 02 109E 01 1.33 E-01 157E 01 3.89601 2.02E st

2.23E41 2 44E45 f4doalews Xet 3 %i 2 6?E Il 2 62F-il 2 62E fl 2 62E. I t 2 6?E-ti 2 66E44 512E05 7 97E 05 106E4s t3?E M 139E44 I 8%E 04 2.II E 04 2 ME 04 2 a:Ee4 19 35m Cal 37een I R9F#24 3 39E on I 99E og 3 99E.ns t 39E44 6 06F45 9HE01 1 19 F44 123F ne I 2ef 64 3 31F ne 1 16F 04 14t F od 4 44Ea4 1 12E 44 uCi/cc Containment Atmosphere Equivalents (uC !cc) 100E + 00 -

.l. f .. i l p .WCHI k~ i 't , 'gg, _ . ,, J r " .(y--=m.- p}% t.00E42 : . /. " ' - L . 12 - .- _ ( W '* W ' M W f.* ' ~ ' ^ ', __, ;_-;A,w ::. 100E-04 c,, , gr .te .: . ~ ; Mr - ~ .=- ... X*I33 *9 1.00E45 , . . ,m -; , ? 0 - .~ _ ._- :.1 '.: 7 " 79 .y 0 1138 eq l 00E-06 _ .z_. ._ -. 2 Cst 37 eq 14:mE 07 I= 1 > c.1 f:l - l .00E-09 - - - - . - - . - 1 Onf410 I imb li - y 0I -0 y } 0710 0800 0410 0%W) 0910 1000 1030 1100 Illo 3700 1210 I*rw mare (gang) 0 69 0 76 0 98 25 40 21.70 20.70 20 #0 20.R0 20.M 20.20 19 75 19 10 1R 45 37.90 17.2s Tewaperat ure (F) 108 109 109 226 221 221 221 221 220 220 219 218 216 215 206 Valeme TPlu) 2.97E + 10 2 97E+ 10 297E+10 2.9 7E + 10 2.97E + 10 2.97E + 10 2.97E+ 10 2.97E+ 10 2.97E + 10 2.9 7E + IO 2.97E + 10 2.9 7E + 10 2 97E+10 2.97E+ 10 2 97E + 30 STP (cel 2 69E + 10 2 70E + 10 2.74E + 30 58tE+lo 530E+so 5.17E + 10 5 taE+10 5stE+10 SI6E+10 510E + 10 5 04E+ 10 4 *E+10 4 87E + 10 4.79E + 10 4 77E + 30 {tt 7dregem] 'b o tw F + 00 0 onE 4 00 0 onF + 00 0 onE +(m 0 tw!F + 00 0 tW1F+ nn e #mE + (un I rut +(m IonF+tp I #wiF + m I MF+ fwl 1onE+no gsurE+(p itr*F+4m i smF + twe G :\6084\ EX E R CISE\ R A D D ABCONTATM S.X LS 6-14 Rev. 8/12/92 j 4 ef 4 RADIOCHEMICAL DATA Containment Building Atmosphere isotopic (uCi/cc) 1200 f2f5 3288 I f245 til5 11.4 1549 8 05E45 7 95E43 7.MF43 7.77E-03 fqemeelente Ll33.ag 1.78E 02 8.26E 01 815E 01 9 04E44 9 07E4% 9 0AE44 9 0$E4m ft3 eq 1.94E 05 9 IDEM 9 09EM s 4 77E4W 4 67EM 4 SWIM 4 49E f4 4 45E M Cet37eq t .07E45 4 ME4m l 0 36 0 55 0fe 0.00 e no Premmer' (s==it ) te.75 2.20 330 o e o Tamperefore O') 194 110 lio 2.97E+ 30 2. 