ML20058L949
| ML20058L949 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 09/01/1993 |
| From: | WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | |
| Shared Package | |
| ML20006G526 | List: |
| References | |
| NUDOCS 9307060340 | |
| Download: ML20058L949 (338) | |
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TABLE OF CONTENTS ,
- c. INTRODUCTION 1.0 .
p OBJECTIVES AND GUIDELINES 2.0 OBJECTIVES GUIDELINES SCENARIO AND TIMELINE 3.0 L SCENARIO TIMELINE CONTROLLER MESSAGES 4.0 ASSIGIGENTS MESSAGES PLANT DATA 5.0 PLANT PARAMETERS PLANT GRAPHS CORE DAMAGE ASSESSMENT MC"EOROLOGICAL DATA 6.0 ;
ONSITE RADIOLOGICAL DATA 7.0 PROCESS RADIOCHEMISTRT PROCESS MONITORS ABRA RADIATION MONITORS INPLANT SURVETS ONSITE PLIME MONITORING OFFSITE RADIOLOGICAL DATA- 8.0 CONTROLLER ASSIGAENTS AND INSTRUCTIONS 9.0 CONTROLLER ASSIGNMENTS' CONTROLLER INSTRUCTIONS EVALUATOR ASSIGItfENTS AND INSTRUCTIONS 10.0 EVALUATOR ASSIGINENTS EVALUATOR INSI E CTIONS EVALUATION CHECKLISTS EVALUATION SIRMART
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SECTION
1.0 INTRODUCTION
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To assure that adequate measures are available to protect.the health and-safety of the general public in the Coffey County area in the event of an incident at the Wolf Creek Generating Station (WCGS), it is necessary to=
conduct.an annual emergency preparedness Exercise which requires the participation of the Emergency Response Organization (ERO) and State and County emergency. response capabilities. Federal agencies will evaluate and critique the annual Exercise to assure proper response in the event of an )
actual emergency at WCGS. -
Exercise participants do not have prior knowledge of the accident scenario 'I or of the starting time of the Exercise. The Exercise should demonstrate i that those individuals and agencies who are assigned responsibilities in a j radiological emergency are adequately trained'to perform according to
- current plans and procedures. Furthermore, this Exercise will provide training for emergency response personnel, and identify any potential !
problem areas in the overall emergency response system. i This manual has been prepared to assist the Exercise controllers, evaluators, and observers in the conduct and evaluation of the Exercise. It !
contains all of the information and data neesssary to properly conduct this Exercise in en efficient and coordinated manner, and is organized as follows:
Section 2.0 Obiectives and Guidelines This section defines the Exercise objectives for the licensee, State of !
Kansas, and Coffey County, and sets forth guidelines for the conduct of the Exercise to meet those objectives.
'i Section 3.0 Scenario and Timeline This section describes the postulated sequence of events occurring at WCGS which requires the ERO to respond.
Section 4.0 Controller Messages This section contains the Exercise messages used to control the development of the Exercise scenario.
Section 5.0 Plant Data '
This section contains information concerning designated plant parameters.
These parameters are updated every 15 minutes throughout the Exercise. To assure that adequate operational data is available in the event of a simulator failure, graphs of plant parameter information have been included in this section.
Section 6,0 MeteoroloRical Data This section contains information about the meteorological conditions in the Coffey County area d,uring the conduct of the Exercise.
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Section 7.0 Onsite Radiological Data j This section contains information about radiological conditions at the !
various onsite monitoring locations. Also included in this section is !
information concerning primary and secondary systems radiochemistry, containment atmosphere radiochemistry, and in-plant radiation levels. ,
Section 8.0 Offsite Radiological Data This section contains information about radiological conditions at the l various offsite monitoring locations.
Section 9.0
- Controllers' Instructions ,
This section provides general instructions to the Exercise controllers in {
the conduct of the Exercise. ,
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Section 10.0 Evaluators' Instructions ,
This section provides general instructions and criteria for evaluating the responses of the Exercise participants and the progress of the Exercico. $
Evaluator's Log Sheets are also provided in this section.
Copies of this manual will be.provided to Exercise controllers, evaluators, and selected observers prior to the Exercise. Following the Exercise, copies of this manual may be distributed to key Exercise participants.
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SECTION 2.0 l
OBJECTIVES AND CUIDELINES Subsections Page OBJECTIVES 2.1 LIST OF ABBREVIATIONS 2.2 LICENSEE 2.4 STATE 2.6 LOCAL 2.13 ;
i GUIDELINES 2.20 l l
CORRECTIVE ACTIONS 2.22 -
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OBJECTIVES Specific objectives to be achieved during the Exercise originate from discussions among the Wolf Creek Nuclear Operating Corporation (WCNOC),
State of Kansas, Coffey County, Nuclear Regulatory Commission - Region IV (NRC), and the Federal Emergency Management Agency - Region VII (FEMA).
The listing of objectives is divided into three groups: WCNOC, State, and local. The WCNOC objectives were obtained from NRC Inspection Procedure.
82302. Group I objectives are to be demonstrated during each annual Exercise. Group II objectives are to be demonstrated at least once during a 5 year period. Like the State and local objectives, the Licensee's objectives are segregated by the facility or group which will demonstrate the objective.
Each objective for each WCNOC and local facility / team will be designated with a "na', ' -- ' or a 'D". Certain parts of some objectives have been enclosed in brackets. This is to indicate it is a two part objective. If both parts of the objective are to be demonstrated, a single 'D' will appear in the facility / team column. Likewise, if both parts are not applicable (na) or not to be demonstrated (--) at this exercise, then only a single
'na" or '- " will be present in the facility / team column. However, if only the bracketed part of the objective is to be demonstrated (D) and the part outside the brackets is not applicable (na), then in the facility / team ,
column a 'D' would appear in brackets and a "na" would appear without brackets.
A list of abbreviations used in assigning responsibilities for objectives follows.
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4 LIST OF ABBREVIATIONS l
Amb Ambulance Service CEOC Coffey County Emergency Operations Center CR Control Room CRBD Coffey County Road and Bridge Department D Objective to be Demonstrated DAEFT COORD Dose Assessment and Field Team Coordination EOF Emergency Operations Facility '
EOFS Emergency Operations Facility, State Dose Assessment Group Hosp Hospital IC Information Clearinghouse ,
JRMT Joint Radiological Monitoring Temn KCPL GO' Kansas City Power and Light Pv4eral Office ,
MED Medical l 1
MI Media Inquiry -
MM. Media Monitoring MRC Media Release Center na Objective Not Applicable to Facility / Function DMT Offsite Monitoring Team Operations Support Center OSC PASS /ERDC Post-Accident Sampling System / Emergency Repair-Damage Control l Team PC Public Concern Rad Lab Radiation Laboratory, Kansas Department of Health and ,
Environment RCC Reception and Care Center School Coffey County Schools i Sec Security (WCNOC) 93-FE 2. 2 l
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SEOC State Emergency Operations Center SFSA State Forward Staging Area TBD To Be Determined .)
-- Objective Not to be Demonstrated ,
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- 1993 OBJsL HVE4 h WCNOC Group I OBJECTIVES PASS / OMT/ IC/ ECPL 4 (every year) C1 SEC TSC BRDC OSC JEMT EDF tec MI PC nel GO MED l ACCIDENT DETECTION AED ASSESSMENT I. Demonstrate the ability.to: evaluate 1
-the sequence of events: keep each facility aware of operational, ,
history and statues use all avail- D na D na D na D na na na na na na-able resources (e.g. offsite. ERDC, and Engineering teams) to support accident identification and mitigation.
EMERGENCY CLASSIFICATI0E
- 2. Demonstrate the ability to classify D na D na na na D na na na na na na emergencies promptly and according to emergency action levels.
- NOTIFICATION OF ONSITE AMD OFFSITE i manGIuCT RESPOEDERS
- 3. Demonstrate the ability to notify i the State, County, and NRC using the proper forms within the proper D na D na na na D na na na na na na time constraints: and to notify plant personnel by sounding the +
emergency alarms and making c appropriate announcements. i
- CateeBICATIDss -I
- 4. Demonstrate the ability to casununi- g cate among facilities and outside D D D D D D D D D D D D --
roops (e.g. State. County. NRC tethesdaheadquarters),andwith emergency personnel in the field.
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1993 OBJECTIVES
$e VCNOC
$ Group I OBJECTIVES (con't) FASS/ OHTl ICf ICPL MED TSC ERDC OSC JRMT EDF RELC MI PC let CO (every year) CIL SEC RADIOLOGICAL EIPOSURE CONTEDL
- 5. Demonstrate the ability to continu. na na na D D D na na --
ously monitor and control radiation D na D D exposure to emergency workers,with-in the facilities and in the field.
FILOTECTIVE ACTION REC 0tenaanATIONS
- 6. Demonstrate the ability to make na na na na na na D na na na D na protective action recomunendations D h sed on all available data, and to emergency workers within the facil-itles and in the field.
STAFF AUGHEETATIDM
- 7. Demonstrate the ability to augment D D D D na na D D D D D D the Control Room staff. D SHIFT STAFFING D na D na D na D D D D D D na
- 8. Demonstrate the ability to maintain a complete shift complement through-out the emergency.
Group II OEJECTIVES (once every five years)
ACTIVATION OF ENERGE30CT EENS CENTER (JOINT INFOttRTION CENTER)
- 1. Demonstrate the ability to develop na na D na na na na na and disseminate clear, accurate, na na na na na and timely information to the news F media.
- v. RIBtDR CONTROL
- 2. Demonstrate.the ability to establish na na na D D D D D na and operate rumor control in a na na na na
. coordinated and timely manner.
1993 OBJECTIVES STATE h
EOFS ORJECTIVES SEGC EDF D& EFT COORD JEMT SFSA IC HRC RAD IA3 MOBILIZATION OF ENERGENCY PERSOEMEL
- 1. Demonstrate the capability to alert and fully mobilize personnel for both emergency facilities and field
- operations. Demonstrate the capa- D D D D D D D na bility to activate and staff emer-gency facilities for emergency operations.
FACILITIES - EQUIPMENT. DISPLAYS, AMD WORK ENVIROIDGMT
- 2. Demonstrate the adequacy of facili-ties, equipnent, displays, and other materials to support emergency D D D na na D D na operations. g DIRECTION AMD CONTROL
- 3. Demonstrate the capability to direct D D D na ns na na na and control emergency operations.
Cott4DNICATIOES
- 4. Demonstrate the capability to cone-unicate with all appropriate emer- D D D D D D D na gency personnel at facilities and in
, the field.
ENERGENCY UDurim EXPOSURE COIfTROL
- 5. Demonstrate.the capability to continuously monitor and control na D D D D na na --
F radiation exposure to emergency workers.
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1993 OEJECTIVES
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n EDFS OBJECTIVES SEOC EDF D& EFT COORD JEMT SFSA IC letC RAD IAB FIELD RADICI4GICAL HDNITORING -
AMBIENT RADIATION RONITORIEG
- 6. Demonstrate the appropriate use of na na na D na na na na equipment and procedures for deter-d ning field radiation measurements.
PLIBM DOSE PROJECTION I
- 7. Demonstrate the capability to na na develop dose projections and pro- na na D na na na tective action recommendations regarding evacuation and sheltering.
FIELD BADIOLOGICAL HONITORING -
AIRBORNE EADIOIODINE AND PARTICUIATE ACTIVITT HDNITORIEG
- 8. Demonstrate the appropriate use of na na na D na na na na equipment and procedures for the measurement of airborne radiciodine concentrations as low as 10 E-7 i.0000001) microcuries per cubic centimeter in the presence of noble gases and obtain samples of particulate activity in the airborne plume.
PLIME PEDTECTIVE ACTION DECISION HAEING
- 9. Demonstrate the capability to make timely and approprlate protective D na D na na na na na action decisions (PAD).
ALERT AED EDTIFICATION g 10. Demonstrate the capability to
. promptly alert and notify the public na na na within the lo-alle plume pathway D na na na na u emergency planning zone (EPZ) and disseminate instructional messages to the public on the basis of decisions by appropriate State or local officials.
1993 OBJa,1tva5 w
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EOFS OBJECTIVES SEOC EDF Da&FT COORD JRHT SFSA IC MEC RAD LAB PUBLIC INSTEDCTIOES AED EMERGENCY INFORMATION
- 11. Demonstrate the capability to coor-na na na na na na dinate the formulation and dis- D na semination of accurate information and instructions to the public.
EMERGENCY INFORMATION - MEDIA
- 12. Demonstrate the capability to coor-dinate the development and dissemin- na na na na na na D na ation of clear, accurate, and timely information to the news media.
EMERCEBCY INFORMATION - RIMDR CONTROL
- 13. Demonstrate the capability to estab- ,
11sh and operate rumor control in ' na na na na na D na na a coordinated and timely manner.
IMPLEMENTATION OF PROTECTIVE ACTIONS -
USE OF KI FOR EMERGENCY WOenus, INSTITUTIOEALIZED IEDITIDUALS, AMD THE GENHitaf- FUBLIC
- 14. Demonstrate the capability and resources to implement potassium iodide (KI) protective actions for D D na na na emergency workers, institutional 1 red na D D individuals, and, if the State plan specifies, the general public.*
IMPLEMENTATION OF PEDTECTIVE ACTIONS -
SPECIAL POPUIATIONS w 15. Demonstrate the capability and
- resources necessary to implement na na na na na na na na appropriate protective actions for o' special populations.
- The State of Kansas does not recommend the use of KI for the general public (State Plan Section 1.3.1 Tab J)
1993 OBJECTIVES e
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t1 I EDFS OBJECTIVES SEOC EOF Da&FT COORD JEMT SFSA IC HEC RAD LAB IMPLEMENTATIOM OF P2DTECTIVE ACTIONS -
SCHOOLS
- 16. Demonstrate the capabillt and resources necessary to in lement protective actions for se col na na na na na na na na children within the plume pathway emergency planning zone (EPZ).
TRAFFIC AMD ACCESS COMTEDL
- 17. Demonstrata se organizational capability 1 resources necessary to control evacuation traffic flow D na na na D na na na and to control access to evacuated and sheltered areas.
RECEPY10M CENTER - MDNITORING.
DECONTAMIMATION, AMD R M ISTRATION
- 18. Demonstrate the adequacy of procedures, facilities, equipment, na na na na na and personnel for the radiological na na na monitoring, decontamination, and registration of evacuees.
CONGREGATE caar
- 19. Demonstrate the adequacy of facilities, equipment, supplies, na na na na na na na na personnel, and procedures for con-gregate care of evacuees.
MEDICAL SERVICES - TEAMSPOETATION
- 20. Demonstrate the adequacy of w vehicles, equipment, procedures and
- personnel for transporting contami- na na na na nated, injured o'r exposed na na na na o individuals.
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M EOFS OBJECTIVES SEOC EDF D&&FT COOED JRMT SFSA IC HEC RAD LAB MEDICAL SERVICES - FACILITIES
- 21. Demonstrate the adequacy of the
. equipment, procedures, supplies, and personnel of medical facilities responsible for treatment of con- na na na na na na na na taminated, injured, or exposed individuals EMERGENCY WDEKEEE. EQUIPMENT. AMD YEHICLES - N)MIT0aTr- AND DECONTAMIMA-TION
- 22. Demonstrate the adequacy of pro-cedures for the monitoring and decontamination of emergency na na na na na na na na workers, equipment, and vehicles.
SUPPLEMENTARY ASSISTANCE (FEDERAL /OTHER)
- 23. Demonstrate the capability to identify the need for external -- na na na na na na na assistance and to request such assistance from Federal or other support organizations.
POST EMtECENCY SAMPLING
- 24. Demonstrate the use of equipment and procedures for the collection and na na na -- na na na na transportation of samples from areas that received deposition from the airborne plume IABORATORY OPERATIONS y
- 25. Demonstrate laboratory operations
- and procedures for measuring and na na na na na na na --
g analyzing samples.
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1993 OBJECTIVES 0 STATE 4
t4 EOFS OBJECTIVES SEOC EDF D&&FT COORD JEMT SFSA IC MLC RAD IAB IBGESTIOR EIPOSURE PATHWAT - DOSE PROJECTION AMD PRDTECTIVE ACTION DECISIOg MArTm
- 26. Demonstrate the capability [to pro-ject dose to the public] for the [na] na [--]
ingestion exposure pathway and to -- -- na na na na na reconnend protective actions.
IBGESTION EIPOSURE PATHWAT -
PROTECTIVE ACTION IMPLEMENTATION .
- 27. Demonstrate the capability to imple-ment protective actions for the -- na na na na na na na ingestion exposure pathway.
RECOVERT. REENTRT AMD RETURN -
DECISION parim
- 28. Demonstrate the capability to develop decisions on relocation. -- na -- na na na na na re-entry, and return.
RELOCATION. EE-ENTET. AMD RETURN -
IMPLEMENTATION
- 29. Demonstrate the capability to imple-ment appropriate measures for -- na ' na na -- na na na relocatlon. re-entry, and return.
CONTINUQUS, 24-BOUR STAFFIEG
- 30. Demonstrate the capability to main-tain staffing on a continuous. 24- -- D -- -- D D na --
hour basis through an actual shift change.
F OFFSITE SUPPORT FDR THE EFACUATION OF g ONSITE PERSOMMEL H
- 31. Demonstrate the capability to pro-vide offsite support for the evacua- na na na na na na na na tion of onsite personnel.
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1993 OBJ w alvss w
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tg EDFS OBJI!CTIVES SEDC EOF DAAFT COOED JRMT SFSA IC Mtc EAD IAR UntAlnIOUNCED nuncISE DE petitl.
- 32. Demonstrate the capability to carry out emergency response functions in -- -- -- -- na -- -- na an unannounced exercise or drill.
OFF-BOURS nuncISE DE Initill.
- 33. Demonstrate the capability to carry out emergency response functions -- -- -- -- na -- -- na during an off-hours exercise or drill.
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Centers OBJECTIVES CEDC JRMT IC MC CRBD School &nb Hosp Lyon Anderson i HDRILIIATIOE OF EbGtRCENCY FIRSOWEL
- 1. Demonstrate the capability to alert
. and fully mobilize personnel for both emergency facilities and. field operations. . Demonstrate the capa- D D D D D na na na D --
bility to activate and staff emer-gency facilities for emergency operations.
FACILITIES - EQUIPMENT, DISPIATS, AMD UDEE ENVIROIBGENT
- 2. Demonstrate the adequacy of facill-ties. equipment, displays, and other materials to support emergency D- na D D D na na na na ns operations. l DIRECTION AND CONTROL 3 .' -Demonstrate the' capability to direct D na na na D na na na D -- !
and control emergency operations.
COMEINICATIONS i 4. Demonstrate the capability to consa-4 unicate with all appropriate emer-- D D D D D D na na D --
gency personnal at-facilities and in the field.
EXERGENCY 1pWEER IIFOSME CONTROL
- 5. Demonstrate the capability to- I na na g continuously monitor and control D D .D D D D D. -- ,
. : radiation exposure to emergency g workers.
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-4 tg Reception / Care Centers >
OEJECTIVES CEDC JENT IC lac CERD School Amb Hosp Lyou Anderson FIELD EADIOIDGICAL BWEITOEIEG -
AMBIENT BADIATION REEITORIEG
- 6. Demonstrate the appropriate use of na D na na na na na na na na equipment and procedures,for deter-mining field radiation measurements'.-
PLIEGE DOSE PROJECTION ,
- 7. Demonstrate the capability to develop dose projections and pro- na na na na na na na na na na tective action recommendations regarding evacuation and sheltering.
FIELD RADIOIDGICAL DENITORING -
AIRBORNE RADI0 IODINE AED FARTICULATE ACTIVITY BWEITORING r
- 8. Demonstrate the appropriate use of na D na na na- na na na na na equipment and procedures for the measurement of airborne radiolodine concentrations as low as 10 E-7 :
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(.0000001) microcuries per cubic '
centimeter in the presence of noble gases and obtain samples of particulate activity in the airborne plume.
PLIBIE FROTECTIVE ACTION DECISION 3saartisc
- 9. Demonstrate the capability to ma'ke timely and appropriate protective na -na na na na 'na- na na na na action decisions (PAD).
At.mnT AND EDTIFICATIOE N
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- 10. Demonstrate the capability to l r-- promptly alert and notify the public
- within the 10-mile plume pathway ,D na na na na' na na na na na emergency planning zone (EPZ) and
, disseminate instructional messages-to the public on the basis of decisions _by appropriate State.or
. local officials.
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. 1993 OBJECTIVES w
4, LOCAL t=3 Reception / Care Centers 01LIECTIVES CEDC JENT IC MEC CRBD School Amb Hosp Lyon Anderson PUBLIC INSTEDCTIGES AED EMERGENCY IMPOEMATION
- 11. Demonstrate the capability to coor-dinate the formulation and dis-semination of accurate information D na na na na na na na na na and instructions to the public.
EMERGENCY IMPORMATION - MEDIA
- 12. Demonstrate the capability.to coor- '
dinate the development and dissemin- na na na D na na na na na na
-ation of clear, accurate, and timely information to the news media.
EMENGENCY IEFORMATION - RInt0iit CONTROL t
- 13. Demonstrate the capability to estab-lish and operate rumor control in na na D na na na na na na na a coordinated and timely manner.
IMPLEMENTATION OF PROTECTIVE ACTIONS -
USE OF El POR EMERGENCY WOaritas, INSTITUTIONALIZED INDIVIDUALS, AMD THE Gpntual- PUBLIC
- 14. Demonstrate the capability and resources to laplement potassium D D na na D D D D na na iodide (EI) protective actions for emergency workers, institutional 1 red individuals, and, if the State plan
- specifies, the general public.* I IMPLEMENTATION OF PROTECTIVE ACTIONS -
SPECIAL POPULATIONS U 15. Demonstrate the capability and - -
e resources necessary to implement u appropriate protective actions for D na na na D na na na na na special populations.
- The State.of Kansas does not reconsnend the use of KI for the general public (State Plan Section 1.3.1 Tab J)
1993 OBJs,IIVa3 U LOCAL 4
tg Reception / Care Centers OMNCTIVES CEDC JEMT IC 19tc cettn School Amb Hosp Lyon Anderson IMPLEMENTATION OF PEDTICTIVE ACTIONS -
SCHOOLS
- 16. Demonstrate the capability and resources necessary to implement protective actions for school D na na na na D na na na na children within the plume pathway esiergency planning zone (EPZ).
TRAFFIC AND ACCESS CONTROL
- 17. Demonstrate the organizational capability and resources necessary D na na na D na na na na na to control evacuation traffic flow and to control access to evacuated and sheltered areas.
RECEPTION CENTER - RONITORING, DECONTAMINATION, AND ENGISTRATION
- 18. Demonstrate the adequacy of procedures, facilities, equipment, na na na na na na na na D --
and personnel for the radiological monitoring, decontamination, and registration of evacuees.
CONGREGATE care
- 19. Demonstrate the adequacy of facilities, equipment, supplies, na na na na na na na na D --
personnel, and procedures for con-gregate care of evacuees.
MEDICAL SERVICES - TRANSPORTATION l
g 20. Demonstrate the adequacy of
. vehicles, equipment, procedures and y personnel for transporting contami- na na na na na na D na na na e nated, in ured or exposed individua s.
1993 OBJew11v u w
.', LOCAL to Reception / Care Centers OBJECTIVES CEOC JEMT IC HEC CRED School Amb Hosp Lyon Anderscu HEDICAL SERVICES - FACILITIES
- 21. Demonstrate the adequacy of the na D na na equipment, procedures, supplies, and na na na na na na, personnel of medical facilities responsible for treatment of con-taalnated, injured, or exposed individuals EMERGENCY if0EEIRS, EQUIPMENT, AMD VEHICLES - DENIITDEING AED DECONTAMIMA-TION
- 22. Demonstrate the adequacy of pro-cedures for the monitoring and decontamination of emergency na na na na -- na na na D --
workers, equipment, and vehicles.
SUPPLEMENTARY ASSISTANCE (FEDERAL /OTHER)
- 23. Demonstrate the capability to identify the need for external na na na na na na na na na na assistance and to request such assistance from Federal or other support organizations.
POST-EMERGENCY SAMPLING
- 24. Demonstrate the use of equipment and na na procedures for the collection and na na na na na na na na transportation of samples from areas that received deposition from the airborne plume LABORATOEY OPERATIGES w
- 25. Demonstrate laboratory operations na na and procedures for measuring and na na na na na na na na e
N analyzing samples.
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O 1993 OBJaw 1Tas e
Y LOCAL m
Reception / Care Centers OBJECTIVES CEDC JDtr IC HEC CRAD School Amb Eosp Lyon Andersce IBGESTION IIPOSURE PATWAY - DOSE PROJECTION AED PECTETIVE ACTION DECISIDE partisc
- 26. Demonstrate the capability (to pro-ject dose to the public] tor the [na) ingestion esposure pathway and to -- na na na na na na na na na recosusend protective actions.
IBGESTION IIPOSURE PATEWLY -
PROTECTIVE ACTION IRLMENTATION .
- 27. Dessonstrate the capability to imple-ment protective actions for the na na na na na na na na na na ingestion exposure pathway.
RECOVERT, MK8mf7ET AED RETURE -
DECISION parTuc
- 28. Demonstrate the capability to develop decisions on relocation, na na na na na na na na na na re-entry, and return.
REIACATION, EE-EETRY. AED RETURE -
IMPLMBETATION
- 29. Demonstrate the capability to imple-ment appropriate measures for- -- na na na na na na na na na relocation, re-entry, and return. ->
CONTINDOUS.'24-RO M STAFFING
- 30. Demonstrate the capability to main-tain staffing on a continuous. 24- -- -- D na -- na na na D ---
hour basis through an actual shift change.
OFFSITE SUPPORT POR TER EVACUATION OF 5 ONSITE PERSOM EL
- 31. Demonstrate the capability to. pro-vide offsite support for the evacua- D na na na na na na na na na .
i tion of onsite. personnel.
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e 1993 OBJauu vs3 U LOCAL m
til Receptica/ Care Centers DEJECTIVES CEDC JRNT IC RELC CERD School Asnb Bosp Lyon Andersost UEAEWOUNCED EXERCISE OE M11 f- l l
- 32. Demonstrate the canability to carry out emergency response functions in -- -- -- -- na na na na na na an unannounced exercise or drill.
OFF-BOURS EKERCISE CE Int 11 r.
- 33. Demonstrate the capability to carry out emergency response functions -- -- -- -- na na na na na na during an off-hours exercise or drill.
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GUIDELINES t
These guidelines define the participants' extent of play in demonstrating 1
the previously listed objectives.
A. The' Exercise will be conducted September 1, 1993.
B. Participants will not have prior knowledge of the scenario or time of the Exercise. However, they will receive a briefing on the guidelines for the Exercise.
C. There will be pre-staging of licensee participants in the Wolf Creek .
Generating Station (WCGS) Simulator and outside the Information i Clearinghouse (IC) and Media Release Center (MRC) in Topeka. The '; '
Licensee IC/MRC particpants will only be allowed into those facilities after simulating an appropriate travel time (~75 minutes following the declaration of an Alert). Station operators will also be pre-staged in r the computer room next to the actual Control Room on site. l D. Personnel will be notified of emergency conditions through methods )
normally employed in making notifications (e.g. GAI-tronics, callout or ,
Security). j i
E. The following emergency response facilities / functions will be participating in the Exercises
- 1. Licensee - Wolf Creek Nuclear Operating Corp.
- a. Control Room (CR)
- c. Operations Support Center (OSC)
- d. Emergency Repair / Damage Control (ERDC) Teams i
- e. Onsite Survey Teams (OSTs)
- f. Security (Sec) l
- g. Offsite Monitoring Teams (OMTs) ~l
- 1. Media Release Center (MRC)
- k. General Office - KCP&L GO
- 1. Media Inquiry /Public Concern / Media Monitoring - i Wichita Office (MI/PC/MM)
- 2. State - Kansas l
- a. Emergency Operations Center (SEOC) Key Personnel
- b. Emergency Operations Facility (EOFS)
- 1. Radiological Assessment
- 2. Emergency Preparedness c '. Information Clearinghouse (IC)
- d. Media Release Center (MRC)
- e. State Forward Staging Area (SFSA)
I 1
93-FE 2. 20 I
l GUIDELINES I
- 3. Local
- a. Coffey County Emergency ,
J
- 1. Operations Center (CEOC)
- 2. County Road and Bridge Department (CRBD)
- 3. Information Clearinghouse (IC)
- 4. Media Release Center (MRC) ,
- 5. Coffey County Ambulance Service * (Amb) '
- 6. Coffey County Hospital * (Hosp)
- 7. Waverly School * (School)
- b. Lyon County
- 1. Reception and Care Center * (RCC)
F. The CR will be simulated from the plant simulator. A full shift complement of operators will staff the simulator.
G. Play will be driven from the plant simulator. A full shift complement of operators will staff the simulator.
H. All communications involving the CR will be duplicated in the simulator. '
except for the Emergency Notification System (ENS) dedicated line and the State / County radios. A commercial telephone will be used in the i simulator for the ENS. ,
I. Fire protection panels (KC008) are not duplicated-on the plant simulator and will be simulated.
I J. Operational and meteorological initial conditions will be established prior to the start of the exercise and will be distributed to those players who would, under e.ctual conditions, be aware of this information. .l K.
)
Participation by onsite personnel directly involved with emergency response shall be carried out to the fullest extent possible without .,
affecting plants operations or plant safety. Dispatch of the following !
teams into the power block will occur as required: 1
- 1. Onsite Survey Teams (OST)
- 2. Emergency Repair and Damage Control Teams (ERDC)
- 3. Search and Rescue Teams
- 4. First Aid Teams
- 5. Security Teams
- 6. Fire Brigade
- These facilities will demonstrate their objectives out-of-sequence !
from the Exercise. l 1
1 1
l l
93-FE 2. 21 i
GUIDELINES L. The phrase,This is a drill", will begin and end all radio and telephone transmissions performed in response to scenario events.
M. If the scenario requires that any personnel working for an organization .
not particpating be contacted, they shall be contacted for the purpose .t_'
of checking comunications only.
e 4
93-FE 2. 22
. SECTION 3.0 l
SCENARIO AND TIMELINE Subsections Page SCENARIO Initial Conditions 3.2 Narrative Summary 3.4 TIMELINE Sumary 3.6 F
9
- h 93-FE 3. 0
SCENARIO A suenary of the scenario events is pfovided in the following subsection.
Operational events will be conducted as written. Other events may vary from those written according to the actions of the players.
r
- b i
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i 93-FE 3. 1
INITIAL CONDITIONS (Page 1 of 2)
Operations The plant has been operating normally at 100% full power for the last 14 days on the sixth cycle of a middle of life core. The WCGS electrical power system is in a very high demand situation.
Maintenance work in progress is as follows:
- 1. The residual heat removal (RHR) system 'B' train pump and heat l exchanger have been removed from service for repair of a tube to shell side leak. Work has progressed to the poin': of reassembling the shell and associated component cooling water (CCW) lines.
Completion of repairs is estimated to take 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> of the 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> remaining before entering a technical specification action level.
- 2. SI Pump tagged out due to motor fault. The motor is not available locally and is being shipped in. It is not able to be repaired during the Exercise.
- 3. The concrete hatch in the roof of the 2026' level of the auxiliary building (aux bldg) has been removed to permit the removal of the RHR "B" train heat exchanger shell. A crane was used to remove the hatch. -
- 4. Auxiliary building (aux bldg) ventilation control is being provided by the fuel / aux b1dg normal exhaust system. A slight negative pressure is being maintained in the aux b1dg to ensure outside air flow is brought into the aux b1dg through the opened roof access.
- 5. Radiological controls at the opened roof access are being provided by a health physics technician. Security personnel are providing access controls.
Meteorolonical ,
It is an overcast and humid day with winds out of the eact-northeast at 12 mph. Daytime temperatures have been ranging from the low 80's to the upper 80's.
6 i
93-FE 3. 2
1 INITIAL CONDITIONS (Page 2 of 2)
Radiochemistry Following is the' latest isotopic analysis performhd on the reactor coolant system (RCS). The analysis was performed at 0730 the day of the Exercise.
Nuclide Activity (uCilec)
P Kr-83 3.83E-03 Kr-85m 1.17E-02 -
Kr-85 4.50E-04 '
Kr-87 2.12E-02 Kr-88 2.90E-02 Xe-133m 1.35E-03 Xe-133 5.11E-02 Xe-135m 1.42E-02 >
Xe-135 4.88E-02 Xe-138 4.34E-02 i I-131 2.59E-03 1-132 3.95E-03 I-133 5.81E-03 I-134 6.78E-03 I-135 5.27E-03 ,
RB-88 1.82E-03 CE-144 9.02E-08 TE-132 2.44E-04 Cs-134 2.26E-04 :
Cs-137 1.69E-04 Cs-138 1.64E-02 LA-140 1.35E-06 LA-142 3.01E-07 i BA-140 2.07E-06 s RCS I-131 Equiv. is 4.86E :
e is
[
3 93-FE 3. 3
SCENARIO NARRATIVE
SUMMARY
This scenario is based on a loss of coolant accident, reduced reactor coolant system makeup capacity, fuel failure, and a loss of containment building integrity following a hydrogen burn.
Initial conditions establish the plant operating normally at 100% full power.
Demand for electricity in the area is very high.
The residual heat, removal (RHR) system *B" train has been removed from service for repair of a tube to shell side leak in the heat exchanger. Repairs are estimated to be 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> away from completion.
The initiating event for the scenario occurs where the operators receive indications of a fire in the switchgear room no. 1. .Although the fire is extinguished within minutes by the halon fire protection system, 4160 volt bus NB01 experiences damage and deenergizes. Diesel generator *A' starts but is unable to reenergize the damaged bus. A Notification of an Dnusual Event is declared based on plant shutdown per Tech Spec. 3.0.3.
Offsite notifications should be made by the Shift Clerk per EPP 01-3.1. Site personnel are notified of the situation through the activation of the plant emergency alarm and the reading of the message found in EPP 01-2.2.
i Approximately thirty minutes later, a 1000 gpm LOCA occurs at normal operating pressures. The exact location of the LOCA is unidentified. Shortly after the LOCA, the reactor trips and safety injection occurs. An RCS cooldown is initiated and pressure drops, therefore the leak rate decreases. Adequate reactor coolant makeup water is supplied by the centrifugal charging pump (CCP) "B'.
An Alert is declared based on the loss ~of the reactor coolant system boundary. Offsite notifications are made and site personnel are notified of the situation. Accountability of personnel (simulated) inside the Protected Area Boundary (PAB) also occurs at this time. Thirty minutes after the Alert i is declared, the TSC is activated. Personnel will begin to staff the EOF, Wichita Rumor Control KCP&L Rwmor Control, and the Topeka Information Clearinghouse (IC).
Approximately an hour later, the size of the LOCA increases and the makeup capacity of CCP 'B' is exceeded. The SI accumulators discharge and the reactor vessel level indicating system (RVLIS) indicates water levels below the top of the core. Core exit thermocouple indications are >l2000 F.
A Site Area Emergency should be declared based on inadequate core cooling conditions but containment closure maintained. Offsite notifications are made, and site personnel are notified. At approximately the same time, the Rumor Control offices and the IC should be activated. Personnel will continue to staff the EOF, and the County and State EOCs should declare their facilities activated. Offsite protective action recommendations should inclade evacuation of John Redmond Reservoir (JRR).
]
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93-FE 3. 4 l l
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i
Over the next two hours, core exit thermocouples continue to increase to approximately 29000 F. and Containment Building (ctmt bldg) hydrogen levels exceed 4% as a zircaloy-water reaction is sustained by the elevated core temperatures. After approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> into the Exercise, a spontaneous hydrogen burn later causes ctmt b1dg pressure to spike to 47 pounds per square inch gauge (psig). The ctmt b1dg breaches at a failure of the etat b1dg mini purge exhaust penetration. A General Emergency is declared based on core uncovery with the RCS not intact and etmt. closure not set.
A filtered release path is provided to the environment through the ctmt b1dg breach to the plant unit vent. The release is monitored and consists almost entirely of noble gases. Offsite protective actions should include, as a minimum, evacuation of subzone 'CTR' and evacuation 2-5 miles downwind.
Conditions improve as the RER system "B' train is energized and the reactor vessel is refilled. Ctmt b1dg pressure continues dropping as it equalizes with the pressure in the auxiliary building and the release is terminated after approximately 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
Repairs are subsequently completed on 4160 volt bus NB01 thereby returning the emergency core cooling system "A" train to operability.
i 1
93-FE 3. 5 f l
1
TDIELINE A timeline sumary and chart indicating times of significant scenario is provided in the following subsection.
Operational events will occur as stated in the timeline, however, times vary slightly in order to provide players " freedom of play'.
s
$_ I 93-FE 3. 6 rp
TIMELINE
SUMMARY
TIME PLANT EVENT
SUMMARY
0730 (H-00:30) - Initial conditions:provided to the Shift Supervisor, the DED, AEC, DEC, REC, TSC, MEC, and the DSC Supervisor; plus the DEM, TRM, RAM and ARM. ,
0800 (H+00:00) - Field Exercise Activities begin.
0815 (H+00:15) NUE - Fire in switchgear room no. 1.
- Automatic activation of halon fire protection system.
- Decnergization of 4160 volt bus NB01.
- Loss of emergency core cooling system (ECCS) 'A' train. CTMT isolation damper GT HZ-12 fails open.
0820 (H+00:20) - Fire in switchgear room no. 1 extinguished by halon fire protection system.
0845 (H+00:45) ALERT - Unidentified loss of coolant accident (1000 gpm) (LOCA) at normal operating pressures.
- Makeup water adequate via centrifugal charging pump (CCP) "B' due to decreasing RCS pressure causing decreasing leak rate.
0847 (H+00:47) - Reactor / turbine trip.
0856 (H+00:56) - Ctmt b1dg pressure steadily increases. >5 psig in etmt.
0945 (H+01:45) - RCS leak rate rapidly increases.
T q - Makeup capacity exceeded for CCP "B'.
0955 (H+01:55) - Accumulator safety injection system
, discharges.
NOTE: Times are approrimations based on previous sinulator runs.
93-FE 3. 7
TIMELINE
SUMMARY
TIMI PLANT EVENT
SUMMARY
1000 (H+2:00) SAE - Reactor vessel level indication l system (RVLIS) indicates water level l below top of core. Core exit thermocouples increase to >l200 F, 0
1040 (H+2:40). - Hydrogen concentration levels inside the ctmt bldg increase.
- Core exit thermocouple temperatures continue to increase.
1100 (H+03:00) - Fuel damage confirmed by post-accident sampling system (PASS).
1200 (H+04:00) - Core exit thermocouples indicate temperatures consistent with a zircaloy-water reaction (>2900 0F).
- Hydrogen concentration levels inside the ctmt bldg exceed 42.
1215 (H+04:15) GE - Hydrogen burn within ctmt bldg.
- Ctmt bldg pressure spikes to 47 psig. The shock from the spike damages etmt bids isolation valve GT HZ-11, failing duct work.
- Ctmt bldg breaches at shutdown purge exhaust ducting penetration GT-V160.
- Containment spray actuation signal s (CSAS) generated. Containment spray pump 'B' starts and containment spray pump 'B' discharge valve EN HV-12' only opens to a 202 full open position.
1218 (H+04:18) - Plant unit vent. process radiation monitors and aux b1dg area radiation monitors (ARM) rapidly trend upscale. Release in progress.
93-FE 3. 8
TIMELINE i l
SUMMARY
. l TIME PLANT EVENT
SUMMARY
1318 (H+05:18) - Plant unit vent process radiation l monitors indicate release rates trending down.
1340 (H+05:40) - Repairs completed on RER Pump *B".
1345 (H+05:45) - RHR system started fran RWST.
- Reflooding of reactor core accomplished.
1350 (H+05:50) - Plant unit vent process radiation i monitors indicated near normal release rates. Ctmt bldg and aux bldg pressure differential nearly equalized. Release terminated.
1515 (H+07:15) - Repairs completed on 4160 volt bus NB01.
- Energizat'lon of the ECCS "A* train.
1530 (H+07:30) - Adequate core cooling initiated.
l
- Plant conditions stabilized.
1600 (H+08:00) - Drill. activities terminated.
Players' critique begin.
s 93-FE 3. 9
TINELINE CHART Initial conditions Established. 0730 > 0730 (H-00:30) l 0800 < 0800 Field exercise activities begin.
(H+00:00)
Fire in switchgear room No. 1. 0815 > g 0815 Deenergization of 4160 volt bus NB01. < 0820 Fire in switchgear room no. I loss of emergency core cooling system extinguished by automatic (halon)
(ECCS) 'A" train fire protection system.
IJnidentified loss of coolant accidect 0845 > < 0847 Reactor / turbine trip. A!J27 0845 (IDCA). Safety injection initiated. Makeup adequate via Centrifugal Charging Pump (CCF) "B'. 0900 (H+01:00)
< 0945 Reacter Coolant System (RCS) leak rate rapidly increases.
Makeup capacity exceeded CCP *B".
Reactor Vessel Indication System (RVLIS) 1000 > 1000 g 1000 indicates water level below to (H+02:00)
Core exit thermocouples >1200*p F. of core.
1100 < 1100 Post-Accident Sampling System (H+03:00) (Pass) confirms fuel damage.
< 1130 Hydrogen concentrations inside ctat b1dg continue to increase.
Hydrogen concentration inside ctat 1200 > 1200 b1dg exceede 41. (H+04:00)
< 1215 Hydrogen buen within etat b1dg. g 1215 Ctat pressure spike to 47 ? SIC.
Plant unit vent process radiation 1218 > Failure of cent bida purge and aux b1dg Area Radiation Monitors exhaust penetration. Ctat b1dg (ARM) rapidly trend upscale. Release breach. Ctat Spray Actuation in progress. Signal (CSAS) generated. Ctat spray pump *B* pumping 201 full flow due to partial opening of valve EN HV-12.
1300 (H+05:00)
< 1318 Plant unit vent process radiation monitors indicate release rates Repairs completed on RER Pump 'B'. 1340 > trending down.
< 1345 RERP "B" started on ctat b1dg sump recirculation phase. Reactor core Plant unit vent process radiation 1350 > re flooded.
monitore indicate near normal release rates. Release terminated.
1400 (H+06:00)
I 1500 (H+07:00)
Repaire completed on 4160 volt bus 1515 >
NB01. Energination of ECCS "A" < 1530 Adequate core cooling initiated.
train successful. Plant conditions stabilized.
Drill activities terminated. Players' 1600 > 1600 critique begin. (H+08:00) o
. 93-FE 3. 10
SECTION 4.0 CONTROLLER MESSAGES Subsections Pane ASSIGNMENTS 4.1 !
MESSAGES 4.2 SCENARIO 4.0-SC-MINI-SCENARIOS 4.0-MINI-PUBLIC INFORMATION 4.0-PI-WOLF CREEK PUBLIC INFORMATION OFFICER 4.0-PIO MEDIA INQUIRY - 4.0-MI PUBLIC CONCERN 4.0-PC MEDIA MONITORING 4 . 0-Mi MEDIA MESSENGER 4.0-MS OFFSITE 4.0-OFF-COUNTY 4.0-CEOC STATE 4.0-SEOC s
93-FE 4. 0 e
ASSIGNMENTS SCENARIO Messane # Time For From Location Assignment 001 0730 SS CR Lead Cont CR 002 0815 SS CR Lead Cont CR 003 0820+ CR Op CR Lead Cont Aux Bldg 004c 0830+ SS CR Lead Cont CR 005 0845+ DED/SS CR Lead Cont CR 006c 0900+ DED/SS CR Lead Cont CR 007c 0945+ DED TSC Lead Cont TSC 008 1100+ State EOF Lead Cont EOF 009 1215+ SEC Sec Lead Cont Sec Bldg 010 1230+ SS CR Lead Cont CR '
011c 1245+ DEM EOF Lead Cont EOF 012 1340 SS CR Lead Cont CR 013 1500+ SS CR Lead Cont CR 014 1515 SS CR Lead Cont CR 015 1600 All Part Fac Lead Conts All ASSIGNMENTS MINT-SCENARIOS 1 0815 --
Loss of 4160 Volt Bus NB01 2 0800+ -- RHR System 'B' Train 3 0800+ --
Aux Bldg Concrete Roof Hatch 4 0830+ --
Isolation Valve GT HZ-12 5 1215 --
EN HV-12 Valve 93-FE 4. 1
I l i ASSIGIGENTS WOLF CREEK PUBLIC INFORMATION OFFICER 1
Messane # Time For From Location Assinnment PIO-1 0845 WC PIO Reporter Wich !
PIO-2 0850 WC PIO Reporter Wich PIO-3 0910 WC PIO Reporter Wich PIO-4 0920 WC PIO Reporter Wich l PIO-5 0945 'fC PIO Reporter Vich PIO-6 1001 WC PIO Congressional Wich Aide ASSIGNMENTS MEDIA INOUIRY Messane # Time For From Location Assignment MI-1 0940 Media Inq Reporter Wich MI-2 0945 Media Inq Reporter Wich HI-3 0950 Media Inq Reporter Wich MI-4 1000 Media Inq Reporter Wich MI-5 1005 Media Inq Reporter Wich MI-6 1010 Media Inq Reporter Wich MI-7 1015 Media Inq Reporter Wich MI-8 1020 Media Inq Reporter Wich MI-9 1025 Media Inq Reporter Wich MI-10 1030 Media Inq Reporter Wich MI-11 1035 Media Inq Reporter Wich MI-12 1040 Media Inq Reporter Wich MI-13 1045 Media Inq Reporter Wich 93-FE 4, 2 4
ASSIGIDMIETS MEDIA INOUIRY Messane # Time For From Location Assinnmunt MI-14 1050 Media Inq Reporter Wich HI-15 1055 Media Inq Reporter Wich MI-16 1100 Media Inq Reporter Wich MI-17 1105 Media Inq Reporter . Wich MI-18 1110 Media Inq Reporter Wich MI-19 1115 Media Inq Reporter Wich MI-20 1120 Media Inq Reporter Wich MI-21 1130 Media Inq Reporter Wich MI-22 1140 Media Inq Reporter Wich MI-23 1150 Media Inq Reporter Wich MI-24 1155 Media Inq Reporter Wich MI-25 1205 Media Inq Reporter Wich MI-26 1220 Media Inq Reporter Wich MI-27 1230 Media Inq Reporter Wich MI-28 1240 Media Inq Reporter Wich MI-29 1250 Media Inq Reporter Wich MI-30 1300 Media Inq Reporter Wich MI-31 1310 Media Inq Reporter Wich MI-32 1320 Media Inq Reporter Wich MI-33 1330 Media Inq Reporter Wich MI-34 1340 Media Inq Reporter Wich MI-35 1350 Media Inq Reporter Wich MI-36 1400 Media Inq Reporter Wich MI-37 1405 Media Inq Reporter Wich MI-38 1410 Media Inq Reporter Wich _
l MI-39 1415 Media Inq Reporter Wich !
MI-40 1420 Media Inq Reporter Wich l HI-41 1425 Media Inq Reporter Wich MI-42 1430 Media Inq Reporter Wich MI-43 1435 Media Inq Reporter Wich MI-44 1440 Media Inq Reporter Wich MI-45 1445 Media Inq Reporter Wich MI-46 1450 Media Inq Reporter Wich i MI-47 1455 Media Inq Reporter Wich MI-48 1500 Media Inq Reporter Wich MI-49 1505 Media Inq Reporter Wich MI-50 1510 Media Inq Reporter Wich MI-51 1515 Media Inq Reporter Wich )
MI-52 1520 Media Inq Reporter Wich MI-53 1525 Media Inq Reporter Wich HI-54 1530 Media Inq Reporter Wich HI-55 1535 Media Inq Reporter Wich MI-56 1540 Media Inq Reporter Wich MI-57 1545 Media Inq Reporter Wich 93-FE 4. 3
ASSIGNMENTS PUBLIC CONCERN PHONE TEAM Messane # Time For From Location Assinnment PC-1 0940 Pub Con Citizen Wich PC-2 0945 Pub Con Citizen Wich PC-3 0950 Pub Con Citizen Wich PC-4 0955 Pub Con Citizen Wich PC-5 1000 Pub Con Citizen Wich PC-6 1005 Pub Con Citizen Wich~
PC-7 1010 Pub Con Citizen Wich __,
PC-8 1015 Pub con Citizen Wich PC-9 1020 Pub Con Citizen Wich PC-10 1030 Pub Con Citizen Wich PC-11 1040 Pub Con Citizen Wich PC-12 1045 Pub Con Citizen Wich PC-13 1050 Pub Con Citizen Wich PC-14 1055 Pub Con Citizen Wich PC-15 1100 Pub Con Citizen Wich PC-16 1105 Pub Con Citizen Wich PC-17 1110 Pub Con Citizen Wich PC-la 1120 Pub Con Citizen Wich PC-19 1130 Pub Con Citizen Wich PC-20 1140 Pub Con Citizen Wich PC-21 1150 Pub Con Citizen Wich
~
PC-22 1200 Pub Con Citizen Wich PC-23 1210 Pub Con Citizen Wich PC-24 1220 Pub Con Citizen Wich PC-25 1230 Pub Con Citizen Wich PC-26 1240 Pub Con Citizen Wich PC-27 1250 Pub Con Citizen Wich PC-28 1300 Pub Con KG&E Employee Wich PC-29 1310 Pub Con Citizen Wich PC-30 1320 Pub Con Citizen Wich PC-31 1330 Pub Con Citizen Wich PC-32 1340 Pub Con Citizen Wich PC-33 1350 Pub Con Citizen Wich I PC-34 1400 s Pub Con Citizen Wich PC-35 1405 Pub Con Citizen Wich PC-36 1410 Pub Con Citizen Wich
'PC-37 1415 Pub Con Citizen Wich PC-38 1420 Pub Con Citizen Wich ,__
PC-39 1425 Pub Con City of Wich ___
Wichita PC-40 1430 Pub Con Citizen Wich PC-41 1435 Pub Con Citizen Wich PC-42 1440 Pub Con Citizen Wich __,
PC-43 1445 Pub Con Citizen Wich PC-44 1450 Pub Con Citizen Wich PC-45 1455 Pub Con Citizen Wich ~
PC-46 1500 Pub Con Citizen Wich !
