ML20118A003
| ML20118A003 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 06/29/1992 |
| From: | Schreiber M WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | |
| Shared Package | |
| ML19341E248 | List: |
| References | |
| WM-92-0119, WM-92-119, NUDOCS 9207060048 | |
| Download: ML20118A003 (185) | |
Text
At ta ttunent to kH 92-0119 i
VOLP CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATION STATION i
DOCKET NO.
50-482 DiERGENCY PREPAREDNESS 1992 FIELD EXERCISE SCENARIO Prepared by:
M. A. Schreiber l
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t TABLE OF CONTENTS-INTRODUCTION 1.0 OBJECTIVES AND CUIDELINES OBJECTIVES 2.0 CUIDELINES SCENARIO AND TIMELINE SCENARIO
- 3,0 -
TIMELINE CONTROLLER MESSAGES ASSIGNMENTS 4.0-MESSAGES PLANT DATA PLANT PARAMETERS 5.0 PLANT GRAPHS C. ORE DAMAGE ASSESSMENT
-METEOROLOGICAL DATA 6.0-ONSITE RADIOLOGICAL DATA PROCESS RADIOCHEMISTRY 7.0 PROCESS MONITORS AREA' RAD 7iTION MONITORS OFFSITE RADIOLOGICAL DATA 8.0 CONTROLLER ASSIGNMENTS AND INSTRUCTIONS ASSIGNMENTS 9.0 INSTRUCTIONS EVALUATOR ASSIGNMENTS AND INSTRUCTIONS-EVALUATOR ASSIGNMENTS 10.0 EVALUATOR INSTRUCTIONS EVALUATION CHECKLISTS-EVALUATION SUDMARY 92-FE-
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l SECTION 1.0 I
i INTRODUCTION a
92-FE-
To assure that adequate mes.sures ere svallable 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 full participation of the Emergency Response Organization. which includes Site, Home Office and General Office personnel, 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 or of the time or date of the Exercise.
The exercise should demonstrate that those individuals and agencies who are assigned responsibilities in a 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.
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 necessary to properly conduct this-exercise in an efficient.and coordinated manner, and is organized as follows:
Section 2.0 05iectives and Guidelines This section defines the exercise objectives and sets forth guidelines for the conduct of the exercise to meet those objectives.
Section 3.0 Scenario and Timeline This section describes the postulated sequence of events occurring at WCGS which requires the Emergency Response Organization to respond.
Section 4.0 Controller Messages This section contains copies of the exercise messages utilized to control the development of the exercise scenario.
Section 5.0 Plant Dats This section contains time-related information concerning the postulated plant conditions, which corresponds to the development of the exercise scenario and reflects simulator responses.
To assure that adequate operational data is available in the event of a simulator failure, graphs of time-related plant parameter information have been included in this section.
Section 6.0 Meteorological Data This section contains'information and data concerning the postulated meteorological conditions in the Coffey County area which will be utilized-in the development of the exercise scenario.
92-FE 1.
1 f
Section 7.0 Onsite RadioloRical Data This section contains time-related information concerning 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 Radiolonical Data This section contains time-related in#ormation concerning radiological conditions at the various offsite monitoring locations.
Section 9.0 Controllers' Instructions This section provides general instructions to the exercise controllers in the conduct of the exercise.
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 exercise.
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 ray be distributed to key exercise participants.
92-FE 1.
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SECTION 2.0 OBJECTIVES AND CUIDELINES Subsections Page OBJECTIVES 2.1 LIST OF ABBREVIATIONS 2.2 LICENSEE 2.4 STATE 2.6 LOCAL 2.13 CUIDELINES 2.20 CORRECTIVE ACTIONS 2.22 P
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OILIECTIVES
. 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 1 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 W"NOC objectives are segregated by the facility or group which will demonstrate the objective.
Each objective for each WCNOC, State 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 indicatc it is a two part objective.
If both parts of the objective are to 'ae demonstrated. a single
- D" will appear in the facility / team column.
Lik.:wi s e, 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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LIST OF ABBREVIATIONS Amb
- Ambulance-Service CEOC_
Cof f ey County Er2rgency Operations Center CR
_ Control Room e
CRBD Coffey County Road and Bridge Department-2 D
tetive to be Demonstrated DA&FT COORD
_ Dose Assessment and Field Team Coordination EOF Emergency Operations Facility
'EOFS Emergency Operations Facility, State Dose Assessment Group Hosp Hospital I';
Information Clearinghouse i
JRMT Joint Radiological Monitoring Team KCPL GO Kansas City Power and Light General Office MED Medical s
MI Media Inquiry MM Media Monitoring MRC Media Release Center na Objective-Not Applicable to Facili_ty/ Function OMT
- Offsite Monitoring Team CSC-~
Operations Support Center-
.. PASS /ERDC Post-Accident Sampling System / Emergency Repair. Damage Control Team PC Public Concern Rad Lab Radiation Laboratory, Kansas Department of Health and Environment
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RCC Reception and Care. Center School Coffey County Schools SEC Security (WCNOC) 92-FE 2.
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-SEOC-State. Emergency-Operations-Center
-SFSA
. State. Forward Staging Area-TED To B'e Determined TSC
-Technical Support C.ter 1
Objective Not to be Den.onstrated
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1992 OBJECTIVES E!
UCNOC Group I t
O BJ ECTIVES PASS /
OMT/
IC/
KCPL (every year)
CR SEC TSC ERDC OSC JRMT EDP MRC MI PC M
C.d.
MED 1.
Accident detection and assessment D
na D
na D
na D
na na na na na na 2.
Emergency classification D
na D
na na na na na na na na na 3.
Notification of onsite and D
na D
na na na D
na na na na na na of f site emergency responders 4.
Communications D
D D
D D
D D
5.
Radiological exposure control D
na D
D D
D D
na na na na na 6.
Protective action recommendations D
na D
na na na D
na na na na na na 7.
Staff augmentation D
na na na na na na na 8.
Shift staffing D
na D
na D
na D
na na na na na na Group II ORJ ECTIVES (once every five years) l 1.
Off-hours staffing D
na D
na D
na D
na na na na na (6 p.m. to 4 a.m.)
2.
Activation of emergency news na na na na na na na
-na na na na na center (Joint Information Center) 3.
Use of fire control teams na na na na na na na na na 4.
Use of first aid and/or na na na na na na na rescue teams 5.
Use of medical support personnel na na na na na na na na na 6.
Use of licensee's headquarters na na na na na na na na na na na na support personnel s-
1992 OEJECTIVES o
7 WCNOC n
tM Group II OBJ ECTIVES PASS /
OMT/
IC/
ECPL (once every five years)
CE S EC TSC ERDC OSC JEMT EOF MEC HI PC MM G.O.
MED 7.
Use of security personnel to
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na na na na na na "ta na na na na provide prompt access for emerRency equipment and support 8.
Use of backup communications na na na na na na na na na na 9.
Rumor Control na na na na na na na na 10.
Use of emergency power (where na na na na na na na na na na na not a part of plant safety systems, e.g. TSC) 11.
Evacuation of Emergency Response na na na na na na na na na Facilities (ERFe) and relocation to backup ERFs where applic.bie 12.
Ingestion pathway exercise na na na na na na na na na na na na 13.
Field monitoring, including na na na na na na na na na na soil, vegetation and water sampling 14.
Capability for determining the na na na na na na na na na na magnitude and impact of the particular components of a release 15.
Capability for post-accident na na na na na na na na na na coolant sampling and analysis 16.
Use of potassium iodide na na na na na na na 17.
Assembly and accountability D
D D
na D
na D
na na na na na na 18.
Recovery and reentry na na na na na na na na to.
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1992 OBJECTIVES STATE l
I EOFS JRMT SFSA IC HRC RAD Ill:
OBJECTIVES SEOC EOF lDALFTCOORD 4
un HOBILIZATION OF EMERGENCT PINSONNEL Demonstratethecapabilithtoalert 1.
and fully mobilize personnel for both emergency facilities and field operations. Demonstrate the capa-na bility to activate and staff emer-i gency facilities for emergency operations.
FACILITIES - EQUIPMENT, DISPLAYS, AND VORK ENVIRONMENT 2.
Demonstrate the adequacy of facili-ties, equipment, displays, and other materials 1o support emergency na na na operations.
DIRECTION AND CONTROL 3.
Demonstrate the capability to direct na na and control emergency operations.
CDHHUNICATIONS 4.
Demonstrate the ability to communi-
.run cate with all appropriate emergency personnel at facilities and in the field.
DERGENCY WORKER EXPOSURE CONTROL 5.
Demonstrate the capability to na na continuously monitor and control na radiation exposure to emergency workers.
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1992 OBJECTIVES STATE e
EDFS OBJECTIVES SEOC
~ EOF lDAEFTCOORD JRMT SFSA IC MRC RAD LAB FIELD RADIOLOGICAL MONITORING -
AMBIENT RADIATIOL' MONITCRING 6.
Demonstrate the appropriate use of na na na na na na na equipment and procedures for deter-mining field radiation measurements.
PLUME DOSE PROJECTION' 7.
Demonstrate the capability to develop dose projections and pro-na na na na na na na tective action recommendations regarding evacuetion and sheltering.
FIELD RADIOLOGICAL MONITORING -
AIRBORNE RADIOIODINE AND PARTICULATE ACTIVITY MONITORING 8.
Demonstrate the appropriate use of na na na na na na na equipment and procedures for the measurement of airborne radiolodine concentrations as low as ?" E-7
(.0000001) microcuries pcr cubic centimeter in the presence of noble gases and obtain samples of particulate activity in the airborne plume.
PLUME PROTECTIVE ' ACTION DECISION MAKING 9.
Demonstrate the capability to make timely and appropriate protective na na na na na na action decisions (PAD).
ALERT AND NOTIFICATION
- 10. Demonstrate the capability to promptly alert and notify the public within the 10-mile plume pathway-na na na na na na na n
emergency planning zone (EPZ) and disseminate instructional messages i
to the-public on the basis of
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'ecisions by appropriat e State or local officials.
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'1992 OBJFCTIVES STATE e
E0PS l
7 OBJECTIVES SEOC EOF lDA&FTCOORD JRMT SFSA IC MFC RAD LAB 1
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PUBLIC INSTRUCTIONS AND EMERGENCY l-INFORMATION i
- 11. Demonstrate the capability to coor-i dinete the formulation and dis-l semination of accurate information na na na na na na na
-and instructions to the public.
j EMERGENCY INFORMATION - MEDLA
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- 12. Demonstrate the capability to coor-.
i dinate the development and dissemin-na na na na na na na.
ation~ of clear, accurate, and timely information to the news media.