97E + 10 2 97E+ t0 2 97E+10 2 97E + 10 Volmene TP dec) 2.97E + 10 2.97E + 10 2 fee + 10 3.18E+ t0 318E + 10 318E+10 STPin) 4 78E+ 10 295E+10 2 59E + 10 3 onE 4 fw) g onE+(w) 0 fw>E+fio e opr+co o twr+oo fifydrogenf 85 100F + 00 1 IWiE + m 6-15 Rev. 8/I2B2 G:\6084\EX ERCIS E\R ADD AT\CONTATM S.XLS 2d* RADIOCHEMICAL DATA Ventilation Stack Isotopic (uCi/cc) n3e i vis t exis t em eus ! e is em i 45 , i.a. i i.i, e i* i tus i n Wie am e Krm%e < LLD < LLD < LLD < LLD < LLD < LLD < LLD < 11D < LLD - 3.44E43 7SSE43 8 84E 01 9.7 t E43 1.t 3E 42 Kres < TID ' < tlD < !lD < TID < tlD < LLD < LE D < t1D < LLD 4 2iE 44 t onE43 1.17E43 131F-03 1.0*E42 l 167E43 1 505 43 . Lir7 -< LIE < LLD < LtD < 11 D <11D < LLD < LLD < LLD < Lt D 93*E 44 1.99E43 2.01E43 2.02E41 1.9A E 43 1.93E43 KrtN < 11D <UD < IID < 11D <IJD <UD < UD < til) < llD 4.81E41 144E42 1. t*E42 8.27E A2 634E42 1.41E42 Krw <11D < 11D <UD < IlD <11D < LLD < Lt D < LLD <11D 1.19E-II LOSE 42 < llD < 11D < llD <11D L133an < IID < flD < 11D <UD < IID < 11D < IID < IID < 11D 2 20E-03 5 2tE41 *USE41 6_86E43 7.**E43 8.55E43 ht33 < t1D < WD < tlD <tJD < tJD < TID < tJD < TID < TID 9.s5E41 234E+00 232E + 00 3. !!E + 00 3.49E + 00 3SSE+00 LI35as <UD <UD < UD < llD < 11D <UD < IJD < IID <UD 5.73 EM 6 93Em 4.o*E-06 237EM 135E m 7 6tE47 Lt.15 < 11D . < 11D < UD < 11D < (ID < IJD < tab <UD <UD 1.M E42 3.92F 42 4 48E 02 5 02E 02 154E42 6.07E 42 Lt37 <UD < UD < IlD <UD < 11D < LLD < 11D < LL.D < LLD 1.49E49 237E-10 1.84 E-f l 1.40E-12 < UD < 11D LI3a < 11D < 11D < t1D < 11D < 11D < 11D < IJD < tJD < 11D 7 S4F46 8 4AFM 4 7AFM 239"46 13*E.sm 7.1*E47 Tdal < tlD < tJD < TID < TID < tlD < t1D < TID < TID < tJD t otE+8M 2 4t E+no 280E+00 3. I*E + nt' 3.58 E + 00 1.9F,+eo it;Jascas 5131 <11D < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD 1.40E43 3.34E43 3.89E43 4.44E43 4.98 E43 5 56E43 .- 1132 < LLD < LLD ( LLD < LLD < LLD < t1D < flD < LLD < LLD m33E45 337E45 3 64E45 3 86E45 4 02E45 4.17E45 1831 < LLD < 11D < LLD <tLD < LLD < Lt D < 11D < LLD < LLD 2.93E44 6 91E44 8.01E44 9.07E 44 iOIE43 1.12E43 i < LLD < LLD < LLD < LLD < LLD < LLD < t.1 D < LLD < LLD 33RE46 7.40E46 7.07E46 6.62EM 6IIE46 5.59EM 1833 < LL D < LLD < 1I D < LI D <tLD <11D < t.1 D < Lt D < 11D 7 69E S1 1.78 E 44 2 OMa4 225E44 2.47F44 2_ME 44 Td al <UD < UD <11D <UD < 11D < 11D < Ilb < IJD <IJD t.79E41 4 2SE 03 4.94 E-03 5 62E41 6.29E41 S **E43 MkrJa andale Cel34 < 1lD < tlD < t1D < tJD < t1D < LLD < LLD < LtB < LIE 185E44 