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l 93-FE 4. 4 i
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ASSIGIDGDtTS PUBLIC CONCERN PHONE TEAM Message i Time For From Location Assinnment PC-47 1505 Pub Con Citizen Wich PC-48 1510 Pub Con Citizen Wich PC-49 1515 Pub Con Reporter Wich PC-50 1548 Pub Con Citizen Wich PC-51 1525 Pub Con Citizen Wich PC-52 1530 Pub Con Citizen Wich
. FC-53 1535 Pub Con Citizen Wich PC-54 1540 Pub Con Citizen Wich PC-55 1545 Pub Con Citizen' Wich 93-FE 4. 5
i ASSIG1902TS MEDIA MONITORING l
Message # Time For From Location Assignmeht i MM-1 0900 Med Mon Radio Wich/KCPL l MM-2 0910 Med Mon TV Wich/KCPL MM-3 0920 Med Mon TV Wich/KCPL MM-4 0930 Med Mon Radio Wich/KCPL MM-5 0940 Med Mon Radio Wich/KCPL MH-6 0950 Med Mon Radio Wich/KCPL MM-7 1000 Med Mon TV Vich/KCPL MM-8 1010 Med Mon TV Vich/KCPL MM-9 1020 Med Mon Radio Wich/KCPL MM-10 1030 Med Mon TV Wich/KCPL MM-11 1040 Med Mon TV Wich/KCPL MM-12 1050 Med Mon Radio Wich/KCPL MM-13 1100 Med Mon Radio Wich/KCPL MH-14 1110 Med Mon Radio Wich/KCPL HH-15 1120 Med Mon Radio Wich/KCPL HH-16 1130 Med Mon TV Wich/KCPL MM-17 1140 Med Mon TV Wich/KCPL MH-18 1150 Med Mon TV Wich/KCPL MM-19 1200 Med Mon TV Wich/KCPL MM-20 1205 Med Mon Radio Wich/KCPL MH-21 1210 Med Mon TV Wich/KCPL MM-22 1220 Med Mon TV Wich/KCPL MH-23 1225 Med Mon TV Wich/KCPL MM-24 1235 Med Mon Radio Wich/KCPL MH-25 1245 Med Mon TV Wich/KCPL HM-26 1255 Med Mon Radio Wich/KCPL KH-27 1305 Med Mon TV Wich/KCPL HH-28 1315 Med Mon TV Wich/KCPL __
MM-29 1325 Med Mon Radio Wich/KCPL MM-30 1335 Med Mon TV Wich/KCPL MM-31 1345 Med Mon Padio Wich/KCPL HH-32 1350 Med Hon Radio Wich/KCPL MM-33 1400 Med Mon Radio Wich/KCPL MM-34 1410 , Med Mon Radio Wich/KCPL HH-35 1420 Med Mon TV Wich/KCPL MM-36 1425 Med Mon Radio Wich/KCPL MM-37 1430 Med Mon Radio Wich/KCPL MM-38 1435 Med Mon Radio Wich/KCPL MM-39 1445 Med Mon TV Wich/KCPL MM-40 1450 Med Mon Radio Wich/KCPL MM-41 1500 Med Mon TV Vich/KCPL MH-42 1505 Med Mon Radio Wich/KCPL KH-43 1510 Med Mon Radio Wich/KCPL MH-44 1520 Med Mon TV Wich/KCPL MH-45 1530 Med Mon Radio Wich/KCPL MM-46 1540 Med Mon Radio Wich/KCPL _,
93-FE 4. 6
ASSIGI9fENTS MEDIA MESSENGER Messane i Time For From Location Assinnment MS-1 1000 Med Msg Reporter MRC MS-2 1015 Med Msg Reporter MRC MS-3 1030 Med Msg Reporter MRC MS-4 1050 Med Msg Reporter MRC MS-5 1110 Med Msg Reporter MRC MS-6 1130 Med Msg Editor MRC MS-7 1150 Med Msg Editor MRC MS-8 1210 Med Msg Citizen MRC MS-9 1230 Med Msg Reporter MRC MS-10 1250 Med Msg Reporter MRC MS-11 1315 Med Msg Reporter MRC MS-12 1335 Med Msg Reporter MRC MS-13 1350 Med Msg Reporter MRC MS-14 1410 Med Msg Reporter MRC MS-15 1425 Med Msg Reporter MRC MS-16 1435 Med Msg Reporter MRC MS-17 1445 Med Msg Reporter MRC MS-18 1455 Med Msg Editor MRC MS-19 1505 Med Msg Reporter MRC MS-20 1515 Med Msg Reporter MRC MS-21 1520 Med Msg Reporter MRC MS-22 1530 Med Msg Reporter MRC 93-FE 4, 7
ASSIG19(ENTS COFFEY COUNTY EOC Hessane i Time Zorr, From Location Assignment CEOC-1 0850 Emrg Prep Citizen County EOC CEOC-2 0930 Commissioners Citizen County EOC CEOC-3 1000 Emrg Prep KMBC-TV County EOC CEOC-4 1030 RO Media County EOC CEOC-5 1100 County Eng Access Ctl County EOC Personnel CEOC-6 1230 RO Fire Leader County EOC CEOC-7 1300 Sheriff Storekeeper County EOC CEOC-8 1330 Commissioners Senator's County EOC Aide CEOC-9 0925 County Agent Farmer County EOC CEOC-10 1400 SSO Allen Co County EOC EPC CEOC-11 1415 HMMT Waverly County EOC' Nurs. Home CEOC-12 1500 SSO Host County County EOC ASSIGNMENTS STATE EOC Messane i Time For From Location Assignment SEOC-1 1030 Dir. KDEP FEMA State EOC SEOC-2 1100 KNG KDWP State EOC SEOC-3 1230 Dir. KDEP FEMA State EOC _
SEOC-4 1300 KDOT Goodwin State EOC _
Construction SEOC-5 1330 KNG CR0 State EOC SEOC-6 1400 KDWP Citizen State EOC SEOC-7 1415 KHP Governor's State EOC Office SEOC-8 1430 KBOA Governor's State EOC Press Sec.
SEOC-9 1500 KBOA County Agent State EOC SEOC-10 1515 KDHE EPA State EOC SEOC-11 1600 KDWP US Fish fr State EOC Wildlife 93-FE 4. 8 e
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HESSAGES l
A complete listing of messages included in this scenario is provided in the j following subsection. Information necessary in making and tracking message i assignments is provided for each message.
The list is categorized by message type, recipient or facility, and finally i by message number. A space for assigning controllers responsible for the message is included.
The scenario messages are provided to instigate actions at various facilities. More detail for particular maintenance activities is provided in the mini-scenarios.
i s
93-FE 4. 2 b
G
~ ~ . -
MESSAGES SCENARIO Time-related scensrio messages are provided in the following subsection. ,
These messagss' provide actions and responses that drive the scenario.
d 9
t 93-FE 4-SC- 0
MESSAGE NO: 001 THIS IS A DETT t-DO NOT initiate actions affecting normal plant operations.
TO: Shift Supervisor FROM: CR Lead Controller LOCATION: Control Room TIME: 0730 (H+00:30)
MESSAGE: Initial Conditions are as follows:
Operationally See attached forms.
Radiochemically RCS I-131 Equiv. is 4.86 E-03.
Meterologically It is an overcast and humid day with winds out of the east-northeast at 12 mph. Daytime temperatures have been ranging from the low 80's to the uppr 80's. j 1
Additional information such as work orders in progress will also l be provided at this time. j I
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THIS IS A DRILL l
93-FE 4-SC- 1 O
ATTACHMENT 1 K02-001A SHIFT SUPERVISOR RELIEF CHECKLIST ;
OFF-GOING SHIFT OFF-GOING SS (PRINT): HERHOLD ;
(ENTER SHIFT) MID DATE 9/1/93 ON-COMING SS (PRINT):
PLANT STATUS
SUMMARY
- ON-COMING SS REVIEW PRIOR TO AS MING SHIFT (CHECK l MODE: 1 l EVOLUTIONS IN PROGRESS: ((7
@ 100% MOL FOR 73 DAYS ,W i O GT HZ-12 WILL NOT CLOSE. GT HZ-11 CLOS D DE-ENERGIZED. REFERENCE T/S
[
3.6.3 b ,=, .
,5QV, .
AV xx SIGNIFICANT MAINTENANCE IN PROGRESS:
@ 'B' SI PUMP OOS DUE TO A MQTDK FAULT. REPLACEMENT MOTOR BEING PROCURED.
O 'B' RHR PUMP OOS TO REPAfDIEAT EXCHANGER TUBE LEAK G 'C' CONDENSER VACUtaf EOMP OOS FOR MIC INSPECTION OF COOLER t A>
SIGNIFICANT TESTING /RESTDRATION IN PROGRESS OR PENDING:
@ PB03 FEEDER BREAKER PB0306 IS OOS FOR ROUTINE BREAKER TESTING. BUSES PB03 AND PB04 ARE CROSS-TIED. '
3 RADWASTE STATUS: NORMAL i
GENERAL:
l REVIEW THE FOLLOWING PRIOR TO ASSUMING SHIFT:
~ ~
~
SHIFT SUPERVISOR'S LOG ACTION STATEMENT
SUMMARY
STANDING /SPECIAL ORDERS SHIFT CREW COMPOSITION (PAGE 2)
EQUIP. OUT OF SERVICE LOG SURVEILLANCE SCHEDULE LICENSED OPERATOR QTR SIGN-OFF LOG UPDATED /
REVIEW THE FOLLOWING AFTER AS5UMING SHIFT: ;
TEMP. MODIFICATION LOG FIRE PROTECTION IMPAIRMENTS DISCHARGE PERMITS IN IGNITION SOURCE PERMITS i EFFECT COMBUSTIBLE MATERIAL PERMITS CLEARANCE ORDER INDEX l
] CONTROL ROOM LOG OPERATIONS TRACKING PROGRAM UPDATEET / '
OFF-GOING SS LSH ON-COMING SS INITIALS . INITIALS PAGE 1 OF 2 ADM 02-010 REV. d Page 7 of 17
ATTACHMENT 1 K02-001 A SHIFT SUPERVISOR RELIEF CHECKLIST SHIFT COMPOSITION SHIFT SUPERVISOR "
O.
AQ SUPERVISING OPE @70R V
e REACTOR OPERATOR A.
e /s BALANCE OF PLANT AUX BLDG WATCH TURBBLDG WATCH RWSTE BLDG WATCH SITE WATCH 4W v
WATER TREATMENT FIRE BRIGADE BRIGADE LEADER MEMBER MEMBER MEMBER MEMBER OTHER CALL SUPERINTENDENT HP TECHNICIAN CHEMISTRY TECHNICIAN PAGE 2 OF 2 ADM 02-010 Rev9 d Page 8 of 17 3 4
9 9
4
ATTACHMENT 2 K02-001B
] SUPERVISING OPERATOR RELIEF CHECKLIST OFF-GOING SHIFT OFF-GOING SO (PRINT): CRAIGHEAD (ENTER SHIFT) MID DATE 9/1/93 ON-COMING SO (PRINT):
PLANT STATUS
SUMMARY
- ON-COMING SS REVIEW PRIOR TO AS UMING SHIFT .
(CHECK l MODE: 1 J EVOLUTIONS IN PROGRESS: CP'
@ 100% MOL FOR 73 DAYS AQp~
0 GT HZ-12 WILL NOT CLOSE. GT HZ-11 CLOSF D DE-ENERGIZED. REFERENCE T/S 3.6.3 b p AW AV -
M gv ,
e i db' v
XY ,
SIGN!FICANT MAINTENANCE IN PROGRESS:
@ 'B' S1 PUMP OOS DUE TO A MOTOR FAULT. REPLACEMENT MOTOR BEING PROCURED.
O 'B' RHR PUMP OOS TO REPAIR HEAT EXCHANGER TUBE LEAK G 'C' CONDENSER VACUUM PUMP OOS FOR MIC INSPECTION OF COOLER i
SIGNIFICANT TESTING / RESTORATION IN PROGRESS OR PENDING:
@ PB03 FEEDER BREAKER PB0306 IS OOS FOR ROUTINE BREAKER TESTING. BUSES PB03 j AND PB04 ARE CROSS-TIED. I
)
RADWASTE STATUS: NORMAL GENERAL:
4 PAGE 1 OF 2 ADM 02-010 )
REV.c Page 9 of 17
ATTACHMENT 2 K02-001B SUPERVISING OPERATOR RELIEF CHECKLIST REVIEW THE FOLLOWING PRIOR TO ASSUMING SHIFT:
- ~
CONTROL ROOM LOG SHIFT CRijiW COMPOSITION STANDING /SPECIAL ORDERS RO TUF3NOVER CHECKLIST
~
EQUIP. OUT OF SERVICE LOG ~
SURVEKfANCE SCHEDULE ACTION STATEMENT
SUMMARY
K94)Qif' ALARMS NOT INHIBITED u.
sw REVIEW THE FOLLOWING AFTER ASSUMING SHIFJ@f
~
~
TEMP. MODIFICATION LOG / FIRE PROTECTION IMPAIRMENTS
~
DISCHARGE PERMITS IN EFFECT XtW ~
IGNITION SOURCE PERMITS
~
CLEARANCE ORDER INDEX AV -
COMBUSTIBLE MATERIAL PERMITS LOCKED VALVE LOG
-v
$37 -
CONDUCT CREW BRIEFING lW PRIOR TO SHIFT TURNOVER, OFF-GOINCrSO ATTACH ANY ADDITIONAL PAGES 7 REVIEW CONTROL ROOM NGS NEEDED TO DESCRIBE PLANT 7 REVIEW RADWASTE LO d' CONDITIONS AND MARK THE NUMBER
] ENSURE COMPONENT CVCLIC OR NEEDED TO DESCRIBE PLANT TRANSIENT LIMIT LOG (CCOTLL) OF CONTINUATION PAGES l0 l iS UPDATED OFF-GOING SO KDC ON-COMING SO o INITIALS INITIALS PAGE 2 OF 2 ADM 02-010 Rev. c Page 10 of 17
" P -
ATTACHMENT 3 K02-001C REACTOR / BALANCE OF PLANT OPERATOR TURNOVER CHECKLIST DATE: 9/1/93 l OFF-GOING SHIFT: (ENTER SHIFT) l MIDS l MODE 1 OFF-GOING: RO SWARTZENDRUBE ON-COMING: RO R
(PRINT) BOP WINZENREID (PRI p. BOP PI ANT STATUS
SUMMARY
- ON-COMING RO AND BOP GVlEW PRIOR TO ASSUMING SHIFT RO BOP A' (CHECK BOX)
/M EVOLUTIONS IN PROGRESS: N'
@ 100% MOL FOR 73 DAYS /*4 O GT HZ-12 WILL NOT CLOSE. GT 51FCLOSED AND DE-ENERGlZED, REFERENCE T/S 3.6.3 b (
3 sy (V
M Ti
[ MAINTENANCE IN PROGRESS:
@ 'B' S1 PUMP OOS DUE TO A MOTOR FAULT. REPLACEMENT MOTOR BEING PROCURED.
O 'B' RHR PUMP OOS TO REPAIR HEAT EXCHANGER TUBE LEAK G 'C' CONDENSER VACUUM PUMP OOS FOR MIC INSPECTION OF COOLER TESTING IN PROGRESS:
@ PB03 FEEDER BREAKER PB0306 IS OOS FOR ROUTINE BREAKER TESTING.
BUSES PB03 AND PB04 ARE CROSS-TIED.
[ COMMENTS:
e PAGE 1 OF 3 ADM 02-010 REV. d Page 11 of 17
ATTACHMENT 3 K02-001C REACTOR / BALANCE OF PLANT OPERATOR TURNOVER CHECKLIST i ROD CONTROL:
[/ MANUAL AUTO ROD POSITION A R C D F SHUTDOWN BANKS , 4 29 229 229 229 229 i CONTROL BANKS 4 29 229 229 229 XENON: REACTO R: 3411 MW 100 %
] lr4 CREASING DECREASING TURBI WER: 1192 MWE
] EQUILlBRIUM TAVG 538.5 'F PZR PRESS 2235 PSIG 660- PPM DATE/ TIME 9/1/93 0430 RCS LEAKRATE: IDENT 1.1 GPM ,
UNIDENT .023 DATE/ TIME 9/1/93 0430 (Note in Comments ifk#ethod other than STS BB-004 is used) >
ESF STATUS PANEL SA066X, YWAND REACTOR PARTIAL TRIP / BLOCK PANEL SB069 SA066Y 'B' SI PlJP3P., ' OOS DUE TO A MOTOR FAULT.
SA066Y 'B' R ifpCMP OOS TO REPAIR HEAT EXCHANGER TUBE '
LEAK i
PROTECTION GRADE PERMISSIVE LIGHTS CONTROL GRADE PERMISSIVE LIGHTS ON OFF ON OFF ON OFF ON OFF '
P6 / P10 / C2 / C9A /
P7 / P11 / C3 / C9B /
P8 # P12 / C4 / C9C /
P9 / P13 / C5 / C16 /
C7 /
CHECK OPERATING EQUIPMENT A CCP A MD AFP LETDOWN ORIFICE / A CCW PMP SERVICE LOOP BCCP B MD AFP A C CCW PMP / A TRAIN
/ PDP TD AFP B B CCW PMP B TRAIN '
/ C D CCW PMP A BAT RECIRC BL ON RECIRC B BAT RECIRC BL FILLING 1
PAGE 2 OF 3 'l ADM 02-010 2 REV. d I Page 12 of 17 !
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ATTACHMENT 3 K02-001C REACTOR / BALANCE OF PLANT OPERATOR TURNOVER CHECKLIST CHECK OPERATING EQUIPMENT CONDENSATE
/ A MFP MAIN TURBINE STATUS / A CIRC WTR PMP DEMINS
/ BMFP / OPERATING / B CIRC WTR PMP STATUS MDMFP SECURED / C CIRC \ P A /
ON TURNING GEAR B /
7 A COND. PMP AUX STEAM SOURCE 7 A SE WTR PMP C
/ B COND. PMP AUX BOILER / 8 VICE WTR PMP D
^
, 2; RVICE WTR PMP E GLAND STEAM SOURCE '
'E W FLOW PMP F
/ A HDP AUX STEAM
/ B HDP / MAIN STEAM A ESW B ESW L.P. HEATERS IN SERVICE: / YES . Ch TRING A B C H.P. HEATERS IN SERVICE / YES 6 - STRING A B S/G TOTAL BLOWDOWN FLOW Jh kibm/HR TO CONDENSER LAKE AP FILLING Mff FILLING .
LEAD AIR COMPRESSOR A B C READING SHEETS REVIEWED:
7 AUX BUILDING READINGS DAILY SITE READINGS (NIGHT SHIFT) 7 TURBINE BUILDING READINGS ON-COMING RO AND BOP REVIEW -
PRIOR TO ASSUMING SHIFT
[ [ CONTROL ROOM LOG SHIFT CREW COMPOSITION (THESE MAY BE REVIEWED AFTER ,
_ _ _ _ ASSUMING SHIFT)
EQUIPMENT OUT OF SERVICE LOG LOCKED VALVE LOG ACTION STATEMENT
SUMMARY
FIRE PROTECTION IMPAIRMENTS INSTRUMENT OUT OF SERVICE LOG COMBUSTIBLE MATERIAL PERMITS SURVEILLANCE SCHEDULE _ _
COMPUTER ALARM
SUMMARY
DISCHARGE PERMITS NIGHT ORDERS :
CLEARANCE ORDER LOG -
STANDING /SPECIAL ORDERS .
[ ] IGNITION SOURCE PERMITS TEMPORARY MODIFICATION LOG CHART RECORDERS '
ATTACH ANY ADDITIONAL PAGES NEEDED TO DESCRIBE PLANT CONDITIONS MARK THE NUMBER OF ADDITIONAL PAGES l 0 l OFF GOING: RO CAS ON COMING: WALKED DOWN MCB, CHECK INITIALS FOR BURNED OUT LIGHTS RO BOP BKW INITIALS BOP ,
INITIALS PAGE 3 OF 3 '
ADM 02-010 ,
REV. d .
Page 13 of 17 i
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ATTACHMENT 1
- EQUIPMENT OUT OF SERVICE LOG ADM 02-105 1 2 3 DECLARED 4 REQUIRED 5 6 MODE 7 TECHNICAL 8 RETURNED TO YR SYS INOPERABLE RETURN APPLICABLE MODES RESTRAINT SPECIFICATIONS OPERABLE EOL DESIG DATE l TIME l SS DATE l TIME l SS 1 l2 l3 l4 l5 l6 l ALL DATE l TIME l SS 9 REMARKS / EQUIPMENT /MWR/TMO/CO/ RETEST 93- CG S'2"3 1543 KD- N/A N/A N/ * * * * *
- N/ N/A N/A 156 g ^ ^ ^ ^ ^ ^
A g
'C' CONDENSER VACUUM PUMP OOS FOR MIC INSPECTION OF ITS COOLER A
93- EM 8'3'S3 KD 9'3'93 KD / / /
157 0211 0211 Q MODE l,2 & 3.5.2 p
R R 3
'B' SAFETY INJECTION PUMP (PE.!01B) DUE TO MOTOR FAULT. Y 93-158 EJ 53383 0740 KD R
383 10740 KD R
- - /
%%~
- MODE l,2 &
3 3.5.2
'B' RilR PUMP (PEJ01B) AND 'B' RilR llEAT EXCIIAN $101B) TO REPAIR IIEAT EXCIIANGER TUBE LEAK PB 9/1/93 0602 KD N/A N/A N/' NI N N/ N N/ '
N/ N/A N/A l R A A PB0306 OOS FOR BREAKER TESTING. PB03 AND PB04 ARE CROSS-TIED ADM 02-105
- Rev. 8
-Page 6 of 6
-. -. -. , - . . - . . . ~ . .
ATTACHMENT 1 EQUIPMENT OUT OF SERVICE LOG ADM 02-105 . ,
1 2 3 DECLARED 4 REQUIRED 5 6 MODE 7 TECHNICAL 8 RETURNED TO YR SYS INOPERABLE RETURN APPLICABLE MODES RESTRAINT SPECIFICATIONS OPERABLE' EOL DESIG DATE l TIME l SS DATE l TIME l SS 1 l2 l3 l4 l5 l6 l ALL 9
DATE l TIME l SS R E MAR KS/EQ U1 P M E NT/MWR/T M O/CO/R ETEST 93- GT 9/1/9 0615 KD N/A N/A N/ / / / / MODE 1,2,3, 3.6.3 160 3 R A &4 GT IIZ-12 WILL NOT CLOSE. GT112-11 IS CLOSED AND DE-ENERGlZED IN ACCORDANCE WITilT/S 3.6.3 b.
A g
AV v
A
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ADM 02-105 Rev.8 Page 6 of 6
..y , = w . w w e , i.,, - - - . . -. -.u , m u.= _ . . . _ _ _ _
ATTACHMENT 6 ACTION STATEMENT
SUMMARY
LOG E.O L. # TECH. SPEC. # ENTERED DEADLINE REMARKS RESTORED
. YR DATE l TIME l SS DATE l TIME l SS DATE l TIME l SS 93-1 3.5.2 8/31/93 0211 9/3/93 0211 'B' S1 PUMP OOS DUE TO KDR KDR ??????
93-2 3.5.2 8/31/93 0211 9/3/93 0211 TO REPAIR 'B' RifR HEAT .
KDR KDR EXCIIANGER TUBE LEAK A i
<V A
V d
M ,
/%
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. M g.
ADM 02-010 Rev.a Page 16 of 16
- .- -- _ _ . -_ -- -- w - -- __.n - - - , v _ ,, -w ,--w- e a , - -- _.-e--
& ~:
4 MESSAGE NO: 002 i
THIS IS A DRILL M NOT initiate actions affecting normal plant operations.
To: Shift Supervisor FROM: CR Lead Controller LOCATION: Control Room TIME: 0815 (H+00:15)
MESSAGE: You have just received indications of a halon discharge on fire protection panel KC008.
NOTE: This message is only provided if the simulator fails.
THIS IS A DRILL 93-FE 4-SC- 2 a
MESSAGE NO: 003 THIS IS A DRILL JX} NOT initiate actions affecting normal plant operations.
TO: Control Room Operator FROM: Auxiliary Building Operator (CR Lead Controller)
LOCATION: Auxiliary Building (Switchgear Room No. 1)
TIME:
0820+ (H+00:20+)
MESSAGE: The fire appears to have been totally extinguished by the halon fire protection system.
NOTE: This message is only provided if the simulator fails.
I l.
THIS IS A DEILL 93-FE 4-SC- 3 ,
i
MESSAGE NO: 004c
/
THIS IS A DRILL
- 20. NOT initiate actions affecting normal plant operations.
TO: Shift Supervisor FROM: CR Lead Controller LOCATION: Control Room TIME: 0830+ (H+00:30+)
MESSAGE: A Notification of an Unusual Event should have been declared based on a plant shutdown per Tech Spec. 3.0.3 (loss of both trains of ECCS).
NOTE: p_0 NOT pass this message without the consent of the Exercise Lead Controller.
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l THIS IS A DRILL _j 93-FE 4-SC- 4 Y
MESSAGE NO: 003 THIS IS A DRILL
,DQ NOT initiate actions affecting normal plant operations.
TO: Duty Emergency Director / Shift Supervisor FROM: CR Lead Controller LOCATION: Control Room TIME: 0845+ (H+01:45+)
MESSAGE: A 1000 gallon per minute LOCA occurs. The reactor and turbine trip.
NOTE: This message is only provided if the simulator fails.
.o g
e j.
THIS IS A DRILL 93-FE 4-SC- 5
- 6
MESSAGE NO: 006c THIS IS A DRILL DQ NOT initiate actions affecting normal plant operations.
TO: Duty Emergency Director / Shift Supervisor FROM: CR Lead Controller LOCATION: Control Room. 'i TIME: 0900+ (H+02:00+)
MESSAGE: An Alert should have been declared based on the loss of one fission product barrier.
NOTE: Do not pass this message without the consent of the Exercise Lead Controller.
THIS IS A DRILL 93-FE 4-SC- 6
MESSAGE NO: 007c THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
TO: Duty Emergency Director PROM: TSC Lead Controller LOCATION: Technical Support Center TIME: 1000+ (H+02:00+)
MESSAGE: A Site Area Emergency should have been declared based on inadequate core cooling conditions with containment closure intact.
NOTE: DO NOT pass this message without the consent of the Exercise Lead Controller, t
THIS IS A DRILL J 93-FE 4-SC- 7 l
MESSAGE NO: '008 THIS IS A DRILL J)O NOT initiate actions affecting normal plant operations.
To State Liaison in the EOF
~
FROM: EOF Lead Controller LOCATION: EOF TIME: 1100+ (H+03:00+)
MESSAGE: Please perform a shift change at this time.
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THIS IS A DRILL 1
1 93-FE 4-SC- 8 l
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. . . . . . . _ . ~ . . . - -.-
MESSAGE NO: 009 THIS IS A DEILL JX} NOT initiate actions affecting normal plant operations.
TO: Security Personnel ,
FROM: Security Controller LOCATION: Security Building TIME: 1215+ (H+04:15+)
HESSAGE: All portal monitors start alarming.
THIS IS A DRILL 93-FE 4-SC
- e
MESSAGE NO: 010 THIS IS A DRTT.T. .
DO NOT initiate actions affecting normal plant operations.
l T0: Shift Supervisor FROM: CR Lead Controller LOCATION: Control Room TIME: -1230 (H+08:30)
MESSAGE: You have just been told that all portal monitors in the Security Building have alarmed.
NOTE: DO NOT pass this message unless the SEC does not relay this information to the Control Rooms.
1
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l THIS IS A DRILL l
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93-FE 4-SC- 10
2 l
l MESSAGE NO: Olle THIS IS A DETY.f.
20 NOT initiate actions affecting normal plant operations.
TO: Duty Emergency Manager FROM: EOF Lead Controller i
LOCATION: Emergency Operations Facility TIME: 1245+ (H+04:45+)
MISSAGE: A General Emergency should have been declared' based on core I uncovery with the containment closure not intact.
NOTE: 20 NOT pass this messa5e without the consent of the Exercise Lead Controller.
?
THIS IS A DRILL I
93-FE 4-SC- 11
MESSAGE Non- 012 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
TO: Shift Supervisor
- FROM: CR Lead Controller LOCATION: Control Room TIME: 1340 (H+05:40)
MESSAGE: You have completed sufficient repairs on the residual heat removal system "B" train to penmit its use.
NOTE: This message is only provided if the ERDC teams do not relay the above information to the Control Room after effecting repairs.
THIS IS A DRILL 93-FE- 4-SC- 12
)
t MESSAGE NO:- 013 THIS IS A DRILL 20 NOT initiate actions af fecting normal plant operations.
TO: Shift Supervisor FROM: CR Lead Controller .
LOCATION: Control Room TIME: 1500 (H+07:00) '
MESSAGE: The concrete hatch has been replaced in the roof of the 2026' level of the auxiliary building.
NOTE: This message is only provided if the ERDC teams do not relay the above information to the Control Room after effecting .,
repairs. '
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1 THIS IS A DRILL ,
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93-FE 4-SC- 13
MESSAGE WO: 014 THIS IS A DRILL DQ NOT initiate actions affecting normal plant operations.
TO: Shift Supervisor FROM: CR Lead Controller LOCATION: Control Room TIME: 1515 (H+07:15)
MESSAGE: You have completed repairs on the 4160 volt bus NB01.
Energization of the bus can be safely accomplished.
NOTE: This message is only provided if the ERDC teams do not relay the above information to the Control Room after effecting repairs.
THIS IS A DRILL 93-FE 4-SC- 14
~
MESSAGE NOt- 015- ,
THIS IS A DETTf.
19 NOT initiate actions affecting normal plant operations.
TO: All Participants FROM: Facility Lead Controllers LOCATION: Emergency Response Facilities TLHE: 1600 (H+08:00)
HESSAGE: Exercise activities have been tenninated. Collect all logs.
notes, etc. and give them to Facility Lead Evaluator.
Participants should prepare for a players' critique.
NOTE: DO NOT pass t.his message without the consent of the Exercise Lead Controller.
s P
1 THIS IS A DRILL 93-FE 4-SC- 15
MESSACES r
MINI-SCENARIOS The following mini-scenarios provide instructions and supplementary
- information for controllers in the Control Room and with the Emergency I Repair and Damage Control (ERDC) Temas.
The information provided in these mini-scenarios assumes that players will take certain actions in response to the Exercise scenario. Controllers must be cognizant of the actions of the players to which they are assigned.
The information provided in this section does not preclude the possibility that controllers will be required to provide additional infor=-tion to the players based on player actions.
1 I
l 93-FE 4.0-MINI- 0
__.I
Maintenance Mini Scenario #1 LOSS OF 4160 YOLT BUS NB01 Times 0815 (H+00:15)
Location: Switchgear Room No. 1 Tasks:
. Loose bolted connections of the main bus between NB0104 and 5 heat up, short to ground, and start a fire. The fire is almost immediately extinguished by the- halon system.
Main breaker (NB0112) trips and the diesel generator "A" starts, but breaker NB0111 doesn't close. The diesle is unable to re-energize the bus.
Relay and Meter technicians find 151G/F Flag, 186/F Flag and 151/F AB&C Phase flagged on cubicle NB0112, and find the NB0112 breaker tripped. All other cubicles are all right.
Maintenance should identify bus and insulation damage at cubicles NB0104 and NB0105. The bus will need to be replaced on B phase and insulation repaired on A and C phases.
To repair NB01, a bus section should be removed from spare cubicle NB0117 and installed in damaged cubicle.
Completions ;
These tasks will take about 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> to complete: NB01 should be returned operable to the plant by H+07:15.
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93-FE 4.0-MINI- 1
Maintenance Mini scenario #2 REPAIRS TO THE RESIDUAL HEAT RDf0 VAL SYSTEM "B" TRAIN .
Times Duration of the Exercise Tasks:
Repairs are in progress to repair a tube to shell side leak in the heat exchanger. Reassembly of the system is in progress. The shell has just been disconnected from the Manitowok crane. Repairs are estimated to take an additional 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> of the 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> remaining before entering a Technical Specification action level (Reft initial conditions).
Completion:
Sufficient repairs are completed on the heat exchanger to permit its use after H+08:00. The timely startup of the system is important to scenario play and coordinated radiological parameters.
c-l 93-FE 4.0-MINI- 2
Maintenance Mini Scenario #3 REPLACEMENT OF THE AUTTT.TARY BUILDING CONCRETE ROOF IULTCH Time Duration of the Exercise Location: Auxiliary building elevation 2047' 6', roof, in the vicinity of the residual heat removal system "B' train heat-exchanger roof hatch.
Tasks:
The concrete hatch in he auxiliary building has been removed to allow for the removal of the heat exchanger shell on the residual heat removal system. The hatch was removed using the Manitowok crane.
Air flow is into'the auxiliary building all the while the hatch is open.
This is not a release point for radiological effluents (Refs initial conditions).
Attempts may be made to replace the concrete hatch so that the auxiliary building ventilator system can be shut down, thereby terminating the release beginning at 1218 (H+04:18).
If the Manitowok crane is used, it stops functioning just as the concrete hatch is being replaced in the roof of the 2026,' level of the auxiliary building. Foul smelling smoke is coming from the engine compartment of the 1 crane. Some of the wiring harness appears burned with melted insulation. '
The concrete hatch is suspended approximately 4 feet above the roof.
Completion:
The repairs on the crane engine wiring may be completed and the crane made functional at H+07:00+.
1
-i 93-FE 4.0-MINI- 3
Maintenance Mini Scenario #4 FAILURE OF VALVE GT HZ-12 Times 0830+ (H+00:30+)
Location: Personnel Hatch outside Containment Tasks:
When the NB01 bus is deenergized, containment isolation valve GT HZ-12 +
fails. Should a repair team be dispatched, the tLme from notification of valve not operating to the scaffolding going up is 2-3 hours.
Trouble-shooting the valve should also take about 2-3 hours. The team discovers that the wrong grease was used during the last tLme maintenance was performed, causing the 0-rings to swell up and the actuator to stop working. Repairs could take from 6-10 hours.
Completion This task cannot be completed in time to isolate the release from the ductwork breach downstream of HZ-12. If an attempt is made to cover the end of the open ductwork, this will require about 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> to accomplish once the scaffolding is in place. The release to the auxiliary building and thus the plant unit vent will be terminated when the pressure inside containment equalizes with pressure inside the auxiliary building.
l 93-FE 4.0-MINI- 4 l
1 9
Maintenance Mini Scenario 1,5, PARTIAL OPENING OF YALVE EN HV-12 Times 1215 (H+04:15) i Tasks: l t i j
When containment spray actuation signal (CSAS) is generated, containment ,
spray pump *B' discharge valve EN HV-12 only opens 20Z due to bent valve !
stem. The bent valve stem causes actuator to torque out approximately 20Z open.
Several methods of repair may be attempted:
- 1) If maintenance jumpers torque switch, motor will lock rotor and trip breaker.
- 2) If Operations tries to manually declutch operator and manually open i I
valve, they find hand wheel just freewheels due to clutch keys being l broken off.
i
- 3) If Maintenance tries to remove actuator, they find stem nut lock nut l bound.
l 4) If Maintenance tries to remove actuator by turning the entire actuator l ,
off stem, they will hit the design supports.
Completion:
This task will not be completed in time to restore the valve to its fully opened position during the Exercise.
s 93-FE 4.0-MINI- 5
1 J
l MESSAGES ,
1 i
l PUBLIC INFORMATION i The following section consists of Wolf Creek Public Information Officer, Media ;
Inquiry, Public Concern, Media Monitoring, and Media Messenger messages.
These messages provide questions and responses from citizenry and the media and ,
assumes ths.t the responses given will provide careful and informative information.
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- -FE 4.0-PI- O s -
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PIO-1 TO: - Wolf Creek Public Information Offic'e r FROM: Reporter TIME: 0845 MESSAGE: 'This is a Drill" This is Bryon Hill at WIEW radio in Topeka. We've been told by a Wolf Creek employee that there is a fire burning inside the plant. Can you confirm this? Is any radioactivity-being released from the plant? Is the fire under control? Was anyone injured?
What caused the fire? Has the NRC been notified? Has the plant been shut down because of this?
PIO-2 To: Wolf Creek Public Information Officer FROM: Reporter TIME: 0850 ,
MESSAGE: "This is a Drill' This is Kelly Waldo at KAKE-TV. Wanted some information about the fire at Wolf Creek. Is the reactor on fire,'like what happened at Chernobyl7 Can we fly our helicopter out there to get photos of the blaze 7 PIO-3 TO: Wolf Creek Public Information Officer FROM: Reporter '
TIME: 0910 MESSAGE: "This is a Drill
- This is Scott Raust at the Eagle-Beacon. What's happening at Wolf' Creek this morning? Is the plant shut down now? How long will repairs take? Does this have anything to do with the refueling operation you did a while back? How much is it going to cost to get back in operation 7 RIs this considered an emergency ,
situation 7 How many other Unusual Events have yoa had7 8
93-FE 4.0-PIO- 1
-PIO-4 TO: Wolf Creek Public Information Officer FROM: Reporter TIME: 0920 MESSAGE: *This is a Drill' This is Ansom Wilson of the Associated Press. We've received your news release about the Wolf' Creek fire. Was anyone hurt? The release says emergency plans are being followed - what does that mean? Have you had unusual events before? How many? Is the problem now solved?
Note: Do not call until NUE release is distributed. '
PIO-5 TO: Wolf Creek Public Information Officer FROM: Reporter TIME: 0945 MESSAGE: "This is a Drill
- Bill Baxter here with KEGS radio in Emporia. I hear there was a s problem at Wolf Creek this morning? What's going on? '
i PIO-6 TO: Wolf Creek Public Information Officer )
l FROM: Congressional Aide
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TEHE: 1000 :1 MESSAGE: "This.is a Drill' l
This is Pam Raspmueller, and I'm an aide to Congressman Don Glassman. Congressman Glassman feels it is appropriate for him to make a public statement about the disaster at Wolf Creek, and I'm helping him compile information to facilitate that endeavor. Can you tell me what caused the problem at the plant? How much do you think it will cost to clean up the damage?
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HI-1 TO: Media Inquiry FROM: Reporter TIME: 0940 MESSAGE: "This is a Drill' Byron 3111 again from WIBS radio in Topeka. I called earlier today about the Wolf Creek fire. What's going on now? Is there any chance of this going out of control?
MI-2 To: Media Inquiry FROM: Reporter TIME: 0945 MESSAGE: "This is a Drill' I'm Martin Rosenthsl at Kansas City Star. What caused the fire today at Wolf Creek? Any idea what it will cost to fix the damage? When was the last time you had an unusual event? How many have you had since the plant started up? Is this more than normal?
MI-3 TO: Media Inquiry FROM: Reporter TIMI: 0950 MESSAGE: 'This is a Drill' I'm John Birnbaum with the Manhattan Me&cury. We got a wire story saying there's an Alert at the Wolf Creek nuclear plant. Can you update me on what's going on out there? Has there been any; release of radiation? If radioactivity is released, what will you do to save the people who live near the plant? Would you-anticpate the need to evacuate Emporia or Topeka?
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l MI-4 70: Media Inquiry l
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FROM: Reporter i TIME: 1000 MESSAGE: 'This is a Drill" This is bee Atweather at WIBW in Topeka. We just had a call from a person in Lyndon who was trying to drive down to I-35. She said we couldn't get through, and that there were all kinds of people in strange plastic suits down by the intersection of Highway 75 and K-31. Is this something to do with Wolf Creek?- Has there-been a release of radioactivity that's been blown up to the Melvern lake area?
Note: Controller notify Lead Controller prior to placing call so rumor can be tracked.
MI-5 TO: Media Inquiry FROM - Reporter TIME: 1005 ,
MESSAGE: "This is a Drill" This is Bill McCoy with KZ-93 radio in Osage City. We've heard Highway 75-at Melvern Lake has been blocked, and there are people in funny suits all over the place there. Do you know what's going on? Is it something to do with the Wolf Creek accident?
Notes Controller notify Lead Controller prior to placing call so rumor can be tracked.
MI-6 To: Media Inquiry FROM: Reporter TIME: 1010-MESSAGE: 'This is a Drill' Hello, this is Jennifer Forest of the Kansas Information Network.
We are getting several calls here about the Wolf Creek emergency.
Can we give reporters from outside the Kansas area an 800 number to call for information? -Do you special numbers for ratepayers to call? We'll be glad to give out some phone numbers if it will help.
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MI-7 TO: Media Inquiry ,
FROM: Reporter TIMES. 1015 MESSAGE: "This is a Drill' This is Billy Martins from the Phoenix Sun. I'm writing a story about the reactor accident. Can you tell me about the explosion and fire? I'd like to put it in terms our readers can understand. Was anyone hurt? Have you evacuated anyone? Is Wolf Creek the same kind of plant as the Palo Verde plant in Wintersburg Arizona? ,
MI-8 TO: Media Inquiry FROM: Reporter TIME: 1020 MESSAGE: "This is a Drill' This is Greg Roberts at KSN news. I need some information on Wolf-Creek to use in our noon newscast. Exactly where iw the plant located? Is there just one reactor there? Are there plans to build a second unit there? Who was the contractor that built the plant? Do you have a phone number I can call? I know there have been a lot of questions about construction quality and whether there was good.enough management during construction. Do you think the accident was caused by poor construction or defective materials, or was operator error at fault? Is this acident as serious as what happened at Three Mile Island? Has the NRC taken over attempts to get the situation under control?
MI-9 TO: Media Inquiry FROM: Reporter ,
TIME: 1025 MESSAGE: 'This is a Drill' Hi, I'm Byron Hill at WIBW radio in Topeka. Say, we have a tip from a Wolf Creek employee that a Site Area Emergency has been -
declared at the plant and that you're getting ready to evacuate some people from the area. Is that true? We haven't seen any official word about it, so we haven't put anything out on the air
- but it it's true, the public has a right to know. What can we say to our listeners? ,
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MI-10 70: Media Inquiry FROM: Reporter i
TIME: 1030 MESSAGE: "This is a Drill"
- Hello, Wayland Robinson here from KSTS-TV in Tulsa, Oklahoma. Is this the Media Release Center where we can go to get news about Wolf Creek? Where is it' located? If we fly in to Topeka, how do you get to the center from the airport? What hours will it be open?-
MI-11 TO: Media Inquiry ,
FROM: Reporter TIME: 1035 (WAIT UNTIL SAE STATDiENT IS ISSUED)
MESSAGE: "This is a Drill" I just got your news release about a Site Area Emergency and I don't understand it at all. This is Kelly Waldo at KAKE-TV, and ;
someone there told me earlier that everything was under control. 't From this release it sounds like there could be radioactivity coming from the plant. We'd really like to come up there - we ,
have'a radiation monitor we got from the university on our '
helicopter, so we would know if we were flying into a radiation cloud. Where is the nearest place we can fly to, and can we do at least a couple passes over the plant to get something on tape? i MI-12 TO: Media Inquiry FROM: Reporter i
TIME: 1040 (WAIT UNTIL SAE STATEMENT _IS ISSUED)
' MESSAGE: 'This is a Drill' ,
This is Martin Rosenthal with the Kansas City Star. We just got your release on the Site Emergency. . Let's speculate-a minute - if.
radiation is released, how many people would be in the path of the radioactive cloud 7 If a release happens.,couldn't a number of people die within a matter of days, like they did at Chernoby1? !
What's different from Chernobyl - seems to me like you have a r plant out of control, like the Russians did. And, radiation's radiation, right? So how are you going to prevent another Chernobyl, right here in Kansas?
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. I MI-13 TO: Media Inquiry FROM: Reporter TIME: 1045 (VAIT UNTIL SAE STATIMENT IS ISSUED)
MESSAGE: "This is a Drill' .i This is Greg Roberts KSN news. We'd like to get permission to go along with a team of your workers at the Wolf Creek disaster and film them doing whatever they do to try and fix the plant. We're willing to 11gn a release to hold your company harmless from any liability fur injury to our crew. All we need is one person to show us around. Will this work? This would really be a big story for us.
MI-14 TO: Media Inquiry FROM: Reporter TIME: 1050 MESSAGE: "This is a Drill' Hello, this is Terry Grote of Kansas Business. I'm writing the background story for the Wolf Creek disaster. One of our reporter said you had packets of information about the plant and the WCNOC emergency plan. If we sent someone over, can we get a couple of the packets? What kind of information is in the packet?
MI-15 TO: Media Inquiry FROM: Reporter TIME: 1055 MESSAGE: "This is a Drill' I'm a reporter from San Luis Obispo California. Can you help me with some questions about the nuclear accident? You know the wire service had Kansas City Power fr Light as the owners. I called that general number and the operator didn't know where to send my call. Someone better let her know there's an emergency going on, because I bet I'm not the only one having trouble reaching you people. Now start at the beginning and tell me about WCNOC's history, about their construction problems at Wolf Creek, and about the emergency you are having. By the way, my name is Alice Owens.
93-FE 4.0-MI- 5
MI-16 TO: Media Inquiry .
FROM: Reporter TIME: 1100 MESSAGE: 'This.is a Drill" Hello. This is Lonnie Sanderson from WKPR TV in Cleveland, Ohio.
I understand a Site Area Emergency has been declared at th'e Wolf Creek nuclear plant in Kansas. What is a Site Arna Emergency exactly? I also understand that two radiation barriers have been broken? What are those barriers? Are they physical barriers?. By the way - where is the plant located? How many generating units are there, and who owns the plant? Who is responsible for clean-up of the plant?
MI-17 To: Media Inquiry FROM: Reporter TIME: 1105 MESSAGE: "This is a Drill' Hello, I am Louise Simpson with KEYN Radio in Wichita. I need.
something cleared up before our next newscast. We have material on Wolf: Creek that says it is a Pressurized Water Reactor FWR.
In one of the newscasts from a TV station, they said it was a SNUPPS plant. Which is correct and what does SNUPPS stand for?
Why don't you nuclear people just say what you mean instead of making up initials to hide the facts?
MI-18 TO: Media Inquiry FROM: Reporter TIME: 1110 MESSAGE: "This is a Drill" This'is Jules Birnbaum with ABC News. Have you had a loss of Coolant Accident at your nuclear power plant 7 Can you tell me if there's danger of a hydrogen buildup in the containment building, and if this buildup could result in an explosion?
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MI-19 TO: Media Inquiry FROM: Reporter TIME: 1115 MESSAGE: "This is a Drill' I want to talk to someone in authority. This is Ray Watson of Channel 4 in Kansas City. We sent a news team to the Wolf Creek site to get a story about the accident. They were stopped by a barricade and the Highway Patrol refuses to let them in to get the news. What are you going to do about it? I'm sure you are familiar with the term " Freedom of the Press!"
MI-20 TO: Media Inquiry FROM: Reporter TIMI: 1120 MESSAGE: 'This is a Drill' Hi, this is Maria Holt, with the Tri-City Herald in Kennewick, Washington. According to the news story about Wolf Creek, the plant's architect-engineer is Bechtel Power Company. The nuclear plant operating 15 miles from our office also used Bechtel Power as their architect-engineer. My question is was the accident due to poor construction and if so, has Bechtel Power issued a statement?
MI-21 TO: Media Inquiry FROM: Reporter TIME: 1130, ,
MESSAGE: "This is a Drill" Hello, this is Dennis Petersen with the Lawrence Journal World.
- We would like to get some comments from the Lawrence group who opposed the Wolf Creek plant during the Atomic Safety and Licensing Board hearings back in 1984. Do you have any of their names or phone numbers?
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, MI-22 70: Media Inquiry FROM: Reporter TIME: 1140 MESSAGE: "This is a Drill" This is Randy Grahm at the Cable News Network. I need some technical information on how a nuclear power plant works. I realize your engineers are probably busy working on the plant, but do you know any experts maybe at K-State or KU. that could give me some information?