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DfERGENCY INFORMATION - RUMOR CONTROL 1
13' Demonstrate the capability to estab-
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lish and operate rumor control'in na na na na na na ns y
a coordinated and-timely manner.
l ll IMPLEMENTATION OF PROTECTIVE ACTIONS -
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USE OF K1 POR EMERGENCY WORKERS.
INSTITUTIONALIZED INDIVIDUALS. AND THE GENERAL PUBLIC
- 14. Demonstrate the capability-and resources to implement potassium na na na na iodide-(KI) protective actions for emergency workers, institutionalized individuals. and, if-the State. plan specifies, the general-public.*
I:MPLEMENTATION OF PROTECTIVE ACTIONS -
-l SPECIAL POPULATIONS'
- 15. Demonstrate the capability and resources necessary to implement appropriate protective actions for na.
na na na na na na
.na
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m 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)1 i
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1992 OILTECTIVES STATE EOFS g
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OBJECTIVES SEOC F"" l'DALFT COORD JRMT SFSA IC MRC RAD LAB m
en IMPLEMENTATION OF PROTECTIVE ACTIONS -
SCIlOOLS
- 16. Demonstrate the capability and resources r.ecessary to implement protective actions.for school na na na na na na na na cf 1dren within the plume pathway emergency planning zone (EPZ).
l TRAFFIC AND ACCESS CONTROL
- 17. Demonstrate the organizational capability and resources necessary na na na na na na to control evacuation traffic flow and to control access to evacuated and sheltered areas.
t RECEPTION CENTER - MONITORING.
DECONTAMINATION, AND REGISTRATION
- 18. Demonstrate the adequacy of procedures, facilities, equipment, na na na na na na na na and personnel for the radiological monitoring, decontamination, and registration of evacuees.
CONGRECATE CARE
- 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 - TRANSPORTATION
- 20. Demonstrate the adequacy-of vehicles, equipment. procedures and personnel for transporting contami-nated, injured or exposed na na na na na na na na m
individuals.
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1992 OBJECTIVES STATE e
EOFS l
7 OBJECTIVES SEOC EOF DA&FT COORD JRMT SFSA IC MRC RAD LAB
- n tn MEDICAL SERVICES - FACILITIES
- 21. Demonstrate the adequacy of the equipment, procedures, supplies, and na na na na na na na na personnel of medical facilities responsible for treatment of con-taminated, injured, or exposed individuals.
EMERGENCY WORKERS. EQUIPMENT. AND VElIICLES - HONITORING AND DECONTAMINA-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 /OTIIER)
- 23. Demonstrate the capability to iuentify the need'for external 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 procedures for the collection'and na na na na na na na transportation of samples from areas that received deposition from the s
airborne plume.
l LABORATORY OPERATIONS
- 25. Demonstrate laboratory operations and procedures for measuring and na na na na na na na p
analyzing samples.
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1992 OBJECTIVES STATE e
EOFS 7
OBJECTIVES SEOC EOF lDALFTCOORD JRMT SFSA IC MRC RAD IAB s
INGESTION EXPOSURE PATHWAY - DOSE PROJECTION AND PEDTECTIVd ACTION DECISION HAKING
- 26. Demonstrate the capability to { pro-ject dose to the public] for the
[na]
na
[--]
ingestion exposure pathway and to na na na nn na recommend protective actions.
INGESTION EXPOSURE PATHWAY -
PROTECTIVE ACTION IMP 1.D(ENTATION
- 27. Demonstrate the capability to imple-ment protective actions for the na na na na na na na ingestion exposure pathway.
RECOVERY, REENTRY AND RETURN -
DECISION MAKING
- 28. Demonstrate the capability to develop. decisions on relocation.
na na na na na na re-entry, and return.
RELDCATION, RE-ENTRY AND RETURM -
IMPLEMENTATION
- 29. Demonstrate the capability to imple-I ment appropriate measures for na na na na na na relocat lon, re-entry, and rMurn.
CONTINUOUS, 24-DOUR STAFFING
- 30. Demonstrate the capability to main-tain staffing on a continuous 24-na hour' basis through an actual snift change.
OFFSITE SUPPORT N THE EVACUATION OF u
ONSITE PERSONNE1
- 31. Demonstrate the capability to pro-e" vide offsite support for the evacua-na na na na na na na na tion of onsite personnel.
1992 OBJECTIVES STATE EOFS e
_ EOF lDA&FTCOORD JRMT
OBJECTIVES SEOC m"
UMANNOUNCED EXERCISE OR DRILL'
- 32. Demonstrate the capability to carry out emergency response functions in D
D D
D na D
D na an unannounced exercise or drill.
OFF-HOURS EXERCISE OR DRILL
- 33. Demonstrate the capability to carry out emergency response functions D
D D
D na D
D
'na during an off-hours exercise or drill.
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h) 1992 O!UECTIVES am in LOCAL I
Reception & Care Centers OBJECTIVES CEOC JRHT IC MRC CRED School Amb Hosp Lyon Franklin Anderson Allen HOBILIZATION OF EMERGENCY PERSONNEL 1.
Demonstrate the capability to. alert l
and fully mobilize pers^nnel for both emergency facilities and field operations. Demons trate the capa-na na na bility to activate and staff emer-gency facilities for emergency operations.
FACILITIES - EQUIIMENT, DISPIAYS, AND WORK ENVIROM(ENT 2.
Demonstrate the adequacy of facili'-
ties, equipment, displays, and other materials to support emergency na
~~
na na na na na na na operations.
DIRECTION AND CONTROL 3.
Demonstrate the capability to direct na na na na and control emergency operations.
COtMUNICATIONS 4.
Demonstrate the ability to corranuni-cate with all appropriate emergency na personnel at facilities and in the field.
j EM]GtGENCY WORKER Elf 0SURE CONTROL 5.
Demonstrate the capability to l
continuously monitor and control na na radiation exposure to emergency F
workers.
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s 1992 OBJECTIVES e
s N
l LOCAL n
tn Reception *_ Care Centers OBJECTIVES CEOC JEMT IC PRC CRED School Amb Hosp Lyon ' Franklin Anderson Allen FIELD RADIOIAGICAL MONITORING -
AMBIENT RADIATION MONITORING 6.
Demonstrate the appropriate use of na na na na na na na na na na'
- l. na equipment and procedures for deter-l mining-fleid radiation measurements.
-l PLtME DOSE PROJECTION 7.
Demonstrate the capability to' develop dose projections and. pro-na na na na.
na na na na na na na na i
tective action recoasnendations -
regarding evacuation and sheltering.
FIELD RADIO 1AGICAL MONITORING -
AIRBORNE RADI0 IODINE AND PARTICUIATE ACTIVITY MONITORING j
8.
' Demonstrate the appropriate use of na na na na na na na na na na na-equipment and procedures for the measurement.of airborne radiolodine
' concentrations as low as 10 E-7 i
(.0000001) microcuries per cubic centimeter.In the presence of noble gases and obtain samples of l
particulate activity.'in the airborne. plume.
l PLIME PROTECTIVE ACTION DECISION MAKING l
9.
Demonstrate'the capability to make i
timely and appropriate protective-na na na na na na na na na na na na action decisions (PAD).
I i
ALERT AND NOTIFICATION
- 10. Demonstrate the capability to F
.promptly alert and notify the public
' na na na na na na
.na within the 10-mile plume pathway na na na na g
emergency planning zone (EPZ) and s
disseminate-instructional messages
'to the-public on the basis of decisions by' appropriate State or local officials.
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W 1992 OBJECTIVES g
y LOCAL Receptica & Care Centers j* 5erson Allen OBJECTIVES CEOC JRMT IC HRC CRBD School Amb Hosp Lyou Franklin PUBLIC INSTRUCTIONS AND EMERGENCY INFORMATIGN
- 11. Demonstrate the capability to coor-dinate the formulation and dis-semination of accurate information na na na na na na na na na na na 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 na na na na na ation of clear, accurate, and timely information to the news media.
EMERGENCT INFORMATION - RIMDR CONTROL
- 13. Demonstrate the capability to estab-lish and operate rumor control in na na na na na na na na na na na a coordinated and timely manner.
l IMPLEMENTATION OF PROTECTIVE ACTIONS -
USE OF KI FOR EMERGENCY WORKERS.
INSTITUTIONALIZED INDIVIDUALS, AND TIIE GENERAL PUBLIC
- 14. Demonstrate the capability and resources to implement potassium na na na na na na na iodide (KI) protective actions for emergency workers, institutionalized individuals, and, if the State plan i
specifies, the general public.*
g IMPIJMENTATION OF PROTECTIVE ACTIONS -
SPECIAL POPULATIONS
- 15. Demir strate the capability and N
+ resources necessary to implement appropriate protective actions for na na na na na na na na na na e"
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)
1992 OBJECTIVES ew l
LOCAL y
tn Reception & Care Centers OBJECTIVES CEDC JRMT IC MRC CRBD School Ash Hosp Lyon Franklin Anderson Allen IMPIJHENTATION OF PROTECTIVE ACTIONS -
SCHOOLS
- 16. Demonstrate the capability and resources necessary to implement prcatective actions for school na na na na ns na na na na na children within the plume pathway emergency planning zone (EPZ).
l TRAFFIC AND ACCESS CONTROL
- 17. Demonstrate the organizational capability and resources necessary na na na na na na na na na na to control evacuation traffic flew and to control access to evacuated and sheltered areas.
RECEPTION CENTER - MONITORING, DECONTAMINATION, AND REGISTRATION
- 18. Demonstrate the adequacy of procedures, facilities, equipment.
na na na na na na na na and personnel for the radiolog cal monitoring, decontamination, and registration of evacuees.
CONGRECATE CARE
- 19. Demonstrate the adequacy of facilities, equipment, supplies, na ns.
ne na na na na na personnel, and procedures for con-gregate care of evacuees.
MEDICAL SERVICES - TRANSPORTATION
- 20. Demonstrate the adequacy of vehicles, equipment, procedures and personnel for transporting contami-na na na na na na na na na na na nated, injured or exposed g
individuals.
e
1992 OBJECTIVES LOCAL Reception & Care Centers
. OBJECTIVES CEDC JRMT IC MRC CRBD School Amb Hosp Lyon Franklin Anderson A.llen MEDICAL SERVICES - FACILITIES
'l. Demonstrate the adequacy of the l
i equipment, procedures, supplies, and na na na na na na na na na na na personnel of medical facilities responsible for treatment of con-taminated, injured, or exposed l
Individuals.