4.41E44 515E 04 5stE44 6 61E os 73*E44 C.I)7* <UD < UD < IID < 11D < 11D <11D < LID < LLD < LLD 1.20E44 2.85E44 332E44 339E44 426E44 436E 44 Cat 3s < IJD < 11D < IlD <UD < IfD < !ID < I.1 D <ILD < Lt.D 1 56F 44 2 6*F44 2 27E ne iRAF44 1.51E44 Il1F44 Twel < TID < tlD < tlD < TID <WD < tJD < UD < tlD < tlD 4 61E44 9 95E44 197E43 1.15E41 1.24E45 1.34E.43 Ib, sb. Te phas < 11D <UD < 11D <UD <IJD < LLD < LLD < LLD < 11D 2.81EM 4.41Em 3.53E46 2.95Em 236E46 232E 46 sure < flD < IID < IID < LID <IJD < LLD < Lib < 11D < LLD 233E47 3 39E-07 2 n9E47 130E47 8 2tE4s 5.48E48 Tet29 <IJD < 11D < IID < 11D < 11D < LLD <11D < 11D < LLD SAE-05 t.20E44 1.40E44 1.e0E-04 1 ROE 44 2.01 E 44 Tel32 < 11D < eld < 11D <IJD < 11D < fl D < LLD < LLD < LLD 2.24E 44 5 32E44 6.19E44 7mE44 7.9 t E44 85tE44 Tet M < 11D < 11D < 11D <IJD < 11D < LLD < 11D < llD < LL D f 4 74F45 8 Ref?45 8fpF44 712E45 6 24E c1 5.41F-01 Twel < UD < 11D <11D < IlD < llD <IJD <UD < IID < llD 3.2SE os 7.4AE44 8 4 *E 04 9 40E*e i 104E43 I.34E 93 MLakaa eerska Srns < t1D < 11D < 11D < E1D < 11D <UD < UD < UD < 11D < 11D <UD < 11D < 11D < 11D < LLD Sr91 < LLD <UD < llD < flD < 11D <UD <UD < 11D <llD < 11D < 11D < 11D < 11D < 11D < UD %98 <tJD < LtD < 11D < Eli) < 11D < eld < i1D < ilD < 11 D <UD < 11D < IlD < UD < 11D < tJD 8es46 _ <t1D <UD < t3D < t1D < t3D < t3D < t1D < 11D < t1D < t3D <UD < t1D < t3D < t3D < 11D Tae nt < 11D < llD < 11D <UD <UD < UD <UD < 11D sUD <UD < UD < UD < 11D < 11D < IID Rare eerske Nb 5 <UD <UD <tJD < t1D < t1D < t1D <UD < t1D < t1D < UD < tlD < t1D < t1D < TID <UD Ts+5 < t1D < TID < t1D < t1D < TID <tJD < t1D < UD <UD < t1D < t1D < tlD <UD < t1D < i1 D !M9 < UD < 11D <LJD < 11D < 11D < 11D < 11D < 11D < 11D < IID < IID < t1D < 11D < t3D l < 11D < 31D <UD < 11D tanto < 11D <UD < 11D <LLD < 11D < 11D l <UD < 11D < E KD < ilD < 11D < UD RrM < IID < 11D < 11D < 11D <IJD < l1D < 11D < 11D < 11D <ilD < 11 b < LLD < t1D . < 11D < 11D Bate 3 < 11D < 11D < 11D < 11D < 11D < 11D < 11D < 11D < t1D <UD < 11D < 11D < 11D < 11D < 11D Tda < 51D < 11D t < itD f < 111) < 11D ! < 11D 1 < 11D < 11D f < l111 1 < 11D < 11D < 11D ! < EJD i < 11D t < 11 D G:WIS MEXERCISE\RADDADVENTSTCK.XLS 6-16 Rev. 842/92 7 2we RADIOCHEMICAL DATA Ventilation Stack hotopic (uCi/cc) III5 