MI-23 TO: Media Inquiry FROM: Reporter TIME: 1150 MESSAGE: "This is a Drill' Hello, this is Bryan Franks of KHBC-TV, in Kansas City. We understand the FAA has closed the airspace above the Wolf Creek '
nuclear plant. We would like to fly our helicopter over and get some shots of the emergency teams at work. Can you get permission for us to fly over about 2:00 p.m.7 MI-24 TO: Media Inquiry FROM: Reporter .
TIME: 1155 MESSAGE: 'This is a Drill' This l's Janette Rives with the Wichita Eagle. Let's assume the accident at Wolf Creek gets worse, and there's a release of radiation something on the scale of Chernobyl. Wouldn't that mean everyone within a hundred miles would need to evacuate? That could include evacuation of Emporia or even Topeka, couldn't it?~
Do your emergency plans consider evacuation of those cities?
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i MI-25 TO: Media Inquiry FROM: Reporter TIMES 1205 MESSAGE: "This is a Drill' .
I'm Martin Rosenthal at the Kansas City Star. I need some te'chnical information for a story we're doing on Wolf Creek. What kind of material are the fuel rods made of7 What is the melting ,
temperaure for these rods? At what temperature does fuel melt? I understand that when you have fuel damage, you have a chance of having a " hydrogen burn." What is that? Does it mean the containment building might be blown apart - is that what you're afraid of? Is there some place I can look at detailed drawings of the plant?
MI-26 TO: Media Inquiry FROM: Reporter TIME: 1220 MESSAGE: "This is a Drill' This is Michael Douglas with 20th Century Fox productions in Los Angeles. We've been listening to the news about your nuclear power accident out there. I think it might just make a good movie, and I'd like to know who.to talk to about getting movie rights. Is someone available now, or should I write a letter to someone?
MI-27 TO: Media Inquiry FROM: Reporter TIME: 1230 (WAIT UNTIL GENERAL DERGENCY HAS BEEN DECLARED)
MESSAGE: 'This is a Drill' I'm Kelly Valdo with KAKE-TV. We just got your news release about the General Emergency. Can you tell me if there has actually.been radioactivity released, or do you just expect-it to happen? When you say a 'significant" amount of radiation, what do you mean - is it enough to kill someone, or make them sick? How does this compare with the amount of radiation released-from the Chernobyl reactor? How many people will have to be evacuated? Will this part of the state be usuable or will the contamination ruin the land for thousands of years?
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MI-28 TO: Media Inquiry FROM: Raporter TIME: 1240 1
! MESSAGE: "This is a Drill' .
This is Wiley Reed at KFDI. I need some clarification on your last news release. What exactly caused you to declare this ,
General Emergency 7 How many people are being evacuated and where are you sending them? Has anyone been contaminated or hurt? Does :
the Nuclear Regulatory Commission know all about this7 have they taken over trying to fix the plant?
MI-29 70: Media Inquiry FROM: Reporter
- TIME: 1250 MESSAGE: 'This is a Drill' Gene Overton, CBS News. We've picked up a wire report that a General Emergency has been declared at your Wolf Creek plant. Is this the most serious accident ever to occur in a nuclear power plant? Has a General Emergency ever been declared in the United States? How does this compare in severity to the Chernobyl.
accident? How much radiation is coming out of the plant? How many people are you going to evacuate?
MI-30 TO: Media Inquiry FROM: Reporter TIME: 1300 s MESSAGE: "This is a Drill' ,
This is Julie May, KSNW-TV. We've heard that you've declared a
- General Emergency at Wolf Creek. According to your background l information, this means radioactivity could be released outside the plant. Has this happened, and has anyone in the area been contaminated?
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MI-31 TO: Media Inquiry
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FROM: Reporter TIME: 1310 MESSAGE: 'This is a Drill" This is Rick Manning with KWCH-TV. I'm following up on the last news release about a General Emergency at Wolf Creek. Does this mean you will have to evacuate people from the area? How many people live within the area which you could evacuate? Where do they go? Will they ever be able to return to their homes?Did.
this explosion or whatever it was that caused you to-do a General Emergency actually blow a hole in the big domed building? We're going to send a camera crew up there - how close to the plant will-they be able to get without being contaminated?
MI-32 TO: Media Inquiry FROM: Reporter TIME: 1320 MESSAGE: 'This is a Drill' This is Charles Tatcher calling from London, England, the London Daily News. We have a UPI report of an accident at your Wolf Creek nuclear power station. Can you confirm this? What's happening? Has anyone been hurt? Are you evacuating anyone?
Didn't I hear that our United Kingdom Central Generating Board purchased the Wolf Creek reactor design and is operating it over-here? How much did they pay? Do you think a design defect caused this accident?
MI-33 TO: Media Inquiry FROM: Reporter TIME: 1330 MESSAGE: 'This is a Drill' I'm Jordon Hunt with the National Enquirer. We have the UPI news report on your Wolf Creek nuke plant disaster. We're ,right at the deadline for this issue, but I'd like to get in a story with some l pictures. Can our reporter and a photographer get over there and l take some pictures? What's the nearest town? Has it been J evacuated?. How do we get there from Kansas City?
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MI-34 TO: Media Inquiry FROM: Reporter TIME: 1340 MESSAGE: 'This is a Drill" .
I'm Sandy' Chapman with KWOX radio in Coffeyville. Was there a meltdown at Wolf Creek? What's the difference between what's happening now and what happened at Chernoby1? Will people hava to leave their homes? Has anyone been hurt 7 i
MI-35 TO: Media Inquiry PROM: Reporter TIME: 1350 l MESSAGE: 'This is a Drill' Hello, is this the Information Center for emergency information7:
I'm Max Watts of the San Diego Dispatch. The Governor of California, while speaking at a luncheon today, said California is fully trained and prepared to handle any emergency that could arise at the Diablo Canyon nuclear plant. Did Kansas have a plan -
before the accident started this morning at the Wolf Creek plant?
MI-36 TO: Media Inquiry FROM: Reporter TIME: 1400 MESSAGE: "This is a Drill' This is Barb Sloan from the Clay County Dispatch in Clay Center, Kansas. I'd like to have some details on the emergency at Wolf Creek. Do you have anything you can send me about Wolf Creek and what happens during a nuclear accident?
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t MI-37 TO: Media Inquiry i FROM: Reporter j TIME 1405 MESSAGE: "This is a Drill' This is Wayne Donaldson, at the St. Louis Post Dispatch. We're working on a story about the Wolf Creek disaster, and I seem to remember that the Callaway plant in Missouri is a duplicate of Volf Creek. Do you think there's-a chance the same thing could go wrong at Callaway? Have your engineers talked to the people at callaway to explain what went wrong?
MI-38 TO: Media Inquiry l FROM: Reporter l
TIME: 1410 MESSAGE: "This is a Drill" I'm Conny Vany with the Denver Post-Dispatch. We have the UPI vire stories on the Wolf Creek accident, but I have a question.
When Chernobyl blew up, radioactivity was_ dispersed all over the world, and they found pretty high levels in some of the European countries hundreds of mile away. What's to keep this accident from doing the same thing - isn't it a good possibility of seeing high levels of radioactivity throughout at least the mid-western states?
MI-39 TO: Media Inquiry FROM: Reporter TIME: 1415 MESSAGE: "This is a Drill' This is Bonnie Tyler at WHO news radio in Chicago. We're on the- '
air now - can you tell our listeners what has happened at Wolf Creek nuclear plant today?
93-FE- 4.0-MI- 13
MI-40 TO: Media Inquiry FROM: Reporter TIME: 1420 MESSAGE: 'This is a Drill
- Hello. This is Bonnie Black from the Boston Globe. It is my understanding that the Wolf Creek Nuclear' Generating Station in Kansas has had a serious accident. What happens after the accident is under control? Will the evacuees ever be allowed to return to their homes? How long before the plant will be allowed to operate again, or will it ever? Who is responsible for repairs and estimating the damage? Is there an emergency fund to pay for the cost of an accident - or will the ratepayers be charged for the costs?
- MI-41 TO: Media Inquiry FROM: Reporter
~
TIME: 1425 I MESSAGE: "This is a Drill' .
{
I'm Kelly Waldo at KAKE-TV. We're putting together our 6:00 p.m.
newscast. Is someone here in Wichita who can do an on-camera j interview? We'd like to come to your office at 4:30 this l afternoon.
MI-42 TO: Media Inquiry FROM: Reporter l
TIME: 1430 ,
MESSAGE: 'This is a Drill' I'm Louise Simpson at KEYN. We just got a call from a guy'who i says he lives near Wolf Creek. He says he just heard another explosion at the plant. Is that true, and if so, has the containment ruptured? Is there more radioactivity leaking out?'
Note Contact Lead Controller before placing call. Rumor to j track.
93-FE 4.0-MI- 14
MI-43 TO: Media Inquiry FROM: Reporter TIMEt 1435 MESSAGE: 'This is a Drill' I'm Wyley Reed at KFDI. We heard there's been another explosion at Wolf Creek. Is this true? Anyone hurt? Has more radiation
, spilled out?
Note: Contact Lead Controller before placing call. Rumor to track.
MI-44 To - Media Inquiry FROM: Reporter TIME: 1440 MESSAGE: "This is a Drill' This is Chuck Checkner, WIBW Topeka. I understand radioactive iodine may be released from Wolf Creek. Am I correct in saying_
this may be deadly to children? How much radioactive iodine can a child be contaminated with before its deadly? How old does someone need to be before the lodine doesn't affect them? What are you doing to protect these poor kids 7 MI-45 TO: Media Inquiry FROM: Reporter TIME: 1445 MESSAGE: "This is a Drill' Connie Ayer, Washington Herald. We've heard about a General Disaster or something like that at your atomic power plant. Was this an explosion or something? How many people were killed? .Is this a Chernobyl-type accident? Will the radioactivity kill all-the wheat and cattle your Kansas farmers grow? We'd like to send a staff writer out to interview some victims of the disaster -
what's the bestway to get there from New York 7 i
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MI-46 TO: Media Inquiry FROM: Reporter TIME: 1450 MESSAGE: 'This is a Drill' Thie is Bart Starr with the Kansas City Times. I'd like to get' some information out about how people can express their concerns about the nuclear accident to KG&E. Are you setting up a special .,
' hotline" for citizens who are calling in about concerns or if i their property has received radiation damage, legal problems, liability concerns and concerns about relatives, friends working at or living near the plant? If so, I'd like a brief description or what the proper procedures are for filing damage claims and what will be considered as a legal claim for damages?
MI-47 TO: Media Inquiry FROM: Reporter TIME: 1455
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MESSAGE: "This is a Drill' I'm Sam Davidson with ABC news in New York. We're planning to do a news update on the nuclear plant accident. Has much radiation escaped the plant? How many people were involved in the evacuation? Will the Price Anderson Act pay for all this or does your company have some liability in it?
MI-48 TO: Media Inquiry FROM: Reporter TIME: 1500 MESSAGE: "This is a Drill' I'm Martin Rosenthal, Kansas City Star. Can you tell me how many billions of dollars the Wolf Creek disaster will' cost KG&E ratepayers? Will the Federal government kick in funds for this?-
Will Western Resources and KCPL go bankrupt, and if so, what will happen to your customers - who's going to provide electricity?
93-FE 4.0-MI- 16 6
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p MI-49 TO: Media Inquiry FROM: Reporter TIME: 1505 MESSAGE: "This is a Drill' John D. Marton here with KLIM Radio in Topeka. One of the residents in the Coffey County ares told us that Western Resources will be receiving General Disaster Funds to purchase homes, crops, animals and land that has been damaged by radiation. Where do residents need to go or call to_ file a claim? Will there be-special forms for them to fill out?
Note: Controller coordinate with Lead Controller prior to placing.
call so misinformation can be tracked.
MI-50 TO: Media Inquiry FROM: Reporter TIME: 1510 MESSAGE: "This is a Drill" This is Candy Harder from WIEW-TV in Topeka. We'd like to do a special broadcast at 6:00 p.m. regarding KGEE's offer to purchase property exposed to radiation during the accident at Wolf Creek.
Where will the funds come from to pay for.this property? What will KGLE pay for an acre of land, chickens, cows, homes? Will it be on an individual basis? Please provide any details you may have.
Note: Controller coordinate with Lead Controller prior to placing call so misinformation can be tracked.
MI-51 TO: Media Inquiry FROM: Reporter TIME: 1515 MESSAGE: 'This is a Drill' I'm Janna Goode with KV0E Radio. What's the latest on the accident?
93-FE 4.0-MI- 17
MI-52 TO: Media Inquiry FROM: Reporter TIME: 1520
- r MESSAGE: 'This is a Drill
- This is Joan Burnstorf, Wichita Eagle speaking. What will the ;
accident at Wolf Creek do to our electric bills? What about pvailability of service - will KGLE have enough electricity to serve their customers? Where will the electricity come from if not Wolf Creek? Are the ratepayers going to have to still pay for the construction of Wolf Creek even if it is not' producing electricity?
MI-53 TO: Media Inquiry FROM: Reporter' TIME: 1525 MESSAGE: "This is a Drill" Hit Jeff Carnes from KV0E Radio. Can I interview someone in your legal or insurance department in regard to what KG&E's liability ,
is after the Wolf Creek disaster? Can they give me information on where people can call to file claims or lawsuits?
MI-54 TO: Media Inquiry FROM: Reporter TIME: 1530 MESSAGE: *This s is a Drill" J. R. Rawlins here from Memphis Courier. I understand Wolf Creek has the plant under control and the radiation release has-stopped. Any idea what caused the accident? Any idea when the plant will produce electricity again? When will the people be able to return home? Can I find out more information from you tomorrow? -Vill this special number for Media Inquiry still be the right one to call tomorrow?- Who do I ask for?
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MI-55 TO: Media Inquiry
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FROM: Reporter TIME: 1535' MESSAGE: "This is a Drill' Jim Johnson with the Dallas Times. Any idea about how long this accident at Wolf Creek is going to last? How long after it'is under control can people start to go back to their homes? I'm i doing a story on the plant and what exactly happened inside the ,
plant. Do you hr.ve any diagrams about what happened insidef can' !
. you give me an overview of what caused the accident?
MI-56 TO: Media Inquiry FROM: Reporter TIME: 1540 MESSAGE: "This is a Drill" This is Louise Simpson from Wichita Radio Station KEYN. Is the accident over? What happens after people are evacuated? Will they be able to return home?
MI-57 TO: Media Inquiry FROMs. Reporter TIME: 1545 MESSAGE: 'This is a Drill' Rolland Headley, KMBC Radio. I'd like to run a tape' for our 6:00 news - can you do the interview? OK, good. We've gotten word of an evacuation in the Wolf Creek area. Will these people ever be- 6 able to return to their homes? What about the-cropland - how many-thousands of years will it be before farmers can again grow food' there? Will the cattle and livestock in the area be killed by I radiation? How far away has the wind carried this deadly. ,
radioactive cloud? That's all for now.
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I PC-1 To: Public Concern Phone Team FROM: Citizen .
TIME: 0940 MESSAGE: "This is a Drill' l
Hy name's Ben.Ballingston, and I live in New Strawn. I've been
- picking up parts of conversation on my ham radio about a ' turbine trip
- at Wolf Creek. What are they talking about? Are we in trouble out here?
t PC-2 TO: Public Concern Phone Team FROM: Citizen TIME: 0945 ,
MESSAGE: "This is a Drill' ;
i I'm Lois Fletcher and I heard on KEYN radio that there is a fire at Wolf Creek. Will this contaminate the state, like the fire at i Chernobyl did?
PC-3 TO: Public Concern Phone Team '
FROM: Citizen l
TIME: 0950 MESSAGE: "This is a Drill' Don Bunker, Bulkon Chemical, here._ We're scheduled to deliver a' '
tanker of chlorine to Wolf Creek today. Heard on the radio about -
your fire - do you still what us to deliver this st'uff? ,
PC-4 70: Public Concern Phone Team i
FROM: Citizen l TIME: 0955 MESSAGE: 'This is a Drill' f
This is-Dwight Goodall and I been a KG&E customer for years. My ?
electric bill keeps going up and up and now you'll probably have '
to spend all kinds more money to clean up this' mess at your -nuke '
plant. What am I 'sposed to do? I just can't pay more to you ,
people.
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PC-5 TO: Public Concern Phone Team l
FROM: Citizen TIME: 1000 MESSAGE: 'This is a Drill' This is Mrs. Alvin Smotzer and I live in Wichita. They said_on the radio there's been a problem at that nuclear power plant. ,
Will we have to leave our homes like those people in Russia did? _ '
I've lived here 32 years, and I don't want to leave.
PC-6 TO: Public Concern Phone Team FROM: Citizen TIME: 1005 MESSAGE: 'This is a Drill" Hello - This is Bob Bonner at Burlington;and I have a question about the accident at Wolf Creek.
I don't really understand what is going on. Is there something wrong with the plant and are we in any danger here?
PC-7 TO: Public Concern Phone Team FROM: Citizen TIME: 1010 l
MESSAGE: 'This is a Drill' I'm Mike Abrahanson at ABC Fire Protection Service. My company sells state-of-the-art fire protection systems for industrial use. I've heard about your fire at Wolf Creek, and wonder if I can see someone about getting one our systems installed, so you won't have to worry about fire again?
PC-8 TO: Public Concern Phone Team FROM: Citizen TIME: 1015 MESSAGE: "This is a Drill' I'm Randy Harwood, and I manage the truck stop at Beto Junction.
Some truckers are asking if it's safe to drive south on highway 75 past the nuke plant. Can you tell me what I should tell them?
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PC-9 TO: Public Concern Phone Team FROM: Citizen j TIME: 1020 l
I HESSAGE: "This is a Drill' I heard about the nuclear plant accident on the radio. I need to '
go to Ottawa on business, and I need to find out if its safe? _My J name is Al Kanfield, and I live in Coffeyville.
PC-10 TO Public Concern Phone Team FROM: Citizen TLHE: 1030 i MESSAGE: "This is a Drill' l Hello, I'm Paul Griffen, and I live in St. Joseph, Missouri. . My daughter is with a group of high school students who are supposed to tour Wolf Creek power plant today. They left this morning early, and were supposed to be there by 10:00. I'm concerned about them because of the accident. Can you tell me if they will ,
be allowed to go to the plant, or will the Sheriff's Department ;
turn them back?
PC-11 TO: Public Concern Phone Team '
FROM: Citizen TIME: 1040 .
MESSAGE: "This is a Drill' My name's Diane kroche and my husband works in security at Wolf Creek. I've been trying to call him but I can't get through. I'm ,
worried that he may have been hurt in the fire, because he's on the fire brigade. Can you tell me if he's okay - his name is-Raymond.
t 93-FE 4.0-PC- 3 O
f PC-12 70: Public Concern Phone Team FROM: Citizen TIME: 1045 MESSAGE: "This is a Drill" h
I'm David Wagner and I'm a customer and I want some answers. I tried to call Western Resources to find out what's going on at ,
Wolf Creek but they cut me off. Who am I talking to now? What's your title? Do you have any information about the accident or can you take a message and have someone call me7 i
PC-13 TO: Public Concern Phone Team l
FROM: Citizen TIME: 1050 ,
MESSAGE: "This is a Drill" I'm Lela Borden. We live about three miles west of Wolf Creek, and I can't find that little booklet with the emergency ,
information in it. Can you tell~me what we're supposed to do, and where to go if we have to evacuate?
PC-14 TO: Public Concern Phone Team FROM: Citizen TIME: 1055 MESSAGE: "This is a Drill' Hi .I'm not sure who I need to talk to, but I have a complaint. l All I've heard this morning on the radio is news about Wolf !
Creek. They talk and talk but it always ends up that there isn't j much infoonation available. Why don't you people tell the-reporters what's going on, so we ordinary people will know. They ;
said the Russians wouldn't give out any information about their '
plant blowing up, but it sounds like you're doing the same thing.
a 93-FE 4.0-PC- 4 4
PC-15 TO: Public Concern Phone Team FROM: Citizen TIME: 1100 MESSAGE: "This is a Drill' Hello, I'm JoAnn Greeley, and I live in Emporia. I'm very concerned about the accident at Wolf Creek. We're only 40 miles east of the plant. If the plant blows up like the one did in Russia, what are we supposed to do? I heard in Russia radiation '
went as far as a thousand miles from the plant. Will we lose our home like those Russian people did?
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.PC-16 TO: Public Concern Phone Team ,
i FROM: Citizen '
TIME: 1105 MESSAGE: "This is a Drill' I need to talk to someone with authority. My television set went '
out on me this morning and it's never given me a bit of trouble before. I was talking to my neighbor who's an electrician and he said he bet when that Wolf Creek plant went out, it caused a big power surge that blew out my TV. That TV's only 7 years old and never had a problem before, so I bet that's what happened. Who
- can I talk to to pay me for the damage to my TV7 PC-17 To: Public Concern Phone Team FROM: Citizen TIME: 1110 MESSAGE: "This is a Drill' My name's Joey Littlejohn and I live just north of Lyndon. I ,
just saw three highway patrol cars go flying past here on 75 - ,
were they going to Wolf Creek? Will someone tell us what to do-and where to go? :
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93-FE 4.0-PC- 5 8
PC-18 TO:- Public Concern Phone Team FROM: Reporter TIME: 1120 MESSAGE: "This is a Drill' This is Woody Hambright, and I'm outdoor editor for the Parsons Sun. For a long time we've been trying to get you to open Wolf Creek lake for fishing. Has this accident dumped any radioactive chemicals into the lake? Will it still be fit for fishing 7 Do you know if there are any plans to open the lake for public fishing?
PC-19 TO Public Concern Phone Team FROM: Citizen TIME: 1130 MESSAGE: 'This is a Drill
- My name's Horrace Ocram and I live a mile south of Lyndon on highway 75. When I tried to go down to I-35, the highway patrol wouldn't let me through--they said there'd been a chemical spill and it might be dangerous. Was this something to do with the accident at the nuclear plant? When will we be able to get through on-the highway?
Notes Controller notify Lead Controller prior to placing call so rumor can be tracked.
PC-20 TO: Public Concern Phone Team FROM: Citizen TIME: 1140 MESSAGE: 'This is a Drill' This is Dean Hanover at Kansas State University. I teach a_ class in nuclear physics here, and we've been studying how pressurized ,
water reactors work. Can you tell me if the problem this morning ,
at Wolf Creek involved a LOCA~, or loss-of-coolant accident? Was this a small LOCA, or the big double-ended LOCA like the
- worse case' scenarios call for? Have you seen a buildup of containment pressure in response to the.LOCA7 Could'I be included on the distribution for the technical analysis of this when it's all over?
93-FE 4.0-PC- 6 '
- PC-21 TO: Public Concern Phone Team FROM: Citizen TIME: 1050 t MESSAGE: "This is a Drill" i Hello, I'm calling about the Wolf Creek accident, is this the right number? My husband went hunting at Melvern lake this morning with my son, and I don't have any way to reach them. Are they safe? Will the sheriff or someone notify people around the lake if they need to get away from the radiation?
Note: Your name is Lisa Michaels from El Dorado if asked. >
PC-22 TO: Public Concern Phone Team l FROM: Citizen TIME: 1200 MESSAGE: "This is a Drill' My name is Allen Mason and I live in Kansas City. I have a ;
daughter who lives with her mother in Burlington. The phone.
exchange is tied up and I can't get through.
Can you tell me if the people in that area have had to evacuate or ,
if any of the people are in danger? Is the State in charge of this kind of emergency? Who else can I call to find out what's going on? i PC-23 70: Public Concern Phone Team FROM: Citizen TIME: 1210 i
MESSAGE: "This is a Drill' This is Dr. Frank Masetta, and I'm an oncology specialist at Wesley Hospital. I'd like to volunteer my services to you in case you have injuries out at Wolf _ Creek from radiation exposure. My phone number is 683 0000 - just call me and I'll be ready to go i anytime.
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PC-24 TO: Public Concern Phone Team FROM: Citizen TIME: 1220 MESSAGE: 'This is a Drill" Yes, is this where I call to find out about the Wolf Creek diraster? I'm Saul Epskin and I'm calling from Abilene. My son and daughter-in-law live in Lebo, down near Wolf Creek. I can't reach them on the phone because the lines are all tied up. Our radio just said you upgraded the emergency, and people may be evacuated. Is there any chance the radiation could go towards Lebo?
PC-25 TO: Public Concern Phone Team FROM: Citizen TIME: 1230 MISSAGE: "This is a Drill'*
KG&E7 My name is George Ballinger and I live in Lebo. My neighbor and I keep smelling this real strange odor. Could we be getting exposed to some of that Wolf Creek radioactivity? Should we go to Emporia to the hospital to be checked out, just in casef PC-26 TO Public Concern Phone Team FROM: Citizen TIME: 1240 MESSAGE: 'This,is a Drill' This is Mrs. Mable Horshmann, and I live-up by the Wolf. Creek plant. I heard on the radio that some poison cloud might come out of the plant out here and make us leave our homes. I'm 87 years old and I don't drive and my husband is gone to town. There ain't any way for me to leave, and I'm afraid I'll die here from this.
Please...can you help me?
(If asked, you live in the old Simpon place - 2 miles north and a mile east of Waverly) 93-FE 4.0-PC-- 8
PC-27 TO: Public Concern Phone Team FROM: Citizen-TIME: 1250 MESSAGE: ' 'This is a Drill' Hello, I'm Bernard White, and I'm principal at the Ottawa Senior High School. We're having PE classes and I was wondering if it is safe for students to be outside, with this Wolf Creek thing going on?
PC-28 TO: Public Concern Phone Team FROM: KG&E Employee TLME: 1300 MESSAGE: 'This is a Drill' Yeah, this is Rock Jones, and I'm in the line department at Fort Scott. We've been hearing rumors that they're going to make us work in the switchyard at Wolf Creek while this accident is going.
on - we heard they're doing something with one of the emergency ,
busses and I guess they can't figure it out. None of us wants to go get nuked at that place - will we lose our jobs if we don't go?
PC-29 TO: Public Concern Phone Team FROM: Citizen l
TIME: 1310 MESSAGE: 'This is a Drill' ,
l My nome is Clinton Sanderstone and.I live three miles due east of Wolf Creek. I have 65 dairy cows. What can I do to protect them ]
l from radiation. If they die or give off radioactive milk, it'll ruin me - we're.just hanging on now. What can I do?
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93-FE 4.0-PC- 9
PC-10 TO: Public Concern Phone Team FROM: Citizen !
t TIME: 1320
+
MESSACE: "This is a Drill' !
I'm Cassandra Maxwell and I live in Emporia. Someone just came to our house and said he was a Wolf Creek employee. He said you are' going to have to evacuate Emporia later today because of the radiation from Wolf Creek, and that unless we bought this. filter he was selling we'd havo.to leave the house for at least a week.
He said this filter would keep out the radioactive particles - he said it was treated with anti-radiation materials and would ,
neutralize the particles. He said we should put the filter in our furnace and it would take care of everything. Then he tried to charge us $250 dollars for it. Why, it looks just like an ordinary furnace filter to me. I didn't buy it, but I started wondering if this guy was on the level. Are you going to evacuate r Emporia? Are you really selling a radiation filter that would protect us from the radiation?
Notes' Controller notify Lead Controller prior to placing call so rumor can be tracked.
PC-31 To: Public Concern Phone Team FROM: Citizen TIME: 1330 MESSAGE: "This is a Drill' Good morning. This is Doyce Atwater at Vichita Iron & Metals company. We have gotten news of the accident at the power plant and are wondering if we will lose electrical power as a' result.
We are about to start running a batch of material and low power would ruin it and cost us a lot of money.
Can you help me or refer me to someone?
(If asked where your business is located, tell them at 922 Merton) l i
93-FE 4.0-PC- 10 I
t PC-32 TO: Public Concern Phone Team 1
FROM: Citizen TIME: 1340 MESSAGE: "This is a Drill' Hi, this is Ron Fantin. My sister and her family live in New Strawn, across the road from Wolf Creek. No one answers-at that ,
number. Can you tell me he',e they moved people out of the area or ,
something?
PC-33 TO: Public Concern Phone Team FROM: Citizen TIME: 1350 MESSAGE: 'This is a Drill' Hello - KG&E7 I hear on the news that your nuclear plant is going- '
wild and giving off a lot of radiation.
If your plant blows what should I do to protect myself or am I in ;
any danger at all this far away? My name is Peter Zeller, and.I live in Ottawa. ,
PC-34 TO: Public Concern Phone Team FROM: Citizen TIME: 1400 MESSAGE: 'This is a Drill' This'is Dr. Jan Stephenson from the Psychology Department at Emporia State. I'm concerned about the psychological impact of the Wolf Creek accident on Coffey County residents. Do you have a company psychologist I can talk to? ;
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PC-35 TO: Public Concern Phone Team FROM: Citizen TIME: 1405 MESSAGE: "This is a Drill'
?
This is Dr. Bradley Bone from the Anthropology Department at-Wichits State University. We have some artifacts in an exhibit on loan to Coffey County Museum in LeRoy. With the Wolf Creek accident and all, I'm very concerned about this exhibit - some of the artifacts are very rare and irreplaceable. Can you have someone move that exhibit out of there, just in case some radiation escapes and contaminates the town?
(If asked, the exhibit is in two show cases, each 6 feet long by 3 feet wide by 7 feet tall). .
PC-36 TO: Public Concern Phone Team FROM: Citizen TIME: 1410 MESSAGE: "This is a Drill' o
This is Dr. Frank Geoffrey, and I'm head of radiological research. ,
at the University of California Medical Center. Part of our research program deals with the effects of radiation on humans. I understand you've had some people exposed out there at your >
disabled nuclear plant, and I'd like to go through whatever channels it takes to get in touch with those people, to arrange a long-term study of the effects on them. Who should I talk to to" set this up?
PC-37 TO: Public Concern Phone Team FROM: Citizen TIME: 1415 MESSAGE: 'This is a Drill' I'm Donna Reece and I live in Lebo. Is it safe for me to drive down to my sister's place in Yates Center? I usually go on 50 highway to highway 75, then south through Burlington. ,
93-FE 4'.0-PC- 12 A
a PC-38 TO: Public Concern Phone Team
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FROM: Citizen TIME: 1420 MESSAGE: 'This is a Drill" r
This is Lionell Jamison. I'm press secretary for Senator Bob t Knoll. We are trying to get more information on the Wolf Creek accident - we've already been briefed by the NRC and FEMA, but wanted to see what you people could tell us. Can you give me a summary of what's happening?
PC-39 TO: Public Concern Phone Team FROM: City of Wichita TIME: 1425 MESSAGE: "This is a Drill' This is Mike Everhard in the Environmental Services Department with the City of Wichita. We want to be ready to do some radiation monitoring here in case there is a major release from Wolf Creek. Can I speak to one of your environmentalists or -
health physicists to get some source term information?
PC-40 TO: Public Concern Phone Team -
FROM: Citizen TIME: 1430 MESSAGE: 'This is a Drill' I'm ' calling from Fort Scott. My husband works for KG&E in the Line Department here, and he called earlier and said he was afraid they'd make him go work at Wolf Creek today. Do you know if anyone from Fort Scott has been sent up there. My name's Sally Jones.
a 93-FE 4.0-PC- 13
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-i PC-41 TO: Public Concern Phone Team j FROM Citizen TIME: 1435 MESSAGE: "This is a Drill
- The news just said this accident at Wolf Creek may be the worst in history. This schres me - I live in Wichita, which isn't that far away. Is there a chance we may get radioactive fallout here? !
PC-42 TO: Public Concern Phone Temn FROM: Citizen !
TIME: 1440 MESSAGE: "This is a Drill' ;
Hi, I'm Conrad Schraeder and I live at 702 W. 2nd.in LeRoy. The )
sky looks kind of hazy over towards Wolf Creek. Is that radioactivity I see7 Should I be doing something to protect myself?
PC-43 TO: Public Concern Phone Team I
.1 FROM: Citizen i
TIME: 1445 MESSAGE: "This is a Drill' Hey, is this where I can get some answers about Wolf Creek? We .l were just having lunch, and started talking about this thing - l who's> going to pay for cleaning up? I mean, we've been paying l these high electric bills because it cost so much to build that !
plant - new are our bills going to go up again because of this?- I don't think that's right if they do - it's KGEE's problem, let ,
them pay for it! l l
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.J PC-44 TO: Public Concern Phone Team FROM: Citizen i i
l TLHE: 1450 ;
MESSAGE: "This is a Drill' I'm Carl Long and I work nights at IBP in Emporia. I just got.out.
of bed, and I'm hearing all this about Wolf Creek on the radio.
What's going on? I have a friend who works out there - have any employees been hurt? Do you think there will be a chance Emporia could be evacuated because of the radioactive fallout?
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PC-45 TO: Public Concern Phone Team j 1
FROM: Citizen TIME: 1455 MESSAGE: "This is a Drill' Is this the number to call for information about the. Wolf Creek disaster? I live in Yates Center which is about 20 miles from Burlington. How can I tell if any radioactive stuff is spreading down here? Can you see the radiation or taste it? Is it sticky?
Is there some kind of antidote I can take if the fallout comes down here? I heard once that lodine is the worst thing to breathe in - does it burn when you breathe it, or how can you tell? Is Wolf Creek going to send someone down here to tell us what to do?
PC-46 TO: Public Concern Phone Team FROM: Citizen TIME: 1500 MESSAGE: "This is a Drill' My name's Joline Robins. I have a restaurant just off I-35 in Lebo. We're about 20 edles from Wolf Creek, and that's pretty close. My customers keep asking if we think there's any danger of radiation coming here. I'm not sure what to tell them. Is there' any danger to us up here?
93-FE 4.0-PC- 15
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PC-47 70: Public Concern Phone Team FROM: Citizen TIME: 1505 MESSAGE: 'This is a Drill" This is Don Wacker, and I live six miles south of Waverly. About this Wolf Creek thing - I ain't about to leave my place just because some radioactivity. Hey, I was in the Army when they bombed them Bikiri Islands, and we weren't more than ten miles from the bomb. I figure I-ain't dead yet and I ain't gonna be.
They ain't gonna try to make me move out are they? ,
PC-48 TO: Public Concern Phone Team FROM: Citizen TIME: 1510 MESSAGE: "This is a Drill" I'm Alice St. John and I'm chairperson for Consumers Against i Radioactive Plants. We at CARP have always said these nuke plants ~
aren't safe - now maybe you'll listen. Anyway, I want to know-who's going to pay to clean this mess up? If it's-going to be the ratepayers, we're going to start building our case against it right nowl PC-49 Tot. Public Concern Phone Team FROM: Reporter TIME: 1515 MESSAGE: "This is a Drill" Hello, this is Marsh Roberts of CBS news. Is this the Media Release Center? Where is it located? If we fly into Topeka, can you give us directions how to get from the airport to the Media Release Center? What hours will it be open?
1 93-FE 4.0-PC- 16 !
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PC-50 TO: Public Concern Phone Team FROM: Citizen TIME: 1520 MESSAGE: 'This is a Drill' I just heard the end of a news broadcast about Wolf Creek. They said something about not evacuating the Wichita area. Was there ever a chance Wichita would be evacuated? I don't know where we'd go or how to get there - no one's ever said anything about it to us.
PC-51 TO: Public Concern Phone Team FROM: Citizen TIME: 1525 MESSAGE: "This is a-Drill' I'm Donna Marconi with the Sierra Club in Kansas City. ~We're very concerned about how this Wolf Creek catastrophe will affect the environment. Will there be miles of land around the plant that.
will be unusable for hundreds of years? In there any way to decontoninate ground that has been contoninated? Is the Environmental Protection Agency in on this?
PC-52 TO: Public Concern Phone Team FROM: Citizen TIME: 1530 MESSAGE: 'This is a Drill" This is Jim James, and I live about two miles from the nuclear plant. I think I heard a explosion a few minutes ago. Did something else happen at the plant? I called a couple radio stations, but they didn't know anything. Was there another explosion over there?
Note: Contact Lead Controller before placing call. Rumor to track.
93-FE 4.0-PC- 17
PC-53 TO: Public Concern Phone Team _
FROM: Citizen i
TIME: 1535 l MESSAGE: "This is a Drill" -l 1
My name is Joe Jones. I farm and raise cattle in the area q evacuated. Who will pay for the damages to my crops'and animals? !
Wolf Creek or my insurance? Do I need to contact my insurance <
agent for him to assess the damage? Then, do I send my claim to l Wolf Creek?
PC-54 TO: Public Concern Phone Team l
FROM: Citizen TIME: 1540 MESSAGE: "This is a Drill" This is Bert Douglas. I heard on the radio that Wolf Creek is buying the property of those people affected by the nuclear plant accident. I own some land out the'e,
~r and would like Wolf Creek to make me an offer for my land.
Note: Controller coordinate with Lead Controller prior to placing call so misinformation can be tracked.
PC-55 TO: Public Concern Phone Team FROM: Citizen TIME: 1545 MESSAGE: "This is a Drill" This is John Sampson. Do you have a list of the names of people who were evacuated and if they are all okay? My parents live in that area, and I haven't been able to get a hold of them. Can you tell me where they are, and how can I reach them?
93-FE 4.0-PC- 18 S
HH-1 TO: Media Monitoring FROM: Radio TIME: 0900 (or 5 minutes after term is activated)
MESSAGE: "This is a Drill"
- We interrupt regular programming for this special report from KFH
' news. A serious emergency seems to be developing at Wolf Creek nuclear power plant near Burlingto.n Kansas. Wolf Creek Nuclear ,
operating Corporation officials notified us of a fire at the plant earlier this morning. The situation has apparently worsened, and the plant is now on emergency alert. Plant officials say no deadly radiation is coming out of the plant yet, but area residents are being advised to be ready to take protective ,
action. KFH news will interrupt programming again as soon as details are available on this potentially serious situation.
MM-2 TO: Media Monitoring FROM: TV TIME: 0910 (or 5 minutes after team is activated) !
MESSAGE: 'This is a Drill" I'm Kelly Waldo with a special TV 10 news bulletin. The controversial Wolf Creek nuclear power plant suffered yet another blow this morning when a fire broke out inside the plant. Plant officials first reported the fire was under control, but have since said the plant is on Alert and emergency procedures are being followed. Apparently no radiation has been released, but people living near the crippled plant are being warned that they. ,
may need to take protective action. We'll have more on the nuclear accident as details become available.
MM-3 TO: Media Monitoring FROM: TV TIME: 0920 (or 5 minutes after team is activated)
MESSAGE: "This is a Drill" This is a special report from the TV-12 newsroom. Wolf Creek' nuclear power plant in eastern Kansas is under an Alert emergency, after a (ire broke out at the plant earlier today. Plant officials say there has been no release of radiation, and that emergency procedures are being followed. KWCH-TV is attempting to '
obtain further details, and will interrupt programming again when-more information is available. I'm Don Williams, from the KWCH newsroom. .
93-FE 4.0-MM. 1
5 MM-4 TO: Media Monitoring FROM: Radio TIME s - 0930 MESSAGE: "This is a Drill' First with news, this is KXLK radio. Wolf Creek Generating Station is on Alert this morning, after fire and other problems czippled the plant. Wolf Creek Nuclear Operating Corporation.says no radiation has been released from the $3 billion dollar. plant, but emergency procedures are being followed.
MH-5 TO: Media Monitoring FROM: Radio TIME: 0940 ,
MESSAGE: "This is a Drill' Good morning, this is Ray Means, KLZS radio news. A serious accident occurred early this morning at Wolf Creek nuclear power plant. Details are sketchy but Kansas Gas and Electric officials tell us the plant is on Alert status, which is the second level of.
four emergency classifications. A fire was reported to have.
started at the plant at 8:00 this morning. .There are unconfirmed reports that three workers were seriously injured either by fire or by radiation - that is an unconfirmed report which we are attempting to verify. We'll have updates on the Wolf Creek disaster later, as~more information becomes available.
Note: Controller notify Lead Controller prior to placing call so this rumor can be tracked.
MM-6 TO: Media Monitoring FROM: Radio TIME: 0950 ,
MESSAGE: 'This is a Drill" This is Louise Simpson, KEYN news - people living near.the Wolf Creek nuclear power plant in Coffey County are on the edge of.
their seats this morning waiting for news of how the emergency at the plant is being handled. Kansas Gas and Electric company is '
saying little about the situation, other than the plant is on Alert status and no radiation has been released. Plant officials are currently following emergency procedures. We'll provide more ,
information as it becomes available. This is Louise Simpson, KEYN news. .
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MM-7 TO: Media Monitoring
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FROM: TV TIME: 1000 MESSAGE: "This is a Drill" This is a CBS newsbreak. I'm Roger Perkins. A serious problem is developing on the plains of Kansas this morning. The Wolf Creek.
Nuclear Power Plant, located 90 miles southwest of Kansas City, Missouri is on Alert following a fire which disabled the plant earlier this morning. Utility officials report the situation is under control, and that no radiation has escaped the plant.
However, area residents are being advised to keep their radios tuned to the Emergency Broadcast System in case the situation worsens and an evacuation is necessary.
Wolf Creek began operation in September, 1985 amid a storm of controversy from critics who charged the plant was not safe. As recently as last July, Congressman Dan Classman.of Kansas charged the Nuclear Regulatory Commission with ' sweeping some things under the rug
- in their review of plant safety and construction quality. Glassman was unavailable this morning to comment on the potential disaster at the plant. We'll have more on the story in a special report, " Nuclear Plants: Power or Poison?", tonight at 11:30 Eastern Standard Time.
MH-B TO: Media Monitoring ,
FROM: TV TIME: 1010 MESSAGE: "This is a Drill" Fromsthe KAKE-TV newsroom, this is an update on the a'ccident at the Wolf Creek nuclear plant near Burlington, Kansas. Informed sources at Kansas Gas and Electric tell us that fire which erupted.
at the plant this morning has been extinguished. However, the plant is still in an emergency situation. Details are still i sketchy, but we do know that people within 10 miles of the plant are being prepared in case evacuation is necessary. We'll interrupt regular programming as needed when more information is available. I'm Kelly Valdo, KAKE news.
93-FE 4.0-MM- 3
4 MM-9 TO: Media Monitoring FROM: Radio TIME: 1020 MESSAGE: 'This is a Drill" We interrupt regular KFFX programming fcr this special bulletin from the newsroom. We have an unconfirmed report that a tank truck possibly carrying radioactive material from the crippled '
Wolf Creek nuclear power plant has overturned three miles north of I-35 on U.S. 75 highway. The highway patrol has confirmed that U.S. 75 north of I-35 has been closed. However, the highway patrol could not confirm the report of radioactive contamination from the wrecked truck. Our KFFX mobile unit is on the way, and we should have a further report within a few minutes. This is Brad Oliver, KFFX news.
Note: Controller notify Lead Controller prior to placing message so rumor can be tracked.
MM-10 TO: Media Monitoring FROM: TV TIME: 1030 MESSAGE: 'This is a Drill" Good morning, this is Greg Roberts, KSN news. The controversial Wolf Creek Generating Station is in the news again this morning.
Earlier, plant officials reported that a fire had started inside the plant, and that other problems later came up which caused plant operators to take emergency action. There have been no reports of injury from the accident, nor do we know of any releases of radiation from the crippled plant. We'll have more on the~Volf Creek emergency on KSN's news at noon.
93-FE 4.0-MM- 4
MH-11 TO: Media Monitoring FROM: TV TIME: 1040 MESSAGE: "This is a Drill" He_.3, I'm Kelly Waldo with a KAKE TV newsbreak. Disaster struck.
the Wolf Creek nuclear power plant near Burlington this morning, when a fire broke out inside the plant. Plant officials tell us ,
that the fire was extinguished, but that a water line break in the plant's reactor has created an emergency situation. Officials tell us that no radiation has escaped, but that plant workers are following emergency procedures. The beleagured power plant began operation in September 1985, after nearly ten years of controversy. We'll have more about the accident on KAKE's news at noon.
MM-12 TO: Media Monitoring FROM: Radio TIME: 1050 MESSAGE: "This is a Drill" This is Ray Means, KLZS radio news. Leading the. news-this morning-is the accident at Wolf Creek nuclear power plant in Eastern Kansas. The plant is on Alert this morning, which is the second level of emergency classification according to plant officials. A fire erupted at the plant earlier this morning, followed by'a loss of coolant around the reactor core. Earlier reports of injuries have proved incorrect. Plant officials assure us no one was hurt in the accident. At last report, plant workers were continuing to follow emergency procedures. We'll have more news as it becomes' available.
93-FE 4.0-MM- 5
MM-13 TO: Media Monitoring
- FROM: Radio TIME: 1100 (WAIT UNTIL SAE STATEMENT IS ISSUED)
MESSAGE: 'This is a Drill' This is Louise Simpson from the KEYN newsroom - we have just' received a news release from Wolf Creek Nuclear Operating I Corporation notifying us that a Site Area Emergency has been: '
declared at Wolf Creek nuclear plant. This-is the second most '
serious emergency classification, and there is a good change some radiation may be released from the plant. Details are sketchy as of the moment, and we're trying to get through to plant officials to determine what this really means. It appears to be a very serious situation. We'll follow up with more information as soon as it's available - stay tuned to your news station. KEYN.
MM-14 TO: Media Monitoring FROM: Radio .
TIME: 1110 MESSAGE: 'This is a Drill
- This just in from the KLZS newsroom - a Site Area Emergency has been declared at Wolf Creek nuclear power plant near Burlington, Kansas. This is the second most serious of four emergency designations for atomic power plants. Federal, state and local officials have been' called in to help with the situation. Wolf Creek is providing few details about the impending disaster, but they are urging local residents to listen to the Emergency Broadcast System for possible evacuation instructions.
t Again.'a Site Area Emergency has been declared at Wolf Creek.
This would appear to have the makings of the worst nuclear power accident ever to occur in the United States. Stay tuned to KLZS for more information as it becomes available. '
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i MM-15 TO: Media Monitoring FROM: Radio TIME: _1120 MESSAGE: "This is a Drill' This is Wyley Reed in the KFDI newsroom. -A bad situation is getting worse at the Wolf Creek nuclear power plant near Burlington. Wolf Creek has upgraded-this morning's Alert emergency to a Site Area Emergency, the second most serious ,
accident classification. During a Site Area Emergency, uncontrolled releases of radioactivity may occur requiring evacuation of area residents around the plant.
Officials say people living within ten miles of the plant have been advised to stay alert, monitor the Emergency Broadcast System and read their Emergency Information booklets for instructions.
The accident-plagued Wolf Creek plant started operation in September of 1985. Today's disaster will almo6L certainly mark the worst nuclear power disaster in United States history, and may approach the magnitude of the mishap at the Chernobyl plant in the Soviet Union. Stay tuned to KFDL for more late-breaking news on the Wolf Creek disaster.
MM-16 TO: Media Monitoring FROM: TV TIME: 1130 MESSAGE: "This is a Drill' Good morning, this is Don Williams with an update on the nuclear accident at Wolf Creek power plant. The situation at the plant.
continues to deteriorate this morning. Wolf Creek officials have declared a Site Area Emergency, the second most serious of'four emergency classifications. We have received unconfirmed reports that state troopers have blocked off roads leading to within 20 miles of the plant, and no one is being allowed _ closer. Officials tell us that there is a possibility radioactivity will be released ,
from the plant, and that area residents should be ready to take- {
emergency action. Our Channel 12 news team is on its way to ;
Topeka, where state, county and utility officials have set up an '
emergency communications facility. We'll have a live report from that facility on our KWCH news at noon. This is Don Williams,- 1 Channel 12 news. i l
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MM-17 TO: Media Monitoring FROM: TV TIME: 1140 MESSAGE: "This is a Drill" This is an NBC newsbreak with Roger Sand. The nuclear utility industry is anxiously watching developments at the Wolf Creek '
nuclear plant in eastern Kansas. An emergency situation that started with a fire at the plant this morning has escalated into what appears to be a very serious nuclear accident. Plant officials are warning area residents to be prepared in case an evacuation is necessary. This is the first serious nuclear power accident since the Chernobyl plant in the Soviet Union exploded in ,
1986. killing more than 30 persons and spreading contamination '
across the globe.
MM-18 TO: Media Monitoring FROM: TV TIME: 1150 MESSAGE: "This is a Drill' We interrupt regular programming for a special news update on the emergency at Wolf Creek Generating Station. WCNOC officials have upgraded the Alert emergency declared earlier this morning to the more serious Site Area Emergency.
A Site Area Emergency is declared when radiation escapes from two of the three radiation barriers at the plant. Federal, state and county emergency response officials have been notified and are monitoring the situation. State officials have assured KSN any actions necessary to protect the public health and safety will be taken.
Citizens of the area who might be affected by the release of radioactivity will be alerted by sirens and by the special tone alert radios issued by Coffey County Emergency personnel.
KSN will keep you informed as the crisis unfolds. Stay tuned.
This is Greg Roberts, KSN news.