IMERCENCY WORKERS. EQUIPMENT. AND VEHICLES - HONITORING AND DECONTAMINA-TION 4
- 22. Demonstrate the adequacy of pro-cedures for.the monitoring and decontamination of emergency na na na na na na workers, equipment, and vehicles.
SUPPLFMENTARY ASSISTANCE (FEDERAL /OTHER)
- 23. Demonstrate the capability to identify the need for external na na na na na na na na na na na na assistance and to request such assistarace from Federal or other support organizations.
POST-EMERGENCT SAMPLING 2'.
Demonstrate the use of equipment and procedures for the collection and na na na na na na na na na na na na transportation of samples from areas that received deposition from the airborne plume.
LAWRATORY OPERATIONS
- 25. Demonstrate laboratory operations N
and procedures for measuring and na na na na na na na na na na na na
[
analyzing samples.
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1992 GBJECTIVES
. N
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. *51 LOCAL t'2 l
Reception & Care Centers.
OBJECTIVES CEOC JRMT IC 15tC -
CRED School Amb Hosp Lyon Franklin Anderson Allen INGESTION EXPOSURE FiTHWAT - DOSE" PROJECTION AND PROTECTIVE ACTION -
DECISION MAKING 26'. Demonstrate the capability [to pro-ect dose to the public] for the
[na]
j ngestion exposure pathway and to na na na na na na na na na na na
'l recorrsnend protective actione'.
INGESTION EXPOSURE PA W AT -
-l PROTECTIVE ACTION IMP 1JMENTATION
- 27. Demonstrate the capability to imple-I ment protective actions for the na na na na na na na na na na na na-
-Ingestion' exposure pathway.
'r RECOVERT, REENTRT AND RETURN -
f DECISION MAKING.
1
- 28. Demonstrate the capability to develop decisions on relocation, na na na na na na na na na na na na re-entry, and return.
RELOCATION. RE-ENTET AND RETURN -
IMPLEMENTATION-
+
i 29., Demonstrate the capability to imple-ment appropriate measures for na na na na na na na na na na na relocation, re-entry..and return.
CONTINUOUS. 24-HOUR STAFFING
.[
- 30. Demonstrate the capability to main-l tain staffing on a continuous. 24-na na na
. hour basis through an actual shift change.
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0FFSITE SUPPORT FOR THE EVACUATION OF ONSITE PERSONNEL.
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31'. Demonstrate the capability to pro-vide offsite support for the evacua-
'na
.na na na na na na' na na.
na na na.
tian of onsite personnel.
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1992 ORJECTIVES y
LOCAL Reception & Care Centers OBJECTIVES CEOC JRMT IC MRC CRED School Amb Hosp Lyon Franklin Anderson:
Allen UNANMOUECED EXE3tCISE OR DRILL lna
- 32. Demonstrate the capability to carry out emerg -
cesponse functions in D
D D
D na na na na na na na' an unannouriced exercise or drill.
OFF-!!OURS EXERCISE OR DRILL
- 33. Dewnstrate the' capabi' ity t o carry I
out emergency response functions D
D D
D na na na na na na na na during an off-hours exercise or drill.
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CITIDELINES These guidelines define the participants' extent of play in demonstrating the previously listed objectives, i
A.
The Exercise will be conducted the week of August 30, 1992, i
B.
Participants will not have prio-1.nowledge of the scenario, date, or time of the Exercise.
However, they will receive a briefing ot the guidelines for the Exercise.
C.
There will be pre-staging of licensee participants in the Wolf Creek i
Generating Station (WCGS) Simulator.
A crew of operators, a Health I
Physics technician, and a Chemistry technician will be scheduled each evening during the week of August 30, to avoid having the date known in advance.
Station operators will also be pre-stageo in the computcr room next to the actual Control Room on site.
D.
The following emergency response facilities / functions will be activated during the Exercise.
1.
Licensee - Wolf Creek Nuclear Operating Corp.
a.
Control Room (CR) b.
Technical Support Center (TSC) c.
Operations Support Center (OSC) d.
Emergency Repair / Damage Control (ERDC) Teams e.
Onsite Survey Teams (OSTs), if necessary f.
Security g.
Offsite Monitoring Teams (GMTs) h.
Emergenc, Operations Facility (. EOF) i 2.
State - Kansas a,
Emergency Operations Center (SEOC) Key Personnel 3.
Local l
a.
Coffey County Emergency Operations Center (CEOC) Key Personnel E;
Extent _of participation for State and local groups:
The State and local EOCs themselves will not be activated.
Only a few l
key players from each group will go to their respective EOC, where they will demonstrate their call down procedures. Agencies notified by phone will only give the_: estimated time of arrival, but will not actually be required to come to their EOC.
F.
Notifications should be made to both the State and local groups:
initially and until the key personnel declare that they are deactivating.
The notifications to the local group (Coffey County Sheriff's dispatchers) may continue throughout the Exercise, unless the dispatcher requests that the notifications stop.
The State should not be notified at all after deactivation.
92-FE
- 2. 20 l
I
CUIDELINES G.
"rhe CR will be simulated from the plant simulator. A full shift complement of operators will staff the simulator.
H.
All communications involving the CR will duplicated in the simulator, except for the Emergency Notification System (TNS) dedicated line and the State / County radios.
A commercial telephone will be used in the J.uiulator f or the ENS.
l.
Fire protection panels (KC008) arc not duplicated on the plant simulator snd will be simulateu.
J.
'perational anc meteorologi al initial conditions will be established prior to the start of the exetcise and will be distributed to those players who would, under actual conditions, be aware of this information.
K.
Participation by onsite personnel directly 1.
alved with emergency response shall be carried out to the fullest extent possible without affecting plant operations or plant safety.
L.
The phrase, "This is a drill" will begin and end all radio and telephone transmissions performed in response to scenario events, d'
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92.FE
- 2. 21 f
(.'
CORRECTIVE AfJ10NS FOR NRC VEARNESSES PREVIOUS 1,Y IDENTIFIED
- 1) Vrakness 482/9029-01:
licensee did not augment t'ne Control Room staff when the BOP operator was called away to act as fire brigade leader.
This will be addressed by Message Number 004.
2)
Inspector Followup Item 482/9029-02:
inadequate logkeeping in the Control Room. This will be addressed by the demonstration of Objective I(4).
This item was a Followup Item f rom 1990.
3)
Weakness 482/9119-01:
manual transmission and tracking of critical plant data for the 15C was identified as an exercise weakness.
This will be addressed by Message Number 009.
- 4) Veakness 482/9119-02:
TLC management applied a nonconservative and unanticipatory approach to important technical assessments performed by TSC staff.
T'..is will be addressed by the dcmonstration of Objective I(1).
- 5) Veakness 482/9119-03:
failure of the_licensve to establish and maintain habitability in the emergency response facilities.
This will be addressed by the demonstration of Objective 1(5).
- 6) Weakness 482/9119 04:
poor coordination and control of field monitoring teams.
This will be addressed by the demonstration of Objective 1(1) and the use of a wind direction and a stability class change which will force the Dose Assessment Coordinator (TSC) and/or the. Radiological Assessment Supervisor (EOF) to redirect the field teams in order to evaluate any possible offsite release.
92-FE
- 2. 22
SECTION 3.0 SCI'.NAR10 Al D TIMEllNJU Submert ions SCENARIO Initial Conditlons 3.2
~
Narratlve Sternary 3.4 TIHELINE Sutmary 3.6 Chart 3.8 92-FE 3,
o
SclWAR10 A summary of the scenario events is provided 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.
m 92-FE 3.
1
INITIAL CONDITIONS (Page 1 of 2)
Operations i
The plant has been operating at 100% full power for the last 10 days cn the sixth cycle of a beginning of life (BOL) core.
The VCGS electrical power system is in a very high demand situation.
Plant operation is normal however, coffey County is under a tornado watch until midnight.
Maintenance work in progress is as follows:
1.
Diesel generator NE01 has been tagged out for scheduled maintenance.
2.
PZR PORV Block Valve (BB HV-8000B) is closed in accordance with Technical Specification 3.4.4 due to seat leakage on BB PCV-456A.
i 3.
"B" Ctmt Spray Pump (PEN 01B) has been out-of-service for the last six hour; for routine motor preventive maintenance.
Technical Specification 3.0.2 (72_ hour) has been entered.
Restoration expected within the next eight hours.
4 Positive Displacement Chatgirig Pump (PBG04) is out-of-service due to excessive leakage.
Restoration not expected for the next three days.
1 5.
- A' Emergency Exhaust Fan (CGG02A) has been out-of-service for the j
last 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br /> to replace the charcoal in the
'A' Emergency Filter I-Adsorber Unit The charcoal has been removed. New charcoal installation has been scheouled to start in about one hour.
6.
The PZR/RCS Liquid Sample Outer Ctmt Isolation Vulve-(SJ HV.127) is l
out-of-service for replacement of its solenoid actuator..The valve is closed with power removed in accordance with Technical l
Specification 3.6.3.
1 7.
'A' Chilled Vater Cooler (SGB01A) is out-of-service for tube inspection.
. Met eorolonical It is an overcast and humid day with winds out of the west-northwest at 10 e.ph. A tornado watch is in effect.
The ambient temperature is.70 F.
Last i
0 night. 0.10' of precipitation was recorded.
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92-FE 13.
2
{
.i
i INITIAL CONDITIONS (Page 2 of 2) i Fadlochemistry Following is the latest isotopic analysis performed on the reactor coolant system (RCS).
The analysis was performed at 0730.the day of the Exetcise.
Nuclide Activity (uCf/ce)
Kr-85m 4.4E-02
.Kr-87 4.3E-02 Kr-88 8.6E-02 Xe-133m 2.6E-02 I
Xe-133 1.3E+00 Xe-135m 7.7E-02 Xe-135 2.4E-01 Xe-138.
5.7E-02 Total Noble Gas = 1.87E+00 1-131 1.4E-02 l
I-132 7.1E-02 j
I-133 4.5E-02 i
I-134 8.3E-02 i
I-135 641E-02 l
l Total Iodines 2.74E-01
=
Cs-134 1.6E-03 I
Cs-137 8.4E-04 Cs-138 1.2E-01 Total Particulate 1.22E-01
=
I Gross Total Activity 2.27E+00
=
RCS I-131 EQUIV. IS 3.50E-02 l
r W
92-TE 3.'