tt3e 1845 1280 1215 3238 I 1249 %hae samen Kr#4m 3.ME45 139E45 .134E05 1.29E45 1.24E.05 1.20E 45 1.15E45 Kr45 4.7 t E46 2.22EM 2.22E44 2.22E46 2.22E46 2.22EM 2.22E-06 Kr97 4.75E4% 1.95E M I.70E44 1.49E44 130E46 I.13E46 9.89E47 Krt4 3.73E45 ' t.65E45 1.55E45 1.46E45 137E45 1.29E.05 1.22E45 Kree < IlD < IJD < UD < 11D < 11D < UD < 11D Ket 33m 238E45 1.IIE45 1.llE45 f.11E45 1.t t E45 1.IIE45 1.11E45 xet33 1.09E42 5.12E-03 3.IIE 03 5.11E43 5.10E43 5.09E43 3.09E43 Xet 35m 1.09E49 2.60E-10 132E-10 6.67E.11 338E-S t 1.7t E-f l 8 69E.12 %=t35 1.6*E4M 7.82E45 7.69E45 7.56E45 7.43E45 7.3 t E45 7.19E 45 Ke137 < 11D < 11D < i1D <UD < 11D < (1D <UD Xel39 9.9 t E- 10 2.22E-10 1.06E-to S fME-11 2.4 t E.11 t.15E-11 5 4sE.12 Tesal I.12bO2 5.25E23 5.24E43 5.23E03 5 22E03 5.2t E03 520041 Italageaa II3I IJ6E45 735E M 734E44 7.33E4% 731E44 732E46 13tE4M I 31 1.09E47 4.74B44 4.40E-08 4.0RE48 3.78E48 - 3.5 3 E4* ' 3.26E4m 1133 3.12E4M I.46E46 3.45E-06 f.43 E-06 442E44 1.4 t E4% I.4024M 8834 1.29E45 4.99E49 4.09E49 336E49 2.75E49 2.26E49 1.s5E49 1135 736E47 337E47 3.29E457 3 20E47 3.12E47 1.04E47 2.96F 47 Teat t.96605 9I9606 9 I6EM 9.t3I:45 9.IDE44 9.07EM 9 04E06 Alks5 edels Cs!34 2 08E4M 9.77E47 9,77E47 9.77E47 9.77E47 9.77E47 9.77E47 Cat 37* t.34E44 630E47- 630E47 630247 630E47 630E47 630E47 Ce134 2.51E 47 3.57E48 6.20Em 4.49Em 3.2*Em 235E4m I 70E44 Td al 3.67E4m i e91<06 1.67E-06 1.65LM I6aE4m I.63006 1.62E m Ib 'n, Te RWIN I.58E-08 I.35E48 1.34E4R 134E48 134E44 134842 134E44 RhW9 2.158-10 1.59E.10 1.53 E-10 1.49 E.10 1.48E-10 1.47E-10 1.47E-10 Tet29 5.ME47 2.66E47 2.66E 47 2.66E47 2.ME47 2.66E47 .2 66E-07 Tel32 ' 2.47E44 1.16E46 1.16E4M 1.16E44 1.15E44 f.tSE44 1.15E4% Tet34 1.19E47 438EJM 3.41E 4R 2.66E42 2.07E48 1.62E4m I.26E m Twet 3.18E4m I49E42 1.47E44 1.46E06 145tM4 1.45LM I.44Ln6 AlkaMae earske Rette < t1D < t1D < llD < t1D < t1D <UD < t1D Sr91 < UD < 11D <11D < 11D < 11D < UD < llD wt < t1D < UD ' < (1D < 11D < 11D <UD < L1D Ra140 < 11D < 11D < t1D <UD < 1 *D < IID < 11D . Tasal < 11D < IlD < LID < 11D < 11D ' < llD < 11D Rare earthe Nb95 < 11D < t1D < 11D < 11D < 11D <11D < 11D h*5 < 11D < IlD < 11D < 11D < (1D < 11D < t1D %** < 11D ' < 11D ' < 11D < LID < 11D < 11D < 11D Iside < t1D ' <11D < 11D < 11D < 11D < *