93-FE 4.0-MM- 8 4
MH-19 TO: Media Monitoring FROM: TV >
TIME: 1200 MESSAGE: 'This is a Drill
- From the KAKE-TV newsroom, this is a specisl report: CRISIS AT WOLF CREEK. KAKE-TV has received word from KG&E that the emergency at Wolf Creek has been upgraded to a more serious SITS AREA EMERGENCY. Apparently some radiation is now leaking from the plant's radiation barriers. Federal, State and County disaster response officials have been alerted and are monitoring the situation.
Reports from persons living near the crippled plant say that there.
has been a marked increase in activity by emergency vehicles in the past hour. KG&E is urging persons living within 10 miles of the plant to tune to a local radio station for emergency information.
Again, a SITE AREA EMERGENCY has been declared at Wolf Creek.
Conditions at the plant have worsened since the fire at the plant happened this morning. Wolf Creek is located in Coffey County about four miles north of Burlington. The plant is 55 miles south of. Topeka and 90 miles southwest of the Kansas City metropolitan area. We'll have more about the Wolf Creek disaster on KAKE news at noon. This is Kelly Waldo reporting.
Note: Controller notify Lead Controller prior to placing call so.
rumor can be tracked.
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5 93-FE 4.0-MM- 9
MH-20 TO: Media Monitoring FROM: Radio TIME: 1205 MESSAGE: 'This is a Drill" The emergency continues to deteriorate at Wolf Creek nuclear-power' plant in southeastern Kansas. KGEE officials have declared a SITE
, AREA EMERGENCY, the second most serious of four emergency classifications. We have received unconfirmed reports of emergency workers in the area around the plant testing for radioactive fallout. If these reports are true, it would seem the ,
health and safety of anyone in the area could be in jeopardy.
State troopers have blocked off roads leading to the plant, and no one is being allowed any closer. . We have no confirmed reports of radiation leaking from the plant, but that's certainly a possibility during this serious mishap. Area residents are being urged to listen to their radios for Emergency Broadcast System ,
instructions. We'll try to have further details later in this WIBW radio newscast.
MM-21 TO: Media Monitoring FROM: TV TIME: 1210 MESSAGE: "This is a Drill" This is Kelly Valdo at KAKE Monday News. Just how disasterous will it be? That'< the question being asked in Kansas and throughout the world in the wake of a major nuclear power accident at Wolf Creek Generating Station. Events began to unfold at just before 6:00 this morning, when fire broke out inside the nuclear plant. Just when that problem appeared to be solved, plant officials report that coolant began to leak from the plant's reactor. Indications are the deadly uranium fuel inside the reactor may soon reach its melting point and cause a release of radiation to the environment. Wolf Creek is now under a Site Area Emergency, and local residents may soon be evacuated. We have a news team setting up in the Wolf Creek media center in Topeka. We hope to have an update from them by the end of this newscast.
93-FE 4.0-MM- 10'
MM-22 TO: Media Monitoring
~
FROM: TV TIME: 1220 MESSAGE: 'This is a Drill' Hello, everyone. I'm Don Williams, and this is KWCH news'at noon. The unthinkable is now happening at Wolf Creek nuclear plant, located 60 miles south of Topeka. The plant has declared a Site Area Emergency, wich is the second most serious of four emergency classifications. Multiple failures of the plant's safety systems has lead to a serious situation, and officials say a release of radiation is possible.
We were unable to arrange an on-camera interview with a Wolf Creek representative. However, we havge arrange to visit Mr. Clyde Widener, from the Union of Concerned Scientists. Mr. Widener, what do you think is going on at Wolf Creek now? -
[ Switch to 2nd Controller for ' Widener")
"Well, Don, it's hard to tell. I would expect.a great deal of uncertainty, bordering on panic, among the plant operators. They realize the instruments they count on to run the plant may not function properly under emergency conditions. And they know if they make one false move, they could actually contaminate half the county or more. I'd say it's probably a real tense situation -
I'm glad I'm not there!'
[ Switch back to ist Controller]
Thank you Mr. Widener. Again, there is a. Site Area Emergency at.
Wolf Creek. Anyone living within ten miles of the plant is urged to listen to Emergency Broadcast System channels for evacuation instructions. We'll have more on the disaster later this afternoon.
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93-FE 4.0-MM- 11
.MH-23 To: Media Monitoring FROM: TV TIME: 1225 MESSAGE: 'This is a Drill' It could be the worst disaster in Kansas history. This is Greg Roberts, KSN news, and that's what experts are saying about the nuclear accident at Wolf Creek. County, state and federal officials have joined Wolf Creek employees to try and regain control of the nuclear power plant. At last report, Wolf Creek officials had declared a Site Area Emergency, the-second most serious emergency classification. Residents of Coffey County are being prepared to evacuate their homes should radioactivity begin spewing from the plant.
NBC news will have a special report tonight at 10:30 Wolf Creek: A Sunflower Disaster will examine the controversial construction of the plant, and look at what may have gone wrong today.
MM-24 TO: Media Monitoring FROM: Radio TIME: 1235 (Wait until General Emergency release is issued)
MESSAGE: "This is a Drill" This is a special report from KKRD. Federal, State and Coffey County officials have been mobilized to prepare for emergency actions near Wolf Creek nuclear power plant in Coffey County.
KGEE has declared a General Emergency, which means clouds of radioactivity could be released from the nuclear reactor at any time. This is an accident very similar to what happened at the Chernobyl plant in the USSR last spring. Concerns during a massive release of radiation first center on' children in the area who could suffer terribly if exposed to only minute doses of the deadly plutonium fallout.
While we have no confirmation of any life-threatening releases of radiation from the plant, listeners are urged to stay tuned to their radios for possible instructions from the Emergency Broadcast System. We'll be back with more details on this
, disaster in a few minutes, i
1 93-FE 4.0-MM- 12 !
MH-25 TO: Media Monitoring FROM: TV TIME: 1245 (Vait until General FJoergency release is issued)
MESSAGE: "This is a Drill' This is Kelly Waldo, KAKE TV news. A General Emergency has been declared at Wolf Creek Nuclear Operating Corporation's Wolf Creek nuclear power station. Officials report that a hydrogen explosion occurred at the plant about an hour ago, and significant amounts of radioactivity is or may soon be released. Persons living within ten miles of the crippled plant are urged to listen to an .
Emergency Broadcast System station for evacuation instructions.
Again, a General Emergency has been declared at Wolf Creek. This is a very serious situation, and is especially dangerous for.
anyone in the Coffey County area. We expect more information within a few minutes from our reporter at the emergency media facility in Topeka. We'll interrupt progrmnaing again when that report is available.
MM-26 TO: Media Monitoring FROM: Radio TIME: 1255 (Wait until General Emergency release is issued)
MESSAGE: "This is a Drill" From the KXLK radio news room, this is Sam Ware. A General Emergency has.been declared at the Wolf Creek nuclear power plant in eastern Kansas. Officials from Wolf Creek made the announcement a few minutes ago in a news release from their emergency media facility. This is the most' serious of four emergency classifications, and radiation is or will soon be leaking from damaged paint. We have no indication of any deaths yet as a result of the accident. KXLK has' learned that emergency ,
officials from the State and Coffey County have joined in '
preparing to evacuate residents living within ten miles of the plant. No plans are yet being made to evacuate anyone outside this ten-mile emergency zone. Wolf Creek has been the center of controversy since construction began in 1977, but this is certainly the most serious problem ever encountered because of the plant. KXLK news is monitoring the situation closely, and will provide more details as they become available.
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4 MM-27 TO: Media Monitoring FROM: TV TIME: 1305 (Valt until General Emergency release is issued)
MESSAGE: 'This is a Drill" This is Greg Roberts in the KSN newsroom, and this is a special report on the Crisis at Wolf Creek nuclear power plant. We've just received word that a General Emergency has been declared at Wolf Creek due to a hydrogen explosion in the reactor building.
Unconfirmed reports from witnesses at the scene indicate that at least a third of the reactor building's doom roof has been blown off. Again these are unconfirmed reports. -Roadblocks have been set up on all roads leading to the plant, and our reporters cannot get close enought to the plant for a first-hand look. If indeed these reports are true, this would indicate a condition far more serious than Wolf Creek officials are telling us - if there is a hole in the reactor building, we could be looking at a radioactive release on the scale of the Chernobyl accident in the Soviet :
Union. We'll have more in a few minutes from our mobile unit now in the Coffey County area.
Note: Controller notify Lead Controller before placing call so rumor can be tracked. t 93-FE 4.0-MM-ll4
I MM-28 TO: Media Monitoring FROM: TV TIME: 1315 (12:38 p.m.)
MESSAGE: "This is a Drill' This is Don Williams, KWCH news with an update on the disaster at Wolf Creek. We now have made contact with our mobile satellite unit in the vicinity of Wolf Creek - let's switch to Wes Huntley ,
at the scene.
[ Change to different " reporter"]
This is Wes Huntley, and I'm standing in a field about a mile and a half to the northeast of the Wolf Creek plant. Roads leading to the plant have been blocked by the highway patrol, but we were able to get a closer look at the plant by taking our four-wheel-drive vehicle across country. At this time, things look quite normal at the plant. There is no evidence from this viewpoint of any damage to the reactor building. There's no smoke or any evidence of radiation escaping from the building. We have a geiger counter here at the truck and'it doesn't read anything out of the ordinary, so apparently there has been no radiation release to this point. We have seen several groups of people at various locations in the area, presumably measuring for radioactivity.
We'll try to get an interview with one of those groups if we can find one close by. This is Wes Huntley, reporting from near Wolf Creek nuclear plant. -
Note: Controller notify Lead Controller before placing this message.
MH-29 TO: Media Monitoring FROM: Radio TIME: 1325 MESSAGE: "This is a Drill' This is KEYN news update, I'm Louise Simpson. Shocking and disgusting - that's how Congressman Don Glassman described'the accident at Wolf Creek nuclear plant. Glassman, a long-term critic of.the project, said he plans to put pressure on the Nuclear Regulatory Commission to determine the exact cause of-the accident. Meanwhile, Wolf Creek officials say the plant is still under a General Emergency.
93-FE 4.0-MM- 15
1 MH-30 TO: Media Monitoring FROM: TV TIME: 1335 1 1
MESSAGE: "This is a Drill' l:- This is a CBS newsbreak,' I'm Roger Perkins. What may be the worst nuclear power accident in U.S. history is now taking place at Wolf Creek Generating Station in eastern Kansas. .A General Emergency, which is the most serious emergency classification, has been declared. Meanwhile in Washington, Congressman Don Glassman of Kansas is calling on the Nuclear Regulatory Commission to begin an investigation into the cause of the accident. We'll have more news later today.
MM-31 TO: Media Monitoring FROM: Radio TIME: 1345 MESSAGE: "This is a Drill' This is Wyley Reed with a KFDI news update. Still no progress in solving the problems at Wolf Creek nuclear plant. Plant officials say there is still a General Emergency, meaning radioactive material may be escaping from the crippled reactor. Residents of Coffey County are being told to listen to Emergency Broadcast System stations for evacuation instructions. We'll have more on the crisis as it develops.
MM-32 TO: Media Monitoring FROM: Radio TIME: 1350 MESSAGE: "This is a Drill' This is Norman Grant of KLZS Radio. The big story today has been the emergency at the Wolf Creek nuclear plant. We contacted a team of Wolf Creek employees at the Wichita, Kansas Rumor Control Hotline. Specially trained employees have assumed their emergency roles at Wolf Creek near Burlington, in Wichita, and at a media information center in Topeka. Assisting Wolf Creek in responding to the country's worst nuclear disaster are emergency teams from ,
Coffey County, Kansas State, and the Nuclear Regulatory '
Commission.
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93-FE 4.0-MM- 16 I
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MESSAGE NO: CEOC-6 THIS IS A DRILL 20_ NOT initiate actions affecting normal plant operations.
TO: Coffey County Radiological Officer
~
FROM: rice Leader LOCATION: County EOC TIME: 1230 (H+04:30)
MESSAGE: If we need to do decontamination at the access control points, we will need more water supplies then we have. Can you locate some water trucks?
i NOTE: 20,NOT TAKE ANY ACTION other than to coordinate a simulated response with the appropriate personnel.
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93-FE 4.-CEOC- 6
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9
MESSAGE NO: CEOC-7 THIS IS A DRTTT.
E NOT initiate actions affecting normal plant operations.
To: Sheriff FROM: Storekeeper LOCATION: County EOC TIME: 1300 (H+05:00)
MESSAGE: This is Brad Simons - I own the drugstore here and I want to know just what kind of protection against looters I'll have if I leave. Are any of your men going to be guarding the stores?
NOTE: M NOT TAKE ANY ACTION other than to coordinate a simulated response with the appropriate personnel.
e THIS IS A DRILL 93-FE 4.-CEOC .
HESSAGE NO: CEOC-8 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
TO: County Commissioners FROM: Senator's Aide LOCATION: County EOC TLHE: 1330 (H+05:30)
MESSAGE: Senator Dan Glickman would like an update from County government on the status of local efforts to deal with the Wolf Creek situation. Do you require any assistance from Senator Glickman as far as cabning down the public?
NOTE: 20. NOT TAKE ANY ACTION other than to coordinate a simulated response with the appropriate personnel.
~
THIS IS A DRILL 93-FE 4.-CEOC- 8
MESSAGE NO: CEOC-9 THIS IS A DRILL M NOT initiate actions affecting normal plant operations.
TO: County Agent FROM: Farmer LOCATION: County EOC TIME: 1345 (H+05:45)
MESSAGE: I want help getting some stored feed for my dairy cows, My name is Herbert Rcgers, my farm is just outside of Lebo, and I need that feed as soon as possible.
NOTE: M NOT TAKE ANT ACTION other than to coordinate a simulated response with the appropriate personnel.
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O b THIS IS A DRILL 93-FE 4.-CEOC- 9
MESSAGE NO: CEOC-10 THIS IS A DRTLL M NOT initiate actions affecting normal plant operations.
To: Shelter Systems Officer FROM: Al' County EPC LOCATION: Cou. 20C TIME: 1400 (H+06:00)
MESSAGE: We are getting calls from evacuees that claim we are supposed to take care of tF. . What gives? I thought that Allen County was-
. no longer a hr 'nty. There must be 20 or 30 people here now that want lodt ad meals because they were told to evacuate.
NOTE: M NOT TAKE ANY ACTION other than to coordinate
- a cimulated response with the appropriate personnel.
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' l THIS IS A DRILL 93-FE 4..CEOC- 10
MESSAGE NO: CEOC-11 l f
THIS IS A DRILL M NOT initiate actions affecting normal plant operations.
To: Health Medical Management Team FROM: Waverly Nursing Home LOCATION: County EOC TIME: 1415 (H+06:15)
MESSAGE: We have had Burlington folks stop by to visit relatives. What is the chance of these evacuees contaminating patients?
NOTE: E NOT TAKE ANY ACTION other than to coordinate a simulated response with the appropriate personnel.
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MESSAGE NO: CEOC-12 THIS IS A DRTIY.
-20 NOT initiate actions affecting normal plant operations.
TO: Shelter Systems Officer FROM: Host County LOCATION: County EOC TIME: 1500 (H+07:00)
MESSAGE: Your RO is to dispose of contaminated items. When vill he get this stuff 7 We have several bags and people are getting concerned.
NOTE: pO_ NOT TAKE ANY ACTION other than to coordinate a simulated response with the appropriate personnel.
THIS IS A DRILL 93-FE 4.-CEOC- 12
HESSAGE NO: SEOC-1 THIS IS A DETLL pg NOT initiate actions affecting nonnal plant operations.
TO: Director or Deputy Director KDEP FROM: Director, FEMA, Region VII (Lead State EOC Controller)
LOCATION: State EOC TIME, 1030 (H+02:30)
MESSAGE: What is the current status of the emergency at the power plant?
Should we anticipate your requesting assistance from us and if so when? I would like to get my people prepared if you feel this situation will worsen. What do you think?
NOTE: DQ NOT TAKE ANY ACTION other than to coordinate a simulated response with the appropriate personnel.
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MESSAGE NO: SEOC-2 THIS IS A DRILL JX} NOT initiate actions affecting normal plant operations.
TO: National Guard FROM: Kansas Department of Wild 11de and Parks LOCATION: State EOC TIHE: 1100 (H+03:00)
MESSAGE: How quickly can you get a helicopter out to Otter Creek? We've found a hunter who's apparently having a heart attack and it will take hours to get him out. What can you do to assist?
NOTE: D0_ NOT TAKE ANY ACTION other than to coordinate a simulated response with the appropriate personnel.
t THIS IS A DRILL 93-FE 4.-SEOC- 2
MESSAGE NO: SEOC-3 THIS IS A DRILL jy2 NOT initiate actions affecting normal plant operations. '
TO: Director or Deputy Director KDEP FRCH: Director, FEMA Region VII LOCATION: - State EOC TIME: 1230 (H+04:30)
MESSAGE: We have had several calls from the media about the emergency. It sounds like things are getting worse. I am going to make a news release in about 15 minutes. What is the current status of utility, state, and local efforts?
NOTE: E NOT TAKE ANY ACTION other than to coordinate a simulated response with the appropriate' personnel, l
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MESSAGE NO: SEOC-4 THIS IS A DETLL Jg! EOT initiate actions affecting normal plant operations.
TO: Kansas Department of Transportation FROM: Goodwin Construction Company LOCATION: State EOC TIME: 1300 (H+05:00)
MESSAGE: We've got a real mess here on 75 just south of Lyndon. Our guys are doing some repair work and have one lane closed. There are about 80 cars backed-up that were trying to go south, and plenty more coming the other way. People are pretty nervous and going awfully fast because of the nuclear plant. I'm afraidwe're going to have a bad accident. What can you do to assist?
NOTE: E NOT TAKE ANY ACTION other than to coordinate a simulated response with the appropriate personnel. -j I
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i 93-FE 4.-SEOC- 4 j 1
MESSAGE NO: SEOC-5 THIS IS A DRILL L
JX} NOT initiate actions affecting normal plant operations.
To: National Guard FROM: Coffey County Radiological Officer LOCATION: State EOC TIME: 1330 (H+05:30)
MESSAGE: Can you furnish water trucks for the Fire Department to use for decontamination at the access control points? How long would it take to get them here?
NOTE: M NOT TAKE ANY ACTION other than to coordinate a simulated response with the appropriate personnel.
t THIS IS A DETil 93-FE 4.-SEOC- 5
MESSAGE NO: SE0C-6 THIS IS A DRILL M NOT initiate actions affecting normal plant operations.
TO: Kansas Department of Wildlife and Parks FROM: Citizen LOCATION: State EOC TIME: 1400 (H+06:00) c MESSAGE: What is going to happen to tha fishing in the Neosho River thanks to Wolf Creek? How far downstream are we going to have te go before we can be sure that the fish are safe to eat?
l NOTE: E NOT TAKE ANY ACTION other than to coordinate i a simulated response with the appropriate personnel.
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THIS IS A DRILL 93-FE 4.-SEOC- 6 1
MESSAGE NO: SEOC-7 l
l THIS IS A DRILL ,
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29 NOT initiate actions affecting normal plant operations. ,
l TO: Kansas Highway Patrol FROM: Governor's Office LOCATION: State EOC TIME: 1415 (H+06:15)
MESSAGE: We are getting calls from several communities about 50-60 miles southeast of Wolf Creek that are thinking about evacuating because of the accident at the plant. How many men can you get to that area to maintain traffic control in an hour? 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />? '
NOTEi 20 NOT TAKE ANY ACTION other than to coordinate a simulated response with the appropriate personnel.
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THIS IS A DRILL 93-FE 4.-SEOC- 7
- i MESSAGE NO: SEOC-8 THIS IS A DRILL 19 NOT initiate actions affecting normal plant operations.
TO: Kansas Board of Agriculture FROM: Governor's Press Secretary LOCATION: State EOC TIME: 1430 (H+06:30)
MESSAGE: We are getting calls from several communities northeast of Burlington that want to evacuate due to Wolf Cre'ek. Should that occur, hov long would it take to get some barricades set up to cordon off secondary roads and maintain traffic flow? _How many people can you supply us with to assist in this effort?
NOTE: DO NOT TAKE ANY ACTION other than to coordinat.e a simulated response with the appropriate personnel.
THIS IS A DRILL 93-FE 4.-SEOC- 8 ,
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MESSAGE NO: SEOC-9 THIS IS A DEILL DO NOT initiate actions affecting normal plant-operations.
TO: Kansas Board of Agriculture FROM: County Agent LOCATION: State EOC TIME: 1500 (H+07:00)
MESSAGE: Some farmers are asking me how long will it be before they can come back to their farms? Will anyone be responsible for milking their dairy cattle while the farmers are away?
NOTE: DO NOT TAKE ANY ACTION other than to coordinate a simulated response with the appropriate personnel.
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l THIS IS A DRII.L 93-FE 4.-SEOC- 9 i
MESSAGE NO: SEOC-10 THIS IS A DRTf.f.
Dg NOT initiate actions affecting nonmal plant operations.
TO: Kansas Department of Health & Environment FROM: Environmental Protection Agency LOCATION: State EOC TIME: 1515 (H+07:15)
MESSAGE: We're sending some of our people from Montgomery, Alabama and they'll be there in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. They'll be bringing their mobile van lab and will want to set it up in the closest possible location to the plume for sampling. Where can we set up?
NOTE: pg NOT TAKE ANT ACTION other than to coordinate a simulated response with the appropriate personnel.
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l 93-FE 4..SEOC- 10 l
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MESSAGE NO: SEOC-11 THIS IS A DRILL M NOT initiate actions affecting normal plant operations.
TO: Kansas Department of Wildlife and Parks FROM: U.S. Fish & Wildlife Service LOCATION: State EOC TIME: 1600 (H+08:00)
MESSAGE: This is Ed Harris from the Denver office of the U.S. Fish &
Wildlife Service. We are very interested in how the accident at Wolf Creek will affect John Redmond Reservoir in the long run.
Do you have any plans to do such a study? If not, is any other State agency planning to follow through?
NOTE: _D_0_ NOT TAKE ANY ACTION other than to coordinate a simulated response with the appropriate personnel, t
, THIS IS A DRILL 93-FE 4.-SEOC- 11
4 SECTION 5.0 t
PLANT DATA Subsections Zage PLANT PARAMETERS 5.1 PLANT GRAPHS. .
5.36 CONTAllWENT BUILDING BREACH FLOW RATE 5.59 PLANT UNIT VENT FLOW RATE 5.61 CORE DAMAGE ASSESSMENT 5.63
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FLANT PARAMETERS l
Time-related plant parameters are provided in the following subsection. The l data includes parameters for primary and secondary systems that may or may '
not have an impact on this scenario. The following subsection, ' Plant l
Graphs' depicts the same data in graph form.
]
1 These parameters may be used as a source of data for control room (CR) .
operators by the CR Lead Controller, in case of simulator failure. ;
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PIWtf PARAMETERS Time 0800 Plant Loop 1~ Loop 2 Loop 3 Loop 4 Relative Time (H+00:00) Values or A or B or C or D values Values Values values PRIMARY SYSTEM Reactor Power (I) 100 - - - -
Reactor Vessel Level (I) - Natural 111 - - - -
Circulation Reactor Coolant System (RCS) Pressure 2297 - - - -
(psig)
Pressurizer Level (I) 60 - - - -
Reactor Coolant System Temp. (OF)
T C
(vide-range) - 558 558 558 558 T
H (vide-range) -
618 618 618 618 AVG (narrow-range) -
588 588 588 588 Core Exit Thermocouple Temp. (OF) 599 - - - -
Reactor Coolant Loop Flows (Z) -
' 100 100 100 100 Boron Concentration (ppm) 658 - - - -
SECONDARY SYSTEMS 6
Main Steam Flow Rate (x10 lbm/hr) - 3805 3805 3805 3805 Steam Generator (WR) Levels (I) - 67 67 67 67 Steam Generator Pressures (psig) - 988 988 988 988 CONTAINMENT BUILDING Pressure (psig) .4 - - - -
Temperature (OF) 80 - - - -
Humidity (Z) 33 - - - -
Hydrogen Concentration (I vol) 0 - - - -
Recirculation Sump Level (in) 0 - - - -
TANKS Accumulator Levels (I) - 59 59 59 59 Accumulator Pressures (psig) - 645 645 645 645 Refueling Water Storage Tank Level (Z) 99 - - - -
93-FE 5. 2
9 FLANT PARAMETERS Time 0815 Plant Loop l' Loop 2 Loop 3 Loop 4 Relative Time (H+00:15) Values or A or B or C or D values values Values Values PRIMARY SYSTEM Reactor Power (Z) 100 - - - -
Reactor Vessel L. 2- g2) - Natural 111 - - - -
Circulation Reactor Coolant System (RCS) Pressure 2289 - - - -
(psig)
Pressurizer Level (Z) 59 - - - -
Reactor Coolant System Temp. (DF)
T C
(wide-range) - 557 557 557 557 T
H (wide-range) -
618 618 618 618 TAVG (narr w-range) - 587 587 587 587 Core Exit Thermocouple Temp. (OF) 599 - - - -
Reactor Coolant Loop Flows (Z) - 100 100 100 100 Boron Concentration (ppm) 657 - - - -
SECONDARY SYSTEMS Main Steam Flow Rate (x10 lbm/hr) - 3784 3761 3811 3784 Steam Generator (WR) Levels (I) - 67 67 67 67 Steam Generator Pressures (psig) - 979 979 979 979 i CONTAINMENT BUILDING Pressure (psig) .4 - - - .
. Temperature (OF) 94 - - - -
Humidity (Z) 33 - - - -
Hydrogen Concentration (I vol) 0 - - - -
Recirculation Sump Level (in) 0 - - - -
)
TANKS Accumulator Levels (2) - 59 59 59 59 Accumulator Pressures (psig) - 645 645 645 645 l Refueling Water Storage Tank Level (I) 99 - - - -
93-FE 5. 3
PLANT PARAMETERS l Time 0830 Plant Loop l' Loop 2 Loop 3 Loop 4 Relative Time (H+00:30) Values or A or B or C or D Values Values Values Values i
PRIMARY SYSTEM Reactor Power (I) 100 - - - -
Reactor Vessel Level (I) - Natural 111 - - - -
Circulation Reactor Coolant System (RCS) Pressure 2301 - - - -
(psig)
Pressurizer Level (I) 60 - - - -
Reactor Coolant System Temp. (OF)
T C
(wide-range) - 557 557 557 557 T
H (w e-range) -
618 618 618 TAVG (narr w-range) - 587 587 587 587.
Core Exit Thermocouple Temp. (OF) 599 - - . -
Reactor Coolant Loop Flows (I) - 100 100- 100 100 Boron Concentration (ppm) 657 - - - -
JECONDARY SYSTEMS Main Steam Flow Rate (x10 lbm/hr) - 3783 3759 3810 3783 Steam Generator (WR) Levels (I) - 67 67 67 67 Steam Generator Pressures (psig) - 978 978 978 978 CONTAINMENT BUILDING Pressure (psig) .8 - - - -
Temperature (OF) 106 - - - -
Humidity (I) 33 - - - -
Hydrogen Concentration (I vol) 0 - - - -
Recirculation Sump Level (in) 0 - - - -
TANKS Accumulator Levels (I) - 59 59 59 59 Accumulator Pressures (psig) - 645 645 645 645 Refueling Vater Storage Tank Level (I) 99 - - - -
93-FE 5. 4 k
PLANT PARAMETERS Time 0845 Plant Loop l' Loop 2 Loop 3 Loop 4 Relative Time (H+00:45) Values or A or B or C or D Values Values Values Values PRIMARY SYSTEM Reactor Power (I) 90 - -
p -
Reactor Vessel Level (Z) - Natural , 109 - - - -
Circulation Reactor Coolant System (RCS) Pressure 2125 - - - -
(psig)
Pressurizer Level (I) 37 - - - -
Reactor Coolant System Temp. (OF)
T C
(wide-range) -
557 557 557 557 T
H (wide-range) - 612 612 612 558 TAVG (narr w-range) -
585 585 585 558 Core Exit Thermocouple Temp. (OF) 595 - - - -
Reactor Coolant Loop Flows (I) - 100 100 100 100 Boron Concentration (ppm) 691 - - - -
SECONDARY SYSTDiS 6
Main Steam Flow Rate (x10 lbm/hr) - 3316 3292 3344 3318 Steam Generator (WR) Levels (I) - 66 66 66 66 Steam Generator Pressures (psig) - 989 989 989 989 CONTAINMENT BUILDING Pressure (psig) 1.6 - - - -
Temperature (OF) 115 - - - -
Humidity (I) 57 - - - -
Hydrogen Concentration (Z vol) 0 - - - -
Recirculation Sump Level (in) 0 - - - -
TANKS Accumulator Levels (Z) . 59 59 59 59 Accumulator Pressures (psig) -
645 645 645 645 Refueling Water Storage Tank Level (%) 99 - - - -
93-FE 5. 5
PLANT PARAMETERS Time 0847 Plant Loop l' Loop 2 Loop 3 Loop 4 Relative Time (H+00:47) Values or A or B or C or D Values Values Values Values PRIMARY SYSTEH Reactor Pqwer (2) .2 - - - -
Reactor Vessel Level (Z) - Natural 99 - - - -
Circulation Reactor Coolant System (RCS) Pressure 1677 - - - -
(Psig)
Pressurizer Level (2) 0 - - - -
Reactor Coolant System Temp. (OF)
T C
(wide-range) - 557 557 557 557 T
H (wide-range) - 559 559 559 559 TAVG (narr w-range) - 558 558 558 558 Core Exit Thermocouple Temp. (OF) 559 - - - -
Reactor doolant Loop Flows (I) - 100 100 100 100 Baron Concentration (ppm) 699 - - - -
SECONDARY SYSTEMS 6
Main Steam Flow Rate (x10 lbm/hr) - 108 85 137 109 Steam Generator (WR) Levels (I) - 55 55 55 55 Steam Generator Pressures (psig) - 1089 1089 1089 1089 CONTAINHENT BUILDING Pressure (psig) 2.7 - - - -
Temperature (OF) 117 - - - -
Humidity (I) 98 - - - -
Hydrogen Concentration (I vol) 0 - - - -
Recirculation Sump Level (in) 0 - - - -
TANKS Accumulator Levels (I) -
59 59 59 59 Accumulator Pressures (psig) - 645 645 645 645 1 Refueling Water Storage Tank Level (I) 99 - - - -
93-FE 5. 6 t
1 PLANT PARAMETERS l l
l Time 0900 Plant Loop l' Loop 2 Loop 3 Loop 4 Relative Time (H+01:00) Values' or A or B or C or D Va~ lues Values Values Values PRIMARY SYSTEM Reactor Power (Z) 0 - - - -
Reactor Vessel Level (Z) - Natural 97 - - - -
Circulation Reactor Coolant System (RCS) Pressure 1141 - - - -
(psig)
Pressurizer Level (Z) 0 - - - -
Reactor Coolant System T'emp. (OF)
T C
(wide-range) - 524 524 524 524 T
H (wide-range) -
565 565 565 565 Tgyg (narrow-range) -
544 544 544 544 Core Exit Thermocouple Temp. (OF) 525 - - - -
Reactor Coolant Loop Flows (Z) - 0 0 0 0 Baron Concentration (ppm) 816 - - - -
SECONDARY SYSTEMS 6
Main Steam Flow Rate (x10 lbm/hr) - 48 62 0 64 Steam Generator (WR) Levels (Z) - 58 58 57 58 Steam Cenerator Pressures (psig) - 1105 1105 1105 1105 CONTAINMENT BUILDING Pressure (psig) 5 - - - -
Temperature (OF) 128 - - - -
Humidity (Z) 98 - - - -
Hydrogen Concentration (2 vol) 0 - - - -
Recirculation Sump Level (in) 0 - - - -
TANKS 4 cumulator Levels (Z) - 59 59 59 59 Accumulator Pressures (psig) - 645 645 645 645 Refueling Water Storage Tank Level (Z) 99 - - - -
93-FE 5. 7
PLANT PARAMETERS Time 0915 Plant Loop 1 Loop 2 Loop 3 Loop 4 Relative Time (H+01:15) values or A or B or C or D Values values Values values PRIMARY SYSTEM Reactor Power (I) 0 - - - -
Reactor Vessel Level (Z) - Natural 97 - - - -
Circulation Reactor Coolant System (RCS) Pressure 1039 - - - -
(psig)
Pressurizer Level (Z) 0 - - - -
Reactor Coolant System Temp. (OF)
T I"' *~#8"E*' ~
C T
H (wide-range) - 554 554 554_ 554 TAVG (narr w-range) - 539 539 539 539 Core Exit Thermocouple Temp. (OF) 500 - - - -
Reactor Coolant Loop Flows (I) - 0 0 0 0 Boron Concentration (ppm) 989 - - - -
SECONDARY SYSTEMS 6
Hain Steam Flow Rate (x10 lbm/hr) - 98 79 119 148 Steam Generator (WR) Levels (I) -
61 61 61 62 Steam Generator Pressures (psig) - 992 992 992 992 SONTAINMENT BUILDING Pressure (psig) 6 - - - -
Temperature (DF) 136 - - - -
Humidity (I) 98 - - . . -
Hydrogen Concentration (Z vol) 0 - - -- -
Recirculation Sump Level (in) 0 - - - -
TANKS Accumulator Levels (I) - 59 59 59 59 Accumulator Pressures (psig) -
645 645 645 645 Refueling Water Storage Tank Level (I) 99 - - . -
)
i 93-FE 5. 8
FLANT PARAMETERS Time 0930 Plant Loop l' Loop 2 Loop 3 Loop 4 Relative Time (H+01:30) Values or A or B or C or D Values Values Values Values PRIMARY SYSTEM Reactor Power (I) 0 - - - -
Reactor Vessel Level (I) - Natural 96 - - - -
Circulation Reactor Coolant Systen (RCS) Pressure 442 - - - -
(psig)
Pressurizer Level (2) 0 - - - -
Reactor Coolant System Temp. (OF)
T C
(wide-range) - 400 400 400 400 T
H (w e-range -
48 T379 (narrow-range) - 530 530 530 530 Core Exit Thermocouple Temp. (OF) 493 - - - -
Reactor Coolant Loop Flows (Z) - 0 0 0 0 Baron Concentration (ppm) 1361 - - - -
SECONDARY SYSTEMS 6
Main Steam Flow Rate (x10 lbm/hr) - 53 39 88 70 Steam Generator (WR) Levels (I) - 66 65 65 66 Steam Generator Pressures (psig) - 445 445 445 445 CONTAINMENT BUILDING Pressure (psig) 6 -- - - -
Temperature (OF) 138 - - - -
Humidity (Z) 98 - - - -
Hydrogen Concentration (2 vol) 0 - - - -
Recirculation Sump Level (in) 0 - - - -
TANRS ;
Accumulator Levels (I) - 39 39 39 39 Accumulator Pressures (psig) - 432 432 432 432 Refueling Vater Storage Tank Level (I) 96 - - - -
93-FE 5. 9
PLAlf? PARAMETERS Time 0945 Plant Loop l' Loop 2 Loop 3 Loop 4 Relative Time (H+01:45) Values or A or B or C or D Values Values Values Values PRIMARY SYSTEM Reactor Power (I) 0 - - - -
Reactor Vessel Level (I) - Natural 76 - - - -
Circulation Reactor Coolant System (RCS) Pressure 345 - - - -
(psig)
Pressurizer Level (I) 0 - - - -
Reactor Coolant System Temp. (DF)
T (wi e-range) - 60 360 360 C
T (wi e-range) -
8 418 H
TAVG (narrow-range) -
530 530 530 530 Core Exit Thenmocouple Temp. (DF) 440 - - - -
Reactor Coolant Loop Flows (I) -
O O O O Boron Concentration (ppm) 1594 - - - -
SECONDARY SYSTEMS 6
Main Steam Flow Rate (zl0 lbm/hr) -
62 78 48 63 Steam Generator (WR) Levels (I) - 73 70 71 71 Steam Generator Pressures (psig) - 285 285 285 285 CONTAINMENT BUILDING Pressure (psig) 6.9 - - - -
Temperature (OF) 141 - - - -
Humidity (I) 98 - - - -
Hydrogen Concentration (I vol) 0 - - - -
Recirculation Sump Level (in) 0 - - - -
TANKS Accumulator Levels (I) - 23 23 23 23 Accumulator Pressures (psig) - 336 336 336 336 Refueling Water Storage Tank Level (I) 94 - - - -
93-FE 5. 10
PLANT PARAMETERS Time 1000 Plant Loop l' Loop 2 Loop 3 Loop 4 Relative Time (H+02:00) Values or A or B or C or D Values Values Values Values PRIMARY SYSTEM Reactor Power (I) 0 - - - -
Reactor Vessel Level (I) - Natural 45 - - - -
Circulation Reactor Coolant System (RCS) Pressure 271 - - - -
(psig)
Pressurizer Level (2) 12 - - - -
Reactor Coolant System Temp. (OF)
T C
(wide-range) - 364 364 364 364 ,
T H
(vide-range) - 410 410 410 410 TAVG (narrow-range) -
530 530 530 -530 Core Exit Thermocouple Temp. (OF) 1250 - - - -
Reactor Coolant Loop Flows (I) - 0 0 0 0 Boron Concentration (ppm) 1789 - - - -
SECONDARY SYSTEMS Main Steam Flow Rate (x10 lbm/hr) -
55 24 47 '31 Steam Generator (WR) Levels (I) -
75 73 73 74 Steam Generator Pressures (psig) - 198 198 198 198 CONTAINMENT BUILDING Pressure (psig) 15 - - - -
Temperature (OF) 149 - - - -
Humidity (I) 100- - - - -
Hydrogen Concentration (2 vol) 0 - - - -
Recirculation Sump Level (in) 0 - - - -
TANRS
{
1 Accumulator Levels (I) - 0 0 0 0 i Accumulator Pressures (psig) -
201 201 201 201 Refueling Water Storage Tank Level (Z) 93 - - - -
l l
93-FE 5. 11 l
. i I
I 1
. PLANT PARAMETERS Time 1015 Plant Loop l' Loop 2 Loop 3 Loop 4 Relative Time (H+02:15) Values or A or B or C or D ,
Values Values Values Values PRIMARY SYSTEM Reactor Power (I) 0 - - - -
Reactor Vessel Level (I) - Natural 45 - - - -
Circulation Reactor Coolant System (RCS) Pressure 152 - - - -
(psig)
Pressurizer Level (I) 0 - - - -
Reactor Coolant System Temp. (DF)
T C
(w de-range) -
316 314 314 315 T
H (v e-range) -
63 363 363 TAVG (narr w-range) - 530 530 530 530 Core Exit Thermocouple Temp. (OF) 1250 - - -
Reactor Coolant Loop Flows (I) - 0 0 0 0 Boron Concentration (ppm) 1889 - - - -
SECONDARY SYSTEMS 6
Main Steam Flow Rate (x10 lbm/hr) -
171 168 184 170 Steam Generator (WR) Levels (I) - 75 74 75 76 Steam Generator Pressures (psig) -
106 104 104 105 CONTAINMENT BUILDING Pressure (psig) 25 - - - -
Temperature (OF) 383 - - - -
Humidity (I) 100 - - - -
Hydrogen Concentration (I vol) 0 - - - -
Recirculation Sump Level (in) 0 - - - -
TANKS Accumulator Levels (I) -
0 0 0 0 Accumulator Pressures (psig) - 125 125 125 125 Refueling Water Storage Tank Level (I) 90 - - - -
l 93-FE 5. 12' l e
PLANT PARAMETERS Time 1030 Plant Loop 1- Loop 2 Loop 3 Loop 4 Relative Time (H+02:30) values or A or B or C or D Values Values Values Values J ?RIMARY SYSTEM Reactor Power (I) 0 - -
f - -
Reactor Vessel Level (I) - Natural 41 - - - -
7 Circulation i
Reactor Coolant System (RCS) Pressure 50 - - - -
(psig)
Pressurizer Level (2) 0 - - - -
Reactor Coolant System Temp. (OF)
T C
("' **#""E' ~
T g (wide-range) -
286 286 286 286 T
AVG I""## "~##"8' ~
Core Exit Thenmocouple Temp. (OF) 1300 - - - -
Reactor Coolant Loop Flows (Z) -
0 0 0 0 Boron Concentration (ppm) 1968 - - - -
SECONDARY SYSTEMS Main Steam Flow Rate (x10 lbm/hr) -
74 54 62 74-Steam Generator (WR) Levels (2) -
74 71 71 77 i Steam Generator Pressures (psig) -
28 29 29 28 l CONTAINHENT BUILDING Pressure (psig) 25 - - - .
Temperature (OF) 383 - - - -
Humid!'y (I) 100 - - - -
Hydrogen Concentration (I vol) 0.5 - - - -
Recirculation Sump Level (in) 0 - - - -
TANKS Accumulator Levels (I) ,
0 0 0 0 Accumulator Pressures (psig) -
26 26 26 26 Refueling Water Storage Tank Level (I) 86 - - - -
93-FE
- 5. 13
PLANT PARAMETERS Time 1045 Plant Loop l' Loop 2 Loop 3 Loop 4 Relative Time (H+02:45) Values or A or B or C or D values values Values Values PRIMARY SYSTEM Reactor Power (I) ,
0 - - - -
Reactor Vessel Level 'I) - Natural 43 - - - -
Circulation Reactor Coolant System (RCS) Pressure 44 - - - -
(psig)
Pressurizer Level (I) 0 - - - -
Reactor Coolant System Temp. (OF)
T C
(wide-range) - 250 255 255 249 T
H (v e-range) - 8 278 278 278 Tgyg (narrow-range) - 530 530 530 530 Core Exit Thermocouple Temp. (OF) 1500 - - - -
Reactor Coolant Loop Flows (I) - 0 0 0 0 Boron Concentration (ppm) 1974 - - - -
SECONDARY SYSTEMS 6
Main Steam Flow Rate (x10 lbm/hr) -
69 41 36 69 Steam Generator (WR) Levels (I) - 74 71 71 77 Steam Generator Pressures (psig) - 25 26 26 25 CONTAINMENT BUILDING Pressure (psig) 25 - - - -
Temperature (OF) 383 - - - -
Humidity (I) 100 - -- - -
Hydrogen Concentration (I vol) 0.5 - - - -
Recirculation Sump Level (in) 100 - - - -
TANKS Accumulator Levels (I) - 0 0 0 0' Accumulator Pressures (psig) - 26 26 26 26 Refueling Water Storage Tank Level (I) 85 - - - -
93-FE 5. 14
PLANY PARAMETERS Time 1100 Plant Loop l' Loop 2 Loop 3 Loop 4 ,
Relative Time .( H+03 : 00 ) Values , or A or B or C or D Values Values Values values PRIMARY SYSTEM Reactor Power (I) 0 - - - -
Reactor Vessel Level (Z) - Natural 43 - - - - r Circulation Reactor Coolant System (RCS) Pressure 44 - - - -
(psig)
Pressurizer Level (I) 0 - - - -
Reactor Coolant System Temp. (OF)
T C
(wide-range) -
250 255 255 249-T (vide-range) - 278 278 278 278 g
Tgyg (narrow-range) -
530 530 530 530 Core Exit Thermocouple Temp. (DF) 1600 - - - -
Reactor Coolant Loop Flows (Z) - 0 0 0 0 Boron Concentration (ppm) 1974 - - - -
SECONDARY SYSTEMS Main Steam Flow Rate (x10 lbm/hr) - 69 41 36 69 Steam Generator (WR) Levels (I) -
74 71 71 77 Steam Generator Pressures (psig) - 25 26 26 25 CONTAINMENT BUILDING Pressure (psig) 25 - - -
Temperature (DF) 383 - - - -
Humidity (Z) 100 - - - -
Hydrogen Concentration (Z vol) 1.5 - - - -
Recirculation Sump Level (in) 100 - - - -
TANKS Accumulator Levels (I) - 0 0 0 0 Accumulator Pressures (psig) -
26 26 26 26 Refueling Water Storage Tank Level (I) 85 - - - -
93-FE 5. 15
PLANT PAR / METERS Time 1115 Plant Loop l' Loop 2 Loop 3 Loop 4 Relative Time (H+03:15) Values or A or B or C or D Values Values Values Values PRIMARY SYSTEM Reactor Power (I) 0 - - - -
Reactor Vessel Level (Z) - Natural 43 - - - -
Circulation Reactor Coolant System (RCS) Pressure 44 - - - -
(psig)
Pressurizer Level (Z) 0 - - - -
Reactor Coolant System Temp. (OF)
T C
(wide-range) - 250 255 255 249 T (wi e-range) -
8 H
TAVG (narr w-range) -
530 530 530 530 Core Exit Thermocouple Temp. (OF) 2000 - - - -
Reactor Coolant Loop Flows (Z) - 0 0 0 0 Boron Concentration (ppm) 1974 - - - -
SECONDARY SYSTEMS Main Steam Flow Rate (x10 lbm/hr) - 69 41 36 69 Steam Generator (WR) Levels (Z) - 74 71 71 77 Steam Generator Pressures (psig) - 25 26 26 25 CONTAINMENT BUILDING Pressure (psig) 25 - - - -
Temperature (OF) 383 - - - -
Humidity (Z) 100 - - - -
Hydrogen Concentration (Z vol) 2.5 - - - -
Recirculation Sump Level (in) 100 - - - -
TANKS Accumulator Levels (I) -
0 0 0 0 Accumulator Pressures (psig) - 26 26 26 26 Refueling Water Storage Tank Level (!) 85 - - - -
1 l
93-FE 5. 16 i l
PLANT PARAMETERS Time 1130 Plant Loop l' Loop 2 Loop 3 Loop 4 Relative Time (H+03:30) Values or A or B or C or D Values Values Values Values PRIMARY SYSTEM Reactor Power (2) 0 - - - -
Reactor Vessel Level (I) - Natural 43 - - - -
Circulation Reactor Coolant System (RCS) Pressure 44 - - - -
(psig)
Pressurizer Level (I) 0 - - - -
Reactor Coolant System Temp. (DF)
T C
(wide-range) -
250 255 255 249 T (wi e-range) - 8 278 278 278 H
TAVG (narrow-range) -
530 530 530 530 Core Exit Thermocouple Temp. (OF) 2500 - - - -
Reactor Coolant Loop Flows (Z) -
0 0 0 0 Baron Concentration (ppm) 1974 - - - -
SECONDARY SYSTEMS 6
Main Steam Flow Rate (zl0 lbm/hr) - 69 41 36 69 Steam Generator (WR) Levels (I) - 74 71 71 77 Steam Generator Pressures (psig) - 25 26 26 25 CONTAINMENT BUILDING Pressure (psig) 25 - - - -
Temperature (OF) 383 - - - -
Humidity (I) 100 - - - -
Hydrogen Concentration (Z vol) 3.75 - - - -
Recirculation Sump Level (in) 100 - - - -
TANKS
_ Accumulator Levels (I) -
0 0 0 0 Accumulator Pressures (psig) - 26 26 26 26 Refueling Water Storage Tank Level (I) 85 - - - -
93-FE 5. 17 l
4 PLANT PARAMETERS Time 1145 Plant Loop 1 Loop 2 Loop 3 Loop 4 Relative Time , (H+03:45) Values or A or B or C or . D Values Values Values Values PRIMARY SYSTEM Reactor Power (I) 0 - - - -
Reactor Vessel Level (I) - Natural 43 - - - -
Circulation Reactor Coolant System (RCS) Pressure 44 - - - -
(psig)
Pressurizer Level (I) 0 - - - -
Reactor Coolant System Temp. (OF)
T C
(vide-range) -
250 255 255 249 T
H (w de-range) - 278 278 278 278 TAVG (narr w-range) - 530 530 530 530 Core Exit Thermocouple Temp. (OF) 2700 - - - -
~
Reactor Coolant Loop Flows (I) 0 0 0 0 Boron Concentration (ppm) 1964 - - - -
SECONDARY SYSTEMS Main Steam Flow Rate (x10 lbm/hr) - 69 41 36 69 Steam Generator (WR) Levels (I) - 74 71 71 77 Steam Generator Pressures (psig) -
25 26 26 25 CONTAINMENT BUILDING Pressure (psig) 25 - - - - J Temperature (OF) 383 - - - -
Humidity (I) 100 - - - -
Hydrogen Concentration (I vol) 4.8 - - - -
l l
Recirculation Sump Level (in) 100 - - - .