3
- .u
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~ ~.
-. - - - ~
i
)
SCENARIO NARRATIVE
SUMMARY
The plant has been operating at 1002 full power for the last 10 days on the sixth cycle of a beginning of life (LOL) core.
The VCGS electrical power system is in a very high demand situation.
Plant operation is normals however, Coffey County is 2nder a tornado watch until midnight.
Several maintenance projects are in progress.
They involve the following pieces of equipment
- 1) NE01 2)
PZR PORV Block Valve (BB HV-8000B) 3)
- B' Ctmt Spray Pump (PEN 01B) 4)
PDP (PEG 04) 5)
- A' Emergency Exhaust Fan (CGG02A) 6)
P2R/RCS Liquid Sample Outer Ctmt Isolation Valve (SJ HV-127) 7)
'A' Chilled Wa'.er Cooler (SGB01A) 3ee the Initial Conditions for more detail.
At 1600, the Control Room night shift crew relieves the shift crew.
Plant operations are normal, decpite the tornado watch.
At approximately 10 minutes after the beginning of the Exercise, a 350 gpm LOCA occurs.
The exact location of the LOCA is unidentified. Ten minutes after the LOCA, the reactor trips and safety injection occurs.
The Shift Supervisor should declare an ALERT based on the loss of the reactor coolant system boundary. Offsite notifications are 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.
Because the emergency occurred during off-hours, callout of TSO/OSC and some EOF personnel begins. Accountability of personnel inside the Protected Area Boundary (PAB) also occurs at this time.
Approximately 60 minutes after the Alert has been declared, the TSC is activated.
Personnel have also begun to staff the OSC and the EOF.- The County and State will declare their EOCs activatea, and then discontinue their participation.
At one_ hour and forty minutes into the Exercise, two lightning strikes will occur almost simultaneously.
One will damage the main feeder bus between transformers 4 and 5 in the switchyards however, no fire will result.
The.
other lightning strike will drop the line to the startup transformer outside the swit chyard.
A loss of offsite power results from the damage done by the l_
lightning, t
92-FE 3.
4
Emergency diesel generator NE02 has been running since 10 minutes after the Exercise began for routine testing.
The lightning strike takes away the running Essential Service Water (ESW) pump resulting in loss of cooling water to the B-train emergency diesel generator heat exchangers.
The generator jacket water system (engine coolant) overheats, and NE02 stops running.
A loss of offsite power results, with the following ramifications for the facilities inside the protected area:
- 1) TWO VAY FM RADIO AT MET TOWER - BATTERY 2ACKUP - DWG E.0HCS16
- AT CONTROL BLDG - BATTERY BACKUP - DWG E-0MCS14 AT SECURITY - DIESEL GENERATOR - HE-CQXXX
- 2) MICROWAVE
- AT MET TOWER - BATTERY BACKUP - KGLE CONTROLLED
- AT CBX (ADti1N BLDG) - BATTERY BACKUP - DWG E-0082
- 3) FIBER OPTICS AT ADMIN BLDG / EOF - BATTERY BACKUP - DWG E-0082 AND 8025-J-00-FQ-01 AT ADMIN BLDG / BURLINGTON - PATTERY BACKUP - DWG E-0082
BATTERY BACKUP - DWG E-0082 c
I
- 5) ONSITE TELEPHONES
- 8000 SERIES NUMBERS - NO BACKUP - OFF
- 4000 SERIES NUMBERS - BATTERY BACKUP - DWG E-0002
- 6) GAITRONICS AND MAINTENANCE JACKS
- 0FF UNTIL DIESEL GENERATOL (NE02) RES? ARTS - DWGS E-11005, E-03QF01 E-03PN01. E-048-0042B 7)
POWER TO THE TSC PER DWG'S A-KAT-14 A-KAT-15. THERE IS POWER TO ALL RECEPTACLES WHEN EMERGENCY DIESEL GENERATOR IS RUNNING The turbine-driven auxiliary feedwater pumprir,also inoperabIe due to iripping on overspeed.
A SITE AREA D{KRGTNCY should{bd declared based on the loss of offsite power and loss of all onsite AC power (more than momentary).
An Exclusion Area evacuation should be simulated.
Offsite notifications should be completed.
Callout of remaining EOF personnel begins.
Protective action recommendations (PARS) should-include evacuating John Redmond Resertoir-(JRR).
A team is dispatched to repair diesel generator NE02. The generator is repaired and power is restored approximataly 2 1/2 hours into the emergency.
The EOF is activated and assumes command and_ control of the emergency, approximately.90 minutes after the declaration of the Site Area Emergency.
At about five hours after the initial LOCA, conditions are stabilized.
The 1992 Exercise will terminate at this point.
92-FE 13, 5-
1 TIMELINE
SUMMARY
JJilE FLANT EVENT
SUMMARY
H+00:00 Exercise begins.
Initial conditions given to the Control Room (Simulator) crew.
H+00:10 350 gpm LOCA occurs.
s H+00:20 Hanual reactor tript safety injection initiated.
Enter EMG E-0.
H+00:23 Transition to EMG E-1.
H+00:24 Transition to EMG ES-03.
H+00:25
- ALERT should be declared.
- Callout of TSC, OSC, and sor.e EOF personnel.
- Walkdowns and accountability begin.
H+00:27 Reenter EMG E-1 due to pressure decreasing.
H+00:32 Commence RCS depressurization to refill pressurizer.
H+00:40 Stop RCS depressurization at 18% pressurizer level.
H+01:40
- Lost offsite power due to simultaneous lightning strikes.
- Diesel generator NE02 started: NB02 energized.
H+01: 42 Turbine-driven auxiliary feedwater pump not running.
H+01:45 Diesel generator NE02 fails.
Enter EMG C-0.
H+01:50 SITE AREA DHERGENCY should be declared.
Exclusion area evacuation (simulated) should begin.
JRR evacuation FAR should be given.
H+01:53 SG depressurization begins per EMG C-0.
H+02:45 NE02 repaired and re-energized.
Stop SG depressurization.
Power restored.
- Times are only approximations based on previous simulator..uns.
92-FE 3.
6
.~. _._. -.
.__.....__.___....m__.
_,_.___.g~
+
}l+ 02 : 4 9 Transition to dig CS-02, I
r 1
11402:50 Transition to dig E-1 H+03:07 Increase auxiliary feedwater flow to max.-
Connence depressurizing SG
'C' to $RCS pressure.
H+03:20 EOF activated.
11+ 05 : 00 Exercise terminated.
t t
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M 92-FE 3,
7
_TIMELING l
(H+00:00)
Exercise begins. Initial l
conditions provided to key players.
350 gpm LOCA (H+00:10) l (H+00:20)
- Safety injection ALERT should be declared (H+00:25)
Callout of ERO based on loss of PCS personnel begins.
barrier. Walkdowns and (TSC, OSC, some EOF) accountability begin.
(H+01:25)
TSC/OSC activated.
I Two lightning strikes (H+01: 40)
. Main feeder bus between transformers 4 & 5 in switchyard damaged
- Line dropped to startup transformer outside switchyard
- Loss of offsite power (H+01:45)
Diesel generator NE02 fails, causing station blackout SITE AREA EHERGENCY should >
(H+01:50)
Callout of remaining be declared based on loss ERO personnel begins of RCS barrier and station blackout.
(H+02: 45)
Diesel generator NE02 repaired: power restored EOF activated.
(H+03:20)
(H+05:00)
Exercise termination 92-FE 3.
8
i 1
SECTION 4.0 CONTR0!.tER MESSAGES Subsections Pate ASSIGNMENTS 4.1 MESSAGES 4.2 SCENARIO 4.0-SC-01 MINI-SCEtiARIOS 4.0-MIN 1-01 i
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i 92-FE 4
0 l
ASSIGNMENTS SCFNARIO Messano 1 Time For From Location Assignment 001 H+00:00 SS CR Lead Controller CR 002c H+00:10 SS CR Lead Controller CR 003c H+00:2$
SS CR Lead Controller CR 004 H+00: 45 SS CR Lead Controller CR 00$c H+01: 40 SS CR Lead Controller CR 006c H+01:42 SS CR Lead Controller CR 007c H+01:43 SS CR Lead Controller CR 008c H+01:45 SS CR Lead Controller CR 009c H+01:50 DED TSC Lead Controller CR 010 H+01:55 All Players CR/TSC/ EOF Lead CR/TSC Controllers EOF 011 H+02:00 Operator Controller CR 012c Ht02:30 SS CR Lead Controller CR 013 H+02:55 All Players CR/TSC/ EOF Lead CR/TSC Controllers EOF 014 H+05:00 All Players Facility Controllers MINT-SCENAPIOS 1
H+00: 45 111 Reactor Operator 2
H+01: 40 Damaged Main Feeder Between Transformers 3
H+01: 41 Dropped Line to Startup Transformer 4
H+01: 42 Auxiliary Feedwater Pump Loss 3
H+01: 45 NE02 Loss 6
H+01:55 NPIS Computer Failure 7
H+00:00 NE01 Out-of-Service Maintenance 92-FE 4,
1
VISSACES A complete listing of messages included in this scenario is provided in the following subsection.
Information necessary in making and tracking message assignments is provided for each message.
The list is categorized by message type. recipient or facility, and finally by message number. A spac-for assigning controllers responsible for the message ds included.
The scenario messages are provided to instigate actions at various facilitieq. More detail for particular maintenance activities is provided in the mini-scenarios.
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l 92-FE 4.
. - _.. _ _. - - ~ _, _ _ - - _ - _
MESSAGE NO:
001 TilIS IS A DRILL 20 NOT initiate acticns affecting normal plant operations.
TO:
Shift Supervisor FROM:
CR Lead Controller 4
LOCATION:
Control Room TIME:
(H-00:10)
MESSAGE:
Initial Canuitions are as follows:
Operationally See attached forms.
Radiochemica112 Total activity - 2.27E+00 uC1/cc.
Met eorolonically It is an overcast and humid day with winds out of the west-northwest at 10 mph.
A tornado watch is in effect.
The ambient temperature is 70oF.
Last night, 0.10' of precipitation was recorded.
Additional information such as work orders in progress will also be provided at this time.
THIS IS A DRILL 92-FE 4.0-SC.
1
MESSAGE NO:
002c THIS IS A DRILL
__DO NOT initiate actions affecting normal plant operations.
TO:
Shift Supervisor FROM:
CR Lead Controller LOCATION:
Control Rooa.
TIME:
(H+00:10)
MF *
- Ar,E s A 350 gallon per minute LOCA occurs.