~~19 . < 11D Brt4 <UD ' < 11D < 11D < 11D < 11D '< 11D < 11D~~

' Rele3 < 11 D ' <UD < 11D < 11D < 11D ' < 31 D ' < 11D Total < E1D < 11D < 11D <11D' f < 11D < 11D < 11D G:684\ EXERCISE \RADDA~RVENTSTCK XLS 6-17: Rev. 8112/W. i. 3 *'

RADIOCHEMICAL DATA Ventilation Stack Isotopic (uCi/cc) me i ms t .= i Mis . = = i eus ! .= i is . i s i ion. i ..is r i. i iM4 e i, 0 00E+ M 0 0nE+00 0 00E4 00 00nE+m 146E4 00 3 42E o 3 9?E+00 4 40E+00 '4 87E+ 04 5,35E +0e Fgusealende Xelha 000E+(e o tmE400 0 00E+00 0 00E+ 00 O foe + 00 113t% OME+00 O ME+ 00 0 00E +m 0.00E + 00 o rmE +&) 0 0nE + au) O rmE + fe 0 00E+0p 0 00E + 00 145E-03 3 4AE-01 403E01 4.59Ee3 Ss6E43 5.75E44 Cet !?M O OnE + tm O (M1E + rs) 000E+00 0 fu'E + 00 0 fmE + fn 6 (mF + M 0 ImF + 00 9 fir 1E + M 0 tuiE+m I 41F 81 299T41 2.eE e4 3 7E 81 31tF 09 3 31E el acuee Ventilation Stack Equivalents (uCi/cc) ,

1 n0E+ Of . ,MW fl 100E + 00 J/- t. . i ^ 1.00F 01 2 N r. '., . ,, ~

~~9 t00E42~~

. r_. * -m 1~ ' -7 _3J I!31 eq ~ __ f - 2. t 00E03 [2 Cs137 eq _3 l .onE 04 I .00E45 , + , .a .,,~. 1.00E 06 4 , 0730 OMO 0830 0'mc 0910 15m 1010 Itte 3310 3290 12tp wark We tene) 4 81E+M 4 81E+04 493E+04 4 83E+04 e s1E+04 481E+04 4 83E+M 481E+04 4.23E + 04 4 89E+04 2.41E + 04 2 41E+M 2.41E + 04 2.4 ?E + M l 2.43E + 04 teem O fmF4 00 ' 0 0DE + m e nnE +M 0 0nE + nn c onF + 0n O tmE + m o fmE+m e tee + tno l o mEc +m roF + no e surE +on O (ssF + no c onE +fM f. OmF+nn e mE +m G:\ 6084\ EX E R CIS E\ RAD D ATW ENTSTC K.X LS 6-18 Rev. 8/12/92 ' RADIOCHEMICAL DATA **'* ' Ventilati<m Stack Isotopic (uCi/c:) 1119 II'le j 1849 5200 l 1219 52 'le 1249 Feniensa Xel33aq 148E-02 689503 680E43 6.71E43 6 61E-03 6.55E43 6 41FAf3 .It31.g 1.62E45 7.59EM 7.StFA 7.57EM 7.57EM 7_56LM 7.55E4 Col.17aa B 92E-M 4 05E M 3 SsE M 335E M 3.79E M 3 75E M 7 71E-M t wack &w (cfud 2.43E + 04 2.4 3E + 04 2 43E+04 2.41 E + 04 0 00E +00 0 0nE + 00 0 00E+ 00 (ceta 00nE+0n G ru)E + on 0 0nE A00 0 00E + M 0 00E+00 c mE + um 0 0nE+ m G:\6084\ EX ERCIS E1 RAD D ABV ENTSTCK.X LS 6-19 Rev.' 8/12/92. ~ . _ _ _ . . ~ .- _ . _ . , - . _ _ . _ - _ . . _. . - 7_ 'l j! RADIOCHEMICAL DATA _. - POST ACCIDENT SAMPLING SYSTEM ANALYSIS REPORTS' An examhle of a post accident sampling system (PASS) analysis report for the RCS _ Coolant is - -included under this heading. A complete set of reports, including the containment building - atmosphere and containment sump analyses wN ha. included in a controller packet to be issued during the controller briefing. Reports are included for each time period indicated in the isotopics for the reactor' coolant system, containment building sump, and the containment building atmosphere. Reports are to ' be issued to participants only upon proper operation of the PASS. One library ofisotopes we.s used to generate all PASS analysis reports. Therefore, all detectable - . isotopes for a sample at any time will be indicated on the one analysis report included for that ' sample and time. Pure beta emitting isotopes (Csl37, Sr89 and Sr90) are not detectable through PASS analysis