)
I TANKS i
Accumulator Levels (I) -
0 0 0 0 I l
Accumulator Pressures (psig) - 26 26 26 26 I l
Refueling Water Storage Tank Level (I) 85 - - - - j i
93-FE 5. 18 l 1
4
- I
PLANT PARAMETERS Time 1200 Plant Loop l' Loop 2 Loop 3' . Loop 4 Relative Time (H+04:00) Values or A or B or C or D Values Values Values Values PRIMARY SYSTEM Reactor Power (Z) 0 - - - -
Reactor Vessel Level (I) - Natural 45 - - - -
Circulation Reactor Coolant System (RCS) Pressure 36 - - - -
(psig)
Pressurizer Level (Z) 0 - - - -
Reactor Coolant System Temp. (OF)
T (w de-range) - 234 242 242 232 C
T (wi e-range) - 66 266 266 266 H
TAVG (narr w-range) -
0 Core Exit Thermocouple Temp. (OF) 2900 - - - -
Reactor Coolant Loop Flows (I) - 0 0 0 0-Boron Concentration (ppm) 1982 - - - -
SECONDARY SYSTEMS Main Steam Flow Rate (x10 lbm/hr's - 59 28 23 59 Steam Generator (WR) Levels (I) - 74 70 70 77 Steam Generator Pressures (psig) - 20 25 25 20 CONTAINMENT BUILDING Pressure (psig) Real time 1200 47 - - - -
Real time 1201 8 Temperature (DF) 383 - - - -
Humidity (Z) 100 - - - -
Hydrogen Concentration (I vol) 6.5 - - - -
Recirculation Sump Level (in) 110 - - - -
TANKS Accumulator Levels (Z) - 0 0 0 0 Accumulator Pressures (psig) - 26 26 26 26 Refueling Water Storage Tank Level (I) 85 - - - -
93-FE 5. 19
PLANT PARAMETERS Time 1215 Plant Loop l' Loop 2 Loop 3 Loop 4 Relative Time (H+04:15) Values or A or B or C or D Values Values Values Values PRIMARY SYSTEM Reactor Power (I) 0 - - - -
Reactor Vessel Level (I) - Natural 47 - - - -
Circulation Reactor Coolant System (RCS) Pressure 30 - - - -
(Psig)
Pressurizer Level (I) 0 - - - -
Reactor Coolant System Temp. (OF)
T C
(wide-range) -
230 230 230 232 T
B (wide-range) -
260 260 260 266 T yg (narrow-range) -
530 530 530 530 Core Exit Thermocouple Temp. (OF) 2900 - - - -
Reactor Coolant Loop Flows (I) -
0 0 0 0 Boron Concentration (ppm) 1982 - - - -
SECONDARY SYSTEMS Main Steam Flow Rate (x10 lbm/hr) -
55 30 20 60 Steam Generator (WR) Levels (I) -
70 70 70 70 i
Steam Generator Pressures (psig) -
20 20 20- 20 CONTAINMENT BUILDING Pressure (psig) 7 - - - -
Temperature (OF) 350 - - - -
I Humidity (I) 100 - - - .
]
l Hydrogen Concentration (2 vol) .5 - - -
l
. 1 Recirculation Sump Level (in) 112 - - - -
TANRS I
Accumulator Levels (I) - 0 0 0 0 Accumulator Pressures (psig) -
26 26 26 26 Refueling Water Storage Tank Level (I) 85 - - - - I l
93-FE 5. 20 O
PLANT PARAMETERS Time 1230 Plant Loop l' Loop 2 Loop 3 Loop 4 Relative Time (H+04:30) Values or A or B or C or D Values Values Values Values PRIMARY SYSTEK Reactor Power (Z) 0 - - t - -
Reactor Vessel Level (Z) - Natural
~
49 - - - -
Circulation Reactor Coolant System (RCS) Pressure 30 - - - -
(psig)
Pressurizer Level (I) 0 - - - -
Reactor Coolant System Temp. (OF)
T C
(v e-range) -
0 230 232 T
H (wide-range) - 200 260 260 266 Tgyg (narrow-range) - 530 530 530 530 Core Exit Thermocouple Temp. (OF) 2700 - - - -
Reactor Coolant Loop Flows (I) - 0 0 0 0 Boron Concentration (ppm) 1982 - - - -
1 SECONDARY SYSTEMS Main Steam Flow Rate (x10 lbm/hr) -
55 30 20 60 Steam Generator (WR) Levels (I) - 70 70 70 70 Steam Generator Pressures (psig) - 20 20 20 20 CONTAINMENT BUILDING I I
Pressure (psig) 7 - - - -
Temperature (OF) 310 - - - -
Hamidity (2) 100 - - - -
-l Hydrogen Concentration (2 vol) .5 - - - -
Recirculation Sump Level (in) 112 - - - -
TANKS Accumulator Levels (I) , - 0 0 0 0 Accumulator Pressures (psig) - 26 26 26 26 Refueling Water Storage Tank Level (I) 85 - - - -
93-FE 5. 21
PLANT PARAMETERS Time 1245 Plant Loop 1- Loop 2 Loop 3 Loop 4 Relative Time (H+04:45) Values or A or B or C or D Values Values Values Values PRIMARY SYSTEM Reactor Power (I) 0 - - - -
Reactor Vessel Level (2) - Natural 51 - - - -
Circulation Reactor Coolant System (RCS) Pressure 30 - - - -
(psig)
Pressurizer Level (Z) 6 - - - -
Reactor Coolant System Temp. (OF)
T C
(w e-range) -
0 230 230 232 T
H (wide-range) - 260 260 260 266 TAVG (narr w-range) - 530 530 530 530 Core Exit Thermocouple Temp. (OF) 2300 - - - .
Reactor Coolant Loop Flows (2) - 0 0 0 0 Boron Concentration (ppm) 1982 - - - -
SECONDARY SYSTEMS Main Steam Flow Rate (x10 lbm/hr) -
55 30 20 60 Steam Generator (WR) Levels (Z) -
70 70 70 70 Steam Generator Pressures (psig) -
20 20 20 20 CONTAINMENT BUILDING Pressure (psig) 5 - - - -
Temperature (OF) 270 - - - -
Humidity (I) 100 - - - -
Hydrogen Concentration (I vol) .5 - - - -
Recirculation Sump Level (in) 112 - - . -
TANKS Accumulator Levels (Z) - 0 0 0 0
Accumulator Pressures (psig) -
26 26 26 26 k
Refueling Water Storage Tank Level (I) 85 - - - -
93-FE 5. 22
i I
PLANT PARAMETERS j
~
l Time 1300 Plant Loop l' Loop 2 Loop 3 Loop 4-Relative Time (H+05:00) Values ~
or A or B or C or D Values Values Values Values PRIMARY SYSTEM i l
Reactor Power (I) 0 - - - -
Reactor Vessel Level (I) - Natural 53 - - - -
Circulation Reactor Coolant System (RCS) Pressure 30 - - - -
(Psig)
Pressurizer Level (Z) 20 - - - -
Reactor Coolant System Temp. (OF)
T C
(wide-range) - 230 230 230 232 T
H (wide-range) - 260 260 260 266 T yg (narrow-range) - 530 530 530 530 Core Exit Thermocouple Temp. (OF) 2000 - - - -
Reactor Coolant Loop Flows (I) - 0 0 0 0 Boron Concentration (ppm) 1982 - - - -
SECONDARY SYSTEMS Main Steam Flow Rate (x10 lbm/hr) -
55 30 20 60 Steam Generator (WR) Levels (I) -
70 70 70 70 Steam Generator Pressures (psig) - 20 20 20 20 CONTAINMENT BUILDING Pressure (psig) 5 - - - -
Temperature (OF) 230 - - - -
Humidity (Z) 100 - - - -
Hydrogen Concentration (I vol) .5 - - - -
Recirculation Sump Level (in) 114 - - - -
TANKS Accumulator Levels (2) -
0 0 0 0 Accumulator Pressures (psig) -
26 26 26 26 1
Refueling Water Storage Tank Level (I) 85 - - - -
93-FE 5. 23 l
l
PLANT PARAMETERS Time 1315 Plant Loop 1- Loop 2 Loop 3 Loop 4 Relative Time (H+05:15) Values or A or B. or C or D Values values Values values PRIMARY SYSTEM Reactor Power (Z) 0 - - - -
Reactor Vessel Level (Z) - Natural 55 - - - -
Circulation Reactor Coolant System (RCS) Pressure 30 - - - -
(psig)
Pressurizer Level (Z) 35 - - - -
Reactor Coolant System Temp. (')F )
T (wide-range) - 230 230 230 232 C
T H
(wide-range) - 260 260 260 266 Tgyg (narrow-range) - 530 530 530 530 Core Exit Thermocouple Temp. (OF) 1600 - - - -
Reactor Coolant Loop Flows (Z) - 0 0 0 0 Boron Concentration (ppm) 1982 -
SECONDARY SYSTEMS l l
Main Steam Flow Rate (x10 lbm/hr) -
55 30 20 60 Steam Generator (WR) Levels (Z) - 70 70 70 70 ,
l Steam Generator Pressures (psig) - 20 20 20 20 l l
CONTAINMENT BUILDING Pressure (psig) 4 - - - -
Temperature (DF) 190 - - - -
Humidity (Z) 100 - - - .
-l Hydrogen Concentration (I vol) .5 - - - -
I Recirculation Sump Level (in) 116 - - - -
TANKS l
Accumulator Levels (Z) - 0 0 0 0 Accumulator Pressures (psig) - 26 26 26 26 Refueling Water Storage Tank Level (Z) 85 - - - - l 93-FE 5. 24 l
l
4 PLANT PARAMETERS Time 1330 Plant Loop 1 Loop 2 Loop 3 Loop 4 Relative Time (H+05:30) Values or A or B or C or D Values Values Values Values PRIMARY SYSTEM Reactor Power (I) 0 - - - -
Reactor Vessel Level (I) - Natu:a1 85 - - - -
Circulation Reactor Coolant System (RCS) Pressure 30 - - - -
(psig)
Pressurizer Level (I) 45 - - - -
Reactor Coolant System Temp. (OF)
T C
(wi e-range) -
0- 230 230 232 Tg (wide-range) -
260 260 260 266 TAVG (narr w-range) - 530 $30 530 530 Core Exit Thermocouple Temp. (OF) 1400 - - - -
Reactor Coolant Loop Flows (Z) -
0 0 0 0-Boron Concentration (ppm) 1982 - - - -
SECONDARY SYSTEMS 6
Main Steam Flow Rate (x10 lbm/hr) -
55 30 20 60 Steam Generator (WR) Levels (I) -
70 70 70 70 Steam Generator Pressures (psig) - 20 20 20 20 CONTAINMENT BUILDING Pressure (psig) 2 - - - -
Temperature (OF) 150 - - - -
Humidity (I) 100 - - - -
Hydrogen Concentration (I vol) .5 - - - - !
Recirculation Sump Level (in) 116 - - - -
TANKS Accumulator Levels (I) -
0 0 0 0 Accumulator Pressures (psig) - 26 26 26 26 1
Refueling Water Storage Tank Level (I) 85 - - - -
93-FE 5. 25 )
I l
PLANT PARAMETERS Time 1345 Plant Loop 1- Loop 2 Loop 3 Leap 4 Relative Time (H+05:45) Values or A or B or C or D Values Values Values Values PRIMARY SYSTEM Reactor Power (I) 0 - - - -
Reactor Vessel Level (I) - Natural 100 - - - -
Circulation Reactor Coolant System (RCS) Pressure 30 - - - -
(psig)
Pressurizer Level (I) 100 - - - -
Reactor Coolant System Temp. (OF)
T C
(wide-range) - 230 230 230 232 T
H (vide-range) - 260 260 260 266 T yg (narrow-range) -
530 530 530 530 Core Exit Thermocouple Temp. (OF) 1000 - - - -
Reactor Coolant Loop Flows (I) - -
0 0 0 0 Boron Concentration (ppm) 1982 - - - -
SECONDARY SYSTEMS 6
Main Steam Flow Rate (x10 lbm/hr) -
55 30 20 60 Steam Generator (WR) Levels (I) -
70 70 70 70 Steam Generator Pressures (psig) - 20 20 20 20 CONTAINHENT BUILDING Pressure (psig) 0 - - - -
Temperature (OF) 110 - - - -
Humidity (I) 100 - - - -
Hydrogen Concentration (I vol) .5 - - - -
Recirculation Sump Level (in) 116 - - - -
TANKS Accumulator Levels (I) - 0 0 0 0 i
Accumulator Pressures (psig) -
26 26 26 26 Refueling Water Storage Tank Level (I) 25 - - . -
93-FE 5. 26 s .
PLANT PAltAMETERS Time 1400 Plant Loop 1- Loop,2 Loop 3 Loop 4 Relative Time (H+06:00) Values or A or B or C or D
- Values values values Values PRIMARY SYSTEH Reactor Power (I) 0 - - - -
Reactor Vessel Level (Z) - Natural 100 - - - -
Circulation Reactor Coolant System (RCS) Pressure 30 - - - -
(psig)
Pressurizer Level (Z) 100 - - - -
Reactor Coolant System Temp. (DF)
C (wide-range) - 230 230 230 232 T
H (v e-range -
66 Tgyg (narrow-range) -
530 530 530 530 Core Exit Thermocouple Temp. (OF) 900 - - - -
Reactor Coolant Loop Flows (I) -
10 10 10 10 Boron Concentration (ppm) 1982 . - - -
SECONDARY SYSTEMS Flain Steam Flow Rate (x10 lbm/hr) - 55 30 20 60 Steam Generator (WR) Levels (!) - 70 70 70 70 Steam Generator Pressures (psig) -
20 20 20 20 CONTAINMENT BUILDING Pressure (psig) 0 - - - -
Temperature (OF) 100 - - - -
Humidity (I) 100 - - - -
Hydrogen Concentration (2 vol) .5 - - . -
Recirculation Sump Level (in) 116 - - - -
TANKS Accumulator Levels (Z) -
0 0 0 0 Accumulator Pressures (psig) -
26 26 26 26 Refueling Water Storage Tank Level (I) 25 - - - -
93-FE 5, 27
PLANT PARAMETERS
. Time 1415 Plant Loop 1- Loop 2 Loop 3 Loop 4 Relative Time (H+06:15) Values or A or B or C or D Values Values Values Values PRIMARY SYSTEM Reactor Power (Z) 0 - - - -
Reactor Vessel Level (Z) - Natural 100 - - - -
Circulation Reactor Coolant System (RCS) Pressure 30 - - - -
(psig)
Pressurizer Level (Z) 100 - - - -
Reactor Coolant System Temp. (OF)
T (vide-range) - 230 230 230 232 C
T (wi e-range -
60 266 H
Tgyg (narrow-range) -
530 530 530 530 Core Exit Thermocouple Temp. (OF) 900 - - - -
Reactor Coolant Loop Flows (Z) - 10 10 10 10 Boron Concent' ration (ppm) 1982 - - - -
SECONDARY SYSTEMS Main Steam Flow Rate (x10 lbm/hr) -
55 30 20 60 Steam Generator (WR) Levels (Z) - 70 70 70 70 Steam Generator Pressures (psig) -
20 20 20 20 CONTAINMENT BUILDING Pressure (psig) 0 - - - -
Temperature (OF) 100 -
Humidity (Z) 100 - - - -
Hydrogen Concentration (Z vol) .5 - - - -
Recirculation Sump Level (in) 116 - - - -
TANKS Accumulator Levels (Z) -
0 0 0 0 1 Accumulator Pressures (psig) -
26 26 26 26 !
Refueling Water Storage Tank Level (Z) 25 - - - -
93-FE 5. 28 b
e
PLANT PARAMETERS Time 1430 Plant Loop l' Loop 2 Loop 3 Loop 4 Relative Time (H+06:30) Values or A .or B or C or D Values Values Values Values PRIMARY SYSTEM Reactor Power (2) 0 -
-l - -
Reactor Vessel Level (Z) - Natural 100 - - - -
Circulation Reactor Coolant System (RCS) Pressure 30 - - - -
(psig)
Pressurizer Level (2) 100 - - - -
Reactor Coolant System Temp. (OF)
T C
(wide-range) -
230 230 230 232 T
g (vide-range) - 260 260 260 266 TAVG (narr w-range) -
530 530 530 530 Core Exit Thermocouple Temp. (OP) 900 - - - -
Reactor Coolant Loop Flows (2) - 10 10 10 10 Boron Concentration (ppm) 1982 - - - -
SECONDARY SYSTEMS 6
Main Steam Flow Rate (x10 lbm/hr) -
55 30 20 60 Steam Generator (WR) Levels (Z) -
70 70 70 70 l Steam Generator Pressures (psig) - 20 20 20 20 CONTAINMENT BUILDING Pressure (psig) 0 - - - -
Temperature (OF) 100 - - - -
1 Humidity (2) 100 - - - -
Hydrogen Concentration (Z vol) .5 - - - -
Recirculation Sump Level (in) 116 - - - -
TANKS Accumulator Levels (I) .
- 0 0 0 0 Accumulator Pressures (psig) -
26 26 26 26 Refueling Water Storage Tank Level (I) 25 - - - -
93-FE 5. 29
PLANT PARAMETERS Time 1445 Plant Loop l' Loop 2 Loop 3 Loop 4 Relative Time (H+06:45) Values or A or B or C or' D Values Values Values Values PRIMARY SYSTEM t
l Reactor Power (Z) 0 - - - -
Reactor Vessel Level (Z) - Natural 100 - - - -
Circulation Reactor Coolant System (RCS) Pressure 30 - - - -
(psig)
Pressurizer Level (Z) 100 - - - -
Reactor Coolant System Temp. (OF)
T C
(" *~#""E ~
T wi e-range) - 0 266 H
Tgyg (narrow-range) -
530 530 530 530 Core Exit Thermocouple Temp. (OF) 900 - - - -
Reactor Coolant Loop Flows (I) - 10 10 10 10 Boron Concentration (ppm) 1982 - - - -
SECONDARY SYSTEMS Main Steam Flow Rate (x10 lbm/hr) - 55 30 20 60 Steam Generator (WR) Levels (I) - 70 70 70 70 Steam Generator Pressures (psig) - 20 20 20 20 CONTAINMENT BUILDING Pressure (psig) 0 - - - -
Temperature (DF) 100 - - - -
Humidity (2) 100 - - - -
Hydrogen Concentration (2 vol) .5 - - - -
Recirculation Sump Level (in) 116 - - - -
TANKS Accumulator Levels (%) - 0 0 0 0 Accumulator Pressures (psig) - 26 26 26 26 Refueling Water Storage Tank Level (I) 25 - - - -
~
93-FE 5. 30 i
l a l
RJutT PARAMETERS Time 1500 Plant Loop l' Loop 2 Loop 3 Loop 4 Relative Time (H+07:00) Values or A or B or C or D Values Values Values Values PRIMARY SYSTEK Reactor Power (2) 0 - - - -
Reactor Vessel Level (2) - Natural 100 - - - -
Circulation Reactor Coolant System (RCS) Pressure 30 - - - -
(psig)
Pressurizer Level (Z) 100 - - - -
Reactor Coolant System Temp. (OF)
T (wide-range) - 230 230 230 232 C
T H
" ~#'"E*' ~
TAVG (narr w-range) - 530 530 530 530 Core Exit Thermocouple Temp. (OF) 900 - - - -
Reactor Coolant Loop Flows (Z) -
10 10 10 10 Baron Concentration (ppm) 1982 - - - -
SECONDARY SYSTEMS Hain Steam Flow Rate (x10 lbm/hr) - 55 30 20 60 Steam Generator (WR) Levels (Z) - 70 70 70 70 Steam Generator Pressures (psig) - 20 20 20 20 CONTAINMENT BUILDING Pressure (psig) 0 - - - -
Temperature (OF) 100 - - - -
Humidity (Z) 100 - - - -
Hydrogen Concentration (2 vol) .5 - - - -
Recirculation Sump Level (in) 116 - - - -
TANKS Accumulator Levels (Z) - 0 0 0 0 Accumulator Pressures (psig) -
26 26 26 26 Refueling Water Storage Tank Level (I) 25 - - - -
93-FE 5. 31
PLANT PARAMETERS Time 1515 Plant Loop l' Loop 2 Loop 3 Loop 4 Relative Time (H+07:15) Values or A or B or C or D Values values Values Values PRIMARY SYSTEM Reactor Power (Z) 0 - - - -
Reactor Vessel Level (I) - Natural 100 - - - -
Circulation Reactor Coolant System (RCS) Pressure 30 - - - -
(psig)
Pressurizer Level (2) 100 - - - -
Reactor Coolant System Temp. (OF)
T (vide-range) - 230 230 230 232 C
T H
(w de-range) -
260 260 260 266 T yg (narrow-range) -
530 530 530 530 Core Exit Thermocouple Temp. (OF) 900 - - - -
Reactor Coolant Loop Flows (Z) -
10 10 10 10 Beron Concentration (ppm) 1982 - - - -
SJCONDARY SYSTEMS Main Steam Flow Rate (x10 lbm/hr) - 55 30 20 60 Steam Generator (WR) Levels (Z) - 70 70 70 70 Steam Generator Pressures (psig) -
20 20 20 20 CONTAINMENT BUILDING Pressure (psig) 0 - - - -
Temperature (OF) 100 - - - -
Humidity (%) 100 - - - -
Hydrogen Concentration (I vol) .5 - - - -
Recirculation Sump Level (in) 116 - - - -
TANRS Accumulator Levels (I)- -
0 0 0 0 Accumulator Pressures (psig) -
26 26 26 26 Refueling Water Storage Tank Level (I) 25 - - - -
93-FE 5. 32 1
PLANT PARAMETERS Time 1530 Plant Loop 1- Loop 2 Loop 3 Loop 4 Relative Time (H+07:30) Values or A or B or C or D Values Values Values values PRIMARY SYSTEM i Reactor Power (I) 0 - - - - I Reactor Vessel Level (I) - Natural 100 - - - - l Circulation i Reactor Coolant System (RCS) Pressure 30 - - - -
(psig)
Pressurizer Level (I) 100 - - - -
Reactor Coolant System Temp. (OF)
T C
(wide-range) -
230 230 230 232 T
H (wide-range) -
260 260 260 266 TAVG (narr w-range) - 530 530 530 530 Core Exit Thermocouple Temp. (OF) 600 - - - -
Reactor Coolant Loop Flows (2) -
10 10 10 10 Boron Concentration (ppm) 1982 - - - -
SECONDARY SYSTEMS Main Steam Flow Rate (x10 lbm/hr) - 55 30 20 60 Steam Generator (WR) Levels (Z) - 70 70 70 70 Steam Generator Pressures (psig) - 20 20 20 20 CONTAINMENT BUILDING Pressure (psig) 0 . . . -
Temperature (OF) 100 - - - -
Humidity (2) 100 - - - -
Hydrogen Concentration (2 vol) .5 - - - -
Recirculation Sump Level (in) 116 - - - -
TANKS Accumulator Levels (2) - 0 0 0 0 Accumulator Pressures (psig) - 26 26 26 26 Refueling Water Storage Tank Level (I) 25 - - - -
93-FE 5. 33-
PT. ANT PARAMETERS Time 1545 Plant Loop 1 Loop 2 Loop 3 . Loop 4 Relative Time (H+07:45) Values or A or B or. C or D Values values Values Values PRIMARY SYSTEM Reactor Power (Z) 0 - - - -
Reactor Vessel Level (Z) - Natural 100 - - - -
Circulation Reactor Coolant System (RCS) Pressure 30 - - - -
(psig)
Pressurizer Level (I) 100 - - - -
Reactor Coolant System Temp. (DF)
T C
(wide-range) - 230 230 230 232 T (wi e-range) - 0 260 260 266 H
T3yg (narrow-range) - 530 530 530 530 Core Exit Thermocouple Temp. ( F) 600 - - - -
Reactor Coolant Loop Flows (I) - 10 10 10 10 Boron Concentration (ppm) 1982 - - - -
SECONDARY SYSTEMS 6
Main Steam Flow Rate (x10 lbm/hr) - 55 30 20 60 Steam Generator (WR) Levels (Z) - 70 70 70 70 l
Steam Generator Pressures (psig) - 20 20 20 20 CONTAINMENT BUILDING l'
Pressure (psig) 0 - - - -
Temperature (OF) 100 - - - -
Humidity (I) 100 - - - -
Hydrogen Concentration (I vol) .5 - - - -
Recirculation Sump Level (in) 116 - - - -
TANKS .
Accumulator Levels (I) -
0 0 0 0 l
Accumulator Pressures (psig) - 26 26 26 26 Refueling Water Storage Tank Level (I) 25 - - - -
93-FE 5. 34 e
E ANT _ PARAMETERS _
Time 1600 Plant Loop 1- Loop 2 Loop 3 Loop 4 Relative Time (H+08:00) Values or A or B or C or D Values Values Values Values PRIMARY SYSTEM Reactor Power (I) 0 - - - -
Reactor Vessel Level (I) - Natural 100 - - - -
Circulation Resctor Coolant System (RCS) Pressure 30 - - - -
(psig)
Pressurizer Level (I) 100 - - - -
Reactor Coolant System Temp. (OF)
T (wide-range) - 230 230 230 232 C
T H
(w e-range - 60 260 260 266 TAVG (narr w-range) - 50 530 530 Core Exit Thermocouple Temp. (OF) 600 - - - -
Reactor Coolant Loop Flows (%) - 10 10 10 10 Boron Concentration (ppm) 1982 - - - -
SECONDARY SYSTEMS 6
Main Steam Flow Rate (x10 lbm/hr) - 55 30 20 60 Steam Generator (VR) Levels (Z) - 70 70 70 70 Steam Generator Pressures (psig) -
20 20 20 20 CONTAINMENT BUILDING Pressure (psig) 0 - - - -
Temperature (OF) 100 - - . -
Humidity (I) 100 - - - -
Hydrogen Concentration (I vol) .5 - - - -
Recirculation Sump Level (in) 116 - - - -
l TANKS Accumulator Levels (Z) - 0 0 0 0 Accumulator Pressures (psig) - 26 26 26 26 l Refueling Water Storage Tank Level (I) 25 - - - -
93-FE 5. 35 l
- I
PLANT CRAPHS l
Time-related plant parameters are provided in the following subsection. The data is depicted in graphic form versus time. The previous subsection, ,
' Plant Parameters", depicts the same data in tabular form. l These graphs may be used as a source of data for Control Room (CR) operators, by the CR Lead Controller, in case of simulator failure, i
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. STEAM GENERATOR LEVELS 4 78.0 a . . . . ..,
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?
. CONTAINMENT BUILDING PRESSURE 4 50.0 m
O 45.0 -
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35.0 -
9 30.0 -
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TIME
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e CONTAINMENT HYDROGEN CONCENTRATION 7.0 x.
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OH 1
n5 a a$g 3h yE
1 l
i CONTAINMENT BUILDING BREACE M,0W RATES l
Time-related containment building (etmt b1dg) breach flow rates are provided '
in the following subsection. The data is depicted in graphic form versus time in units of cubic feet per minute (cfm).
Flow rates graphed are calculated at 14.7 psia and 100 F and not at the conditions of inside the ctmt bldg.
93-FE 5. 59
O O
1 0
7+ H y
O yO E y 7:
T 0 A y+
R y H
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+
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+
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OH 0 0 0 0 0 0 0 0 0 0 0 2 0 8 6 4 2 0 8 6 4 2 2 2 1 '1 1 1 1 n2 h 3Oa(L
- 4M .
v 8
PLANT UNIT VENT FLOW RATE Time-related plant unit vent flow rates are provided in the following subsection. The data is depicted in graphic forms versus time in units of cubic feet per minute (cfm).
Flow rates graphed are calculated from the conditions existing at the unit vent, 14.7 psia and 100 F.
l
. 1 93-FE 5. 61
1 O
o 9
m m
o
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93-FE 5. 62 2
CORE DAMAGE ASSESSMENT A precalculated core ihventory necessary in assessing core damage is included in the following subsection.
The core inventory is a summation of curies present in the total mass of fuel pellets at the time of damage to the core. The inventory can be considered to be a corrected fuel pellet inventory for accident assessment purposes. Various assumptions utilized are listed on the following pages.
93-FE 5. 63
CORE DAMAGE ASSESSMENT CORE INVENTORY Corrected Fuel Pellet Nucl1de Inventory (C1)
KR-83M 1.48E+07 KR-85M 4.62E+07 ;
KR 1.46E+06 KR-87 8.32E+07 KR-88 1.14E+08 XE-133M 4.93E+06 XE-133 2.00E+08 i XE-135M 5.55E+07' XE-135 1.91E+08 XE'-138 1.70E+08 I-131 8.94E+07 I-132 1.36E+08 I-133 2.00E+08 I-134 2.34E+08 I-135 1.82E+08 RB-88 1.07E+08 CE-144 6.80E+07 s TE-132 2.30E+08 CS-134 3.70E+07 CS-137 1.80E+07 CS-138 7.01E+07 LA-140 2.93E+08 LA-142 3.00E+07 BA-140 2.70E+08 1
1 l
I 93-FE 5. 64
CORE DAMAGE ASSESSMENT Assumptions:
- 1. Clad gap activities can be assumed to be 10.0% of fuel pellet activity for all isotopes except KR-85 which is 30%
of core activity.
- 2. Radioactive decay, time after shutdown, is a factor for accident assessment.
- 3. Reactor coolant system volume is static at 10600 cu ft, 3.00E+08 cc.
Results: Core damage should be assessed to be failure of 2002-252 fuel cladding and overtemperature conditions in approximately 20%
of the core. A zircolay-water reaction occurred adequate enough to produce greater than 4.0% hydrogen in the containment building.
i
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SECTION 7.0 ONSITE RADIOLOGICAL PARAMETFRS subsections Page PROCESS RADIOCHEMISTRT 7.1 PROCESS MONITORS AIRBORNE 7.14 LIQUID 7.32 AREA RADIATION MONITORS 7.34 INPLANT SURVEYS RADIATION 7.37 ONSITE PLOME MONITORING -
7.47 i
l l
I 93-TE 7, o l
. l
PROCESS RADIOCHDGSTRY '.
Time-related process radiochemistry is provided in the following subsection. Concentration data is provided by isotope in units of uCi/cc for the reactor coolant system (RCS)-including the containment building (ctmt bldg) emergency sump, the ctmt atmosphere, and the plant unit vent.
Isotopic concentrations are determined using the radiation monitoring system as a reference. All samples are determined at 14.7 psia and 100 F.
Concentrations will change considerably if referenced from another pressure or temperature.
Time frames at the top of the page are based on the time at which the sample is collected, not when it was analyzed.
A time delay of 30 minutes should be allowed from the time a post-accident sampling system (PASS) sample is collected to when the sample is analyzed and results are obtained.
l l
1 l
l 93-FE 7. 1 i
e 7 19M Field Exercise Data N CONTAIM4ENT ATM.
Tite H+0$0TO 1 H+0:45 H+1m H+1:15 H+1:30 H+1:45 H42.00 H+ 2:15 H+0 30 NUCLR (vCVcc)
! Kr-SSe 6 8?E47 308E G 4 4T2 55 TEM 5eEM $ 214 61143 191+01 Kr41 12E2 S QE G 66tE4 TEM 69EM 58E G 621 43 1 TE +01 Kr48 1TE M T49E 2 10E44 128E 44 12'E 44 1 tE 44 13E42 4 0E*01 Xe 133 30TM 14N44 211 44 2 TT44 29E 44 2 8T44 3 E 42 11E'*02 Ko 133ne 191 2 3 71E46 55N4 11E M T EE G TE4 9 01E 44 291 0)
K+135 28NG 132E44 19E44 2 G44 251 44 24T44 292E42 92E*01 Xe-1 A 83I 47 19E M 151E4 987E46 S TEM 2614 162E44 261 41 Xe-130 2 5EG S TIE 4 TEE 25EEG 132EM 61E46 36[ 44 561E41 TOTAL NCetE GAS 131 5 51E44 681 44 81T44 831 43 185E44 90E42 2 8E*02 1-131 3 0E-12 31E-12 3 6E 12 3TE 12 3 80E-12 11E-11 3 9T 10 200E 4 1-132 4 5T-12 4TE-12 5 5 & 12 5 2-E 12 4 2E-12 139E 18 4 E 10 180E 46 6133 6 TE-12 6 9E-12 8 08E-12 8 2E-12 8 41E-12 25E 11 85E 10 42NE 0134 7 8E-12 811-12 9 4E-12 T WE-12 6 TT 12 16T-11 4 62E-10 131En 8-135 611E-12 631-12 13E-12 F IE-12 T 3E 12 21T 11 11E-10 3 41E46
, !OTAll0DWE 281-11 291-11 341-11 3 2SE-11 313E-11 881 11 286E M 12E4 DOSE EGAVLENTIODINE S E-12 581-12 6TE 12 6 8N-12 6 98E 12 20E-11 T OE 10 351 2 Cs-1M T 4E-12 8 E 12 851E 12 1 8 I 11 2 TTE-11 301 11 9 2E-10 4 TEG Co-131 55E 12 6 47E 12 63E 12 137E-11 20E 11 231-11 691-10 351 46 Co-13e 5 3E-10 625E 10 4 4E-10 6 92E 10 161-10 81T-10 184Ea 361 2 La 1e 461-14 4 GE 14 46E 14 414E-14 5 00E 14 551 14 4 5E-11 2 TIE Ba-te 11E-14 10T.14 18T-14 T E-14 15 E 14 9 E 14 10E-11 42E E Total Pa:1kwales 5 5 I 10 641 10 4 6 I-10 12E-10 811E-10 86E 10 20Ta 515EE GROSS TOTAL ACTMTV 13T5 51E44 681 44 815E44 831 43 18T 44 90E42 28E+02
?
N
O 1993 Field Exercise Data h
CONTAIPNENT ATM.
TitaE H+ 2:30 H+2:45 H+ 3.00 H+3;t5 H+3:30 H+3:45 H+4 00 H+415 NUCUDE (ucticci Kr45ms 181 02 182E*02 191E+02 16T+02 14E+02 15E*02 124E*02 14E*02 Mr47 19E*02 13%+02 12E+02 10E+02 8 2T+01 190E+01 564 01 594 01 Mr48 3 91E*02 3 6E*02 3 77E.02 3 2E*02 21 0 02 2 8E+02 22L02 25LO2 Xe133 112E+03 112E*03 12X+(D 111 03 101 03 111*(D 92T+02 111E+03 Xe 133ns 29 +01 297E+01 32L01 2 94 +01 2TT+01 2 97E+01 2 42E*01 2 9E*01
- Xe.135 92E*02 91T*02 9 TJE*02 817E*02 T 85E*02 8 4E+02 6 82E*02 8OE 02 X&135se 13E+00 69E41 3 8T41 1TT41 8 2SE42 461 42 1 S3E 42 118E42 Xe-13s 21T+00 132E+00 69E41 3 OE41 135E41 111E42 2 81E42 1 E42 TOTAL MOSLE GAS 2 E+G3 2TT+03 2 9I+(D 261+03 2 3E+03 252E.G3 2 0 I .03 2 4T+03 8131 20T41 3 0N+00 11T*00 T OT*00 4 90E*01 501+01 48E.01 $GE 01 1132 16E41 2 32E*00 50E+00 4 6E*00 31&+01 281 01 25E*01 2 4'E+01
~
1-133 4 24E41 6 32E*00 148E*01 14T +01 101E+02 101 02 9 FE*01 10tE*02 8134 10E41 131+00 2 55E+(D 2 0E+00 11E+01 9 91E*00 180E+00 6 6E+00 1-135 33I41 4 8E*00 112E+01 10E+01 13E+01 7 3I+01 6 afE+01 694 01 TOTAllODeNE 12 LOO 178E+01 4 0E+01 3 9I+01 2 EE*02 26E+02 2 4E.02 2 52E*02 DOSE EQUlvtENTIODINE 350E41 522E 00 171+01 12T+01 8 38E*01 8 5T*01 812E+01 8 41E+01 Cs-134 465E41 4 TT41 9 TIE 00 9 SE*00 6 4T+01 6 5 I .01 6 2E 01 6 5L01 Co 137 34T 41 3ST 41 128E*00 71E*00 4BT+01 4 9T*01 411+01 4SE+01 Co 138 25M+00 19E*00 2 78E*01 19E.01 961 01 111E*01 4 9E*01 37I+01 12148 8 OT41 81T41 2 82E*01 541 01- 3 61E+02 3T1E*02 3 51E +02 371E+02 Ba-140 12E*00 128E*00 4 44E.01 8 5E+01 S T2E+02 58002 55002 591 02 Total Pareci4ases S G.00 4 8 BOO 117E+02 1 TE+02 11E+03 115E+03 107E*G3 111+03 gross T0TAL ACTMTY 2 E 03 2 TE+03 3 08E.G3 2 8E*G3 315E+03 31E+03 33003 37E+G3
+
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e
e y 1993 Field Evrcise Data y CONTAIMWENT ATE Tite H+4.30 H+4 45 H+5.00 H+ 5:15 H+5 m H+5 45 H+4 00 H+415 seuCUDE tuCWal Kr45m 15T.02 131 02 1 E.02 111 02 102E.02 109E*02 1 0 % .02 1 1E.02 K 47 S E .01 4 E .01 4 51E.01 3 2E.01 2 5T.01 2 SE.01 2 28E+01 20E.01 Kv48 25E.02 2tE.02 231 02 188E.02 16T.02 16E.02 16E 02 16tE.02 X+133 12T.(D 1 OE.03 12E.03 1 Ef+(D 951 02 1(EE*03 111 03 111.G3 X+13h 31E.01 2 8E.01 3 3E.01 27E.01 251 01 2 7E.01 2 91E.01 3(EE.01 Is-135 8 5E.02 15E+02 8 6T+02 111E.02 6 31+02 6 8E.02 T(rf.02 12E*02 X*135m 29E43 6 47E 4D 17TG T E C4 3 E 44 191E44 10tE44 5 38E OS 3e 138 851EG 36EG 207E C3 8 3tE C4 362E44 t R ot 9 7& CS 4 E 05 TOTAL MOELE GA3 2 55E 03 2 2E.G3 2 5 % .03 2 E .03 19E.03 2 0E.03 2 E .G3 221 03 513t 5 00E.01 48T.01 4 9T.01 41T.01 460E.01 410E+01 411 01 4 EE.01 3 132 2 27E.01 201 01 191E.01 171 01 15E.01 14E.01 131E.01 12E.01 3 133 1 0 I .02 9 5E.01 969E 01 921 01 894 01 911 01 911 01 9tE.01 8.t34 5 E.00 4 3E.00 3 6E.00 2 8JE.(D 2 27E.00 19T.00 l.135 157E 00 130E.00 6 TE.01 6 H .01 6 3 I .01 591 01 5 ST 01 5 62E.01 5 54E.01 5 E.01 T3TAL 800lHE 2 E .02 2 32E.02 2 M.02 21E.02 211 02 211E.02 2 09E.02 2 OE 02 DOSE EQUfVLENT IODINE 8 37E.01 8OE.01 812E.01 7 7E.01 7 5E.01 169E.0t 11E*01 7 7E 01 Co 134 65% 01 6 31E.01 6 45E+01 6 07E.01 591 01 Cs-137 4 9fE.01 6 07E.01 611 01 6 2T+01 4 TI.01 4 8E.01 4 5T.01 4 4T.01 4 5T.01 C+138 27IE.01 4ET.01 4 GT 01 1 8 I .01 1 E+01 9 51E.00 6 TE.00 t.S te 4 R.00 3 6 % 00 2 67E*0) 37E.02 3 5E.02 37tE*02 3 E .02 3 3T.02 Bat # 3 45E.02 3 50E.G2 35K 02 6OT.02 5 7E 02 5 9aE.02 5 SaE.02 5 4E.02 5 61E+02 571E.02 5 81E.02 Totd Parsudaees 111 03 10E.G3 111 03. 101 03 9 9T.02 101.Q3 101 03 105E*03 GROSS TOTAL ACTMTY 3 92E.(D 3 Yf.03 3 91.G3 3 3E.03 3 0E.03 3 2T.03 3 3E.03 3 4'f.03 7
- e e
O 93 Field Exercise Data CONTAINMENT ATM.
Tike M*8.30 14+4 4$ H+T OS 6167.15 NJCUDESm CA* H+F:30 H+T:45 H+0 00 Ks45se 9 69E*01 9 51E.01 9 4tE*01 8 6%+01 Kr-81 8 65E+01 8 55E.01 8ttE.01 166E 01 148E.01 11E.01 Kr4s 11E.01 1 OE.01 9 85E.00 13E.02 13]E 02 8 TIE.CU 12E 02 11%.02 111 02 Xe-133 105E 03 101E.G3 101 02 941 01 X *1h 11E.(D t 01 03 1 OT+03 105E.03 2 78E*01 284E 01 105E 03 2 9tE.01 2 TE.01 281 01 Xa 135 641 02 281 01 281 01 X+1h 65N+02 65I 02 6tT.02 62E.02 6 00E*02 2 49E45 6(CE*02 Xe-135 171 4 6MM 3 2E 45 172E E 85147 212 @ 51& 47 10E 2 521M 2 4TM 1 ZEM 182E41 352E 01 '
TOTAL HOBLE GAS 201 03- 2 01E.03 2 0E.03 1 9 I .03 19E.G3 188E.03 18?E.03 1131 4?E.01 4 M*01 411 01 4 TE 01 8132 4 74E*01 4FIE.01 47E+01 11E.01 10E 01 101E*01 1-133 9 2E 00 8 6T+00 191 00 8 91E+01 8 88E+01 1 P5+00 ,
8 8E*01 8 M.01 8 M *01 .
8134 105E.00 8 81E*01 791E 01 861 41 7 t1E41 5 TIE 41 8135 4 ilE 41 3EK 01 2 TT 01 5 21E.01 51&+01 5 0#E*01 4 83E*01 4 Pl+01 455E.01 451 01 TOTAL 100eE 201E+02 1 RE*02 19E.02 192E*02 191E.02 1&E 02 171+02 DOSE EQUtVtfMTICDINE F 51 0t T$9E.01 761E 01 1 SE.01 7 SI.01 - 151 01 124E.0t Cs-134 651 01 6 5E.01 6 6E*01 6 53E.01 Co.137 4 9T.01 611 01 67401 6 KE.01 491 01 4 9E.01 4 9E.01 Ce-13e 20E 00 451 01 461 01 4 ST 01 148E.00 108E+00 T T3E41 La 14e 37tE*02 571 41 341 41 20141 3 M +02 3 7E.02 37tE+02 so.14e 3 48E 02 339E*02 3 4]E.02 6GE+02 614E.T 6 21E.02 615E+02 5 7E.02 55N 02 55T 02 Total ParscWasee 111E+(D 1 tile 03 111 03 117E.G3 1 IT 03 9 89E.02 101 (D ORDE% TOTAL ACTMTY 335 03 3 38E+03 341 03 3 2 % .03 3 2E.03 30E.03 3 05E.03
." 5 h
e Y 1993 Field Exercise Data E RCSi CONT. SUMP TlaE H+8:08 TO M+8.46 H+1.80 H+1:1$ H+1:38 H+1 # H+2.98 H+ 2-15 H+8:38 NUCWE juca.4 Mr-85sn 11E42 1 *E G 5 2E44 4 af M 49E G 451 5 12E43 2 63E*00 Mr47 2 E42 18E43 T BE44 6 SE& 59E06 502E M 12E43 23E 03 Mr48 29EG 26E43 12EE G 11E44 111E2 101E E 21E G 5 5E.00 X+133 541E W 5 00E 43 - 250EG 2 E44 2 50E G 240EM 699E 43 150E.01 Xe-133m . 1NG t32E 44 6 GE & 63E4 662E41 63E& 185E44 397E41 .
Xe in 48EW 4 EE43 23E43 2IE44 25EM 2 GEM 6 OEG 12E.01 Xe 135m t42E42 7 OE44 1 TE44 8EG 4 61E& 225E& 331 2 361 42 X*138 4 34E42 20E G 4 92E 44 2 /EM 11EM S 2E 07 7 41E& T6E42 TOTAL NOBLE GAS 221E41 181E42 829E43 T 2E 44 151E05 6 JE & 18E W 3 8E.01 l-131 25E43 52E44 52E44 52E44 5 3E44 52E44 13E42 99E 01 ,
1-132 39E43 150E44 695E44 64E44 609E 44 5SE44 12EQ 8 98E.01 8.133 581E43 11EG t IE43 11E43 11E 43 11E43 27EG 2 E 02 5 134 6 78E43 1 IE43 9 K 44 765E44 6 39E44 51E44 101Q 6 52E*01
- s.12 52E43 10E43 1RG 10E43 931 44 950E C4 22EQ t 70E.02 TOTALIODedE 2 4E42 4GE G 43E G 4 IE43 39E43 3 TE43 865E42 6 3E*02 DOSE EQUIVtfMT 100NIE 4 SEG 9 8K44 9 E 44 962E44 9TE44 94E44 231E42 1 TE 02 Co.1M 2SE44 4 SE4 46E2 4 8EE 4 8E5 451 4 6 45EG 9 3I 41 Co137 1 E 44 35E 4 3 SE& 3 EEG 3 SE4 3E4 4 SE43 7 OE41 Co-13e 16E42 2 45E43 1 TEG 132E43 99E44 6SE44 6 7E42 ? CE.00 '
La te 135EM 29E47 29E47 3 UE47 30E41 28E47 3 EE& 52E41 Ba se 20EM 4 SE41 4 SE47 4 7tE41 4 IE 47 4 4E41 6 OE 4 82E41 Teeuf Parecidaens t SEG 2 SIG 1 SSE 43 1EG 1 OE 43 80E44 iBE W t00E*01 OROS$ 10TAL ACTMTY 262E41 2 5E W 145EM 621 43 50E 43 4 5E 43 184 41 6 8E.02
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e I' 1993 Fictd Exercise Data N RCS1 CONT. SUMP Tite H+2:30 H+ 3:45 H+ 341 H+3:15 H+ 3.30 H+3:45 H+4 to H+4:15 NUCUDE tuCurt) 1(r45se 81T.00 i R .00 751E.(D T08E.(D 6 6E.(D 6 SE.00 6 Off.00 Kr47 6OE.00 6 6E.00 5T1E.00 $ E .00 4 E00 3 T2E.00 Mr4e 3 31E.00 2 TE.00 251 00 164 01 I SE.01 14E.01 13E.01 126E 01 121E+01 t E .01 10E.01 Xs-133 481*01 4 ?E 01 4 !KE.01 4TE.01 4 GT 01 4 iT.01
- 4ST.01 470E.01 Xe 13ne 12E.(D 12E.(D 12?E.00 12E 00 122E.00 12E.00 11E+00 12E.00 Xe 135 3 9E.01 3 81E.01 381 01 3 6E+01 3 53E.01 3 5E.01 31E.01 3 42E.01 Xe 135sn $ 5E42 271M 151E42 151 43 3 M 43 19E4D 9 41E44 4 5EE44 XS138 11Eet 55E42 2 4 42 12E 42 60E 4D 29E43 13E43 691E44 TOTAL NOBtf OAS 121E.02 115E.G2 115E.02 11E+02 10E.02 10E.02 991 01 102E.02 8 131 5 E03 8 SE.(D 9 E03 2OT.04 20T+04 21E 04 t-132 190E.04 2IT.04 4 5EiE 03 6 9E.(D 115 03 13E.04 17E.04 12T.04 10T+04 l-133 1(DE.04 124 04 1 EE.04 20E.04 415E.04 411 04 431 04 3 8E.04 4 2E.04 8134 32tE 03 3 9E.G3 3 SGE.(0 5 89E.03 4 SE 03 41E.03 3 OE.03 211 03 5135 994.(0 14E.04 I m04 30E.04 301 04 30E+04 271E.04 2 9 I .04 i TOTAll0 DINE 3m04 5 3E.04 51E.04 111E.05 108E.05 111E.05 9 78E+04 10E.05 ,
00$E EQUlvtDIT KIDedE 101 04 156E.04 1 E 04 3 4E.04 341 04 ,, 3 510 04 3 2tE.04 351 04 Cw134 1 TI.00 187E 00 20E.00 18?E 00 t E .00 185 00 t ET.00 185 00 Cs 137 1 5 00 t 41 00 15T.(D t 4T.03 13T+00 14T.00 12E.00 t4T+00 Co 13e 9 E.00 1600 S TE.00 3 88E.00 2 61E.(D 2aE 00 12E.00 104 00 La te 31E.00 475E.00 5 38E.00 10E 01 9 3E.00 Ba te 10E 01 85E 00 10E.01 4 96E.00 7 4E.00 844 00 t 6?E.01 148E.01 16E.01 1 E01 168E.01 Teest ParecWales 2 0E.01 2 2E.01 231E 01 3 4E+01 2 0 01 321 01 261 01 31E 01 GROSS TOTAL ACTMTY 3 FT.04 5 35E.04 5 TE.04 112E.05 10E 05 111E+05 9 M .04 10E.(5 M
e Y 1993 Field Exerdse Data N RCSiCONT. SUMP TIME H+4.30 H+4.45 H+500 H+$:1$ H+5:30 H+5.45 H+400 H+ 0.15 MUCLM twCWec)
Mia$re 5 9 % .00 5 6E.00 5 6E.00 521 00 4 SE.00 4 8T.00 412E.00 4 6E.00 Kr47 221 00 192E.00 1 TT 00 144 00 12T.00 t 12E.00 9BT01 8 E 01 Kr48 1GE 01 9 4aE.(D 931 00 8 JE.00 7 E .00 1 E.00 101E.00 671 00 Xe 133 4 8 I .01 41T.01 4WE.01 4 TE 01 4 ET.01 4TE.01 475E.01 4 8T.01 Xe 133se 124 00 12E 00 13T.00 12E.00 12I.00 12E.00 12E.00 12E.00 Xo 135 341 01 3 3E.01 33E.01 3tE.01 3 0E*01 304 01 3 04E.01 301 01 Xe-135se 25aE44 12E44 681 4 331EM 16E m 8 51M 4 3E G 22E2 Xe-13e 3 E 44 16E44 8 05E2 3E2 17TG 8 61EE 411 4 20E G TOTALNOBtf GA8 1 E .02 9 E .01 101E 02 9 51E.01 91E.01 9 2 I .01 9 E 01 914 01 6131 2 20E+04 21T+04 2 3E+04 21 04 201 04 210E*04 215E 04 2 2E.04 l-132 994 03 8 E .03 8 9E.Q3 T SE.(D 66E.03 6 51E.(D 61E.03 5 8E.03 1 133 4 41E.04 4 tE 04 4 54E.04 412E 04 3 R .04 4 0E.04 4 E .04 411 04 1-134 2 E .03 18E.03 16E.(D 12E*03 9 85E.02 8 E .02 F E.02 5 9E.02 1135 2 9E.04 2 TE 04 294 04 2 6E.04 2 E .04 251E.04 215E.04 2 SE.04 e
TOTAll0DW4E 10E 05 101E.05 1 H .(5 9 7E.04 981E 04 9 41E.04 944 04 9 5E.04 Dost EQUnftINT 100#eE 3 68E.04 35E 04 3 8lE.04 3 E.04 3 2E*04 3 E.04 3 $E.04 3 E .04 Co.134 201 00 18E.(D 211 00 18E.00 t E.00 187E+00 191 00 2 0 % 00 Co-137 15E 00 1 E.00 16E.00 1 E *00 ,1 3 I .00 1 E.00 14E.00 Co138 15E.00 8 2E41 55E41 46141 2EE41 19E41 15I 41 I tSE41 8 M 42 1.a-148 11E.01 10E.01 125E 01 10E.01 9 E .00 10E.01 Be-140 11tE.01 t tE.01 18T.01 11E 01 2(TI.01 Il1E+01 15E.01 172E.01 181+01 18E 01 Tome Par 9cidates 3 4E*01 31E.01 39E 01 311 01 2110t 312E+01 3 2E.01 3 4IE.01 GRMS TOTAL ACTMTY tGE.05 101E.(5 1 GE 05 91E.04 9 E .04 9 E .04 9 46E*04 9 5 % .04
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___ __ ___ _ _ _ _ m _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ __- - _ __ __ ~ _ _ _ . _ _ _ _
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1993 Field Ezeicise Data i
RCSi CONT. SUMP iM H+4.38 H+4.48 M*F.08 H+7:18 H+F:38 H+7 4 H+B.tB NUCtal (the)
Nr4hm 4 3E4 41000 4 EE.a) 3 EE4 3 M .00 3 tie.00 3 4E+00 Nr4T 7 E of 65tE41 56E41 49 Eof 435E41 3 8E 41 3 21E 41 Mr48 61000 5 NE4 5 E.00 51E.(D 4 OE.00 4 6E*00 4 2E.00 Xe 133 4 E.01 4 E.01 411E+01 4 ME.01 4 TE.01 4 E .01 4 FE.01 Xe 133mm 12E 4 125E.G) 12E.00 12E.00 125E.00 12E.00 125 00 Xe 138 2!8E.01 2 E .01 281E.01 215E.01 2 E .01 2 ti6E.01 2 tie 01 Xe 130mi 111E46 5 tie 47 2 SE47 1 E 47 7 45E48 2 2I 48 8EG Xe-138 S E 4l 4 85E41 22I47 10E47 521E48 22E48 625 TOTAL 1000tf GAS 8 M *01 - 8 85E* 01 8 E.01 8 SE.01 8 5E.01 8 3E.01 8 2E+01 8131 21E+04 2 E 04 215E 04 21E.04 21E+04 212E.04 211 04 klat 51563 40E 4 45E @ 411 03 39E@ 3 82E4 3 E .03 8 133 39E 04 3 E .04 4 01E.04 - 3 OE+04 3 9E.04 3 E .04 39E.04 11M 4 6E.02 3 BE.02 321 02 2SE.02 215E.02 175E.02 1 E.02 1 138 23E.04 22E 04 - 22E 04 2 lE.04 21E.04 211 04 215E.04 TOTAL 8005E - - 8 9E*04 8 E .04 8 91E.04 8 5E.04 8 E .04 8 6E.04 8 6E.04 DOGE EGNULSITIEMisE 3 E .04 3 41E.04 3 4E 04 - 3 35E 04 3 E.04 - 3 E.03 3 E.04 Co134 18E41 621E41 S m et 525E41 - 49E41 4 2 41 4 GBE41 Co13F 1 R 41 4 E 41 - 43E41- 39E41 - 3 E 41 3 E 41 315E41 Co 138 5ES 1 E 4? - 9ES 6 2ES - 425EG Le148 10E 4 2ME43 10EG 3 M *00 32E+0W 29E.00 281E 00 2 5E.00 -2 E .00 Se 148 1 E .00 5 7E.00 5 E .00 4 SE.00 . 46E+00 4 31E*00 - 39E 03 .