The reactor and turbine trip.
NOTE: This message is only provided if the simulator fails.
a THIS IS A DRILL 92 7" 4.0 5C.. l 1
( )
MESSAGE NO:
003c TIIIS IS A DRILL 29 NOT initiate actions affecting normal plant operations.
TO:
Shift Supervisor FROM:
CR Lead Controller LOCATION:
Control Room TIME:
(H+00:25)
MESSAGE:
An alert should have been declared based on the loss of one fission product barrier (RCS breach).
a NOTE:
DO NOT pass titis message without the consent of the Drill Lead Controller.
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l TIIIS IS A DRILL 92-FE-4.0 50 3
MESSAGE H0:
004 THIS IS a DRILL 20 EDT initiate actions affecting normal plant operations.
TO:
Shift Supervisor FROM:
CR Lead Controller LOCATION:
Control Room T1HE:
(H+00: 45)
MESSAGE:
The Reactor Operator has complained of having a bad case of the flu.
He has left his post and has gone to the CR bathronm to vomit.
He says he is no longer capable of manning his station and requests to be relieved.
NOTE:
Direct the person filling the Reactor Opernt.or position to leave the simulator and return to his normal work duties
-- not. related to the E. Plan Exercise. The Shift.
Supervisor should call out. a replacement. wit.hin 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per Technical Specification 6.2.2. Table 6.2 1.
See mini-scenario #1.
THIS IS A DRILL 02.FE 4.0.SC.
4
MESSAGE 110:
00$c TilIS IS A DRII.1, LQ y,07 initinte actions af f etting normal plant operations.
TO:
Shift Supervisor FR0!!:
CR Lead Controller LOCATIO!1:
Control P.com TIME:
(11+ 01 : 40)
MESSAGE:
Two lightning strikes occur almost simultaneously.
A loss of ofisite power occurs and diesel generetor 11E02 in used to supply backup power.
NOTE: This inessage is only provided if the minrulator fails.
See mini-scenarios #2 and 13.
i
- l T!!IS IS A drill 92-FE 4.0-SC-5
-... ~ ~. _ -
MESSAGE NO:
006c TilIS IS A DRILL i
J20 NOT initiate actions af f ecting normal plant operations.
N 70:
Shitt Supervisor FROM:
CR Lead Controller i
LOCATIO!!:
Control Room TIME:
(H+01:42)
MESSAGE:
1he turbine. driven auxiliary feedwater pump is not running.
NOTE: This message is only provided if the simulator falls.
See-min 1. scenario $ 5.
+
7 6
THIS IS A DRILL t
92-FE 4 C-SC.
6
. ~ -.
MESSAGE NO:
007c TIIIS IS A DRILL pg ypg initiate actions affecting normal plant operations.
to:
Shift Supervoor TRUM:
CR Lead 2)ntroller a
LOCATIOD:
Contr^1 Room TIML:
(11+ 01 s 6 3 )
HI$ SAGE:
A 'D3 2 Trouble' alarm is received.
(The Control Room should send ar. operator to the Engine Annunciater Panel in the diesel room.)
NOTE:
This message to be provided only if the simulator fails.
L I
THIS IS A DRILL 92.FE-4.0.SC.
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MESSAGE NO:
008c Ti!IS IF A DRILL DQ NOT initiate actions affecting normal plant operations.
70:
Shift Supervisor FROM:
CR Lead Controller F
',0 CATION : Control Room 11M2:
(H+01: 45)
MESSAGE:
Diesel gentietor NE02 is no longer running.
Bus NB02 is no longer energized.
t NOTE.t This message to be provided only if the simaalator f ails.
s 6
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THIS IS A DRILL 92.FE 4.0 5C.
8 l\\
- _ - --:,+.-...
HES9 AGE NO:
009e Tills IS A DRI.,
pg HEI initiate actions af f ecting normal plant operations, 70:
DED FROM:
TSC TIME:
(11401:50)
MESSAGE:
A Site Area Emertency should be declared based on a loss of all offsite power and a loss of onsite AC power (more than momentary).
N0YF:
Do not nass this message until instructed by the 1. cad Controller.
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l 7111S IS-A DRII.L I
92-FE 4.0-5C-9
- -~.
MESSAGE 110:
010 l
i Tills IS A DRILL i
29 NOT initiate actions affecting normal 1.. ant operations.
TO:
All players in CR TSC. EOF FROM:
CR/TSC/ EOF Lead Controller LOCATIO!l:
CRITSC/ EOF TIME:
(H+01:SS)
MESSAGE:
Due to unknown circumstances that are not pertinent to the cmergency, the NPIS computer screens have gone blank.
You no longer have the capability to receive data from NPIS. This situation vill continue until further notice from the Exercise controllers.
NOTE: 1) This message is intended to have facility players practice the manual transmission and tracking of data to close out an NRC weakness.
- 2) Certain screens must be left operable In the Simulator.
The data provided by these screens is accessible in the Control Room through means other than NPIS: but the Simulator can not access this dsta except through NPIS.
The applicable screens are:
- Area radiation monitors
- 3) See mini. scenario 16.
Tl!IS IS A DRILL 92-FE 4.0.SC.-10
-_. _ ~
l MESSACE NO:
011 i
THIS IS A DRII.L
_D_O,NOT initiate actions affecting normt.1 plant operations.
TO:
Operator dispatched to check Diesel Room annunicator panel FROM:
Control 1er irom Computer Room 4
LOCATION:
Diesel Room TIME:
'H+02:00 after dispatch when annunciator panel in Diesel Room is reached.
MESSAGF:
The alarm 'JV Temp High' is indicated on the annunciator panel.
NOTE: The operator should relay this message to the Control Room, who should ask for an ERDC team to investigate. See Mini-scenatio 14.
r Q
%d s
THIS IS A DRILL 92.FE' 4.0 5C. 11
MESSAGE NO:
012r THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
TO:
Shift Supervisor FROM:
CR Lead Controller i
LOCATION:
CR TIHE:
(H+02: 45)
HESSAGE:
Diesel generator NE02 has been repaired and power restored.
/
NOTE: This message is only provided if the ERDC teams do not relay the above information to the Control Rona af ter affecting repairs.
.~
e THIS IS A DRILL 92.FE 4.0.SC. 12
~ _ _.
MESSAGE NO:
013 TilIS IS A DRILL pg 32I initiate actions af f ecting normal plant operations.
TO:
All Players in CR, TSC. EOF FROM:
CR/TSC/ EOF Lead Controllers LOCATION:
CR/TSC/ EOF TIME:
(H+02:55)
MESSAGE:
NPIS is now operable and usable.
l TilIS IS A DRILL 92-FE 4.0-SC-13
.i'l
MESSAGE NO:
014 THIS IS A DRILL 29 E2I initiate actions effecting normal plant operations.
To:
All Facilities FROM:
Facility Lead Controllers 1
TIME:
(H+05:00)
MESSAGE:
The Exercise activities have been terminated.
Collect all logs, notes, etc. and give them to the Facility Lead Evaluator.
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l THIS IS A DRILL 92-FE 4.0-SC-141
- ,,,7 r
wen----we-wm#
yw a-w,w,y
MESSAGES HINI-SCENARIOS The following mini-scenarios provide ir.structions and supplementary information for controllers in the Control Room and with the Emergency Repair and Damage Control (ERDC) Teams.
The information provided in these mini-scenarios assumes that players vill 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 information to the players based on player actions.
92-FE 4.0-MINI-0
~
control Room M1ni Scenarlo il Time:
11+ 00 : 4 5 TiiE RFACTOR OPERATOR BE^0MES ILL AND MUST BE REPLACED.
Task:
The Shift Supervisor should arrange to have the sick operator replaccd in order to maintain needed crew complement.
2 Completion:
The task is complete when the ill Reactor Operator is repirced.
The task may be completed at any time, but the sick operator must be relieved within two hours in order to satisfy the requirement of Technicial Specification Section 6.2.2, Table 6.2-1.
92-FE 4.0-MINI-1
L l
Maintenance Mini Scenario #2 Time H+01:40 DAMAGED TRANSFORMERS IN SWITCHYARD Taskst During a thunderstorm, lightning strikes the bus between the 14 and #5 transformers on the east side of the switchyard.
The damage caused by the l
lightning strike causes the bus between the transformers to contact the 2
I ground potential support holding the bus.
The ground contact causes the 14 l
and 15 transformers to be disabled.
Controller actionst I' a team is dispatched to investigate the damage, View
'L' (long-range view), and View 'C" (short-range view) are to be shown to the players.
These diagrams are in a separate controller's packet.
Expected player actionst
- 1) '? sing a hack saw, it would be possible with effort to isolate and separate the two transformers' bus connections and re-energize the 14 transformer via the Athens or the REC outside lines.
(The after hours nighttime schedule for the Field Exercise may create delays ar.d result in this action not being taken.)
- 2) Eva.aate the grounded bts ac too extensive and contact KG&E line crews for support.
Completion:
This task could be completed in one hour after discovery of condition.
It may be completed anytime during the Exercise.
Caution: All E-Plan drill actions involving work in the switchyard should be sinalated f rom outside the switchyard proper.
92-FE 4.0-MINI-2
Maintenance Mini Scenario #3 Time: H+01:41 DROPPED LINE OUTSIDE SWITCHYARD Tasksi During a thunderstorm, lightning strikes the line tower just outside the switchyard.
The strike damages the tower such that the phase (two lines) on the east side of the tower drop.
The contact with earth causes a short disabling the power feed to XMROI startup transformer.
Controller actions:
If a team is dispatched to investigate the damage, View "A' is to be shown to the plcyers depicting the line drop.
The diagram is in a separate controller's packet.
Expected player actions:
Report the line drop.
Very little to b2 done other than call a line crew from KGLE, Completion:
This task vill require 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> to complete, and may be completed anytime during the Exercise.
Caution: All E-Plan drill actions involving the switchyard should be simulated and can be evaluated from outside the switchyard proper.
92-FE 4.0-MINI-3
Maintenance Mini Scenarlo 14 Time: H+01: 42 TURBINE DRIVEN AUXILIARY J'EEDWATER FUMP LOSS Tasks:
The turbine driven auxiliary feedwater pump will have tripped due to overspeed.
The Emergency Connecting Rod is sheared at the point of smallest diameter at the end of the threads (see diagram in separate controller's packet).
The mechanical cverspeed trip will have to be manually reset.
The Emergency Cornecting Rod is not available 1:
ne Varehouse, so the rod will either have to be welded for repair or expe-_ted from another source.