and hence are not indicated on PASS analysis reports. :1 FASS analysis reports must nel be issued independently of PASS operation. Participants will rece ve PASS data only in response to actual operation of the PASS. It is important to note that,-

although the PASS may be powered and operational, the associated valves to obtain samples may g not have power or instrument air and hence are not operational. In these cases Participants are unable to obtain PASS samples. . k i'~ l T 036084\ EXERCISE \ DOCS \ toc 6.WP5 - 6 - 20' 8/12/92-9 - g-'-, o __- , ,,,, '_ A RADIOCHEMICAL DATA EOST ACCIDENT SulPLING SYSTEM ANALYSIS REPORTS (cont) I OPPD FT. CALildUN CANBERRA SERIES 90 S$MI'LE: RCS COOLANT DATA COLLECTED ON 1-OCTOBER 92 AT 0730 DECAY TO 0. DAYS, 0.0000 HOURS BEFORE THE START OF COLLECT RADIONUCLIDE ANALYSIS REPORT NUCLIDE ACTIVITY CONCENTRATION IN uCi/gr ENERGY COMPARISON DECAY (KEV) MEASURED ERROR CORRECTED ERROR EXPECT DIFF KrS5m 5.25E-03 + -4.5 2 E-04 5.25E-03 + -4.52 E-04 151.32 Kr85 < LLD < LLD 514.00 KrS7 1.13E-02 + -9.72 E-04 1.13E-02 + -9.72 E-04 402.58 Kr88 1.35E-02 + -1.16 E-03 1.35 E-02 + 1.16E-03 196.28 Kr89 < LLD < LLD 220.90 Xel33rn < LLD < LLD 233.18 Xel33 2.85 E-02 + -2.45 E-03 2.85E-02 + -2.45 E-03 81.00 Xel35m 4.40E-02 + -3.7 8 E-03 4.40E-02 + -3.78 E-03 526.62 Xel35 4.21 E-02 + -3. 62 E-03 4.21 E-02 + -3.62E 03 249.74 Xe137 < LLD < LLD 455.40 Xel38 0.00E + 00 + -0.00E + 00 0.00E + 00 + -0.00E + 00 258.31 < 1131 1.90E-03 + - 1.63 E-04 1.90E-03 + - 1.63 E-04 364.46 1132 2.74E-02 + 2. vE-03 2.74 E-02 + -2. 36 E-03 667.68 1133 2.19E-02 + l.88E-03 2.19E-02 +-l.88E 03 529.89 1134 5.26E-02 + -4.52E-03 5.26E-02 +-4.52E 03 847.03 1135 3.77 E-02 + -3.24E-03 3.77E-02 + 3.24E-03 1260.41 Csl34 < LLD < LLD 795.81 Csl37* < LLD < LLD 649.00 Csl38 < LLD < LLD 1435.79 Rb88 2.llE-02 + - 1. 8 t E-03 2. l l E-02 + -1. 81 E-03 1836.01 RbS9 < LLD < LLD 1031.94 Tel:9 < LLD < LLD 111.57 Tel32 < LLD < LLD 228.30 Te134 < LLD < LLD 767.20 Sr89 < LLD < LLD Sr91 < LLD < LLD 1024.30 Y91 < LLD < LLD 1204.90 Bal40 < LLD < LLD 537.38 Nb95 < LLD < LLD 871.10 Zr95 < LLD < LLD 756.72 Mo99 < LLD < LLD 739.58 Lal40 < LLD < LLD 1596.49 -Br84 < LLD < LLD 881.50 Rul03 < LLD < LLD 497.08 TOTAL 3. 85 E-01 + -3. 31 E-02 3.85E-01 + 3.31 E-02 G n6084\ EX E R CI S E\ R AD D AT\ P A S S F R M .X LS 6-21 Rev. 8/7/92 I DOSE ASSESSMENT DATA and PLUME MAPS '![ TABLE of CONTENTS' , Page-