TeamlParecedaams 3 3E+00 111E.01 10E.01 8 3E.00 8 SE.00 7tiEE.00 6 9E.00 StOSS TOTAL ACTMTY 8 9E.04 8 E .04 892 04 8EE+04' 8 6E.04 8IEE.04 8liBE.04 t
r a -re--- - s-e-m ----N 2 - .xa -, u ---,u- -- - - -- - - --- - - ----r- - - - - --u.---- -
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M 1993 Field Exercise Data UMT VENT THE H+8m TO H+845 H+1.88 Met 15 H+12 H+185 H+1.110 H+t15 H+8:38 NUCtEE fuCucci Kt45m 45E G 45E S 45E M 4 5ES 4 5E48 45E M 4 5E G 45E G Nr# 83E M $ 3Ea 83E48 83E M 83E48 8XEG 83E46 83E M Mrat 1 tEW t IEW IIEW t 1EW t IE41 11EW 11E 47 11E47 K+133 20E41 20TW - 20E6 20TW 20EW 20E6 20EW 20E41 M+13ne 5 ?SE49 SMS 52SE G 521 48 SNG 525E49 525E G 52E G 2+138 18'f 4T 185E W 18'E& i S'f & ' 185E47 18E41 185E W 1 H 41 X+1h S N48 53E48 S N 48 SNG 5H48 $ N 48 535E48 $ N 48 X+t38 156E W 15E W 15E41 156EW t 55E47 156E W 156EW t SE41
- TOTAlleOSE GAS SE& 8 E41 8 E47 SEW 8 E47 S E4? 8 E41 8 E 47 6131 10E 12 1 OE-12 t OE-12 10E-12 1 OE-12 1 OE-12 t OE-12 1GE 12 6132 15 E St 15tE-11 151E-11 151E-11 151E-t t 151E 11 151E-11 151E-11 1133 2ZEtt 222E-11 2 22E-it 222E It 2 22E-S t 2 22E-11 2 22E-11 222E 11 8 tM - 2E tt 2E 11 2 E-s t 2 62E-11 2 E-S t 262E 11 2 E-11 2 62E-fl 1-138 2E1E tl 2EE tt 2 E-11 2 E-11 2E 11 2 E-t t 2 EE-St 2(DE 11 TOTAL 900BE 9 E 11 9 E 11 9 E-11 9 E-11 9 E-11 9 E 11 9 E-11 9 E 11 008E EGANLENTIODBE 18E-11 18E-ti 18E-St 18E tt 18E-11 18E-t t 18E fl 18EE-It Co 134 271-11 2 75E-St 2 75E 11 2 75E tt 2 75E-S t 2 75E-It 2 75E-11 271-11 Co 13T 20EE 11 2 WE-11 20E 11 20E it 201-18 20E-t t 2 0E-11 2 0EE-11 Ca 138 20EG 200E4 20EG 20E4 20EM 20ES 20E49 20E G La 148 115E-13 175E-13 115E-13 171-13 175E-13 17 f-13 115E 13 1 75E 13 3+ N8 2 E-13 2 EE-13 2 8E-13 2 8E-13 2 SE 13 2EE 13 2 EE 13 281-13 feed Parecassans 231E S 231Ea 231E49 2 JiE49 231ES 231E& 231E49 2 31E&
TOTAL Gft08S ACTMTV S E47 8E& SE& $ E41 SE& SES S E 01 8EW
?
E
'6 0 .
4:
1993 Field Enerdse Data ,
UMTVENT TIE H+138 H+145 H+2.tB H+2-1$ H+138 H+2:45 H+3 se H+3:15 HUCLEE (uCIksi Nt4 ass 4 SEM 4WM 4 SE46 4 SEM 45EG 4 SE3 4 SE 48 4SE 2 Kt& S H 48 S M 48 8He SMG 83E48 83E48 8MM - 83E G Kr4e I1EW 11E& 11EW 11E 41 11EW t 1E41 11EW 11E 41 Xe 133 -- 20EW 2GEW 23EW 20EW 2GEW 2 0E W ' 2 GE41 20E 41 c
- Xe-133m 52E4B - 525E S - 5 25ES 5 25ES 5NG 52EG 52E m - 52EG Xe 135 1 85E W 1 EE& 1 E 47 1 EEW - TEE 41 185EW ^t85E W t SE&
Xe 130sn 535E4B S R 4B 5He S N 48 S N os $35E48 5Ha SRG Xe tm 15 tie & 15E W : 156E& 156 Eof 156E41 156E& 156E & 156E 47 TOTALleOStf GAS 8EW 8E& 8E& 8E& 8 E41 8E& 8 E 41 8 E 47 t-131 10 E 12 10E-12 1 OE-12 1GE 12 1DE 12 1 GE-12 1OE 12 1 OE-12 ftu tSIE-tt 151E-11 151E-11 I SE-t t 151E 11 151E-11 15tE.11 151E 11 1 133 - 2 H 11 2 ZE-t t 2 E-It 221-11 2 M-11 2 2 I -11 222E 11 222E 11 6134 2E 11 2E 11 2E-t t 2E tt 2 E 11 2 E-11 2 E 11 2E st 813 2 E-11 2 E-11 2GE 11 2 0E-11 2E-f t 2 E-11 2 E 18 2 GE-11 TOTAL 8000E 9 E-11 9 E-11 9 E-it 9 E 11 9 E 11 9 E-11 9 E-11 9 E 11 t
DOSE EGMLBfT 10 DOE 1 OE-11 - 1 NE-11 1 NE-11 18E 11 18E 11 18E 11 18EE 11 18E-t1 Co-134 2 75E-t t 2 75E-11 275E 2 75E-t t 215E-11 - '
2 7E 11 2 /E-11 2 75E-It Co-tw 20E-f t 2GE-t t 20E-11 2 G E-11 20E 11 20E-fl 20E 11 20E 11 Co-tas 20E4 2 0EG - 20ES 20EW 20ES 20E G 20E 49 20E49 La 140 - 17E13 175E-13 175E-13 175E 13 175E 13 1 75E 13 115E 13 175E 13 Se te 25E-13 2 EE 13 2 E-13 2 E 2 EE-13 29E 13 2 6E-13 2EE 13 Teed Pas 8admass 231ES 231EG 231E5 231E49 231EG 231E49 231E G 23E4 i TOTAL MCSS ACTMTY - 8EW 8E& 8E& 8E& 8 E47 8 Eel 8 E47 8 E 41 y i L
--],- - w- , - + - - , , , . , ,n,-- . ,- - -, , ,a i e . ., - , , n v - , . , . , ., , , , ,
, +
0 1993 Field Exerdse Data 4M UMT VENT Tite H+3at H+3.45 H+4.te H+4.15 H+4.30 H+4 # H+5m H+5.15 DEJC1EE (uCVec)
Kr-ses 4 SEC 4 SEM 4SE a 9 3E+01 122E+02 1 E *02 13E+02 t 4E*02 Kr41 8 3Ea 8 3EM 83Ea 4 2E+01 50E+01 5 61E*01 44E+01 32E+01 Kr4B 11E& 11EW ' i1E& 1 6E+02 211 02 2 SE 02 2 tE*02 18E+02 Xe 133 200EW 20EW 20E47 6 91E*G? 9 E*02 120E.C3 10E+03 10E*03 Xe 133m 52E& S21 49 521a 183E+01 2 SE*01 31E=01 2 SE+01 2T5 01 Xe 135 185EW 185EW 18EW $13E+02 6 86E*02 8 5E+02 7 61E*02 10E 02 Xe 135m 5 35E M $36E m S N 48 14M42 511 42 64E43 29Em 135E44 Xe-138 156EW - 156EW 156E W 12EW 111E W 85E43 36E43 82144 l
. TOTAL 1000E GAS 8EW SEW S ECT 151 03 2 0E*03 25E*03 2 2E+03 2ttE*G3 1-131 10E 12 10E.12 10E-12 80E M 100E44 11E44 10E44 130E2 8 132 151E-11 151E-11 151E 11 4 23E& 49E 4 4 95EM 4 21E& 4 69E&
1-133 221-11 2 2E-11 2 22E-11 1 E 44 202E44 2 21E44 19E 44 2 $6E4 1-134 2 62E 11 2 E-11 262E 11 13E G 13I 5 12EM 8 9'E5 FEW 1-135 2 E-11 2E 11 2E 11 11E44 13E44 1 E 44 132E44 16EG TOTAL 100edE 9 E-11 9 E tI 9 E-11 412E44 50E44 5 E 44 4 E 44 6Ee DOSE EWIVENT100eE 18E-11 18E-11 1 OE-t1 135E44 16E44 1 SE44 16E44 21Em Co 134 2 75E 11 2 75E-11 2 FE-11 11EM 11E& 11EG 11E M 23EE Co-137 20E-11 20E 11 2 0E-11 856E4 S TE5 8 86EG 871 5 tiSE E Co tse 20Em 20E m 20EM 89E M E EE5 4 8EM 3E5: 36E W La 140 175E-13 175E 13 t 15E-13 6EM 6EM 6 TIE 6Em 131 4 Be-tes 2 E -13 2 E-13 2 E-13 1 M 44 1OE44 10E44 1OE44 21ES Totd Parecessee 231EG 231E# 231EG~ 71Itce 215E44 215E44 211E44 391E&
TOTALOROSS ACTMTV 8EW SEW 8EW 'J 152E+03 20E+03 2 5E+03 2 6E.G3 211E.(D
+
8 4 1993 Field Exercise Data M UMT VENT DATA TibE H+ S.30 H+ S.45 H+4.40 H+4.15 H+4.30 H+4 45 H+ 72 H+1:15 H+7.30 H+74 NUCUDE (Wikr)
Mr45m 1 EE+02 10E+02 39E47 38F& 26E & 3 SE & 3 4E 47 33T 47 31E41 3 OIN Kr47 2 6E+01 2 4SE 01 8 30E48 12T 49 63148 551 2 4 E 48 4 21E 48 36Ea 331 2._,
Krat 1 Ef+02 164E+02 59EW 56tE47 5 27E N 49E N 46E47 4HW 413E W 401 47 Xe133 9 ?I+GF 101 03 4 0TG 40T46 40T3 4 0T G 40T E 40T M 4 0TG 40T E Xa-t*he 2 5E+01 2 7E*01 10E W 10EW 10EW 10EW 10E47 10E 47 10E 47 106E CT Xe 135 6 5E+02 6T5E+02 25EE 2 52E5 24E5 2EG 23E46 23E M 23E G 22T E Xe 135ss 3 E 44 18E44 3 6E-13 18E-13 9 E -14 4 E-14 2 4E-14 12E14 6 3T 15 301-15 Xe 13e 31I 44 19T44 3 5 I -13 17T-13 81E-14 3 9E-14 1 9E-14 91E 15 4 4T-15 18E.15
+
TOTAL NOBLE GAS 1 H +G3 2 GE+G3 T T5E2 7 6EG F 5E4 14E5 73T5 7 2EE 7 tEG 709E G l-131 511En 22TG 1 EE-11 11T-t t 101-11 101-11 105E-fl 10T.11 9 FEE-12 8 8T-12 1132 172EM 6 8EW 301 12 2 E 12 2 4E-12 2 3E-12 2 2]E-12 19E-12 175E-12 152E 12 k133 99EG 4 2EG 201-11 21T-11 1 RE-11 192E-11 196E-11 18E-11 1 E-11 16E 11 5-134 251 6 88E48 34E13 29E-13 221-13 18E13 15E-13 121-13 11T-13 101-13 8-135 6EG 26EG 121-11 125E-11 11tE-11 11T 11 111E-11 1 GE-11 9 6SE-12 T9T-12 TOTAL 500lNE 23E 2 98EG 4 6E-11 4 TE-11 4 28E-11 4 2E 11 43E-tt 41T-11 3 9E 11 3 5 & 11 DOSE EGJrvtENTIODIME 8E4 36W5 17tE 11 1 TE-11 161 11 16E 11 16E-11 16T-11 15E 11 141E 11 Co-134 8 E 47 48EW 28E 11 291 11 2 80E tt 2 E 11 28T 11 28tE 11 2 79E-11 26E 11 C&t37 63EW 36IW 215E-11 2 20E-11 21T It 211 11 25 -11 21T 11 2 2T-11 t tT-11 Co-138 9 6EM 39EG 1 TIE-i2 12E-12 8 73E-13 6 3E-13 4 6E-13 331-13 2 RE-13 281-13 La-14e 4 7EM 2TER 16E-10 18E-10 15E-10 161E-10 16E.10 15E 10 16T 10 15T-10 Ba-14e T TEG 4 4E5 26E 10 2 TE-10 261E 10 285E 10 2 7T-10 261-10 2 5T-10 2 45E-10 Tease Pareculates 1 41E M 81T5 4 8E-10 4 9E-10 4 7T-10 4 7E 10 48 E 10 4 TIE-10 4 GT-10 4 3E-10 GR063 TOTAL ACTMW 1 Tf *03 2 GE+03 175E G 16E& T $EG T 4E5 13[ 2 T 2E G 71EE 7OEG
PROCESS MONITORS AIRBORNE Time-related implant rirborne process monitoring data is provided in the following subsection. Concentration data is provided in the units as indicated. The process monitors are identified by identification numbers as well as its common name.
Some of the listed process monitors have three channels to monitor particulates,.
iodines or noble gases. For the process monitor data'we have assumed'that the particulate and noble gas channels determine gross activities whereas the iodine channel determines the activity of Iodine 131 and not gross iodine.
93-FE 7. 14
~
PROCESS MONITORS AIRBORNE Time Real 0800 0815 Relative (H+00:00) (H+00:15)
GTRE 21A/B Unit Vent Eff P (uCi/cc) 2.40E-09 2.30E-09 I 1.00E-11 9.90E-12 G 8.80E-07 8.40E-07 GHRE 10A/B Radwaste Building Eff. P'(uCi/cc) 1.00E-12 1.00E-12 I 1.00E-11 1.00E-11 G 2.00E-06 2.00E-06 ABRE 114 MSRV Monitor S/G A (mR/hr) 4.00E-01 4.00E-01 ABRE 113 S/G B (mR/hr) 4~00E-01 4.00E-01' ABRE 112 S/G C (mR/hr) 4.00E-01 4.00E-01 ABRE 111 S/G D (mR/hr) 4.00E-01 4,00E FCRE 385 Aux. Feed Pumo Turbine (mR/hr) 4.00E-01 4.00E-01 GLRE 60 Aux. Blde. Vent Ex. P (uci/cc) 2.00E-11 2.00E-31 GKRE 41 Access Control Vent P (uCi/ce) 3.00E-11 3.00E-11 GGRE 27 Fuel-Bldg. Vent Ex. P (uC1/cc) 3.20E-10 3.20E-10 I 1.40E-11 1.40E-11 G 2.10E-07 2.10E-07 GGRE 28 P (uci/cc) 3.10E-10 3.10E-10
- I 1.30E 1.30E-11 G 2.00E-07 2.00E-07 CERE 92 Condenser Air Discharge G (uCi/cc) 2.00E-06 2.00E-06 GTRE 22 Containment Purge Ex. P (uC1/cc) 1.00E-12 1.00E-12' I 1.0rE-12 1.00E-12 G 1.r0E-07 1.00E-07 GTRE 33 P (uC1/cc) 1.00E-12 1.00E-12 I 1.00E-12' -1.00E-12 G 1.00E-07 1.00E-07 GHRE 22 Radwaste B1da. Vent P fuci/cc) 1.00E-11 1.00E-11 GHRE 23 Gas Decay Tank Vent Ex. G (uCi/cc) 2.20E-06 2.20E-06 GKRE 04 Control Room Supply P (uci/cc) 3.00E-12 3.00E-12 I 2.00E-11 2.00E-11 G 4.00E-06 4.00E-06 GKPE 05 P (uCi/cc) 3.00E-12 3.00E-12 1 2.00E-12 2.00E-12 G 4.00E-06 4.00E-06 GTRE 31 bantainmentAtmosphere P (uci/cc) 8.00E-11 8.00E-11 I 4.00E-12 4.00E-12 G 6.60E-06 6.60E-06 GTRE 32 P (uCi/cc) 8.10E-11 8.10E-11 I 4.00E-12 4.00E-12 G 6.90E-06 6.90E-06 GTRE 59 Ctmt.' High Range Rad. (R/hr) <1.00E+00 <1.00E+00 GTRE 60 (R/hr) <1.00E+00 <1.00E+00 l
l 93-FE 7. 15 i
I i
PROCESS MONITORS AIRBORNE Time Real 0830 0845 Relative (H+00:30) (H+00:45)
GTRE 21A/B Unit Vent Eff. P (uCi/cc) 2.30E-09 1.60E-09 I 1.00E-11 1.00E-11 G 8.80E-07 7.40E-07 GHRE 10A/B Radwaste Building Eff. P (uC1/cc) 1.00E-12. 1.00E-12 I 1.00E-11 1.00E-11 G 2.00E-06 2.00E-06 ABRE 114 MSRV Monitor S/G A (mR/hr) 4.00E-01__ 4.00E-01 ABRE 113 S/G B (mR/hr) 4.00E-01 4.00E-01 ABRE 112 S/G C (mR/hr) 4.00E-01 4.00E-01 ABRE 111 S/G D (mR/hr) 4.00E-01 4.00E-01 FCRE 385 Aux. Feed Pump Turbine (mR/hr) 4.00E-01 4.00E-01 GLRE 60 Aux. Bldn. Vent Ex. P (uCi/ce) 2.00E-11 2.00E-11 GKRE 41 Access Control Vent P (uCi/cc) 3.00E-11 3.00E-11 _
GGRE 27 Fuel Bldg. Vent Ex. P (uCi/cc) 3.20E-10 3.20E-10 I 1.40E-11 1.40E-11 G 2.10E-07 2.10E-07 GGRE 28 P (uCiicc) 3.10E-10 3.10E-10 I 1.30E-11 1.30E-11 G 2.00E-07 2.00E-07 GERE 92 Condenser Air Discharne G (uCi/ce) 2.00E-06 2.00E-06 GTRE 22 Containment Purge Ex. P (uCi/cc) 1.00E-12 1.00E-12 I 1.00E-12 1.00E-12 G 1.00E-07 1.00E-07 GTRE 33 P (uCi/cc) 1.00E-12 1.00E-12 I -1.00E-12 1.00E-12 G 1.00E-07 1.00E-07 GHRE 22 Radwaste Blda. Vent P'fuC1/cc) 1.00E-11 1.00E-11 GHRE 23 Gas Decay Tank Vent Ex. G (uCi/ce) 2.20E-06 2.20E-06 GKRE 04 Control Room Supply P (uC1/cc) 3.00E-12 3.00E-12 I 2.00E-11 2.00E-11 G 4.00E-06 4.00E-06 GKPE 05 P (uCi/cc) 3.00E-12 3.00E-12 I 2.00E-12 2.00E-12 G 4.00E-06 4.00E-06 GTRE 31 Containment Atmosphere P (uCi/cc) 8.00E-11 8.10E-11 I 4.00E-12 1.10E-11 G 6.60E-06 5.00E-03 GTRE 32 P (uci/cc) 8.10E-11 8.1E-11 I 4.00E-12 4.00E-11 G 6.90E-06 5.00E-03 GTRE $9 Ctmt. High Range Rad. (R/hr) <1.00E+00 3.30E+00 GTRE 60 (R/hr) <1.00E+00 3.40E+00 93-FE 7. 16
PROCESS MONITORS AIRBORNE Time Real 0900 0915 Relative (H+01:00) (H+01:15)
GTRE 21A/B Unit Vent Eff. P (uci/cc) 1.20E-09 9.30E-10 I 1.00E-11 1.00E-11 G 6.60E-07 6.20E-07 GHRE 10A/B Radwaste Building Eff. P (uCi/cc) 1.00E-12 1.00E-12 I 1.00E-11 1.00E-11 C 2.00E-06 2.00E-06 ABRE 114 MSRV Monitor S/G A (mR/hr) 4.00E-01 4.00E-01 ABRE 113 S/G B (mR/hr) 4.00E-01 4.00E-01 ABRE 112 S/G C (mR/hr) 4.00E-01 4.00E-01 ABRE 111 S/G D (mR/hr) 4.00E-01 4.00E-01 FCRE 385 Aux. Feed Pump Turbine (mR/hr) 4.00E-01 4.00E-01 GLRE 60 Aux. Blda. Vent Ex. P fuCi/ce) 2.00E-11 2.00E-11 GKRE 41 Access Control Vent P (uci/ce) 3.00E-11 3.00E-11' GGRE 27 Fuel Bldg. Vent Ex. P (uCi/cc) 3.20E-10 3.20E-10 ,
I 1.40E-11 1.40E-11 G 2.10E-07' 2.10E-07 GGRE 28 P (uCi/cc) 3.10E-10 3.10E-10 I 1.30E-11 '1.30E-11 G 2.00E-07 2.00E-07 CERE 92 Condenser Air Discharge G (uCi/ce) 2.00E-06 2.00E-06 GTRE 22 Containment Purge Ex. P (uCi/cc) 1.00E-12 1.00E-12 I 1.00E-12 1.00E-12 G 1.00E-07 1.00E GTRE 33 P (uC1/cc) 1.00E-12 1.00E-12 I 1.00E-12 1.00E-12 G 1.00E-07 1.00E-07 GHRE 22 Radwaste Blda. Vent P fuci/cc) 1.00E-11 1.00E-11 GHRE 23 Gas Decay Tank Vent Ex. G (uCi/cc) 2.20E-06 2.20E-06 GKRE 04 Control Room Supply P (uci/cc) 3.00E-12 3.00E-12 I 2.00E-11 2.00E-11 G 4.00E-06 4.00E-06 GKPE 05 P (uCi/cc) 3.00E-12 3.00E-12:
I 2.00E-12 2.00E-12 G 4.00E-06 4.00E-06 GTRE 31 Containment Atmosphere P (uCi/cc) 5.00E-10 6.00E-10 I 3.50E-11 4.00E G 6.20E-03 7.50E-03 GTRE 32 P (uCi/cc) 5.20E-10 6.20E-10 I 3.40E-11 4.50E-11 G 6.20E-03 7.60E-03 GTRE 59 Ctmt. High Range Rad. (R/hr) 4.50E+00 4,80E+00 GTRE 60 (R/hr) 4.60E400 4.90E+00 93-FE 7. 17
b PROCESS HONITORS AIRBORNE Time Real 0930 0945 Relative (H+01:30) (H+01:45)
GTRE 21A/B Unit Vent Eff. P (uCi/cc) 6.90E-10 4.70E-10 1 1.10E-11 1.00E-11 G 6.10E-07 5.80E-07 GBRE 10A/B Radwaste Building Eff. P (uCi/cc) 1.00E-12 1.00E-12 I 1.00E-11 1.00E-11 G 2.00E-06 2.00E-06 ABRE 114 MSRV Monitor S/G A (mR/hr) 4.00E-01 4.00E-01 '
ABRE 113 S/G B (mR/hr) 4.00E-01 4.00E-01 ABRE 112 S/G C (mR/hr) 4.00E-01 4.00E-01 ABRE 111 S/G D (mR/hr) 4.00E-01 4.00E-01 FCRE 385 Aux. Feed Pumo Turbine (mR!hr) 4.00E-01 4.00E-01 GLRE 60 Aur. BldR. Vent Ex. P (uCi/cc) 2.00E-11 2.00E-11 GKRE 41 Access Control Vent P (uci/cc) 3.00E-11 3.00E-11 GGRE 27 Fuel Bldg. Vent Ex. P (uCi/cc) 3.20E-10 3.20E-10 I 1.40E-11 1.40E-11 G 2.10E-07 2.10E-07 GGRE 28 P (uCi/cc) 3.10E-10 3.10E-10 1 1.30E-11 1.30E-11 G 2.00E-07 2.00E-07 GERE 92 Condenser Air Discharne G (uCi/ce) 2.00E-06 2.00E-06 GTRE 22 Containment Purge Ex. P (uC1/cc) 1.00E-12 1.00E-12 I 1.00E-12 1.00E-12 G 1.00E-07 1.00E-07 GTRE 33 P (uC1/cc) 1.00E-12 1.00E-12 I 1.00E-12 1.00E-12 G 1.00E-07 1.00E-07 GHRE 22 Radwaste Blde, Vent P (uCi/cc) 1.00E-11 1.00E-11 GHRE 23 Gas Decay Tank Vent Ex. G (uci/cc) 2.20E-06 2.20E-06 GKRE 04 Control Room Supply ? (uCi/cc) 3.00E-12 3.00E-12 1 2.00E-11 2.00E-11 G 4.00E-06 4.00E-06 GKPE 05 P (uCi/cc) 3.00E-12 3.00E-12 I 2.00E-12 2.00E-12 G 4.00E-06 4.00E-06 GTRE 31 Containment Atmosphere P (uCi/cc) 7.00E-10 8.50E-10 1 5.50E-11 6.60E-11 G 8.70E-03 >1.00E+02 GTRE 32 P (uci/cc) 7.10E-10 8.20E-10 I 5.20E-11 6.50E G 8.80E-03 >1.00E+02 GTRE 59 Ctmt. High Range Rad. (R/hr) 5.50E+00 0.00E+00 GTRE 60 (R/hr) 5.60E+00 9.10E+00 a
t 93-FE 7. 18 i
E
)
PROCESS HONITORS AIRBORNE Time Real 1000 1015 Relative (H+02:00) (H+02:15)
GTRE 21A/B Unit Vent Eff. WP (uCi/cc) 3.80E-10 4.30E-10
'I 9.90E-12 1.30E-11 G 5.30E-07 5.80E-07 GHRE 10A/B Radwaste Building Eff. P (uC1/cc) 1.00E-12 1.00E-12 I 1.00E-11
- 1.00E-11 G 2.00E-06 2.00E-06 ABRE 114 MSRV Monitor S/G A (mR/hr) 4.00E-01 4.00E-01 ABRE 113 S/G B (mR/hr) 4.00E-01 4.00E-01 ABRE 112 S/G C (mR/hr) 4.00E-01 4.00E-01 ABRE 111 S/G D (mR/hr) 4.00E-01 4.00E-01 .
FCRE 385 Aux. Feed Pumn Turbine (mR/hr) 4.00E-01 4.00E-01 GLRE 60 Aux. Bldg. Vent Ex. P (uCi/cc) 2.00E-11 2.00E-11 GKRE 41 Access Control Vent P (uCi/cc) 3.00E-11 3.00E-11 GGRE 27 Fuel Bldg. Vent Ex. P (uCi/cc) 3.20E-10 3.20E-10 1 1.40E-11 1.40E-11 G 2.10E-07 2.10E-07 GGRE 28 P (uCi/cc) 3.10E-10 3.10E-10 I 1.30E-11 1.30E-11 G 2.00E-07 2.00E-07 GERE 92 Condenser Air Disc'tarne G (uCi/cc) 2.00E-06 2.00E-06 GTRE 22 Containment Purge Ex. P (uCi/cc) 1.00E-12 1.00E-12 I 1.00E-12 1.00E-12 ,
G l.00E-07 1.00E-07 GTRE 33 P (uCi/cc) 1.00E-12 1.00E-12 I 1.00E-12 1.00E-12 G 1.00E-07 1.00E-07 GHRE 22 Raduaste Blda. Vent P (uCi/cc) 1.00E-11 1.00E-11 GHRE 23 Gas Decay Tank Vent Ex. G (uCi/cc) 2.20E-06 2.20E-06 GKRE 04 Control Room Supply P (uC1/cc) 3.00E-12 3.00E-12 I 2.00E-11 2.00E-11 G 4.00E-06 4.00E-06 -
GKPE 05 P (uCi/cc) 3.00E-12 3.00E-12 I 2.00E-12 2.00E-12 G 4.00E-06 4.00E-06 GTRE 31 Containment Atmosphere P (uCi/cc) 2.60E-08 0FF SCALE I 3.00E-09 HIGH G >1.OnE-02 GTRE 32 P (uCi/cc) 2.40E-08 0FF SCALE I 2.50E-09 HIGH G >1.00E-02 GTRE 59 Ctmt. High Range Rad. (R/hr) 1.30E+03 1.00E+05 GTRE 60 (R/hr) 1.30E+03 1.00E+05 93-FE 7. 19 I
I I
PROCESS MONITORS AIRBORNE Time Real 1030- 1045 ,
Relative (H+02:30) (H+02:45)
GTRE 21A/B Unit Vent Eff. P (uci/cc) 4.50E-10 4.10E-10 I 1.30E-11 1.30E-11 G 5.60E-07 5.50E GHRE 10A/B Radwaste Building Eff. P-(uCi/cc) 1.00E-12 1.00E-12 I 1.00E-11 1.00E-11 G 2.00E-06 2.00E-06 ABRE 114 MSRV Monitor S/G A (mR/hr) 4.00E-01 4.00E-01 ABRE 113 S/G B (mR/hr) 4.00E-01 4.00E-01 ABRE 112 S/G C (mR/hr) 4.00E 4.00E-01 ABRE 111 S/G D (mR/hr) 4.00E-01 4.00E-01 FCRE 385 Aux. Feed Pump Turbine (mR/hr) 4.00E-01 4.00E-01 GLRE 60 Aux. BldR. Vent Ex. P (uCi/cc) 2.00E-11 2.00E-11 GKRE 41 Access Control Vent P (uCi/cc) 3.00E-11 3.00E-11 GGRE 27 Fuel Bldg. Vent Ex. P (uci/cc) 3.20E-10 3.20E-10 I 1.40E-11 1.40E-11 G 2.10E-07 2.10E-07 GGRE 28 P (uCi/cc) 3.10E-10 3.10E-10 r I 1.30E-11 1.30E-11 G 2.00E-07 2.00E-07 GERE 92 Condenser Air Discharge G (uCi/cc) 2.00E-06 2.00E-06 GTRE 22 Containment Purge Ex. P (uCi/cc) 1.00E-12 1.00E-12 I 1.00E-12 1.00E G 1.00E-07 1.00E-07 GTRE 33 P (uCi/cc) 1.00E-12 1.00E-12 I 1.00E-12 1.00E-12 G 1.00E-07 1.00E-07 GHRE 22 Radwaste B1de. Vent P (uCi/cc) 1.00E-11 1.00E-11 GHRE 23 Gas Decay Tank Vent Ex. G (uci/ce) 2.20E-06 2.20E-06 GKRE 04 Control Room Supply P (uC1/cc) 3.00E-12 3.00E-12 I 2.00E-11 2.00E-11 G 4.00E-06 ~~
4.00E-06 GKPE 05 P (uCi/cc) 3.00E-12 3.00E-12 I 2.00E-12 2.00E-12 G 4.00E-06 4.00E-06 <
GTRE 31 Containment Atmosphere P (uci/cc) 0FF SCALE OFF SCALE I HIGH -HIGH G
GTRE 32 P (uCi/cc) 0FF SCALE OFF SCALE I HIGH HIGH G
GTRE 59 Ctmt. High Range Rad. (R/hr) 9.40E+05 8.50E+05 GTRE 60 (R/hr) 9.40E+05 8.50E+05 93-FE 7. 20
FROCESS MONITORS
~
AIRBORNE ,
Time Real 1100 1115 Relative (H+03:00) (H+03:15)
GTRE 21A/B Unit Vent Eff. P (uCi/cc) 5.10E-10 2.5E-09 I 1.40E-11 1.0E-11 G 5.60E-07 8.5E-07 GHRE 10A/B Radwaste Building Eff. P (uCi/cc) 1.00E-12 1.00E-12 I 1.00E-11 1.00E-11 G 2.00E-06 2.00E-06 ABRE 114 MSRV Monitor S/G A (mR/hr) 4.00E-01 4.00E-01 ABRE 113 S/G B (mR/hr) 4.00E-01 4.00E-01 ABRE 112 S/G C (mR/hr) 4.00E-01 4.00E-01 ABRE 111 S/G D (mR/hr) 4.00E-01 4.00E-01 FCRE 385 Aux. Feed Pump Turbine (mR/hr) 4.00E-01 4.00E-01
- GLRE 60 Aux. BldR. Vent Ex. P (uCi/cc) 2.00E-11 2.00E-11 GKRE 41 Access Control Vent F (uci/cc) 3.00E-11 3.00E-11 GGRE 27 Fuel Bldg. Vent Ex. P (uCi/cc) 3.20E-10 3.20E-10 I 1.40E-11 1.40E-11 G 2.10E-07 2.10E-07 GGRE 28 P (uCi/cc) 3.10E-10 3.10E-10 I 1.30E-11 1.30E-11 G 2.00E-07 2.00E-07 GERE 92 Condenser Air Discharge G (uCi/cc) 2.00E.05 ,
2.00E-06 GTRE 22 Containment Purge Ex. P (uCi/cc) 1.00E-12 1.00E-12 I 1.00E 1.00E-12 G 1.00E-07 1.00E-07' '
GTRE 33 P (uCi/cc) 1.00E-12 1.00E-12 I 1.00E-12 1.00E-12 '
G 1.00E-07 1.00E-07 GHRE 22 Radwaste BldR. Vent P (uCi/ce) 1.00E-11 1.00E-11 GHRE 23 Gas Decay Tank Vent Ex. G (uCi/cc) 2.20E-06 2.20E-06 GKRE 04 Control Room Supply P (uCi/cc) 3.00E-12 3.00E-12 I 2.00E-11 2.00E-11 G 4.00E-06 4.00E GKPE 05 P (uCi/cc) 3.00E-12 3.00E-12 I 2.00E-12 2.00E-12 G 4.00E-06 4.00E-06 ,
GTRE 31 Containment Atmosphere P (uCi/cc) 0FF SCALE OFF SCALE ,
I HIGH HIGH' G
GTRE 32 P-(uC1/cc) 0FF SCALE OFF SCALE- ;
I HIGH HIGH G
GTRE 59 Ctmt. High Range Rad. (R/hr) 7.90E+05 7.40E+05 GTRE 60 (R/hr) 7.90E+05 7.40E+05 I
93-FE 7. 21
E PROCESS MONITORS AIRBORNE Time Real 1130 1145 Relative (H+03:30) (H+03:45)
GTRE 21A/B Unit Vent Eff. P (uCi/cc) 2.5E-09 2.5E-09
- I 1.0E-11 1.00E-11 G 8.5E-07 5.80E-07 GHRE 10A/B Radwaste Building Eff. P (uC1/cc) 1.00E-12 1.00E-12 I 1.00E-11 1.00E-11 G 2.00E-06 2.00E-06 ABRE 114 MSRV Monitor S/G A (mR/hr) 4.00E-01 4.00E-01 ABRE 113 S/G B (mR/hr) 4.00E-01 4.00E-01 ABRE 112 S/G C (mR/hr) 4.00E-01 4.00E-01
- ABRE 111 S/G D (mR/hr) 4.00E-01 4.00E-01 FCRE 385 Aux. Feed Pump Turbine (mR/hr) 4.00E-01 4.00E-01 GLRE 60 Aux. Blda. Vent Ex. P (uCi/ce) 2.00E-11 2.00E-11 3.00E-11 GKRE 41 Access Control Vent P (uCi/cc) 3.00E-11 GGRE 27 Fuel Bldg. Vent Ex. P (uci/cc) 3.20E-10 3.20E-10 I 1.40E-11 1.40E-11 G 2.10E-07 2.10E-07 GGRE 28 P (uCi/cc) 3.10E-10 3.10E-10 I 1.30E-11 1,30E-11 G 2.00E-07 2.00E-07 GERE 92 Condenser Air Discharge G (uci/ce) 2.00E-06 2.00E-06 GTRE 22 Containment Purge Ex. P (uci/cc) 1.00E-12 -1.00E-12 I 1.00E-12 1.00E-12 G 1.00E-07 1.00E-07 GTRE 33 P (uCi/cc) 1.00E-12 1.00E I 1.00E-12 1 003 G 1.00E-07 1.00E407 GHRE 22 Radwaste Blde. Vent P (uCi/ce) 1.00E-11 1.00E-11 GHRE 23 Gas Decay Tank Vent Ex. G (uCi/cci- 2.20E-06 2.20E-06__
GKRE 04 Control Room Supply P (uci/cc) 3.00E-12 3.00E-12 I 2.00E-11 2.00E-11 G 4.00E-06 4.00E-06 GKPE 05 P (uC1/cc) 3.00E-12 3.00E-12 I 2.00E-12 -2.00E-12 G 4.00E-06 4.00E-06 GTRE 31 Containment Atmosphere P (uC1/cc) 0FF SCALE OFF SCALE I HIGH ~HIGH G
GTRE 32 P (uci/cc) OFF SCALE OFF SCALE I HIGH HIGH G
, GTRE 59 Ctmt. High Range Rad. (R/hr) 6.90E+05 6.50E+05 GTRE 60 (R/hr) 6.90E+05 6.50E+05 i
l l
93-FE 7. 22- j u
)
~
PROCESS MONITORS AIRBORNE Time Real 1200 1215 Relative (H+04:00) (H+04: 15)
GTRE 21A/B Unit Vent Eff. P (uCi/cc) 2.5E-09 >1.0E-7 I 1.0E-11 >1.0E-6 G 8.5E-07 2.06E+03 GHRE 10A/B Radwaste Building Eff. P (uci/cc) 1.00E-12 1.00E-12 I 1.00E-11 1.00E-11 G 2.00E-06 2.00E-06 ABRE 114 MSRV Monitor S/G A (mR/hr) 4.00E 4.00E-01 ABRE 113 S/G B (mR/hr) 4.00E-01 4.00E-01 ABRE 112 S/G C (mR/hr) 4.00E-01 4.00E-01 ABRE 111 S/G D (mR/hr) 4.00E-01 4.00E-01 FCRE 385 Aux. Feed Pump Turbine (mR/hr) 4.00E-01 4.00E-01 GLRE 60 Aux. Bldn. Vent Ex. P (uCi/cc) 2.00E-11 2.00E-11 GRRE 41 Access Control Vent P (uCi/cc) 3.00E-11 3.00E-11 GGRE 27 Fuel Bldg. Vent Ex. P (uCi/cc) >1.00E-07 >1.00E-07 1 >1.00E-06 >1.00E-06 G >1.00E-02 >1.00E-02 GGRE 28 P (uCi/cc) >1.00E-07 >1.00E-07 I >1.00E-06 >1.00E-06' G >1.00E-02 >1.00E-02 GERE 92 Condenser Air Discharge G (uci/ce) 2.00E-06 2.00E-06 GTRE 22 Containment Purge Ex. P (uCi/cc) 1.00E-12 1.00E-12 I 1.00E-12 1.00E-12 G 1.00E-07 1.00E-07 GTRE 33 P (uCi/ce) 1.00E-12 1.00E-12 I 1.00E-12 1.00E-12 G 1.00E-07 1.00E-07 GHRE 22 Radwaste Blda. Vent P (uCi/cc) 1.00E-11 1.00E-11 '
GHRE 23 Gas Decay Tank Vent Ex. G (uCi/cc) 2.20E-06 2.20E-06 GKRE 04 Control Room Supply P (uCi/cc) 3.00E-12 3.00E-12 I 2.00E-11 2.00E-11 G 4.00E-06 4.00E-06 GKPE 05 P (uCi/cc) 3.00E-12 3.00E-12 I 2.00E-12 2.00E-12 G 4.00E-06 4.00E-06 GTRE 31 Containment Atmosphere P (uCi/cc) 0FF SCALE OFF SCALE I HIGH HIGH G
GTRE 32 P (uCi/cc) 0FF SCALE OFF SCALE I HIGH HIGH G
GTRE 59 Ctmt. High Range Rad. (R/hr) 6.20E+05 5.80E+05 GTRE 60 (R/hr) 6.20E+05 5.80E+05 93-FE 7. 23
i 4
I PROCESS MONITORS AIRBORNE Time Real -1230 1245 Relative (H+04:30) (H+04:45)
GTRE 21A/B Unit Vent Eff. P (uci/cc) >1.00E-07 >1.00E-07~
I >1.00E-06 >1.00E-06 G 2.44E+03 2.58E+03 GHRE 10A/B Radwaste Building Eff. P (uCi/cc) 1.00E-12 1.00E-12 I 1.00E-11 1.00E-11 G 2.00E-06__ 2.00E-06 ABRE 114 MSRV Monitor S/G A (mR/hr) 4.00E-01 4.00E-01 ABRE 113 S/G B (mR/hr) 4.00E-01 4.00E-01 ABRE 112 S/G C (mR/hr) 4.00E-01 4.00E-01 ABRE 111 S/G D (mR/hr) 4.00E-01 4.00E-01 FCRE 385 Aux. Feed Pump Turbine (mR/hr) 4.00E-01 4.00E-01 GLRE 60 Aux. Blde. Vent Ex. P (uCi/ce) 2.00E-11 2.00E-11 GKRE 41 Access Control Vent P fuCi/cc) 3.00E-11 3.00E-11 GGRE 27 Fuel Bldg. Vent Ex. P (uci/cc) >1.00E-07 >1.00E-07 I >1.00E-06 >1.00E-06 G >1.00E-02 >1.00E-02 GGRE 28 P (uCi/cc) >1.00E-07 >1.00E-07 I >1.00E-06 >1.00E-06 G >1.00E-02 >1.00E-02 GERE 92 Condenser Air Discharge G (uCi/ce) 2.00E-06 2.00E-06 GTRE 22 Containment Purge Ex. P (uci/cc) 1.00E-12 1.'00E-12 I 1.00E-12 1.00E-12 G 1.00E-07 1.00E-07 GTRE 33 P (uci/cc) 1.00E-12 1.00E-12 I 1.00E-12 1.00E-12 G 1.00E-07 1.00E-07 GHRE 22 Radwaste Elda. Vent P (uCi/cc) 1.00E-11 1.00E-11 GHRE 23 Gas Decay Tank Vent Ex. G (uci/cc) 2.20E-06 2.20E-06
- GKRE 04 Control Room Supply P (uCi/cc) 3.00E-12 3.00E-12 I 2.00E-11 2.00E-11 G 4.00E-06 4.00E-06 GKPE 05 P (uci/cc) 3.00E-12 3.00E-12 I 2.00E-12 2.00E-12 G 4.00E-06 4.00E-06 GTRE 31 Containment Atmosphere P (uCi/cc) 0FF SCALE OFF SCALE-I HIGH HIGH G
GTRE 32 P (uC1/cc) 0FF SCALE OFF SCALE I HIGH HIGH G
GTRE 59 Ctmt. High Range Rad. (R/hr) 5.50E+05 5.30E+05 GTRE 60 (R/hr) 5.50E+05 5.30E+05 93-FE 7. 24
PROCESS HONITORS AIRBORNE Time Real 1300 1315 Relative (H+05:00) (H+05:15)
GTRE 21A/B Unit Vent Eff. P (uCi/cc) >1.00E-07 >1.00E-07 I >1.00E-06 1.00E-06 G 2.29E+03 2.62E+03 GHRE 10A/B Radwaste Building Eff. P (uCi/cc) 1.00E-12 1.00E-12 I 1.00E-11 1.00E-11 G 2.00E-06 2.00E-06 ABRE 114 MSRV Monitor S/G A (mR/hr) 4.00E-01 4.00E-01 ABRE 113 S/G B (mR/hr) 4.00E-01 4.00E-01 ABRE 112 S/G C (mR/hr) 4.00E-01 4.00E-01 ABRE 111 S/G D (mR/hr) 4.00E-01 4.00E-01 FCRE 385 Aux. Feed Pump Turbine (mR/hr) 4.00E-01 4.00E-01 GLRE 60 Aux. Blde. Vent _Ex. P (uci/cc) __'.00E-11 2.00E-11 GKRE 41 Access Control Vent P (uCi/cc) 3.00E-11 3.00E-11 GGRE 27 Fuel Bldg. Vent Ex. P (uCi/cc) >1.00E-07 >1.00E-07 I >1.00E-06 >1.00E-06 G >1.00E-02 >1.00E-02 GGRE 28 P (uCi/cc) >1.00E >1.00E-07 I >1.00E-06 >1.00E-06 G >1.00E-02 >1.00E-02 GERE 92 Condenser Air Discharge G (uCi/cc) 2.00E-06 2.00E-06 GTRE 22 Containment Purge Ex. P (uCi/cc) 1.00E-12 1.00E-12 I 1.00E 1.00E-12 G 1.00E-07 1.00E-07' GTRE 33 P (uCi/cc) 1.00E-12 1.00E-12 I 1.00E-12 1.00E-12 G 1.00E-07 1.00E GHRE 22 Radwaste Blde. Vent P (uCi/ce) 1.00E-11 1.00E-11 GHRE 23 Gas Decay Tank Vent Ex. G (uci/cc) 2.20E-06 2.20E-06 GKRE 04 Control Room Supply P (uCi/cc) 3.00E-12 3.00E-12 I 2.00E-11 2.00E-11 G 4.00E-06 4.00E-06 GKPE 05 P (uCi/cc) 3.00E-12 3.00E I 2.00E-12 2.00E-12 G 4.00E-06 4.00E-06 GTRE 31 Containment Atmosphere P (uci/cc) 0FF SCALE OFF SCALE I HIGH. HIGH G
GTRE 32 P (uCi/cc) 0FF SCALE OFF SCALE I -HIGH HIGH G
GTRE $9 Ctmt. High Range Rad. (R/hr) 5.00E+05 4.70E+05 GTRE 60 (R/hr) 5.00E+05 4.70E+05 93-FE 7. 25
PROCESS HOKITORS AIRBORNE ,
Time Real 1330 1345 Relative (H+05:30) (H+05:45) ,
P (uC1/cc)
GTRE 21A/B Unit Vent Eff. >1.0E-07 >1.0E-07 I .>1.0E-06 >1.0E-06 G 1.95E+03 2.05E+03 GHRE 10A/B Radwaste Building Eff. P (uCi/cc) 1.00E-12 1.00E-12 I 1.00E-11 1.00E-11 G 2.00E-06 2.00E-06 ABRE 114 MSRV Monitor S/G A (mR/hr) 4.00E-01 4.00E-01 ABRE 113 S/G B (mR/hr) 4.00E-01 4.00E-01 ABRE 112 0,'G C (mR/hr) 4.00E-01 4.00E-01 ABRE 111 S/G D (mR/hr) 4.00E-01 4.00E-01 FCRE 385 Aux. Feed Pumn Turbine (mR/hr) 4.00E-01 4.00E-01' GLRE 60 Aux. Blde. Vent Ex. P (uci/cc) 2.00E-11 2.00E-11 GKRE 41 Access Control Vent P (uCi/cc) 3.00E-11 3.00E-11 GGRE 27 Fuel Bldg. Vent Ex. P (uci/cc) >1.00E-07 >1.00E-07 I >1.00E-06 >1.00E-06 G >1.00E-02 >1.00E-02 GGRE 28 P (uCi/cc) >1.00E-07 >1.00E-07 I >1.00E-06 >1.00E-06 G >1.00E-02 >1.00E-02 GERE 92 Condenser Air Discharge G (uci/cc) 2.00E-06 2.00E-06 GTRE 22 Containment Purge Ex. P (uCi/cc) 1.00E-12 1.00E-12 I 1.00E-12 1.00E-12' G 1.00E-07 ,
1.00E-07 GTRE 33 P (uC1/cc) 1.00E-12 1.00E-12 I 1.00E-12 1.00E-12 G 1.00E-07 1.00E-07 GHRE'22 Radwaste Blda. Vent P (uci/cc) 1.00E-11 1.00E-11 GHRE 23 Gas Decay Tank Vent Ex. G (uCi/cc) 2.20E-06 2.20E-06 GKRE 04 Control Room Supply P (uCi/cc) 3.00E-12 3.00E-12 I 2.00E-11 2.00E-11 G 4.00E-06 4.00E-06 GKPE 05 P (uCi/cc) 3.00E-12 3.00E-12 I 2.00E-12 2.00E-12 G 4.00E-06 4.00E-06 GTRE 31 Containment Atmosphere P (uCi/cc) 0FF SCALE -OFF SCALE I HIGH HIGH G
GTRE 32 P (uci/cc) OFF SCALE OFF SCALE I HIGH HIGH G
GTRE 59 Ctmt. High Range Rad. (R/hr) 4.50E+05 4.30E+05 GTRE 60 (R/hr) 4.50E+05 4.30E+05 93-FE 7. 26
PROCESS HONITORS AIRBORNE Time Real 1400 1415 Relative (H+06:00) (H+06:15)
GTRE 21A/B Unit Vent Eff. , P (uCi/cc) -5.15E-10 5.15E-10 1.00E-11 I 1.00E-11 G 7.80E-06 7.80E-06 GHRE 10A/B Radwaste Building Eff. P (uCi/cc) 1.00E-12 1.00E-12 I 1.00E-11
- 1.00E-11 G 2.00E-06 2.00E-06 ATRE 114 MSRV Monitor S/G A (mR/hr) 4.00E-01 4.00E-01 '
ABRE 113 S/G B (mR/hr) 4.00E-01 4.00E-01 ABRE 112 S/G C (mR/hr) 4.00E-01 '4.00E-01 ABRE 111 S/G D (mR/hr) 4.00E-01 4.00E-01 FCRE 385 Aux. Feed Pump Turbine (mR/hr) 4.00E-01 4.00E-01 GLRE 60 Aux. BldR. Vent Ex. P (uCi/ce) 2.00E-11 2.00E-11 GKRE 41 Access Control Vent P (uci/cc) 3.00E-11 3.00E-11 GGRE 27 Fuel Bldg. Vent Ex. P (uCi/cc) 2.40E-08 2.40E-08 I 1.00E-08 1.00E-08 G 1.60E-04 1.60E GGRE 28 P (uCi/cc) 2.40E-08 2.40E-08 I 1.00E-08 1.00E-08 G 1.60E-04 1.60E-04 GERE 92 Condenser Air Discharge G (dCi/cc) 2.00E-06 2.00E-06 GTRE 22 Containment Purge Ex. P (uci/cc) 1.00E-12 1.00E-li I 1.00E-12 1.00E-1*.