NOTE: The following IEC work may be in parallel with Maintenance workers reparing/ replacing the Emergency Connecting Rod.
If Turbine startup is attempted before the EG-M repair, the turbine will continue to trip on overspeed.
I&C may be called to troubleshoot the Woodward governor control system.
This is a difficult system to troubleshoot and would possibly involve several hours of reference material research and actual testing in the plant.
For the purposes of this Exercise scenario, the EG-M amplifier board output will prove to be unstable and therefore, this amplifier board should be replaced.
The failed amplifier board may be found by following the setup and calibration section (section 6) of M021-00086.
Section 6 will then give the instructions for calibrating the EG-M.
Completion:
This task will take approximately 12. hours and so will not be completed in l
time to return the turbine driven auxiliary feedwater pump to service during the Exercise.
92-FE 4.0-MINI-4
Maintenance Mini Scenario 75 Time: H+01:45 EMERGENCY DIESEL GENERATOR (EDG) NE02 Tasks:
NE02 has been running since H+00:10.
At H+01:40, the lightning strike takes away the running ESW pump, resulting in loss of cooling water flow to the B--
train EDG Heat Exchangers.
This causes the jacket water system (engine coolant) to overheat.
The diesel engine (KKJ01B) shuts down on High Jacket Water (JW) Temperature trip, resulting in NE02 output breaker opening on under-frequency.
Tne Control Room received "DG 2 Trouble" alarm when the engine shuts down.
When the operators see the engine annunciator panel in the Diesel Room,-they will see the alarm "JW Temp High."
This alarm should key the Control Room to dispatch Mechanical _ Maintenance (MMA) to investigate.
Expected Player Actions:
The repair team assessment should determine that at least two jacket water temperature switches (KJ TSH 0159 A, B, C D) have closed satisfying 2 of 4 trip logic.
This information should be given to the TSC Engineering Team.
NOTE: The 2 of 4 logic may not be switches A & B.
Any other combination will cause the trip.
The team should arrive at the conclusion that the thermostatic elements
(" power pills") in KJTCV0160 (jacket water' thermostatic control valve) should be replaced.
The correct parts and replacement procedure should be identified.
Completion:
This task will require about 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to complete; NE02 should be given back to the plant by H+02: 45.
b 92-FE 4.0-MINI-5
Kaintenance Mint-Seenario f6 Time:
H+01:55 ACTIVITIES ASSOCIATED WITH NPIS COMPUTER FAILURE Tasksi The plant computer system has stopped updating.
Computer screens will lock-up on the last display and the upper right hand corner will have a flashing-message (" Time not Updating").
Repair team investigation should find the top LAN. Bridge in computer room cabinet RJ148 has failed.
Inspection of the LAN-Bridge will show that all LEDs on back of the unit are extinguished and also the white circuit breaker bucton is
'out.'
The circuit breaker will not reset and the only possible repair is either complete LAN-Bridge replacement or module repair /
replacement within the unit.
Completion:
This task would take several hours to complete; however, NPIS will be returned as operable by H+02:55.
The reason for losing NPIS is to demonstrate a 1991 Exercise weakness for manual updating and tracking of critical plant parameters. Message #13 has been inserted in the controller messages to ensure the return of NPIS. The ERDC team performing this task should follow through all needed repair steps and simulate reporting repairs back to the Control Room.
92-FE 4.0-MINI-6
gintenance Mini Scenario 77 Time Duration of Exercise NE01 REPAIRS Tasks:
NE01 has been tagged out (inoperable) for a scheduled maintenance outage.
At H+00:00, Mechanical Maintenance (MMA) is finishing cleaning of the Lube 011 Strainer.
The status of the machine is:
Clearance is still in effect with a) Jacket Water System (engine coolant) drained b) Starting air isolation valves shut c) Starting air reservoirs depressurized d) Barring device engaged e) NE01 output breaker tagged in "open' position f) Lube oil and jacket water cooled down.
Completion:
In this state, restoration of NE01 would require approximately:
a) 2-3 hours to refill the Jacket Water System, lift the clearance and perform valve line-ups, b) 30-45 minutes to re-charge the starting air reservoirs c) 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to heat up the jacket water and lube oil systems i
i l
92-FE 4.0-MINI-7
b m
SECTION 5.0 PLANT DATA 4
Subsections Zgfa PLANT PARAMETERS 5.1 PLANT GRAPHS 5.18 CORE DAMAGE ASSESSMDfT 5.41 92-FE 5.
0 4
~
PIANT PARAMETERS Time-related plant parameters are provided in the following subsection.The data includes parameters for primary and secondary systems _that may or may not have an impact on this scenario.
The following subsection, " Plant Graphs" depicts the same data in graph form.
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.
i I
L I
92-FE 5.
1
PLANT PARAMETERS Plant Loop 1 Loop 2 Loop 3 Loop 4 Relative Time (H+00:00-00:10)
Values or A
~ or B or C or D Values Values Values Values PRIMARY SYSTEM Reactor Power (Z) 100 Reactor Vessel Level (Z) - Natural 112 Circulation Reactor Coolant System (RCS) Pressure 2294 (psig)
Pressurizer Level (Z) 61 Reactor Coolant System Temp. (OF)
T (wide-range) 559 559 559 559 g
I (wide-range) 618 618 618 618 g
TAVG (narrow-range) 589 589 589 589 Core Exit Thermocouple Temp. (OF) 600 Reactor Coolant Loop Flows (Z) 100 100 100 100 Boron Concentration (ppm) 1140 SECONDARY SYSTEMS 6
Main Steam Flow Rate (x10 lbm/hr) 3786 3786 3786 3786 Steam Generator (WR) Levels (Z) 66 66 66 66 l
l Steam Generator Pressures (psig) 490 990 990 990 I
CONTAINMENT BUILDING Pressure (psig) 0 l
Temperature (OF) 80 Humidity'(Z) 33 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 Vater Storage Tank Level (Z) 97 92-FE 5,
2
PLANT PARMG'TERS-Plant Loop 1 Loop 2 Loop 3 Loop 4-Relative Time (H+00:10)
Values or A or B or C or D Values Values Values values PRJMARY S'lSTEM Reactor Power (2) 100 Reactor Vessel Level (2) - Natural 112 Circulation Reactor Coolant System (RCS) Pressure 2290 (psig)
Pressurizer Level (2) 60 Reactor Coolant System Temp. (OF)
T (wide-range)
$59 559 559 559 C
T (vide-range) 618 618 618 618 H
TAVG (narrow-range) 589 589 589 589 Core Exit Thermocouple Temp. (OF) 600 Reactor Coolant Loop Flows (Z) 100 100 100 100 Baron Concentration (ppm) 1140 SECONDARY SYSTEMS Main Steam Flow Rate (x10 lbm/hr) 3786 3786 3786 3786 Steam Generator (WR) Levels (%)
66 66 66 66 Steam Generator Pressures (psig) 990 990 990 990 CONTAINMENT BUILDING Pressure (psig) 0 Temperature (OF) 80 Humidity (%)
33 Hydrogen Concentration (
vol) 0 Recirculation Sump Level (in) 0 TARKS Accumulator Levels (Z) 59 59 59 59 Accumulator Pressures (psig) 645 645 645 645 Refueling Water Storage Tank Level (:)
97 92-FE 5.
3
Pl. ANT PARAMETERS Plant Loop 1 Loop 2 Loop 3-Loop 4 Relative Time (H+00:20)
Values or A or B or C or D l
Values Values Values Values PRIMARY SYSTEM Reactor Power (2) 0.1 Reactor Vessel Level (2) - Natural 100 Circulation Reactor Coolant System (RCS) Pressure 2010 (psig)
Pressurizer Level (2) 11 Reactor Coolant System Temp. (OF)
T (vide-range) 557 557 557 557 C
T (v e-range) 618 618 560 560 H
TAVG (narrow-range) 588 588 559 559 Core Exit Thermocouple Temp. (OF) 560 100 100 100 100 Reactor Coslant Loop Flows (:)
Boron Concentration (ppm) 1140 SECONDARY SYSTEMS 6
Main Steam Flow Rate (x10 lbm/ar) 107 110 109 137 Steam Generator (WR) Levels ( )
44 44 44 44 Steam Cenerator Pressures (psig) 1095 1095 1095 1095 CONTAINMENT BUILDING Pressure (psig) 1.3 Temperature (OF) 95 Humidity (:)
98 4
Hydrogen Concentration (2 vol) 0 Recirculation Sump Level (in) 0
_ TANKS 59 59 59 59 Accumulator Levels (2)
Accumulator Pressures (psig) 645 645 645 645 Refueling Water Storage Tank Level ( )
97 92-FE 5.
4
PLANT PARAMFTERS Plant Loop 1 Loop 2 Loop 3 Loop 4 Relative Time (H400:30)
Values or A or B or C or D Values Values Values Values PRIHARY SYSTEM Reactor Power (Z) 0 Reactor Vessel Level (2) - Natural 100 Circulation
+
Reactor Coolant System (RCS) Pressure 1974 (psig)
Pressurizer Level (I) 10 Reactor Coolant System Temp. (OF)
T (wide-range) 557 557 557 557 C
T (vide-range) 558 558 558 558 H
TAVG (narrow-range) 558 558 558 558 Core Exit Thermocouple Temp. (OF) 558 Reactor Coolant Loop Flows (2) 100 100 100 100 Boron Concentration (ppm) 1214 SECONDARY SYSTEMS 6
Main Steam Flow Rate (x10 lbm/hr) 91 91 84 80 Steam Generator (WR) Levels (:)
50 50 50 50 Steam Generator Pressures (psig) 1089 1089 1089 1089 CONTAINMENT BUILDING Pressure (psig) 1.6 l
Temperature (OF) 98 Humidity (I) 98 Hydrogen Concentration (2 vol) 0 Recirculation Sump Level (in) 0 TANKS Accumulator Levels ()
59 59 59 59 l
Accanulator Pressures (psig) 645 645 645 645 Refueling Water Storage Tank Level (%)
96 92-EE 5,
5
PLANT PARAMETERS Plant Loop 1 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
-1 i
Reactor Power (Z) 0 Reactor Vessel Level ( ) - Natural 99 Circulation i
Reactor Coolant System (RCS) Pressure 1365 (psig)
Pressurizer Level (I) 0 Reactor Coolant System Temp. (OF)
T (wide-range) 540 540 540 540 C
T (wide-range) 541 541 541 541 g
TAVG (narrow-range) 541 541 541 541 Core Exit Thermocouple Temp. (OF) 541 Reactor Coolant Loop Flows (Z) 100 100 100 100 Boron Concentration (ppm) 1257 SECONDARY SYSTEMS 6