~~TABLE of CONTENTS 7.1-~~

~~-* METEOROLOGICAL DATA~~

~~SUMMARY~~
~~7. 2 '~~
ERFCS DISPLAY - MET AND RAD DATA, PAGE~197' -7,14

VENTILATION STACK RELL.ASE 7.6

PLUME EXPOSURE DATA 7.8
+
f G. WVtEXERCISEiDOCSiTOC7.WPs 7-1 8/6/92'
as+,F A-< i DOSE ASSESSMENT DATA and OFFSITE PLUME Af APS
~~., 51ETEOROLOGICAL DATA SUS 151ARY The summary for the meteorological data is provided under this heading.~~
The data is modeled after typical meteorological conditions surrounding the site during the fall. The predominate average stability class ranges between D and E, moderately stable and slightly ste.ble, respectively. Typical days are clear with sorr.: clouding and afternoon winds. t l l G 6044 EXERC150, DOCS. TOC 7.WP5 ~/ - 2 8/6/92
~~.- ~ _ . - . . -. - -- . . . . .. - -. .~~
~~DOSE ASSESSMENT DATA and PLUME MAPS - METEOROLOGICAL DATA~~
~~SUMMARY~~
(cont) - Target 4 Wind Direction- %d Speed - Delta Temp Ambient Temp Pasquill Sector 8 Time (from) (mph) ('C/100m) ('C) Class - llom 49m tem IDm II0m 4%m IDm 10m S tro 10m 10m s 07:30 300.6 306,9 315.0 315.8 12.2 11.1 ieJ 10.2 As . 0.2 46 6.2 . - 6.4 . 6.2 D-07:45 302.5 307.6 315.0. 316.4 12.2 11.2 10.2 10.2 -0.8 0.2 -0.8 6.2 ~ 6.4 6.2 D
~08:00 299.7 307.8 - ~315.0 316.4 12.2 ~ II.2 10.2 10.2 48 0.2 0.8 6.2 6.4 6.2 D 08:15 297.4 307.0 316.0 317.3 12.7 11,7 10.7 10.7 0.9 0.1 0.9 6.7 6.9 ; 6.7 D 08:30 300.8 310.0 318.0- 318.7 13.0 12.0 11.0 11.0 0.9 0.8 ' 0.9 7.1 7.3 : 7.1 D-08.45 305.7 313.6 319.0 321.2 13.1 12.1 11.1 11.1 48 DJ 0.8 7J 7.7 7.5 D 09:00 304.8- 314.8 320.0 321.8 14.0 13.0 12.8 12.0 . l .0 0.0 .l .0 8.4 8.2 8.0 D. [
09:15 306.8 - 313.8 321.0 322.4 13.9 12.9 11.9 11.9 09 0.1 -0.9 4.4 8.6 8.4 D 09:30 304.9 313.8 322.0 323.9 13.7 12.7 18.7 . 11.7 0.8 0J 48 ~ 8.6 8.8 8.6 ~b 09.45 304.1 313.8 -320.0 328.5 13.5 12.5 llJ 11.5 0.8 ' 8.2 48 8.9 ~ 9.1 8.9 D 0-10:00 309.0 3 t?.9 325.0 327.2 13.4 12.4 II.4 11.4 0.5 SJ 0.5 9.4 9.6 9.4 D G,H 10:15 365.0 374.6 0.0 1.0 '13.2 12.2 11.2 IlJ 46 0.4 46 9J - 9.7 9.5 D J 10.30 -22,7 29.5 35.0 37.2 - 13.0 12.0 !!.8 .11.0 0.7 0.3 47 . 9.6 9.8 9.6 D K.L 10:45 38.8 48.7 54.0 56.2 ' 12.7 II .7 10.7 10.7 48 0.2 08 9.7 : . 9.9 9.7 'D L.M 11:00 72.8 I2.8 P0.0 91.0 12.5 11.5 IOJ - 10.5 l .0 9.8 . l .0 9.8 10.0 - 9.8 D N 11:15 87.4 96.9 103.0 105.1 12.3 11.3 10J 10.3 l.1 4a -l .1 93 10.1 9.9 D N,P 11:30 99.0 104.9 112.0 113.7 12.1. 11.1 10.1 10.1 1.1 - 4.1 -1.1 10.0 10.2 10.o - D P 11:45 104 0 .113.2 lit.0 121.7 11.9 10.9 9.9 9.9 .l.24.2 - 1.2 10.l. 10.3 10.1 D P 12:00 121.7 131,5 140.0 148.9 11.6 .10.6 9.6 9.6 .l.2 . 