G 1.00E-07 1.00E-07 GTRE 33 P (uci/cc) 1.00E-12 1.00E 12 I 1.00E-12 1.006-12 G 1.00E-07 1.00E-07 GHRE 22 Radwaste Blda. Vent P (uci/cc) 1.00E-11 1.00E-11 GHRE 23 Gas Decay Tank Vent Ex. G (uCi/cc) 2.20E-06 2.20E-06 GKRE 04 Control Room Supply P (uCi/cc) 3.00E-12 3.00E-12 I' 2.00E-11 2.00E-11 G 4.00E-06 4.00E-06 GKPE 05 P-(uCi/cc) 3.00E-12 3.00E-12 l I 2.00E-12 2.00E-12 G 4.00E-06 4.00E-06 GTRE 31 Containment Atmosphere P (uci/cc) 0FF SCALE OFF SCALE ]
I HIGH HIGH !
G ,
GTRE 32 P (uci/cc) 0FF SCALE OFF SCALE l I HIGH HIGH !
G q GTRE 59 Ctmt. High Range Rad. '(R/hr) 4.20E+05 4.20E+05,_ I GTRE 60 (R/hr) 4.20E+05 4.20E+05 ]
l 93-FE 7. 27. j
I ,
PROCESS MONITORS AIRBORNE Time Real 1430 1445 Relative (H+06:30) (H+06:45)
GTRE 21A/B Unit Vent Eff. P (uci/cc) 5.30E-10 5.30E-10 1 1.10E-11 1.10E-11 G 7.80E-06 7.80E-06 GHRE 10A/B Radwaste Building Eff. P (uci/cc) 1.00E-12 1.00E-12 I 1.00E-11 1.00E-11 G 2.00E-06 2.00E-06 ABRE 114 MSRV Monitor S/G A (mR/hr) 4.00E-01 4.00E-01 ABRE 113 SlG B (DM/hr) 4.00E-01 4.00E-01
_ABRE 112 S/G C (mR/hr) 4.00E-01 4.00E ABRE 111 S/G D (mR/hr) 4.00E-01 -4.00E-01 FCRE 385 Aux. Feed Pump Turbine (mR/hr) 4.00E-01 4.00E-01 GLRE 60 Aux. Bld R . ' Vent Ex. P (uCi/ce) 2.00E-11 2.00E-11 GKRE 41 Access Control Vent P (uCi/cc) 3.00E-11 3.00E-11 GGRE 27 Fuel Bldg.-Vent Ex. P (uCi/cc) 2.40E-08 2.40E-08 I 1.00E-08 1.00E-08 G 1.60E-05 1.60E-05 GGRE 28 P (uCi/cc) 2.40E-08 2.40E-08 I 1.00E-09 1.00E-09 G 1.60E 1.60E-05 GERE 92 Condenser Air Discharge G (uCi/cc) 2.00E-06 2.00E-06 GTRE 22 Containment Purge Ex. P (uCi/cc) 1.00E-12 1.00E-12 1 1.00E-12 1.00E-12 G 1.00E-07 1.00E-07 GTRE 33 P (uci/cc) 1.00E-12 1.00E-12 I 1.00E-12 1.00E-12. '
G 1.00E-07 1.00E-07 GHRE 22 Radwaste Bldg. Vent P (uCi/cc) 1.00E-11 1.00E-11 ,
GHRE 23 Gas Decay Tank Vent Ex. G (uCi/cc) 2.20E-06 2.20E-06 GKRE 04 Control Room Supply P (uci/cc) 3.00E-12 3.00E-12 I 2.00E-11 2.00E-11 G 4.00E-06 4.00E-06 GKPE 05 P (uci/cc) 3.00E-12 3.00E-12 1 2.00E-12 2.00E ,
G 4.00E-06 4.00E-06 GTRE 31 Containment Atmosphere P (uci/cc) 0FF SCALE OFF SCALE I- HIGH HIGH G
GTRE 32 P (uci/cc) 0FF SCALE OFF SCALE I HIGH HIGH ,
G GTRE 59 Ctmt. High Range Rad. (R/hr) 4.10E+05 4.10E+05 GTRE 60 (R/hr) 4.10E+05 4.10E+05 I
93-FE 7. 28 i
PROCESS MONITORS AIRBORNE Time Real 1500 1515 Relative (H+07:00) (H+07:15)
GTRE 21A/B Unit Vent Eff. P (uC1/cc) 5.00E-10 5.10E-10 1 1.00E-11 1.00E-11 C 7.60E-06 7.50E-06 GHRE 10A/B Radwaste Building Eff. P (uci/cc) 1.00E-12 .).00E-12 I- 1.00E-11 *
. 00E-11 G 2.00E-06 2.00E-06 ABRE 114 MSRV Monitor S/G A (mR/hr) 4.00E-01 4.00E-01 ABRE 113 S/G B (mR/hr) 4.00E-01 4.00E-01 ABRE 112 S/G C (mR/hr) 4.00E-01 4.00E-01 ABRE 111 S/G D (mR/hr) 4.00E-01 4.00E-01 FCRE 385 Aux. Feed Pump Turbine (mR/hr) 4.00E-01 4.00E-01 GLRE 60 Aux. Bldg. Vent Ex. P (uCi/cc) 2.00E-11 2.00E-11 GKRE 41 Access Control Vent P (uCi/ce) 3.00E-11 3.00E-11 GGRE 27 Fuel Bldg. Vent Ex. P (uCi/cc) 2.40E-10 2.40E-10 I 1.00E-11 1.00E-11 G 4.00E-06 4.00E-06 GGRE 28 P (uCi/cc) 2.40E-10 2.40E-10 I 1.00E-11 1.00E-11 G 4.00E-06 4.00E-06 GERE 92 Condenser Air Discharge G (uC1/cc) 2.00E-06 2.00E-06 GTRE 22 Containment Purge Ex. P (uCi/cc) 1.00E-12 1.00E-12 I 1.00E-12 1.00E-12 G 1.00E-07 1.00E-07 GTRE 33 P (uCi/ce) 1.00E-12 1.00E-12 I 1.00E-12 1.00E-12 G 1.00E-07 1.00E-07 GHRE 22 Radwaste Blde. Vent P (uCi/ce) 1.00E-11 1.00E-11 GHRE 23 Gas Decay Tank Vent Ex. G (uCi/cc) 2.20E-06 2.20E-06 GKRE 04 Control Room Supply P (uC1/cc) 3.00E-12 3.00E-12 I 2.00E-11 2.00E-11 G 4.00E-06 4.00E-06 GKPE 05 P (uCi/cc)' 3.00E-12 .3.00E-12 1 2.00E-12 2.00E-12 G 4.00E-06 4.00E-06 j GTRE 31 Containment Atmosphere P (uCi/cc) 0FF SCALE OFF SCALE. l I HIGH HIGH ,
G l GTRE 32 P (uC1/cc) 0FF SCALE OFF SCALE l I HIGH HIGH j '
G GTRE 59 Ctmt. High Range Rad. (R/hr) 4.00E+05 3.90E+05 GTRE 60 (R/hr) 4.00E+05 3.90E+05 l
1
'l 93-FE 7. 29 j l
1 I
.., - _ _ -w-
l FROCESS MONITORS AIRBORNE !
Time Real 1530 1545 Relative (H+07:30) (H+07:45)-
GTRE 21A/B Unit Vent Eff. P (uci/cc) 5.10E-10 5.15E-10 I 1.00E-11 1.0$E-11 G 7.50E-06 7.40E-06 GHRE 10A/B Radwaste Building Eff. P (uCi/cc) 1.00E-12 1.00E-12 1 1.00E-11 1.00E-11 G 2.00E-06 2.00E-06 ABRE 114 MSRV Monitor S/G A (mR/hr) 4.00E-01 4.00E-01 ABRE 113 S/G B (mR/hr) 4.00E-01 4.00E-01 ABRE 112 S/G C (mR/hr) 4.00E-01 4.00E-01 ABRE 111 S/G D (mR/hr) 4.00E-01 4.00E-01 FCRE 385 Aux. Feed Pump Turbine (mR/hr) 4.00E-01 4.00E-01 GLRE 60 Aux. Blde. Vent Ex. -P (uCi/cc) 2.00E-11 2.00E-11 GKRE 41 Access Control Vent P (uCi/cc) 3.00E-11 3.00E-11 GGRE 27 Fuel Bldg. Vent Ex. P (uCi/cc) 2.40E-10 2.40E-10 I 1.00E-11 1.00E-11 G 4.00E-06 4.00E-06 GGRE 28 P (uci/cc) 2.40E-10 2.40E-10 I 1.00E-11 1.00E-11 ;
G 4.00E-06 4.00E GERE 92 Condenser Air Discharge G (uCi/ce) 2.00E-06 2.00E-06 l GTRE 22 Containment Purge Ex. P (uCi/cc) 1.00E-12 1.00E-12 I 1.00E-12 1.00E-12 G 1.00E-07 1.00E-07 GTRE 33 P (uCi/cc) 1.00E-12 1.00E-12 I 1.00E-12 1.00E-12 G 1.00E.07 1.00E-07 1 GHRE 22 _Radwaste B1da. Vent P fuCi/ce) 1.00E-11 1.00E-11 )
GHRE 23 Gas Decay Tank Vent Ex. G (uCi/cc) 2.20E-06 2.20E-06 GKRE 04 Control Room Supply P (uC1/cc) 3.00E-12 3.00E-12 l I 2.00E-11 2.00E-11 G 4.00E-06 4.00E-06 l GKPE 05 P (uCi/cc) 3.00E-12 3.00E-12 l I 2.00E-12 2.00E-12 G 4.00E-06 4.00E-06 .
GTRE 31 Containment Atmosphere P (uCi/cc) 0FF SCALE OFF SCALE l I HIGH HIGH G
GTRE 32 P (uCi/cc) OFF SCALE OFF SCALE )
I HIGH HIGH-- !
G I GTRE 59 Ctmt. High Range Rad. (R/hr) 3.90E+05 3.80E+05 GTRE 60 (R/hr) 3.90E+05 3.80E+05-93-FE 7, 30 1
r -
PROCESS MONITORS AIRBORNE Time Real 1600 Relative (H+08:00)
GTRE 21A/B Unit Vent Eff. P (uCi/cc) 5.15E-10 I 1.05E-11 G 7.40E-06 GHRE 10A/B Radwaste Building Eff. P (uCi/cc) 1.00E-12 I 1.00E-11 G 2.00E-06 '
ABRE 114 MSRV Monitor S/G A (mR/hr) 4.00E-01 ABRE 113 S/G B (mR/hr) 4.00E-01 ABRE 112 S/G C (mR/hr) 4.00E-01 ABRE 111 S/G D (mR/hr) 4.00E-01 FCRE 385 Aux. Feed Pump Turbine (mR/hr) 4.00E-01 GLRE 60 Aux. Bldn. Vent Ex. P (uC1/cc) 2.00E-11 GKRE 41 Access Control Vent P (uci/ce) '3.00E-11 GGRE 27 Fuel Bldg. Vent Ex. P (uci/cc) 2.40E I 1.00E-11 G 4.00E-06 GGRE 28 P (uci/cc) 2.40E-10 I 1.00E-11
- G 4.00E-06 GERE 92 Condenser Air Discharne G (uCi/cc) 2.00E-06 GTRE 22 Containment Purge Ex. P (uCi/cc) 1.00E-12 I- 1.00E-12' G 1.00E-07 GTRE 33 P (uC1/cc) 1.00E I 1.00E-12 G 1.00E-07 '
GHRE 22 Radwaste Bldt. Vent P fuci/cci 1.00E-11 GHRE 23 Gas Decay Tank Vent Ex. G (uCi/cc) 2.20E-06 GKRE 04 Control Room Supply P (uCi/cc) 3.00E-12 I 2.00E-11 G 4.00E-06 -
GKPE 05 P (uC1/cc) 3.00E-12 I- 2.00E-12 G 4.00E-06 GTRE 31 ContainmentAt$osphere 'P (uCi/cc) OFF SCALE I I HIGH L. G GTRE 32 P (uci/cc) 0FF SCALE I HIGH c
- GTRE 59 Ctmt. High Range lad. (R/hr) 3.80E+05 !
GTRE 60 (R/hr) 3.80E+05
)
93-FE 7. 31
,, y --e
.m .
PROCESS MONITORS LIQUID Time-related inplant liquid process monitoring data is provided in the following subsection. Concentration data is provided in the units as indicated. The process monitors are identified by identification numbers as well as its common name.
~
e a
93-FE 7. 32
, ~ . .
PROCESS MONITORS LIQUID ID Number Time: Real 0800-1600 Relative (H+0:00-II+08:00)
~
LERE 59 Turbine Bldg. Dram (uCUcc) 6.00E-07 HFRE 45 Sec. Liquid Waste Discharge (uCi/cc) 5.50E-09 FBRE 50 Aux. Steam Cond. (uCUcc)
Recovery Tank 4.00E-07 AERE 4A Senice Water Return (uCucc) 4.00E-08 AERE 4B (uCi/cc) 4.00E-08 EFRE 35 Essential Water Senice (uCi/cc) 5.00E-07 EFRE 36 (uCi/cc) 5.00E-07 EGRE 09 CCW Train A (uCi/cc) 4.50E-07 EGRE 10 CCW Tram B (uCi/cc) 4.50E-07 '
SJRE 02 S/G Liquid (uCi/cc) 3.00E-07 BMRE 25 S/G Blowdown Process (uCi/cc) 3.50E-07 BMRE 52 S/G Blowdown Discharge (uCUcc) 3.50E-07 SJRE 01 CVCS Letdown (uCUcc) 7.40E-02 i HERE 16 Boron Recycle Distillate (uCi/cc) 5.00E-07 HBRE 18 Liquid Waste Discharge (uCi/cc) 3.00E-05 i
r 1
93-FE 7.33
AREA RADIATION MONITORING Time-related inplant area radiation monitoring data is provided in the following subsection. Radiation data is provided in the units as indicated. The area radiation montiors are identified by identification numbers as well as its common name.
Radiation levels indicated with a < or > sign indicate the monitor is reading offscale low or offscale high respectively.
The location of area radiation monitors within the auxiliary and fuel buildings are designated on the inplant radiation maps.
4
{
93-FE 7. 34 b
TIME TIME : TIME TIME TIME TIME j TIME TIME T4ME TIME 0800 -0846 0900 0915 0930 CS46 1000 1016 1030 1045 1146 1206 O ~ --~~
e M N!iOR LOCATION DO5E~RKfE-W (mR.hR)
N RADWASTE BLOG. CORROOR, BASEMENT (W) 02 02 01 02 02 02 02 02 02~ 02 50RE01
" '5bME62 RKDWK5fE~BEUG C6RRID6R'B45EMENT(Cnt0 02 02 02' O2 02 7} 61 02 02 02 SDRE03 RADWASTE BLDG. CORR; DOR. BASEMEN T (E) 02 02 02 02 02 02 02 02 02 02
'5bME64 RKDWK5TETILDG CORRi5BW 2066-(W) 02 02 02 02 02 02 02 02 02 02 RADWASTE BLOG.CORRADOR,200J (Cnu) 02 02 02 02 02 02 02' 02 02 02 50RE05 SDRED6 56LIO RAUWK5TE KREX 266cy 02 02" o2 02 02 02 0 O2 02 02 SDRE07 RADWASTE BLOG. TRUCK 5 PACE,2000' 02' 02 02 02 02 02 02 0 2l 02 02 50HE08 RKDWK3TEBLDG.SAMF ETXsdRKT6RY 02 02 02 52 02 02 02 02 02 02 SDRE09 : RADWA5TE BLOG. VALVE ROOM CORRIDOR,2047 (E) 02 02: 02 02 02 02 02 02 02 02 55RETO RKDWK5TEBEDG. VALVE R06M C6MRiD6R 2674(W) 02 02 02 02 02 01 02 02 o'2' 02 SDREt1 RADWASTE BLOG. HVAC FILTER UNIT 02 02 02 02 02 02 02 -02 02 02 5DRE12 AUX. BLDG. CORRIDOR. BASEMENT 1974' (SE) 05 ~~63 61 05 05 05 1060 ~7007 1206B ~ t266D SDRE13 AUL BLOG. CORRDOR, BASEMEN T 1974' (NE) 0.5 05 05 05 05 05 100 0 700 0 1200 0 12000
$DRE14 AUX. BEDG CORRiDD CBK5EMENTWF(N) 05 ~D3 05 6X 05 73 50 0 ' 36iTO 6060 -- B66 6 05 05 05 05 05 05 50 0 300 0 600 0 600.0 SDRE15 AUX.BiDG.CCRRIDOR BASEMENT t974JV) 5DREi6 AUX ~BINTC6MRIDDR BASEMERTil74'(5'W) 05 05 05 75 05 03 50 0 -' 607 3 606b 606b NONRAD)OACTiVE PIPE TUNNEL & PER50NNEL ACCESS t974' O5 05 05 05- 05 05 10 0 60 0- 100 0 100 0 50RE17
'55REi8 AUX. BLDG. GROUND FLOOR CORRlD6RMTN) 1.0 10 1.0 10 10' 10 106b ~ 760 0 1266b M 50 ret 9 AUX 6 LOG. GROUND FLOOR CORROOR 2000'(SE) 0.5 05 05 0.5: 05 0.5 75 0 500 0: 900 0 900e 5DRE20 AUX BLDG.VATvEM6DWC6RRTDBM 266fr(s) 50 50 so 50' 50 50 50 0 306b 566 0 366B 50RE21 AUX. 0LDG. VALVE ROOM CORROOR 2000' (5) 10 0 10 0, 10 0 10 0 10 0 '
10.0 50 0 300 0-500 0 500 0 5bRC22 KUX. BLOG. 6 MOUND FLOOW2666 (SW) O5 73 65 05' O5 O5 50 0 - 360 D 506b 366b SDRE23 AUX. BLOG GROUND FLOOR 200J g 05 05 05 05, 0.5' 0.5 50 0 300 0 500 0 500 0 5BRE24 XUX BEDG SAMPLsNG ROOM 2000f (Cnt0 50 7670 50' S0 S O' SO O - 366 5 500 0 ~766b SDRE25 AUX. BLDG. VENT FILTER 05 05 05 05 05 05 100 0 700 0 1200 0 >10000 5DRE26 RRRTEAT EXCHAN6ER~6DT5IDET5M 05 03 OL 7571 05'70 7 607 700 0 TBDb SDRE27 CONT. PURGE EXHAUST FIL TER UNIT 2047 05 0.5 05 05 0.5 05 100 0 700 0 1200.0 >10000 7250 ~663
~
55RE28 C6NT P'ER5DfiNEL HATCH 204T 05 05 61 73 05 05' 8 1400 0 WOD66~
SDRE29 HOT MACHINE SHOP 02 02 02 02 02 02 05 05 05 05 5DRE30 R6TlR5TRUMENT5 HOP O2 02' 62 52 02 02' O.5 03 05 05 SDRE31 CONTROL BLDG HOTLAB 02 02 02 02 02 02 05 05 0.5 05
'5DRE32 C6HTROL BMG CORRiUOR 02 02 02 02 02 02 0.5 05 05 05 5DREM CONTROL ROOM 2047 02 02 02 02 02 02 05 05 05 05 5DRE34 CASKRANDEIN64 MEA 2000' 06 03 0.5 0.5 0.5 05 63 05 05 ' 05 SDRE35 NEW FUEL 5TORAGE 2026 0.5 05 0.5 05 0.5 05 05 05 05 20.0
'5DRE36 NEW FUEL STORAGE CORRIDOR 2026' O5 - DT 05 ' 05 05 0h a5 05 ~61 20 6 SDRE37 SPENT FUEL POOL AREA 05 0.5 0.5 05- 0.5 05 05 05 05 05 5DREM EPENTTUEEPDOL AREA 05 05' 05 05 05 os 51 05 05' '- Os 50RE39 SEAL TABLE AREA 2026 (N) 30.0 3000 3900 4100
~
5100 000G >100tB *t0000 >t0000 >10000 5DRE~46 PER56NNEL ACCESS HATCH AREA INSIDEN47 (SW) 15 0 ~3566' 410b 4566 536B 9500 >t0000 >10000 >10000 II 666~ 0 50RE46 CONTAtNMENT BLOG.2g7 NW) 25 0 4100 5300 5500- 5700 9700 >10000 >10000 >10000 >t0000 y
5DRE42 CBNTKINMENTHEDGr (E) 20 0 fi36D W 586b siU666 >10000 >10000 >1D600 N
- 50RE43 TECHN' CAL SUPPORT CENTER 02 02 02 0.2 02 02 02 02 02-02
'5DRE44 EMiM6ERC76PERATIONS FACILITY 02 02 02 02 02 02 02 --~'6 2 02 02 w
- SDRE47 i PASS SAMPLING ROOM 2000' q 10 0 10 10 10. to 10q 40u 400 400 400:
Page I
TIME TIME TIME TIME TIME TIME 1216 1230 1245 1300 1315 1330 1345 -1500 e
y -MONITOR LOCATlON m 02 02 02 02 02 10 0 M 5DRE04 RADWASTE BLDG.CORRtDOR, BASEMENT 3 W) l RIDWA5TE BEDC C5RRtDOR, BASEMENT (Cnti) 02 62 02 0.2 02' 73 SDRE02 02 02 02 02 02 2.0 5DRE03 RADWA5TE BLDG. CORRLDOR, BASEMENT (E) 10D 55RE04 RKDWK5TE~BIDd DDRRID6Rh (W) 02 02 02 02 02 RADWASTE BLOG. CORRIDOR,2000 (Cnti) 02 02 02 02 02 70 SDRE05 01 5DRE66 SOLID RADWA3TE AREA,2006 02 0.2 02' O2 02 RADWASTE BLDG. TRUCK 5 PACE,2000 02 02 02 02 02 02 SDRE07 01 7.6 RXDWK5TEBLDG. SAVfLE LABORATORY 02 02 62 02 SDREba RADW ASTE BLOG. VALVE ROOM CORRIDOR,204T (E) 02 02 02 0.2 02 02 50RE09 02 ~52 01 02 02 02
~5DME10 RKDWX57E BLDG. VALVE M6BfJE5RRIDOR. 204T (W) 02 02 02 0.2 02 02 SDREt t RADWASTE BLOG. HVAC FALTER UN6T >10000 5DRE12 AUX. BLDG. CORRID6R~BX5EMENT 1974' (SE) 12060'M726U O 1200.0 1200 0 12030 1200 0 1200 0 ' 1200 0 1200 0 >10000 SDREi3 AU A. BLDG. CORR 4 DOR, BASEMENT 1974' (NE) 666 0 600 0 6000 600 0 600 0 >1006D
'50RE14 AUX BEDC EURRID6FBK5EMENT 1974'(N) 600 0 600 0 6C0 0 600 0 600.0 >10000 SDREt5 AUX. BLOG. CORRsDOR. BASEMENT 1974' (W) 5DREI6 AUX BLDG. CORRIDOWBAKEMENT 1974' (5W) 666'O 600 0 6060 N0 6661 >1006b 100 0 100 0 100.0 100 0, 100 0 >t0000 SDRE17 -
NONRADOACTIVE PIPE TUNNEL & PERSONNEL ACCESS t974' 5DREl8
~~~
KUX. BLOG. GRDUND FLOOR CDMRiDORYdfW) 1200 0 12000"W0 -T2607 1206b >10006 900 0 900 0 5000 900 0 900 0 >10000 SDRE19 AUX BLOG. GROUND FLOOR CORRIDOR 2000' (SE) >10606 500 0 560 0 500 0 500 0 500 0
'5DRE20 AUX. BLDC. VALVE R5DiffDRRIDOR 2000 (S)
SDRE21 AUX. BLDG. VALVE ROOM CORR 6 DOR 2000 (S) 500 0 500 0 500 0 SCO O 500 0 >1E 5DRE22 AUX BEDG GR5UNDTLOOR 2000'(SW) 506TD ~ 66D7D'ND 5 500 0 >10066 500 0 500 0 500 0 500 0 500 0 >100u0 SDRE23 AUX _ BLOG. GROUND FLOOR 2000' (W) 500 0 3.0 506b 56iT6 506 O' >t0066 SDRE24 AUX BEDG. SAMPLING ROOM 2000'(Cnti)
>10000 >10000 > 10000 =10000 >10000 >100uc 50RE25 AUX. BLDG. VENT FILTER RHWREAT EXCHANGER OUTSIDE 2026 700 0 700 0 706B ~70T6 700 0 >10666 5DRE26
>10000 >10000 >10000 >10000 ,>10000 >10u00 SDRE27 -
CONT. PURGE EXHAUST F4LTER UNIT 204T
> 10000 310000 R 0000 > 10000 >10000 >10000 5DRE28 COl4T PERSCHRElHATCH 204T i0 t .0 1.0 1.0 i .0 1.0 50RE29 HOT MACHINE SHOP 10 1.0 1.0 10 1.0 1.0 5DRE30 FiO5 TIN 5TRUMEF4T SHOP 1.0 t .0 1.0 t .0 t .0 t .0 SDRE31 CONTROL BLOG. HOT LAB 1.0 1.0 1.0 1.0 to 1.0 50RE32 C6NTRBEBLDG.CORRiDDR 10 1.0 1.0 1.0 10 1.0 SORE 33 CONTROL P.OOM 2047 05 OT 05 0.5 05 0.5 5DRE34 CASK HANDORG AREA 2006 100 0 800.0 4000 0 9000O! 9000 0 90000 SORE 35 NE~W FUEL STORAGE 2026 7 000 000 0 4000 0 9000 0 9000 0 9066b SDRE36 NEW FUEL STORAGE CORRIDOR 2026 1000 0 4000.0 5000.0 7000.0 9u00 0 9u000 50RE37 SPENT FUEL FOOL AREA ~
$DRE38 5 PENT FUEL PODEAREA >16666 >10000M 0000 >10000 mf0000 > 10000
>10000 >10000 >10000 >10000 > t 0tMO >t0000 SDRE39 SEAL TABLE AREA 2026 (N)
PERSONNEEXCCE551ATCIFKRM51DE 254WW) >tB666- >10000 >10666~ >t0000 >t0000 >10000 5DREi0
>10000 >10000 =10000 >10000 >10000 >10000 SDHE4i CONTAINMENT BLOG. 204i' (NW)
>10000 >t6660- >100sT iT0660~ WO600 B6000 7 SDREi2 DUNTKINMENTELDG. 204T (E) 02 02 02 02 02 02 SDRE43 IECHNICAL SUPPORT CENTER O2 02 02 02 02 02
$ '5DRE44 EMERCENDVDPERKT16N5TACtLITY 400 400 400 400 400 400 SDRE47 l, PASS SAMPLING ftOOM 20LC hge t
INPIANT SURVEYS RADIATION l l
Time-related inplant survey map data is provided i~ the following subsection. Data is provided for each floor leve : 2 the auxiliary, fuel and diesel' generator buildings. Radiation data is provided in the units as indicated. The data is designated by a letter and corresponds to the circled letter zones on the map.
Radiation levels indicated with a < sign indicate areas where readings will generally be below the lower level of detectabilty for instruments used in determining radiation levels.
Area radiation monitors are designated on the maps as the monitor number preceeded by a 'SD'. The data for these monitors is provided in the area radiation monitoring data.
93-FE 7. 37
' I L
'SD l6 S 0 15 s ,
g SD"i7 a.
b0
@t@ @ @ .
@ l@. ~@ @. . _
SD12 SO 63 F e e g .-
=T
_1 ,
3 (
AUX. BLDG. 1974'-0* #
)@
(RAatAf!05 L2v213 INDICAfgD A2315 t/5t) flae taal 0008 Dets MS4 0845 0000 0015 ~ 09M 094S 100 talative (5+08:00) (5+00:13) (5+40 e M) (5+00:45) (5+41:00) (5+41:13) (h+01:30) 1(5+01:45) ,(5+02:0 (A) Corridor Area 4 0.002 < 0.002 < 0.002 4 0.002 < 0.002 < 0.002 < 0.002' < 0.002 < 0.00' (B) Pumo tocus Areas 0.020 0.020 0.020 0.020 0.020 0.020 0.020 0.020 0.02 ,
(C) Borlc Acid tank Arese 4 0.002 4 0.002 4 0.002 < 0.002 4 0.002 4 0.003 < 0.002 4 0.002 - < 0.00 *
(D) Corridor Aree < 0.002 4 0.002 4 0.002 4 0.002 4 0.002 < 0.002 4 0.002 < 0.002 4 0.00- I (E) Aus FW Pump Arte < 0.002 4 0.002 4 0.002 4 0.002 < 0 002 4 0.001 -t 0.002 , < 0.002 ' < 0. 00 -
Time taal 1913 1034 1945 1100 1115 113e 1145 1200 - 122 malative (5+02:13) (5+02 s M) (5+42s45) (5+03:00) (3+43:15) (5+03 s M) (5+03:45) '(5+04:00). - (5+44:1 (A) Corridor Area 0.100 0.100 0.100 0.700 1.100 1.200 1.200 1.200 '1.20 l (S) Pues Roam Areae 0.0$0 0.0$0 0.030 0.100 0.150 0.130 0.150 0.150 ' O.15 - i' (C) Sorlc Acid Tsak Areee 0.050 0.050 0.050 0.075 0.100 . 0 100 0.100 -0.100 0.10 (0) Corrider Ares 0.030 0.050 0.050 0.300 0.600 0.600 0.600 - 0.600 0.60 -
(2) Aus FW Pump Area 0.100 0.100 0.100 0.700 1 200 1.200 1.200 - 1.200' 1.20 i Ties maal 1234 1243 1Me 1315 13Se 1MS 1415 .
'143 Balative (5+44:30) -(5+44s43) .(5+43 00) .(5+05:15) (5+45 30) ( 5+0Ss45) 1400 (5+46:00) . (5+46:15) - (5+04:3 (A) Corridor Area 1.200 1.200 1.200 1.200 1.200 200.000 200.000 200.000 200.00L '
'(3) Pump Roam Arese 0.130 0.150 0.150 0.130 0.130 1200.000 1200.000 .1200.000 1200.00' i (C) terle acid tent Atoss 0.100 0.100 0.100 0.100 0.100 2.200 2.200 2.200 2.20, 6 (D) Corridor Area 0.600 0.600 0.400 0.600 0.600 .200.000 200.000 200.000 200.c0 1 (2) Aus PV Pump Area 1.200 1.200 1.200 1.200 1.200 200.000 200.000 . - 200.000
- 200.00 Time taal 1445 1300 1513 ISM '1545 1600 "
Balative (5+00:45) (B+07:00) (5+07:13) (5+47sM ) (5+47 s 45) (5+48:00) +
(A) Corridor Area 200.000 200.000 200.000 200.000 200.000- 200.000 1 (B) Puen Room Areas 1200.000 1200.000 1200.000 1200.000 1200.000 1200.000- 6 (C) Sorlc Acid Tshk Areae 2.200 2.200 2.200 2.200 2.200 2.200 (D) Corridor Area 300.000 200.000 200.000 200.000 200.000 200.000 (E) Aus PV Pump Area 100.000 200.000 200.000 200.000 200.000 200.000
. .i 93-FE 7. 38
. t
IL _,
6 n
@ s.- ,
1 l_
q @ @ J" g@ I Y l a .m C
-l
. a= ll -
a E _
I 3 - C -
LJ I
- l. ' l AUX.BLDO. 1988'-O' and 1989*-6*
(RADIATION LIVIL$ INDICATED A12181/H)
Time smal 0804 0813 Osse 0445 090s 0013 0010 0045 1000 talative (3+00sDe) (5400e13) (B+00e34) (E+00 43) (3+41:De1 (D+01:13) (E441:30) (B+01:4S1 (B+02s00)
(A) 121 Encapsulation Arena 0.013 0.01$ 0.013 0.013 0.013 0.015 0.015 0.015 0.011 (n) Corridor Ares < 0.002 < 0.002 4 0.002 4 0.002 4 0.002 4 0.002 < 0.002 < 0.002 4 0.002 (C) Corridor Area 4 0.001 < 0.002 4 0.002 4 0.002 4 0.002 4 0.002 4 0.002 4 0.002 4 0.002 flan Esal 1015 1910 1945 1100 1115 1130 2 1200 1215 Ealative (S+42:13) (B +02:34) (9+02:45) (E+43:00) (5+03:13) (B+03:34) (E+0. +04:00) (E+04:13) 1 (A) 121 Encapsulation Areas 0.100 0.100 0.100 0.700 1.200 1.200 , 1.200 1.200 1.2C0 (5) Carridor Area 0.010 0.010 0.010 0.070 0.120 0.120 0.120 0.120 0,120 (C) Corridor Area 0.003 0.003 0.003 0.033 0.600 0.600 0.600 0.600 0.600 Tbse taal 1234 1245 1500 1313 1314 1345 1400 1415 1430 Relative (5+64e30) (sWO4:45) (5+03:00) (5+05:13) (E+03:30) (E+4Ss45) (B+44:00) (5+04s13) (R+46:30)
(A) 121 Encapsulation Areae 1.200 1.200 1.200 1.200 1.200 000.000 000.000 800.000 800.000 (3) Corridor Area 0.120 0.120 0.120 0.120 0.120 50.000 50.000 30.000 50.000 (C) Corridor Area 0.400 0.600 0.600 0.600 0.600 15.000 13.000 13.000 15.000 Time taal 144S 1500 1515 1534 1543 1606 Relative (5+04 s 4 5) (5+47:00) (E+07:13) (E+07:30) (R+07:43) (5+08:00)
(A) LH tacapsulatloa Arese 800.000 000.000 800.000 000.000 800.000 800.000 (3) Corrider Area 30.000 50.000 30.000 30.000 30.000 30.000 (C) Corridor Area 15.000 13.000 15.000 13.000 13.000 15.000 93*M 7. 39 ,
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5 AUX. BLDG. 2000'-0* i (RADIATION LEY 215 ICICAT O Att IN 1/HR)
- 1me ' Real 0000 0013 0850 0845 - 0000 0013 0958 0943 1000 Beistive (S+08:00) (9+00:15) . (5+00:50) (R+00:45) (5601:00) (5+41s15) (5+41s M) (E+01:43) (E+02:00)
A) EB1 Encapoulation Arese 0.015 0.013 0.015 0.015 0.015 0.013 0.015 0.013 'O.013
- 8) Corridor Arse < 0.002 4 0.002 < 0.002 < 0.002 < 0.002 4 0.001 4 0.002 < 0.002 < 0.002 C) Corridor Ares e 0.002 < 0.002 < 0.002 < 0.002 - < 0.002 4 0.001 4 0.002 < 0.002 < 0.002 Time heal 1915 1930 1945 1190 1115 11H 1145 1200 1213 teletive (5+42s15) (D+42 s M) (5442s45) (5+45:00) (9+03:15) - (E+05:30) (5+03s45) (S+04:00) (E604:13)
(A) RER 2acapsalation Areae 0.100 0.100 0.100 0.700- 1.200 1.200 1.200 1.200 - 1.200 ,
(5) Corridor Area 0.010 0.010 0.010 0.070 0.120 0.120 0.120 0.120 0.120 <
(C) Corridor Area 0.005 0.005 0.005 0.055- 0.600 0.600 0.600 - 0.600 0.600 Tises ' Real' 1130 1245 150s 151S 1538 1545 '1400 1415- '1450 E Relative (B+04s M) (5+04:45) (D+03:00) (S+05s15) (9+eS s M) (9+45s45) (9+eeste) (D+04:15) . (E+0e s 30) '
(A) RER tatspoulation Areae 1.200 1.200 1.200 - 1.200 1.200 - 800.000 000,000 800.000 800.000 -r
- (3) Corridor Aree 0.120 0.120 0.120 0.120 0.120- 30.000 30.000 30.000 30.000 *
(C) Corridor Area 0.600 0.600 0.600 0.600 0.600 15.000 '15.000 15,000 15.000 -
0 Time Rani 144S 1500 1515 15 54 1345 toes .
Reistive (5+06:43) (S+07s00) -(9647:15) (E+47 s M) (9+47:43) (9+40s00)
( A) EMR Encapsulation Areet 800.000 000.000 800.000 800.000 000.000 800.000-(S) Corridor Aree 30.000 30.000 $0.000 30.000 50.000 30.000 (C) Corridor Area - 13.000 15.000- 15.000 15.000 13.000 13.000 93-FE 7 40 e'
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T1ase taal 0000 0013 0030 0045 0900 0913 0950 0945 1000 Emlative (S+00s00) (5400:13) (E+00:30) (E+00:45) (E+01:00) (5+01:2.5) (5+01:30) (E+01:45) (5+02:00),
(A) Elect. Fenetration Areas < 0.002 < 0.002 4 0.002 4 0.002 4 0.002 < 0.002 < 0.002 < 0.002 < 0.001 ft) Corridor Area 4 0.002 < 0.002 4 0.002 < 0.002 < 0.002 4 0.002 4 0.002 < 0.002 < 0.002 (C) CCW Pump Areas < 0.002 4 0.002 4 0.002 4 0.002 < 0.002 < 0.002 < 0.002 4 0.002 < 0.002 (D) Main FW Pump Arese < 0.002 < 0.002 < 0.002 4 0.002 < 0.002 4 0.002 4 0.002 < 0.002 < 0.001 Time Real 1913 1930 1645 1100 1215 1130 1145 1200 1215 Relat.1ve (E+03:13) (S+02:30) (E+02:43) (3+03:00) (5+03:13) (E+03: 30) (H03:45) (5+04 :00) (B+04:13)
(A) Elect. Penetratica Areas 0.100 0.100 0.100 0.700 1.200 1.200 1.200 1.200 1.200 (3) Corridor Area 0.100 0.100 0.100 0.700 1.200 1.200 1.200 1.200 1.200 (C) CCW Pump Arose 0.010 0.010 0.010 0.070 0.120 0.120 0.120 0.120 0.120 (D) Main fW Pump Arese 0.100 0.100 0 100 0.700 1.200 1.200 1.200 1.200 1.200 T1 Jam Real 1230 1243 1300 1313 1330 1S45 1400 1415 1430 Salative (5+04:30) (H04:43) (E+05:00) (5603:13) (E+03:30) (E+03:43) (5+00s00) (E+06:15) (E+06:30)
(A) Elect. Penetration Areae 1.200 1.200 1.200 1.200 1.200 20.000 20.000 20.000 20.000 (3) Corridor Area 1.200 1.200 1.200 1.200 1.200 20.000 20.000 20.000 20.000 (C) CCW Pump Arese 0.120 0.120 0.120 0.120 0.120 2.000 2.000 2.000 2.000 (D) Mata FW Pump Areas 1.200 1.200 1.200 1.200 1.200 20.000 20.000 20.000 20.000-flan Real 1445 1500 151$ 1530 1545 1600 Eslative (E+00 :45 ) - (U+07:00) (E+07:15) (E+07 s 30) (H07 43) (E+00:00)
(A) Elect. Fenetration Areae 20.000 10.000 20.000 20.000 '20.000 20.000 (3) Corridor Area 20.000 20.000 20.000 20.000 30.000 20.000 (C) CCW Pump Areas 3.000 2.000 2.000 2,000 2.000 2.000 (D) Main FW Pump Areas 20.000 20.000 20.000 20.000 20.000 20.000 e
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bC AUX.BLDO. 2047'-6' (2ADIAt2CN L2V21.8 INDICATED Alt la R181) 3 Time Baal 0000 0013 0010 0645 - 0900 0913 0010 0045 1000 Estative (S+00s00) (5+00:13). (E+00:30)' (5600:43) (R+01:00) (5+01:3.3) (St01:30) (5+01:45) (5+02:00)
(A) Forsonnel Estch Area 4 0.002 4 0.002 < 0.002 < 0.002 < 0.002 4 0.002 < 0.002 4 0.002 4 0.002 (8) Aus 81d3 koof Area < 0.002 < 0.002 4 0.001 < 0.002 < 0.002 4 0.002 4 0.002 < 0.002 < 0.002 (C) Ctat Purge tahaust Area 4 0.002 4 0.002 < 0.002 < 0.002 < 0.002 < 0.002 < 0.002 < 0.002 < 0.001 (D) Ctat Purge Supply Area 4 0.002 4 0.002 < 0.002 < 0.002 4 0.002 4 0.002 < 0.002 ~ <- 0.002 < 0.002 (t) CR Flitration Aree < 0.002 < 0.002 4 0.002 4 0.002 4 0.002 4 0.002 4 0.002 4 0.002 4 0.001 Time Smai 1015 1030 104S 1100 1115 1130 1143 1200 1215 Ralat.1ve (5+02:13) (5+02:30) (5+02:43) (a+03:00) (5+03 s LS) (5+03:30) (3+03:43) (R+04:00) (5 t04 :15 )
(A) Personnel Eatch Area 0.125 0.123 0.125 0.800 1.400 1.400 1.400 1.400 7000.000 (B) Aus Sidg toot Area 0.001 0.002 0.002 0.002 0.002 0.002 0.002 0.002 0.100 (C) Ctat Punge Eshaust Aree 0.100 0.100 0.100 0.700 1.200 1.200 1.200 1.200 6000.000 (D) Ctat Purge Espply Area 0.100 0.100 0.100 0.700 1.200 1.200 2.200 1,200 6000.000 (E) CR Filtration Area 0.002 0.002 0.002 0.002 0.002 0.002 0.002 0.002 0.100 Time Smai 1130 1243 1300 1315 1310 1S45 1400 141S 2430 -
Relative (5904M) (E+44:45) (E+03:00) ($+05:13) (5+0$ s M) (5+03:43) (5+00:00) (E*04:15) (t+06:10)
(A) torsonnel Batch Area 0000.000 9000.000 12500.000 12300.000 $00.000 300.000 220.000 180.000 140.000 (8) Aus Sids toof Area 0.150 0.130 0.200 0.175 0.010 0.003 0.003 0,005 0.005 (C) Ctat Pusgo tahaust Area 8000.000 8000.000 10$00.000 10500.000 400.000 200.000 170.000 130.000 130.000 (D) Ctat Purge Supply Area 4000.000 4000.000 10500.000 10500.000 400.000 200.000 170.000 130.000 130.000 i (E) CA Filtration Aree 0.150 0.150 0.200 0.175 0.010 0.003 0.005 0.005 0.005 fame test 1445 1300 1515 1530 1545 1600 Ratative (5+00:43) (5+07:00) (R+07:13) (8+07 30) (5+07:45) (5+00:00)
(A) Fereonnel Esteh Area 150.000 140.000 180.000 100.000 180.000 180.000 (8) Aus Sidg toof Area 0.005 0.003 0.005 0.005 0.005 0.003 (C) Ctat Purge tahaust Area 130.000 130.000 130.000 130.000 130.000 130.000 (D) C tat. Purge Supply Area 130.000 130.000 130.000 130.000 130.000 130.000 (1) CR Filtration Mes 0.005 0.005 0.003 0.005 0.005 0.005 93-FE 7. 42 o'
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FUEL BLDO. 2000'-O' (RADIATION LIV 2La INDICATED ALE 15 E/RI) 0930 0945 1000 0413 04M 0843 0900 Time taal 0400 (9+41:00) 0913 . (5+01:50)
(5+41:15) (t+01:45) (5+02:005 Relatjye (5+00:00) (E+00:13 ) ( W s30) (E*08:43) 4 0.002- < 0.002 < 0.002 < 0.002 < 0.002
< 0.002 < 0.001 < 0.002 < 0.002 0.005 0.003 0.005 (A) Leydown Aree 0.003 0.005 0.003 0.005 0.005 (3) Best Exchange Area 0.003
'1130 1145 1200 1215 -
1034 1945 1100 1113 -
Time Real 1015 (5+03:15) (5+03s M) - (5+43:43) (B+04:00) (5+04:13)
(br02:13) (5+02:30) (5+42s45) (E+03:00)
Balative 4 0.002 < 0.001 4 0.002 < 0.002 4 0.002 4 0.002 4 0.002 4 0.002 4 0.002 0.005 0.003 0.005 0,005 (A) Lardown Area 0.003 0.005 0.003 0.003 0,003 (8) uset Eschange Area 1415 1430 1213 1334 1S43 1400 1238~ 1245 1300 (S+06s13) (E+06:303 -
Time taal (5+43s00) (5+03:13) (5+43 s M) (5+05:45) (5+06:00)
' amlatAre (5+04:30) (5944s45)
< 0.002 < 0.002 < 0.002 < 0.002 < 0.002 4 0,002 4 0.002 < 0.A02 < 0.002 0.005 0.005 0.005 0.005 (A) (mFd own Area 0,003 0 005 0.003 0.005 (s) usat tachange Ares 0.003 131S 1538 1545 1640 1645 1300 Time Rani (E+04:45) (5+07:00) (5+07:13) (5+47:30) (5+47:45) (5+44:00)
Ratatlee 4 0.002 < 0.002 < 0.002 4 0.002 < 0.002 (a) Lardown Area < 0.002 0.003 0.005 0.003 0.003 0.003 0.003 (8) Beat Eachange area i.