Main Steam Flow Rate (x10 lbm/hr) 34 26 0
33 Steam Generator (WR) Levels (!)
61 61 61 61 Steam Generator Pressures (psig) 959 959 959 959 CONTAINMENT BUILDING Pressure (psig) 1.7 Temperature ( F) 99 Humidity ( )
98 Hydrogen Concentration (2 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 (I) 95 92-FE 5.
6
PLANT PARAMETERS Plant Loop 1 Loop 2 Loop 3 Loop 4 Relative Time (H+01:00)
Values or A or B or C Values or.D Values Values Values
-PRIMARY SYSTEM Reactor Power (2) 0 Reactor Vessel Level (I' - Natural 34 Circulation Reactor Coolant System (RCS) Pressure 1444 (psig)
Pressurizer Level (Z) 51 Reactor Coolant System Temp. (OF)
T (wide-range) 505 505 505 510 C
T (wide-range) 507 507 507 514 g
TAVG (narr w-range) 530 530 530 530 Core Exit Thermocouple Temp. (OF) 514 Reactor Coolant Loop Flows (2) 0 0
0 100 Boron Concentration (ppm) 1424 SECONDARY SYSTEMS Main Steam Flow Rate (x10 lbm/hr) 0 0
44 0
Steam Generator (WR) Levels (Z) 69 68 68 63 Steam Generator Pressures (psig) 734 734 734 734-CONTAINMENT BUILDING Pressure (psig) 1.4 Temperature (OF) 95 Humidity (I) 98 Hydrogen Concentration ( vol) 0 Recirculation Sump Level (in) 0 TANKS Accumulator Levels (!)
59 59 59 59 Accumulator Pressures (psig) 645 645 645 645 Refueling Water Storage Tank Level (I) 93 92-FE 5,
7
?LANT PARAMETERS j
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 (!)
0 Reactor Vessel Level (I) - Natural 34 Circulation J
Reactor Coolant System (RCS) Pressure 1589 (psig)
Pressurizer Level (Z) 64 Reactor Coolant System Temp. (OF)
T (wide-range) 507 507 507 511 C
T (wide-range) 508 508 508 514 g
TAVG (""## "'
""8' Core Exit Thermocouple Temp. (OF) 515 Reactor Coolant Loop Flows (2) 0 0
0 100 Boron Concentration (ppm) 1579 SECONDARY SYSTEMS 6
Main Steam Flow Rate (x10 lbm/hr) 0 0
40 0
Steam Generator (WR) Levels (2) 70 70 70 64 Steam Generator Pressures (psig) 737 737 737 737 CONTAINMENT BUILDING Pressure (psig) 1.4 Temperature (OF) 95 Humidity (I) 98 Hydrogen Concentration (2 vol) 0 3ecirculation Sump Level (in) 0 TANKS Accumulator Levels (I) 59 59 59 59 Accumulator Pressures (psig) 645 645 645 645 Refueling Water Storage Tank Level (!)
91 92-FE 5.
8
PLANT PARAMETERS Plant Loop 1 Loop 2 Loop 3 Loop 4 Relative Time (H+01:30)
Values or A or B-or C or D Values Values Values Values fRIMARY SYSTEM Reactor Power (2) 0 Reactor Vessel Level (2)
Natural 34 Circulation Reactor Coolant System (RCS) Pressure 1556 (psig)
.)
Pressurizer Level (2) 64 Reactor Coolant System Temp. ( F)
T (vide-range) 503 503 503 507 C
T
"' *~##"E*'
~
H T4yg (narrow-range) 530
$30 510 530 Core Exit Thermocouple Temp. (OF) 511 Reactor Coolant Loop Flows (2) 0 0
0 100 Boron Concentration (ppm) 1597 SECONDARY SYSTEMS Main Steam Flow Rate (x10 lbm/hr) 0 0
34 0
Steam Generator (VR) Levels (2) 70 69 70 63 Steam Generator Pressures (psig) 713 713 713 713 CONTAINMENT BUILDING 1
l Pressure (psig) 1.4 Temperature (OF) 95 l
Humidity (2) 98 Hydrogen Concentration (2 vol) 0 Recirculation Sump Level (in) 0 TANKS l
l Accumulator Levels (2) 59 59 59 59 Accumulator Pressures (psig) 645 645 645 645 Refueling Water Storage Tank Level (2) 90 92-FE 5.
9
ZbAN7 PARAMETERS Plant Loop 1 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 CYSTTU Reactor Power (2) 0 Reactor Vessel Level (2) - Natural 32 Circulation Reactor Ooolant System (RCS) Pressure 1484 (psig)
Pressurizer Level (I) 64 Reactor Coolant System Temp. (OF)
T (vide-range) 505 505 505 506 C
T (wide-range)
$22 522 522 522 g
TAVG (narrow-range) 530 530 530 530 Core Exit Thermocouple Temp. ( F) 517 Reactor Coolant Loop Flows (Z) 0 0
0 0
Boron Concentration (ppm) 1614 SECONDARY SYSTEMS 6
Main Steam Flow Rate (x10 ILm/hr) 0 0
32 0
Steam Generator (WR) Levels (Z) 69 68 69 67 Steam Generator Pressures (psig) 737 737 737 737 CONTAINMENT BUILDING Pressure (psig) 2.2 Temperature (OF) 113 Humidity (I)
Hydrogen Concentretion (2 vol) 0 Recirculation Sump Level (in) 0 TANKS Accumulator Levels (2) 59 39 59 59 Accumulator Pressures (psig) 645 645 645 645 Refueling Water Storage Tank Level (:)
89
- Station blackout - gauge automatically goes to zero 92-FE 5, 10
PI. ANT PARAMETERS Plant Loop 1 Loop 2 Loop 3 Loop 4-Relative Time (H+02:00)
Values or A or B or C or D Values Values Values 1 values i ~.
IRIMARY SYSTEM Reactor Power (2) 0 Reactor Vessel Level (2) - Natural 31 Circulation Reactor Coolant System (RCS) Pressure 1068 (psig)
Pressurizer Level (I) 30 Reactor Coolant System Temp. ( F)
T (vide-range) 522
-522 522 527 C
T (vi e-range) 557 557 558 558 H
TAVG (na r w-range)
O Core Exit Thermocouple Temp. ( F) 547 Reactor Coolant Loop Flows (2) 0 0
0 0
Baron Concentration (ppm) 1614 SECONDARY SYSTEMS Main Steam Flow Rate (x10 lbm/hr) 436 151 434 432 Steam Generator (WR) Levels (%)
67 67 67 65 Steam Generator Pressures (psig) 857 863 864 887 CONTAIRMENT BUILDING Pressure (psig) 3.5 Temperature (OF) 124 Humidity (I)
Hydrogen Concentration (! vol) 0 Recirculation Sump Level (in) 0 TAKKS i
i L
Accumulator Levels (!)
59 59 59 59 Accumulator Prescures (psig) 545 645 645 645 I
Refueling Water Storage Tank Level (I) 89
- 5. 11
PLANT PARAMETERS Plant Loop 1 Loop 2 Loop 3 Loop 4 Relative Time (H+02:15)
Values or A or B or C or D valus Values values values PRIMARY SYSTEM Reactor Power (2) 0 Reactor Vessel Level (%) - Natural 30 Circulation
-2 Reactor Coolant System (RCS) Pressure 711 (psig)
Pressurizer Level (2) 0 Reactor Coolant System Temp. (OF)
T (wide-range) til 411 502 408 C
T (wide-range) 476 476 407 476 y
TAVG (narrow-range) 530 530
$30 530 Core Exit Thermocouple Temp. (OF) 462 Reactor Coolant Loop Flows (2) 0 0
0 0
Baron Concentration (ppm) 1614 EECONDARY SYSTEMS 6
Main Steam Flow Pate (x10 lbm/hr) 31 71 188 31 Steam Generator (VR) Levels (%)
48 48 64 46 Steam Generator Pressures (psig) 398 396 907 388 CONTAINMENT BUILDING Pressure (psig) 4 Temperature (OF) 128 l
Humidity (!)
l Hydrogen Concentration (% vol) 0 Recirculation Sump Level (in) 0 j
TANKS Accumulator Levels (2) 59 59 59 59 l
Accumulator Pressures (psig) 645 645 645 645 Refueling Water Storage Tank Level (%)
8!