4.2 - l.2 .IOJ 10 4- 10.2 D- Q 12:15 12 4.9 132.5 140.0 140.5 11.5 10.5 9.59.5 1.3 4.3 .l .3 _10J 10.5 10.3 D Q 12:30 128.1 133.6 140.0 . 141.0 11.5 10.5 9.$ - 9.5 1.3 43 .l .3 10.4 '10.6 10.4 D- Q 12.45 124.7 134.5 140.0 140.6 11.4 10.4 9.4 _ 9.4 1.4 4.4 -1.4 10.4 .10.6 10.4 D Q 01:00 125.7 131.9 140.0 142 8 11.3- 10.3 9.3 9.3 1.5 4.5 - 1. 5 18.6 10 8 10 6 D 0 Note: Pasauill Class Definitions Bold faced data (first set of data for 10m . x < = .1.9 very unstable A clevation) is data used to calculate offsite radiological releases.-
~~.l.9 < a < = 1.7 unstable B.~~
~~1.7 < x < = 1.5 slightly unstable C~~
.l.5 < x < = .0.5 moderate D 0.5 < x < = + 1.5 slighdy stable .E- + 1.5 < x < = + 4. stable P a> +4.0 'tery stable .0 ' Meteorological Foreegg 10/14/92: Clear day with late morning clouding. Tet.peratures expected from a low of 45'F te a high of 80'F. Winds are expected to be light from the northwest increasing in intcusity to 15 mph by late morning. A weak cold front is expected to E be passing through the area in the late morning. Winds are expected to shift to the southeast. A 30% chance for precipitation is forecast for the late morning Skies should clear again in the afternoon.-
~~I I L I G:\6084\ EXERCISE \RADDA*DM ETSUM.XLS 7-3 Rev. 8/l3/92~~
~~.~ -_ . .. .~~
}
~~[p DOSE ASSESSMENT DATA and OFFSITE PLUME MAPS . v~~
~~= ERFCS DISPLAY - MET AND RAD DATA. PAGE 197 An example of the emergency response facility computer system (ERFCS) display, " Met and.~~
Rad Data", Page 197, is included under this heading. A complete set of displays is included in. a participant message packet to be issued during the controller briefing. ,
- A display is included for each time period included in the " Meteorological Data Summary", page 7.2. Displays are to be issued to participants only upon proper inquiry of the ERFCS and must not be issued to participants before the time indicated on the sheet.
f. P G A6084iEXERCISE\ DOC $n oC7.WPs 7-4 '8/13/92 d '.w a,.+ - ., - - , , , , , - .-. , , . , - -
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i i DOSli ASSliSSMiiNT DATA and OFFSITli Pl.UMil MAPS YJ3.11LX110N SuGLRELIMSE Ventilation stack release data and graphs are included un6.r this heading. Ventilation stack Dow rates, release concentrations and rays for :!chle 'jas, iodine, and par ' late is summarited in a data table and graphs. This data is for use by controllers as a reference and will not be issued to participants. 5 o w rmeistmestiocms- 7 8/6/92
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