9 93-FE 7. 43 e'
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FUEL BLDO. 2026'-0*
(RADIATICW 1 EVE 18 INDICATED ALE 15 ElRE) 0413 0034 0643 0900 0915 0930 0945 1000 Time taal 0000 (5+00 00) (5+04 13) (5+00s M) (5+00:43) (5+01:00) (5+41:15) (5+41 H) (5+01:43) (R+01:00) salative 4 0.002 < 0.001 4 0.002 4 0.002 4 0.003 4 0.002 4 0.001 < 0.002 < 0.001 (A) Puel Sidg AC Areas 10M 104S liet 1113 1134 1143 1200 1215 Time taal 1013 (5+01sLS) (5+02:30) (5+01:43) (5+03:00) (5+03:13) (5+41 H) (5+03:43) (5+04 00) (5+04:13)
Balaties
< 0.002 < 0.001 4 0.002 < 0.002 < 0.001 4 0.001 4 0.002 < 0.001 0.024 (A) Fuel 314g AC Arose 1245 1300 1315 13M 1345 1400 141S 1430 Time taal 1234 (5+04 s M) (5+44:43) (5+03:00) (5+03:13) (5+03 H) (5+43:43) (5+06:00) (5+08:15) (5+06s30) salative 0.100 0.000 4.000 9.000 9.000 0.000 9.000 9.000 0.000 (A) Fuel lid.3 AC Areas 1445 1500 13 15 1330 1345 1608 fles seal (5+47:43) (5+04:04)
Estative (5+06:43) (5+07:00) (5:07:13) (5+07 s M) 9.000 9.000 9.000 9.000 9.000 9.000 (A) Fuel tids AC areae e
93-FE 7. 44
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n n n n so 37 r1 FUEL BLDG. 2047'-S' (RADIAT10e LEVELS INDICATED ARE IN 2/88) -
Time tant 0000 0415 0830 8000 0919 0930 0943 1000 Enlative (5+00:00) (5+00:13) (5+00 M) 0845 . (5+41:00)
(5+00:43) (B+41:13) (5+41s M) (5+01:43) (5+02:003 -
(A) Lardous Area < 0.002 < 0.002 4 0.001 < 0.002 4 0.002 4 0.002 < 0.002 < 0.002 4 0.002~ .
(5) Corridor Area 4 0.002 < 0.002 4 0.002 < 0.002 4 0.002 < 0.002 < 0.002 4 0.002 4 0.002 (C) Baergency Filtration Area 4 0.002 4 0.001 4 0.002 4 0.002 < 0.032 4 0.002 4 0.002 < 0.002 < 0.001 Time Real 1015 10M 1945 liet 1115 11M 1145 1215 Ralative (5+42s15) (5+02 s M) (5+42:43) (5+03:40) (B+4S:13) (B+03sM) (5+03:45) 1200 . (5+04:13)
(5+44:00)
(A) 1.aydcan Area 4 0.002 4 0.002 4 0.002 4 0.002 4 0.002 4 0.002 4 0.002- < 0.002 < 2.000 (B) Corridor Area < 0.002 < 0.002 < 0.002 < 0.002 4 0.002 e 0.002 4 0.002 4 0.002 's 2.000 (C) 2mergency Filtration Area 4 0.002 4 0.002 4 0.002 < 0.002 4 0.002 < 0.002 < 0.002 < 0.002 1.500 fisse Baal itse 1245 1300 1315 1320 1345 1400 1415 1450 Relative (5+44 s M) (5+44s45) (5+4Seet) (5+05:13) (5+0S s M) (5+45s45) (B+06:00) (5+46:13). (5+04:30)
(A) (Jydown Area 1.000 1.000 4.000 5.000 7.000 9.000 -9.000 - 9.000 9.000 (3) Corr 1&or Area 100.000 100.000 500.000 500.000 400.000 100.000 90.000 50.000 50.000 -
(C) Smergency filtratica Area - 1000.000 .1000.000 3000.000 5000.000 4000.000 - 1000.000-. 9000.000 5000.000 5000.000 Time Baal 1443 1500 1S15 1530 1543 1000 Relative (5+46 43) (5+47:00) (5+07:15) (5+07sM) (5+47s43) (5+00 00) d (A) 1,4fdous Area 9.000 9,000 9.000 -- 9.000 9.000 9.000' ' i (B) Corridor Area 50.0 % 30.000 50.000 50.000 50.000 S0.000 (C) Smerlency F11tration Area 50 % .000 5000.000 5000.000 5000.000 3000.000 5000.000 93-FE 7. 45 ;
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i OlESEL GEN. BLDG. 2000'-0*
(1ADIATICE L272LS INDItat3D A22 IS El55) 0845 Otes 0913 0934 0945 1000 0000 0815 0438 Time taal (5+00:43) (5+CasDel (5+01:13) (5+01:30) (E+01:45) (B+02:00)
Raiatlee (9+00ste) (5440:13) (5+00sH)
< 0.002 4 0.002 4 0.002 < 0.002 < 0.002 < 0.002 < 0.002 (A) General floor Area < 0.002 4 0.002 < 0.002 4 0.002 < 0.002 4 0.003 < 0.002 4 0.002 4 0.002 4 0.002 4 0.002 (3) General Floor Ares 1643 1200 1115 1134 1143 1200 1213 time taal 1913 1938 '
(5+02:43) (D+03:40) (5+03:13) (5+03:30) (5+03:45) (O+04:00) (5+04:13) helative (B+02:13) (5+e2s M) 4 0.002 4 0.002 4 0.002 4 0.002 4 0.002 < 0.002 < 0.002 < 0.002 *
(A) Deneral Floor Area 4 0.002 4 0.002 4 0.002 < 0.002 4 0.002 < 0.002
< 0.002 4 0.002 4 0.002 4 0.002 (5) General Floor area 1313 1336 1345 1400 1413 1638 123e 124S 1500 Time taal' (5+45:00) (9+03:13) (5+03 s M) (5+05:45) (5+46:00) (5+06 15) (B+06:30)
Relaties (5+04sM) (9644:45) 4 0.002 4 0.002 4 0.002 < 0.002 4 0.002 4 0.002 < 0.002 4 0.002 (A) General Fisor Area 4 0.002 4 0.002 4 0.002 4 0.002 < 0.002
< 0.003 < 0.002 4 0.002 < 0.002 4 0.001 (3) General Floor Area 1500 1515 13M 1543 1400 Time taal 1645 (5+47:44) (5+07s13) (9+07 38) (5+07 43) (5+teste) talative (5+e0:43) 4 0.002 < 0.002 < 0.002 < 0.002 < 0.002 < 0.002 (A) General Floor Area 4 0.002 < 0.002 < 0.002 4 0.001 4 0.002 4 0.002 (8) General Floor area 93-FE 7. 46
/
ONSITE PLUME MONITORING Time-related onsite plume monitoring data is provided in the following subsection. Radiological data is provided in the units as indicated. The data is designated by a letter and corresponds to the lettered isopleths on the map.
Count rates do not include background. Controllers should determine what the background reading is and add the value to the nepm prior to passing the ,
data to the survey team members.
Radiological data used in determining beta dose rates takes into account a beta correction factor of 4.0. Field team members will be required to calculate beta dose rates from the data passed to them.
e.g. To determine the beta dose rate at H+04:30 on isopleth line "B":
Closed. Window Reading (gamma) = 285 mR/hr -
Open Window Reading (gamma + beta) = 340 mR/hr Beta Dose Rate = 4 X (42 R/hr - 32 R/hr) = 40 R/hr Ioding and particulate count rates of air samples whose volumes differ from 20 ft should be multiplied by an appropriate factor as follows:
3 Actual Samole volume (ft 1 Sample neem at 20 ft = Sample ncpm at 20 ft" X 1 Actual Volume Iodine count rates are based on gross iodine. Iodine 131 count rate is deteomined by multiplying by the isotopic ratio of I-131 to total iodine listed under " Aux Bldg" on pages 7.2 - 7.13 for the same time period. For example, at H+04:30 for isopleth line 'B's Gross Iodine Concentration = 902 nepm/20 ft I-131 Conc. (nepm/20 ft ) = (902 nepm/20 ft ) X 4.75E+01 mC1/cc 2.09E+02 mci /cc t
= 205 ncpm/20 ft Gross particulate and lodine count rates determined with an HP-210 probe or equivalent.
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IIME ISOPLETE DIST FT. fMI) 9fEF, PARTICULATE PARTICULATE todine Iodine' Iodine XLQ CLO$ED RI R BETA R!ER SE!1 acifcc S.Eli uC1fcc h; '
1218-1330 - A S00 (0.0947) 2.97E-04 N/A 1035 N/A 27219 2.16E-07 28861 1.24E-05 7.453 (B+04:18 - 03:50) :
3 3500 (0.6629) 9.28E-06 42.028 32.329 38.795 850 6.76E-09 902 3.89E-07 0.233 -l
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OBSITE SUEFACE DEPOSITION DATA SURFACE . 100 cm2 smear l TIME ISOPLETH (mRfhr -contact. R0-21 *mRlhr - contact. 10-2 All-Timee A - -
B' -- --
W-1._, . -- , ~ , - . - - . . . - . . _ - - . . . . . , , . ..- ., . . . . . . . . - . . . ~ - . . . . - -. . . . . . . -
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SECTION 8.0 0FFSITE RADIOLOGICAL DATA Su t>s ections f_a.gg f
PLIME CONCENTRATIONS AND DOSE RATES 8.1 ,
9 93-FE 8.0 I
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PLIME CONCENTRATIONS AND DOSE RATES Time _related offsite plume monitoring data is provided in the following section. The data is presented in the units in which it would normally be available to the field teams from the instruments used to monitor the plume.
Data is presented for radiation exposure rates (open and closed window values) and for airborne concentrations of gross lodine and particulates.
The airborne iodine and particulate concentrations do not include the backcround count rate. which should be added by the controller as avorovriate.
Airborne concentrations are expressed as net counts.per minute (NCPM) per a 20 cubic foot sample. Particulate and iodine count rates are based on eross particulate and iodine activities. In determining count rates for a specife nuclide, the nuclide ratios (pages 7.1 7.21) listed under the heading ' AUX
.l' BLDG
- for the same time period as the air concentration and dose rates map of interest must be.used along with the formulas. For sample sizes other than 20 cutic feet, the concentrations should be adjusted as follows:
NCPM{ ora Actual sampig 20 f t sample x volume in ft = Adiusted NCPM from MAP I table 20
, l Data is presented as follows: -
Plume Isooleths (A. B. C. etc.): The controller should use the value for-the nearest isopleth or enould interpolate values between isopleths as appropriate.
Predesignated Monitorine Locations (XI. X2. etc.): For a field team located at a predesignated monitoring location, the controller may read the values directly from the table below the map.
Examples
- What are the dose rate and airborne lodine and particulate concentations at predesignated location X2 at time 11:307 Assume a 15 cubic feet air sample l is collected. l 93.FE 8.1 e
Solution:
~
0 1 The following values for location X2 may be read directly from the table below.
Closed window dose rate: 1655 mR/hr Open window dose rate: 2151 mR/hr ;
5 Gama dose rate: 1655 mR/hr Beta dose rates (2151-1655) mR/hr x appropriate beta correction factor for the instrument used (i.e. 4) = 1984 0
Iodine cartridge count rate (excluding background) for location X1 is 108 NCm for a 20 cubic feet sample. The corrected value fer a 15 cubic feet s. ample would therefore be:
Airborne iodine 108 x M = 81 NC m 20 0 If the count rate for the particulate filter is above the maximum' scale for the RM-141 then an R0-2 detector is used to measure the contact dose rate from the filter. If the reading is 17 mR/hr for 20 cu. ft. then i
adjustnents shall be made as follows:
Particulate concentration: 17 mR/hr x JJ, = 12. 7 5 mR / hr .
20 '
TABLE.XLS TIME ACTUAL: 12:00 ELAPSED: 6:00 Osf gas (R/Hr) PARTicuutTES . loolNEs (M9 X)Q oPEN CLOSED BFTA CPM uCDec CPM ucUce RWR E.Aa 0.25 1.4 bi-o6 33.J +0 26.954 Ii.ith 643. 6.43E-09 725. 3.12E41 0.481 AA 1.8 1.57E-06 7.110 5.470 4,563 144, 1.14E-09 153. 4.58E-08 0.039 2 MI 2 1.30E-06 5.888 4.529 S.4 35 119. 9.44E-10 126. 5.45E-06 0.033 X1 2.14 1.!!E46 5.027 3.867 4.640 102. 8.09E-10 108, 4.85E-08 0.026 K2 3.5 4.75E 07 2.151 1.655 1.986 44, 3.46E-10 46. 1.99E-08 0.012 K3 3.77 4.15E47 1.479 1.446 1.735 38. 3.021 10 40. 1.74E-08 0.010 Bs 4.3 3.27E47 1.441 1.139 1.367 30. 2.38E-10 32. 1.37E-08 0.008 K4 4.66 2.43E-07 1.282 0.986 1.183 26. 2.06E-10 23. 1.19E-08 0.007 6 MI $ 2.49E-07 1.128 0.867 1.041 2.1. 1.81E-10 24 1.04E-08 0.006 K4 5.89 1.85E47 0.838 0.644 0.773 17. 1.35E 10 18. 7.76E-09 0.005 CC 6.8 1.43E-07 0.644 0.498 0 .598 13. 1.04E-10 14. 6.00E-09 0.004 10 7.12 1.31E47 0.593 0.456 0.548 12. 9.55E 11 13. 5.40E 09 0.003 K7 8.39 9. 75E-08 0.442 0.340 0.408 9. 7.11E 11 9. 4.09E 09 0.002 Do 9.3 8.09E-08 0.366 0.282 0.338 7 $.90E-11 8. 3.39E-00 0.002 KS 9.7 7.49E-08 0.339 0.261 0.313 7. 5.46E-11 7. 3.14E-09 0.007 to hs 10 7.09E-08 0.321 0,247 0. F96 6. 5.17E.11 7. 2.97E-09 0.002 93-FE 8.2 e
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A s' 993 FIELD EXERCISE
i l
1
-1 SECTION 9.0 l
)
CONTROLLER ASSIGNMENTS AND INSTRUCTIONS I Subsections Page ASSIGNMENTS 9.1 INSTRUCTIONS 9.3 93-FE g, o
CONTROLLER ASSIGNMENTS ASSIGNMENT Frig, Lead Controller (3)
CR (Simulator) Controller CR HP/ Chemistry CR Communications CR Plant Teams (dispatched from computer room)
Security TSC Lead Controller TSC Dose Assessment TSC Rad. Assessment TSC Engineering TSC Communications OSC Lead Controller OSC Health Physics _
OSC Onsite Teams (4)
PASS Team Offsite Monitoring Teams and Joint Radiological Monitoring Teams (4)
EOF Lead Controller EOF Engineering EOF Dose Assessment EOF Rad Team EOF Communications EOF State Dose Assessment EOF State Coordination Information Clearinghouse Media Release Center
. Rumor Control - Wichita Rumor Control - KCPL 93-FE 9. 1
9 CONTR0ffM ASSIGNMENTS'(con't1 State EOC State Forward Staging Area - t Coffey County EOC The Control Room Simulator and NPIS computer will be operated by Dale Moses, Dave Fehr, and Glenn Reeves.
l 93-FE 9. 2 i
CONTROLLER INSTRUCTIONS Controller instructions define the types of interactions and conduct.
expected from controllers. The instructions included in the following subsection must be adhered to since controllers will at times have a direct input into the development of scenario activities and subsequently the success of the Exercise.
93-FE 9. 3
l CONTROLLER INSTRUCTIONS A. Controllers shall pre-position themselves in the appropriate emergency response facility no later than 30 minutes prior to the commencement of Exercise activities.
B. Controllers must comply with instructions from the Exercise Lead Controller.
C. Prior to the commencement of Exercise activities, controllers shall test telecommunications to ensure operable communication links to the Exercise Lead Controller.
D. Prior to the commencement of Exercise activities, controllers shall synchronize their watches through the Exercise Lead Controller to ensure the coordinated dispatch of time-related messages and data.
E. Controller messages, specifically scenario, onsite, offsite and public information messages, must be approved by the facility Lead Controller prior to issuance.
F. Special messages and messages designated as contingency must be approved by the Exercise Lead Controller prior to issuance.
G. Information regarding scenario events or data must only'be provided upon request from the appropriate players.
H. Information regarding scenario events or data must not be provided prior to the times noted on the message or data sheets.
I. Controllers will ensure that players do not use radios in Area 5 of the plant.
J. Exercise objectives are considered confidential information and are not to be provided to Wolf Creek participants.
93-FE 9. 4
SECTION 10.0 EVALUATOR ASSIGNMENTS AND INSTRUCTIONS Subsections Page Evaluator Assignments 10.1 Evaluator Instructions 10.4 Evaluation Checklists Evaluation Sunnary 10.5 Control Room 10.6 Security 10.8 Technical Support Center 10.9 PASS /Onsite Survey /ERDC Team 10.13 Operations Support Center 10.14 Offsite Monitoring Team and Joint Radiological Monitoring Team 10.16 Emergency Operations Facility 10.18 Information Clearinghouse / Media Release Center 10.22 Media Inquiry /Public Concern / Media Monitoring 10.24' KCP&L General Office 10.26 Emergency Operations Facility / State Dose Assessment
& Field Team Coordinators 10.27 Emergency Operations Facility / State Coordination 10.28 State EOC 10.29 State Forward Staging Area 10.30 -
Coffey County EOC 10.31 County Road and Bridge Department 10.32 Waverly School 10.33 Coffey County Ambulance 10.34 Coffey County Hospital 10.35 Host County - Lyon 10.36 Sununary of FEMA Areas Requiring Corrective Actions 10.37 Sumanary of NRC Areas Requiring Corrective Actions 10.39 Evaluation Log Sheets t
93-FE 10. 0
. . .. = . .- - - . . .
EVALUATOR ASSIGNMENTS ;
ASSIGNMENT NAME Lead Evaluator CR (Simulator) Evaluator CR HP/ Chemistry CR Communications ,
CR Plant Teams (dispatched from computer room) !
Security ,
TSC Lead Evaluator TSC Dose Assessment TSC Rad. Assessment i TSC Engineering TSC Communications OSC Lead Evaluator OSC Health Physics OSC Onsite Teams (4)
PASS Team i Offsite Monitoring Teams and Joint Radiological Monitoring Teams (4)
EOF Lead Evaluator EOF Engineering EOF Dose Assessment EOF Rad Team EOF Communications EOF State Dose Assessment EOF State Coordination I.nformation Clearinghouse Media Release Center Rumoc Control - Vichita Rumor Control - KCPL State EOC State Forward Staging Area Coffey County EOC 93-FE 10, 1 ,
EVALUATOR ASSIGNMENTS County Road and Bridge Department Waverly School Coffey County Ambulance Coffey County Hospital Host County - Lyon b
d 93-FE 10. 2
EVALUATOR ASSICMMENTS (con't)
A. Evaluators shall pre-position themselves in the appropriate emergency response facility no later than 30 minutes prior to the commencement of Exercise activities.
B. Evaluators must comply with instructions from the Exercise Lead Evaluator.
C. Prior to the commencement of Exercise activities, evaluators shall -
synchronize their watches through the Exercise Lead _ Evaluator to ensure a coordinated accounting of Exercise events and player activities.
D. Interactions with the players must be held to a minimum by all evaluators.
E. All evaluators shall take detailed notes of player activities utilizing the blank evaluation log sheets. Each evaluator should care. fully note the arrival and departure times for players, the times at which major activities or milestones occur, and any problem areas encountered.
F. Evaluation checklists for the applicable functional area should be completed by each evaluator. The completed checklists will be used to determine if the_ assigned objectives were satisfactorily demonstrated. <
G. Toward the end of Exercise activities, each facility Lead Evaluator shall distribute the attendance sheet and collect player comments.
Player comment forms are included in the facility Lead Evaluators' packets.
H. All facility Lead Evaluators shall turn in their evaluation logs and checklists to the Exercise Lead Evaluator at the controller / evaluator critique after the Exercise. The date for this critique will be I. A:1 facility Lead Evaluators shall submit a formal critique to be completed following the termination of Exercise activities. The format of the critique will be as follows:
1.) Summary of Events and Overall Evaluation 2.) Time'line of Activities 3.) List of Observations Improvement Items and Deficiencies J. The facility Lead Evaluators shall ensure that players' paperwork, logs, notification forms, etc. produced in the course of Exercise activities are turned into the Exercise Lead Evaluator during the controller / evaluator critique.
93-FE 10. 3
EVALUATOR INSTRUCTIONS Evaluation checklists are included in the following subsection.
checklists are categorized by facility or response' function and then into specific objectives to be demonstrated by that f acility or response function. The objectives provided in the checklists-correspond to the objectives to be demonstrated as idencified in the matrices in Section 2.0.
The Evaluation Summary (following the Evaluation Checklists) should list the most significant positive or negative items noted by the evaluator during the Exercise. The following definitions apply to the headings on the EVALUATION
SUMMARY
Deficiencr: A significant failure or inadequacy. It indicates that the level of emergency preparedness does not provide -
reasonable assurances that adequate protective measures can and will be taken in the event of a radiological emergency. These are addressed through KGP-1210,
" Performance Improvement Request."
Veakness: A failure or inadequacy in any WCNOC-related emergency planning procedure, program, implementation, or documentation. It indicates that the level of preparedness could have precluded effective implementation of the emergency plan in the event of an actual emergency. These are addressed through KGP-1210.
Improvement i Item An opportunity to enhance the Emergency Planning Program that, if not implemented, would not reduce the effectiveness of the Emergency Planning Program. These ]
items are below the threshold of KGP-1210 and are j tracked through the E-Plan Action Item Tracking System. j Good Practice: An item identified during drills and exercisec which !
should be continued to enhance the implementation of l the Emergency Planning Program. l l
93-FE 10. 4 l
l I
EVALUATION INSTRUCTIONS !
EVALUATION SIDMART ;
1 Evaluators l I
Assignment:
(Use additional pages as required)
POTENTIAL DEFICIENCIES: ;
POTENTIAL kT.AKNES SES :
POTENTIAL IMPROVEMENT ITEMS:
GOOD PRACTICES:
93-FE 10. 5
EVALUATION INSTRUCTIONS Evaluator:
Assignment:
Control Room Yes No N/0 N/A KRC Obiective I.1. . Accident detection and assessment
- a. Did the Shift Supervisor properly evaluate the emergency? __.
I.2. Emergency classification
- a. Was an NUE declared promptly7 ___
- b. Was an Alert declared promptly? __,
I.3. Notification of onsite and offsite emergency responders
- a. Did the CR Communicator complete.
the Immediate Notification form (Form EP 01-3.1-1) and call the appropriate personnel within applicable time limits (15 min.
for State and County; ASAP and within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for NRC);
- for the NUE7 __
- for the Alert? __,
- b. Did CR personnel promptly sound the emergency alarm and announce via GAI-tronics :
- for the NUE7 (Form EP 01-1.0-1) __
- for the Alert? (Form EP 01-1,0-2) __
- c. Were followup notifications made to the State and County every 30 minutes after the Immediate Notification? __
I.4. Communications 1
- a. Were phones and GAI-tronics operable for making notifications or trans-mitting information? ___ l l
- b. Were radios operable if phones were -
l inoperable? __
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l 93-FE 10. 6 l
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EVALUATION INSTRUCTIONS Control Room Yes No N/O Ela NRC Obiective I.S. Radiological exposure control
- a. Was CR habitability established? __,
- b. Did the Shift Supervisor authorize ,
overerpee-tre or recommend the use of KI to any WCNOC emergency worker? __
- c. Was this authorization / recommendation based on criteria in EPPs 01-9.1 and 01-9.3 and were the proper forms completed? ___
I.6. Protective action recommendations
- a. Did the Shift Supervisor include any protective action recommendation on the Immediate Notification Forms
- for the NUE7 __
- for the Alert? _ _ .
- b. If a) is "yes', were the recommendations based on the criteria in EPP 01-10.17 __
I.8. Shift staffing
- a. Was a complete Control Room shift complement available throughout the Exercise? __
)
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l 93-FE 10. 7 ;
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EVALUATION INSTRUCTIONS Evaluator:
Assignment:
Security Yes No N/O N/A NRC Obiective I.4 Communications
- a. Were the following types of communication operable during the drill?
- Phones _
- Radios _
I.7. Staff Augmentation
- a. Did Security augment the control Room staff during the emergency as required by Table 1.1-1 of the WCGS Plan? __
O 93-FE 10. 8
EVAI,UATION INSTRUCTIONS Evaluator:
Assignment Technical Suncort Center Yes No N/0 EL&
NRC Objective I.1. Accident detection and assessment
- a. When the TSC was activated was the DED aware of all significant events prior to that time? __.
- b. Did the REC promptly requess that two offsite Monitoring Tear, be dispatched? __,
- c. Did the DED convene regular managers' meetings and then update the balance of the TSC staff on the event ,
status 7 ___
- d. Did the TSC personnel actively I support the Control Room's efforts j to identify the cause of the inci-dent and mitigate it? __
determine short and long range ]
solutions to the incident 7 i
- f. Were ERDC Teams requested for dis-patch to problem areas promptly?- ___ l
- g. Were the status boards maintained regularly and accurately? __, !
I.2. Emergency classification d i
- a. Was the Site Area Emergency promptly declared by the DEDi __,
s ,
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93-FE 10. 9
2 _ . . ,_ _ _ _ . . . _ _ -
KVALUATION INSTRUCTIONS i Technical Support Center I Yes No N/0 Bj_4 NRC Obiective I.3. Notification of onsite and offsite emergency responders
- a. Did the TSC Communicator complete the immediate Notification Form (Form EP 01-3.1-1) and call the appropriate personnel within appli-cable time constraints (15 min. -
State, County; ASAP and within one hour - NRC)7 __.
NOTE: NRC communications are performed by the ENS Communicator using Form 01-3.1 2.
- b. Did the CR sound the Plant Emergency Alarm and announce, via GAI-tronics, Form EP 01-1.0-3
- for a Site Area Emergency? ._.
- c. Were followup notifications made to the State and County every 30 minutes after the Immediate Notification? .
- d. Vere the State, County and NRC l notified of TSC activation? __ l I.4. Communications
- a. Vere the following types of communication operable during )
the drill:
- ERO nones __ i
- ENS Phone __
- HPN Phone {
- PIC ringdown _
- Fax machine _
- Radios __
I.S. Radiological exposure control
- a. Did the DED authorize overexposure or recommend the use of KI to any VCNOC emergency worker? __.
93-FE 10. 10 1
1
, ___ - - _ _ .l
EVALUATION INSTRUCTIONS Technical Support Center Yes No N/0 N/A NRC Obiective
- b. Was this authorization / recommendation based on criteria in EPPs 01-9.1 and 01-9.3 and were the proper forms completed?
~
- c. Was TSC habitability established and verified at least every hour 7 ___
- Did the airlock doors remain closed? __,
I.6. Protective action recommendations
- a. Did the DED include any protective action recommendations on the Immediate Notification Forms for the SAE7 _
- b. If a. is 'yes", were these recommendations based on discus-sions with the REC and OEC7 __, ,
- c. Were PARS posted correctly on the status boards and the notification form? _
- d. Vere the PARS followed up by the DED with the County / State as to the status of their implementa-tion? _
- e. Vere Offsite Monitoring Teams aware of the PARS? _
I.7. Staff Augmentation ,
- a. Did the TSC Lugment the Control Room staff as required by Inspection Procedure 82205 and Table 1.1-1 of the VCGS Plan? ,
I
)
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1 93-FE 10. 11 I
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i EVALUATION INSTRUCTIONS ,
Je s.L No N/0 N/A NRC Obiective I.8. Shift staffing
- a. Was the TSC activated within 30 minutes after the Alert was classified? __
- b. Was a complete TSC shift comple-ment available throughout the Exercise? __
t i
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93-FE 10. 12 i
KVALUATION INSTRUCTIONS Evaluator:
Assignment:
PASS /Onsite Survev/ERDC Team Yes No N/0 N/A 4 NRC Objective ,
I I.4 Communications ,
- a. Were the radios operable? __,
I.5. Radiological exposure control
- a. Was respiratory protection required for the Team's assign-ment? __,
- b. If a. is "yes", was the proper equipment available and used? __,
- c. Were Team members supplied with !
correct range dosimetry and ;
TLDs? __,
- d. If samples were obtained, were they handled in a way to minimize exposure? __,
I.7. Staff Augmentation
- a. Did the teams augment the Control Room staff as required by Table 1.1-1 of the WCGS Plan? __
i 4
i
?
93-FE 10, 13
- -e .
- r;,-
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EVALUATION INSTRUCTIONS i l
1 Evaluator !
Assignments l
Operations Suonort Center i Yes No N/0 N/A NRC Objective ,
i Is1. Accident detection and assessment
- a. Were Onsite Survey Teams /ERDC Teams briefed on:
- radiation / contamination levels ___
i
- route to and from work area ___
- dosimetry, PC, respirator requirements ,__
- allowable doses or stay time __,
- air monitoring and radiological control requirements __
- their team identification ___
I.4. Communications
- c. Were phone communications avail-able between the OSC Supervisor's office and the TSC7 ___
I.5. Radiological exposure control
- a. Was OSC habitability established then verified every hour? __,
- b. Were the Team members issued adequate dostmetry for the radio-logical conditions they might encounter? __
- c. Was KI recommended to be taken by any Tema member? __,
- d. If c. is 'yes", was KI readily available and were the proper forms .
completed? ___
93-FE 10. 14
EVALUATION INSTRUCTIONS Operations Support Center Yes No N/0 N1A NRC Obiective 1.7. Staff Augmentation
I.8. Shift staffing
- a. Was the OSC r;ctivated within 30 minutes post-classification of the Alert? ,_,
I l
1 i
93-FE 10. 15 l
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l EVALUATION INSTRUCTIONS Evaluator:
Assignment:
Offsite Monitorinn Teams and Joint Radiological Monitoring Teams
)
Yes No N/0 N/A NRC Obiective I.4 Communications
- a. Were the vehicle radios operable? __,
I.5. Radiological exposure control )
- a. Was respiratory protection required for the Team's assign-ment? __
- b. If a. is *yes", was the proper equipment available and used? ___
- c. Were Team members supplied with correct range doolmetry and TLDs? ,
(0-500 mR and 0-5 R for WCNOC; 0-200 mR and 0-20 R for State / County) __,
- d. Were Team members briefed on:
- magnitude and composition of any actual or potential radiological releases .
- source of leak [],
- expected duration of release __
- projected or measured offsite dose rates _
- current and projected meteoro-logical conditions __.
- location.to join offsite Monitoring Team, if applicable __,
- e. Did Team members keep their exposure ALARA by moving to low background areas for counting of samples? _,_
- f. Was dostmetry checked periodically? ___
93-FE 10. 16
EVALUATION INSTRUCTIONS Offsite Monitoring Teams and Joint Radiological Monitorina Teams Yes No 1(f.0 p_f,A NRC Objective
- g. Were survey instruments used properly? ___
- h. Were personnel, equipment and vehicle checked for contamination? ___ ;
- i. Was decontamination performed properly? __.
- j. Was dosimetry checked and the readings recorded when the Team returned to the EOF 7 __
- k. Was KI available if recommended, and were the proper forms completed? __,
I.7. Staff Augmentation -
- a. Did the teams augment the Control Room staff as required by Table 1.1-1 of the :
WCGS Plan? .,_,,
FEMA Obiectives (For Joint Radiological Monitoring Teams only)
The following FEHA objectives will also be demonstrated: 1, 4, 5, 6, 8, 14.
Evaluation checklists from FEHA'lLEP-15.
" Exercise Evaluation Manual' wilj. be used.
t e
93-FE 10. 17
EVALUATION INSTRUCTIONS Evaluator:
Assignment:
Emernency Onerations Facility t
Yes No N/0 N/A NRC Objective I.1. Accident detection and assessment
- b. Did the RAM promptly request that l 4 Jo' int Radiological Monitoring Teams (JRMTs) be formed? __,
- c. Did the DEM convene regular managers' meetings and then update the balance of the EOF staff on the event status?
mitigate the incident? __
- e. Did the EOF Engineering Team work with the TSC Engineering Team to determine short, mld, and long range solutions to the incident? ___
I.2 Emergency classification
- a. Was a General Emergency promptly i declared by the DEM7 __.
I.3. Notification of onsite and offsite emergency responders
- a. Did the EOF Communicator complete the Immediate Notification Form (Form EP 3.1-1) and call the appropriate personnel within applicable time constraints'(15 min. - State County; ASAP and within one hour? - NRC7) __, .
NOTE: NRC communications are performed by the ENS Communicator using Form 01-3.1-2.
i 93-FE 10. 18 l 1
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1 l
EVALUATION INSTRUCTIONS I Emergency Operations Facility Yes No N/0 N/A ,
_NRC Obiective I
- b. Did the CR sound the Plant Emergency Alarm and announce, via GAI-tronics. Form EP 01-1.0-4
- for a General Emergency? _
- c. Were follovup notifications made to the State and County every 30 minutes? _
- d. Were the State. County and NRC notified of TSC activation? _
I.4 Communications
- a. Were the following communication lines operable:
- ERO phones _
- ENS phone _
- HPN phone _
- PIC ringdown _- _
- Fax machine _
- Radios _
I.5. Radiological exposure control
- b. Was this authorization based on criteria in EPPs 01-9.1 and 01-9.37 _
- c. Was EOF habitability established-and verified at least every hour? _
- Did the airlock doors remain closed? _
- d. Was dosimetry positioned through-out the EOF 7 _
- e. Was dosimetry checked periodically? _
93-FE 10. 19 r e- <-
- T * *- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
- _- - ~ - - - . -.
I EVALUATION TNSTRUCTIONS ,
Emarnency coerations Facility !
i Yes No N/0 N/A I NRC Objective l
I.6. Protective action recommendations
- a. Did the DCH include new protective action recommendations on the immediate Notification Form for the GE7 __
- b. If a. is "yes', were these recommendations based on:
- dose calculations, ___
J
- discussions with the RAM and IRM or ,____ ___
- automatic PARS in EPP 01-10.1 __,
- c. Were PARS posted correctly on the status boards and the notification form? __,
- e. Were changes in PARS transmitted to the State and County within 15 minutes of being made? __,
- f. Was implementation of the PARS followed up by the DEM as to the -1 status of their implementation? __,
- g. Were JRMTs aware of the current PARS? __,
I.7. Staff Augmentation
- a. Did-the EOF augment the Control Room staff as required by Table 1.1-1 of the VCGS Plan? ___
- b. Was the WCNOC Representative at the County dispatched to the County EOC7 _ _ _ .
93-FE 10. 20
EVALUATION INSTRUCTIONS Emergency Operations Facility Yes No N/0 N/A NRC Obiective I.8. Shift staffing :
- a. Was the EOF activated within 90 minutes after the Site Area Emergency classification? .
l l b. Did the EOFC have the EOF ready for activation within 60 minutes? _
- c. Was a complete EOF shift complement available through-out the exercise? _
l l
l l
I 93-FE 10. 21
EVALUATION INSTRUCTIONS Evaluator:
Assignment:
Information Clearinghouse (IC)_
and Madia Release Center (MRC)
Yes No N/O ELA NRC Obiective
. I.4. Communications a.) Were the following communication lines operable
. Facility phones? __
. PIO Ringdown? _ ;
. Fax machine? _
. Computer? __,
. Conference call to Wichita, Kansas City? _
. Media phones? __
b.) Were any wrong numbers found in the RETD 7 __
I.7. Staff augmentation a.) Was the 'C/MRC activated quickly
(<=5 minutes after arrival) after players were allowed in? __
I.8. Shift staffing a.) Was a full complement of IC/MRC players present in the facilities? ._.
b 1I.1. Activation of Emergency News Center (Joint Information Center) a.) Were prese statements reviewed by WCNOC, State and County PIDs ,
(if available) prior to their issuance? s:
b.) Were press statements approved by the DED/DEM if required? _ _ _ . ]
1 1
l l
l 93-FE 10. 22 l 1
l
EVALUATION INSTRUCTIONS Evaluator:
Assignment:
Information Clearinnhouse (IC) and Media Release Center (MRC)
Yes No N/0 N/A NRC Objective
! b.) Was up-to-date, accurate I information available from the EOF 7 __,
c.) Were news conferences well organized? __
L d.) Were unanswered questions at the news conferences followed up with'a response at a later news conference? ___
e.) Was accurate, up-to-date infonnation presented during the news conference by:
- the VC Spokesperson? . ___
- the State PIO7 (if available) __,
the County PIO7 (if available) ___
II.2. Rumor Control 1.) Did the WCPIO refute or verify I rumors quickly? ___
l 2.) Were these rumors then passed I on at the news conferences? __,
3.) Were the Wichita Information Team Supervisor and the KCP&L Rumor Control Coordinator informed of the status of I the rumor? __ l FEMA Obiectives ,
The following' FEMA objectives will also be' demonstrated: 1,2, 4, 12, 13 (shift change for IC State and County PIOS only).
Evaluation checklists from FEHA REP-15
' Exercise Evaluation Manual" will be used.
93-FE 10. 23 1
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EVAIUATION INSTRUCTIONS- ;
i Evaluators' j Assignment:
Wichita Office . Rumor Control Ibedia Inouiry Phone Teams Public Concern) ,
Yes No N/0 NLA NRC Obieet lve I.4 Communications a.) Were the following communication lines operable during the Exercise:
- Phones?
- Fax machine? "((
. Computer? _
I.7. Staff augmentation a.) Did the Wichita Rumor Control staff augment the plant emergency staff? ._.
I.8. Shift Staffing a.) Were Vichita Rttmor Control personnel notified within 30 ,
minutes of the Alert classi.
fication?
b.) Were all Rumor Control posi.
tions staffed throughout the Es.ercise? _
i II.2. Rumor Control a.) Did the Rumor Control personnel log in calls or broadcasts on the proper form? __,,_ .,_,
b.) Were questions answered according to the information available in the EPIG and released by the WCPIO7 __,
c.) Did the Phone Team return
any calls to impart further i information, if requested? __
93-FE 10, 24
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l EVALUATION INSTRUCTIONS Evaluator:
Assignment:
Wichita office - Rumor control (Media Inauiry Phone Teams Public Concern)
Yes No N/O y],A NRC Objective d.) Were any rumors passed on to the Wichita Information Team Sopervisor or Manager? ___
e.) Did the WIT Supervisor or Manager pass the rumors on to the WCPIO in the Information Clearinghouse? __
f.) Was the WIT Manager or Supervisor informed by the WCPIO as to the status of the rumor 7 __.'
g.) Were the Rumor Control personnel aware of the status of the rumor? __
t h.) Did the Information Team Assistant '
ensure approved news statements were available in a timely fashion? __
i.) Did the Information Team Assistant send news statements to the INPO network? __
FEMA Ohlectiven
- The following FEMA objective will also be demonstrated: 13.
The Evaluation checklist from the FEMA REP-15
- Exercise Evaluation Manual" will be used.
93-FE 10. 25
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EVAI.UATION INSTRUCTIONS Evaluator:
Assignment KCPEL General Office . Rumor Control Yes No N/O N/A NRC Objective I.4. Communications a.) Were the following communication lines operable during the Exercise:
- Phones? ._
. Fax machine? ._.
- Computer? _
_ News conference telecon?. __,
I.7. Staff augmentation a.) Did the KCP&L Rumor Control staff augment the plant emergency staff 7 ._.
I.8. Shift Staffing ,
a.) Were the KCP&L Rumor Control personnel notified within 30 minutes of the Alert classi..
fication? ._. _
b.) Were all Rumor Control posi-tions staffed throughout the Exercise? ,_.,
II.2 Rumor Control a.) Did the Rumor Control Coordinator (RCC) log any rumors and pass them on to the WCPIO in the IC7 ._.
b.) Was the RCC informed by the WCPIO as to the status of the rumor 7 __
c.) Were the Media Monitoring Teams
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aware of the status of the rumor? __
93.FE 10. 26 9
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EVALUATION INSTRUCTIONS Evaluator:
Assignments pnernency Operations Facility Dose Assessment & Field Team Coordinator FEMA Obiective '
The following FEMA objectives'will be demonstrated:
1,2.3,4,5,7,9, 14.
Evaluation checklists from FEMA REP-15 " Exercise Evr.luation Manual
- will be used.
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EVALUATION INSTRUCTIONS ,
Evaluator: ,
Assignment:
Emernency Operations Facility State coordination FM4A Obiective The following FEMA objectives will be demonstrated:
1, 2, 3, 4, 5, 14, 30.
Evaluation checklists from FEMA REP-15 ' Exercise '
Evaluation Manual' will be used.
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- EVALUATION INSTRUCTIONS Evaluator: '
Assignment:
State EOC
'I FEMA Obiective t h
The following FEMA objectives will be demonstrated:-
1, 2, 3, 4, 9, 10, 11, 17. ,
3 Evaluation checklists from FEMA REP-15 'Erercise Evaluation Manual' will be used, t l
93-FE 10, 29 g ( -- mw
- j EVALUATION INSTRUCTIONS
Evaluator:
Assignment:
State Fotward Staning Area FEMA Obiective .)
The following FEMA objectives will be demonstrated: I 1, 4 , 5, 14, 17, 30 (for Kansas Wildlife & Parks individual only)
Evaluation checklists from FEHA REP-15 " Exercise Evaluation Manual
- will be used.
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EVALUATION INSTRUCTIONS Evaluator
~
Assignment:
CoffeY County EOC FEMA Obiective The following FEMA objectives will be demonstrated -
1, 2, 3, 4, 5, 10, 11, 14, 15, 16, 17, 31.
1 Evaluation checklists from FEMA REP-15 " Exercise Evaluation Manual
- will be used.
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E7ALUATION INSTRUCTIONS Evaluator Assignment:
County Road and Bridge Department FEMA Obiective The following FEMA objectives will be demonstrated:
1, 2, 3, 4, 5, 14, 15, 17.
Evaluation checklists from FEMA REP-15 " Exercise Evaluation Manual
- will be used.
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EVALUATION INSTItUCTIONS Evaluator:
Assignment Waverly School FEMA Obiective The following FEMA objectives will be demonstrated:
4, 5, 14, 16.
t Evaluation checklists from FEMA REP-15
- Exercise Evaluation Manual
- will be used.
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EVALUATION INSTRUCTIONS .]
Evaluator )
Assignment: 1 l
Coffey County Ambulance :
FFMA Oblectsve
- The following FEMA objectives will be demonstrated: ,
5, 14, 20.
Evaluation checklists from FEMA REP-15 " Exercise Evaluation Manual" will be used. ,
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EVALUATION INSTRUCTIONS Evaluator:
Aseignment:
Coffey County Hospital
_FDfA _Ob tective t
The following FEMA objectives will be demonstrated:
5, 14, 21.
Evaluation checklists from FEMA REP-15
- Exercise Evaluation Manual" will be used.
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93-FE 10. 35 4
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EVAIEATION INSTR.UCTIONS Evaluator:
Assignment Host County - Lyon FFMA obiective The following FEHA objectives will be demonstrated:
1, 3 , 4 , 5, 18, 19, 22, 30.
Evaluation checklists from FEHA REP-15 " Exercise i Evaluation Manual" will be used.
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SIDMARY OF FEMA AREAS REQUIRING CORRECTIVE ACTIOff (ARCA)
State Emernency Operations Center l 1
- 1. The State EOC failed to notify the FEHA Regional Office of any emergency classification levels, protectiva actions, or status updates in accordance with state SOPS. (NUREG-0654 E.1 and E.2).
This ARCA will be addressed through the demonstration of Objective 1.
Dose Assessment / Field Team Coordination
- 2. The second shift personnel arrived at the EOF without direct-reading dosimeters. As the EOF is located near the plant' site, the second shift staff traversed the plume EPZ to arrive at the facility without the ability to determine the dose to which they may have l been exposed. (NUREG-0654. K.3.a). This ARCA will be addressed through the demonstration of Objective 5.
- 3. The plume boundries were not accurately defined because the field ,
monitoring teams were not properly directed. (NUREG-0654. I.10).
This ARCA will be addressed through the demonstration of Objective 3.
Field Monitoring Teams
- 4. County members were not dispatched as part of the Joint Radiological Monitoring Teams as required by the plan. (NUREG-0654. I.8). This ARCA will be addresLcd through the demonstration of Objectives 6 and 8.
Medis Release Center
- 5. The State PIO failed to include one subzone (E-2) in the description of the evacuated area during one media briefing. However, this l subzone had been appropriately included in the EBS message released ,
to the public. (NUREG-0654, G.3.a). This ARCA will be addressed through the demonstration of Objective 12.
Forward Staginz Area
- 6. The Kansas Department of Wildlife and Parks did not conduct a shift change in accordance with the plans. This ARCA will be addressed through the demonstration of Objective 30.
.Coffev County Hospital
- 7. The ambulance ti.rney on which the patient was transported and the covered floor area of the hospital across which the gurney traversed were not checked for contamination prior to releasing the ambulance ,
, crew. The crew was subsequently allowed to retrace their steps over the unmonitored area. (NUREG-0654, L.1; GM MS-1: FEHA-REP-14 FEMA-REP-15). This ARCA will be addressed through the demonstration of Objective 21.
93-FE 10. 37 -
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E SIMfARY OF FEMA AREAR REQUIRING CORRECTIVE ACTION ( ARCA) _
- 8. Hospital staff monitoring the ambulance did not cover the survey meter (Bicron) probe with plastic. (NURET-0654. L.1; GM MS-1; FEMA-REP-14). This ARCA will be addressed through the demonstration of Objective 21.
- 9. The hospital staff did not use the portable survey instrument.(CD V-700) earphones during monitoring. (NUREG-0654, L.1; GM MS-1: FEMA-REP-14; FEMA-REP-15). This ARCA will be addressed through the demonstration of Objective 21.
Coffey County Ambulance
- 10. One crew member touched the contaminated ground and patient's clothing prior to utilizing clean equipment, such as bandages and the blanket to wrap the patient. (NUREG-0654, L.1: GM MS-1: FEMA-REP-14). This ARCA will be addressed through the demonstration of Objective 20.
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SIDMARY & 11tc WEAKRESSES
~
- 1. Weakness 482/9119-03: failure of the licen:ee to establish and ,
maintain habitability in the emergency response facilities. Parts ,
of this weakness were closed during the 1992 Exercises'however, the l TSC airlock door did not remain closed, and so the weakness remains 1 open pending further review of the TSC habitability procedure. This weakness will be addressed by the demonstration of Objective I(5).
I
- 2. Weakness 482/9214-01: delays in making initial notifications to the State and county and in activating the group pagers. Subsequent late activation of the TSC and OSC was also part of this weakness.
This weakness cannot be closed until the next unannounced Exercise, tentatively scheduled for 1997.
- 3. Weakness 482/9213-01: the emergency classification of accident conditions was identified as a weakness during the July 1992 simulator walkthroughs. This weakness will be addressed by.the demonstration of Objective I(2).
- 4. Weakness 482/9213-02: failure of licensee to make accurate and timely notifications and protective action recommendations to offsite authorities (identified during July 1992 simulator walkthroughs). This weakness will be addressed by the demonstration of' Objectives I(3) and I(6).
- 5. Weakness 482/9213-03: failure of the dose assessment procedure to provide guidance on obtaining accurate integrated dose projections ,
based on prior release conditions (identified during July 1992
- y. simulator walkthroughs). The procedure has been revised, and this i
weakness will also be addressed by the demonstration of Objective ,
I(1).
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