(
- Station blackout - gauge automatically goes to zero 92-FE
- 5. 12 l
PLANT PARAMETE2S Plant Loop 1 Loop 2 Loop 3 Loop 4 Relative Time
(.9+ 02 : 3 0 )
Values or A or B or C or D Values Values Values Values PRIHARY SYSTEM Reactor Power (2) 0 Reactor Vessel Level (2) - Natural 25 Circulation i
Reactor Coolant System (RCS) Pressure 307 (psig)
Pressurizer Level (Z) 0 Reactor Coolant System Temp. (OF)
T (wi e-range 18 318 424 319 C
T (wide-range) 380 380 424 358 H
Tgyg (narrow-range) 530 530 530 530 Core Exit Thermocouple Temp. (OF) 354 Reactor Coolant Loop Flows (Z) 0 0
0 0-Baron Concentration (ppm) 1614 SECONDARY SYSTEMS Main Steam Flow Rate (x10 lbm/hr) 21 21 0
65 Steam Generator ('w'R) Levels (2) 13 14 63 12 Steam Generator Pressures (psig) 67 68 901 65 CONTAINMENT BUILDING Pressure (psig) 3.8 Temperature ( F) 128 Humidity (I)
Hydrogen Concentration (2 vol) 0 Recirculation Sump Level (in) 0 TANF.S Accumulator Levels (I) 59 59 59 59 Accumulator Pressures (psig) 645 645 645 645 Refueling Water Storage Tank Level (I) 89
- Station blackout - gauge automatically goes to zero 92-FE
- 5. 13
L jf
^^
l PLANT PARAMETERS Plant Loop 1 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 (2) 0 Reactor Vessel Level (:) - Natural 24 Circulation Reactor Coolant System (RCS) Dressure 131 (psig)
Pressurizer Level (I) 0 Reactor Coolant System Temp- (OF)
T (vide-range) 296 296 152 277 C
T (wide-range) 335 335 349 335
?gyg (narrow-range) 530 530
$30 530 Core Exit Thermocouple Temp. (OF) 322 Reactor Coolant Loop Flows (%)
0 0
0 0
Boron Concentration (ppm) 1664 SECONDARY SYSTEMS 6
Main Steam Flow Rate (x10 lbm/hr) 31 31 20 65 Steam Generator (WR) Levels (Z) 5 6
64 4
Steam Generator Pressures (psig) 90 90 894 93 CONTAINMENT BUILDING Pressure (psig) 3.4 Temperature (OF) 127 Hamidit y' ( 2 )
Hydrogen Concentration (2 vol) 0 Recirculation Sump Level (in) 0 TANKS Accumulator Levels (%)
59 59 59 59 Accumulator Pressures (psig) 645 645 645 645 Refueling Water Storage Tank Level (I) 88
- Station blackout - gauge automatically goes to zero 92-FE
- 5. 14
PLANT PARAKETERS Plant Loop 1 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 (I) - Natural 31 Circulation i
Reactor Coolant System (RCS) Pressure 388 (psig)
Pressurizer Level ( )
100 Reactor Coolant System Temp. (OF)
T
"' "'#8"E*'
~
C T
(vide-range) 330 330 330 330 g
T VG (narrow-range) 530 530
$30 530 Core Exit Thermocouple Temp. (OF) 323 Reactor Coolant Loop Flows (I) 0 0
0 0
Boron Concentration (ppm) 1863 SECONDARY SYSTEMS 6
Main Steam Flow Rate (x10 lbm/hr) 30 30 20 50 Steam Generator (WR) Levels ( )
11 6
64 11 Steam Generator Pressures (psig) 74 92 887 71 CONTAINMENT BUILDING l
Pressure (psig) 2.6 Temperature (OF) 120 Humidity (I)
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 Refueling Water Storage Tank Level (I) 83
- Station blackout - gauge automatically goes to zero 92-FE
- 5. 15
PLANT PARAMFTPIS Plant Loop 1 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 (2) 0 Reactor Vessel Level (2) - Natural 32 Circulation Reactor Coolant System (RCS) Pressure 317 (psig)
Pressurizer Level ( )
100 Reactor Coolant System Temp. (OF)
T
'#""E"
~
C T
(vide-range) 352 352 352 352 y
TAgg (narrow-range) 530 530
-530 530 Core Exit Thermocouple Temp. ( F) 344 Reactor Coolant Loop Flows (2) 0 0
0 0
Boron Concentration (ppm) 1863 SECONDARY SYSTEMS 6
Main Steam Flow Rate (x10 lbm/hr) 35 35 25 55 Steam Generator (WR) Levels (?)
30 6
43 30 Steam Generator Presstres (psig) 118 124 89 116 CONTAINMENT BUILDING Pressure (psig) 2.3 Temperature (OF) 117 Humidity (Z)
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 (2) 83
- Station blackout - gauge automatically goes to zero 92-FE
- 5. 16
PLANT PARAMETERS Flant Loop 1 Loop 2 Loop 3 Loop 4 Relative Time (H+03:30+)
Values or A or B or C or U Values Values Values Values PRIMARY SYSTEM Reactor Power (2) 0 Reactor Vessel Level (2) - Natural 31 Circulation Reactor Coolant System (RCS) Pressure 241 (psig)
Pressurizer Level (2) 80 Reactor Coolant System Temp. (OF)
T
("
"'#8"E
~
C T
(wide-range) 371 371 372 371 g
Tgyg (narrow-range) 530 530 530 530 Core Exit Thermocouple Temp. (OF) 363 Reactor Coolant Loop Flows (Z) 0 0
0 0
Boron Concentration (ppm) 1863 SECONDARY SYSTEMS 6
Main Steam Flow Rate (x10 lbm/hr) 35 35 25 55 Steam Generator (WR) Levels (t) 46 6
44 46 Steam Generator Pressures (psig) 118 159 161 117 CONTAINMENT BUIt'. ;NG Pressura (psig) 2.0 Temperature (OF) 115
=
Humidity (2)
Hydrogen Concentration (
vol) 0 Recirculation Sump Level (in) 0 TANKS Accumulator Levels ( )
59 59 59 59 Acewmulator Pressures (psig) 645 645 645 645 Refueling Water Storage Tank Level (Z) 83
- Station blackout - gauge automatically goes to zero l
92-FE
- 5. 17
Pl. ANT GRAPHS
' lime-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.
These graphs may be used as a sottrce of data for Control Room (CR) operators, by the CR Lead Controller, in case of Simulator failure, i
e 92-FE
- 5. 18
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- 5. 20
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CORE DAMACK ASSF.SSMENT A precalculated core inventory 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.
(
92-FE
- 5. 41
_ ~ _,
4 C0_RE DAMAGE ASSESSMENT CORE INVENTORY Corrected Fuel Pellet Nuclide Inventory (Cl)
KR-83M 1.48E+07 KR-85M 4.62E+07 KR-85 1.46E406 KR-87 8.32E+07 KR-86 1.14E+08 XE-133H 4.93E+06 XE-133 2.00E408 XE-135M 5.55E407 XE-135 1.91E+08 XE 133 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 TE-132 2.30E+08 CS-134 3.70E+07 CS-137 1.80E407 CS-138 7.01E+07 LA-140 2.93E+08 LA-142 3.00E+07 BA-140 2.70E+08 92-FE
- 5. 42
CORE DAMAGE ASSESSKKKT Assumptiora.
1.
Clad gap activities can be assumed to be 10.0% of fuel pellet activity for all isotopes except ER-85 which is 30!
i of core activity.
I 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.
i 1
Results:
Core damage should be assessed at less than.012 clad damage and no fuel overtemperatures.
i
{
92-FE
- 5. 43 I
I I
i SECTION 6.0 METEOROLOGICAL DATA I
f f FE 6.
0
HETE0_R0[,0GICA!. DATA (NPIS Met. Data Read Out)
Time Relative (HRS:HIN)
(H+00:00)
(H+00:15)
(H+00:30)
(H+00:45)
Wind Speed (ml/hr) i 10m 9.2 9.9 10.3 9.3 35m 9.6 10.2 10.5 9.9 60m 11.0 10.5 10.9 10.0 Wind Direction (Deg)
(from) 10m 304 298 304 297 35m 310 305 307 300 60m 311 312 309 305 Wind !>1rection Var. (Deg) 10m 16.9 16.8 15.9 15.8 60m 14.3 14.2 13.7 13.6 Vert. Temp. Dif f. (Dog F)10-35m
-0.8
-0.8
-0.8
-0.8 10-60m
-1.0
-1.0
-1.0
-1.0 10-85m
-1.1
-1.1
-1.1
-1.1 Dew Point (Deg F) 10m 68 70 70 70 Ref. Temp. (Deg F) 10m 70 70 70 72 Precipitation (Inches) 0.1 0.1 0.1 0.2 Stability Class D
D D
D 92-FE 6.
1
. _ ~. ~.
METE 0E01,0GICAI, DATA (NPIS Het. Data Read Out)
Time Relative (HRS HIN)
(H+01:00)
(H+01:15)
(H+01:30)
(;i+ 01: 4 5)
Wind Speed (ml/hr) 10m 11.2 10.5 9.7 10.1 35m 11.3 11.1 10.1 10.5 60m 12.0 11.3 10.4 10.5 Wind Direction (Deg)
(from) 10m 300 304 301 295 35m 302 309 311 305 60m 306 312 311 306 Wind Direction Var. (Deg) 10m 15.8 16.2 16.3 16.1 60m 13.5 14.0 13.9 14.1 Vert. Temp. Diff. (Deg F)10-35m
-0.8
-0.8
-0.8
-0.8 10-60m
-1.0
-1.0
-1.0
-1.0 10-85m
-1.1
-1.1
-1.1
-1.1 Dew Point (Deg F) 10m 70 70 72 72 Ref. Temp. (Deg F) 10m 72 72 72 72 Precipitation (Inches) 0.2 0.2 0.2 0.2 Stability Class D
D D
D 92-FE 6.
2
- _ ~. _. -..
hETEOR01.OGICAI, DATA (NPIS Het. Data Read Out)
Time Relative (HR' HIN)
(H+02:00)
(H+02:15)
(H402:30)
(H+02:45)
Vind Speed (mi/hr) 10m 10.8 9.5 8.7 9.1 35m 10.9 10.1 9.1 9.5 60m 11.8 10.3 9.4 9.5 Wind Direction (Deg)
(from) 10m 310 3' 4 316 305 35m 320 s27 329 323 60m 350 356 358 350 Wind Direction Var. (Deg) 10m 15.9 16.0 15.7 15.8 60m 13.7 13.8 14.0 13.3 Vert. Temp. Diff. (Deg F)10-35m
+0.20 40.20
+0.20 40.20 10-60m
+0.75
+0.75
+0.75
+0.75 19-85m
+1.00
+1.00
+1.00
+1.00 Dew Point (Deg F) 10m 7 ?.
72 r2 72 Ref. Temp. (Deg F) 10m 72 73 72 73 Precipitation (Inches) 0.2 0.2 0.2 0.3 Stability Class D
D D
D 92-FE 6.
3
METEOR 0!.0GICA!, DAT4 (NPIS Met. Data Read Out)
Time Relative (HR$sHIH)
(H+03:00)
(H+03:15)
(H+03:30)
(H+03:45)
Wind Speed (milhr) 10m 6.0 6.2 6.6 6.5 35m 6.4 6.7 6.9 6.5 60m 6.5 7.1 7.3 7.2 Wind Direction (Deg)
(from) 10m 355 351 353 345 35m 357 353 358 355 60m 1
1 0
0 Wind Direction Var. (Deg) 10m 15.9 16.0 15.7 15.8 60m 13.7 13.8 14.0 13.3 Vert. Temp. Diff. (Deg F)10-35m
+0.20
+0.20
+0.20
+0.20 10-60m
+0.75
$0.75
+0.75
+0.75 10-85m
+1.00 41.00
+1.00
+1.00 Dew Point (Deg F) 10m 72 73 73 73 Ref. Temp. (Deg F) 10m 73 73 75 75 Precipitatioh (Inches) 0.3 0.3 0.3 0.3 Stability Class F
F F
F 92-FE 6.
4
~~
..._.s
--m.
.m
HFTEOROLOGICAL DATA (NPIS Met. Data Read Out)
Time Relative (HRS:HIN)
(H+04:00)
(11+04 ' 5 )
(H+04:30)
(H+04:45+)
Wind Speed (mi/hr) 10m 7.0 7.5 7./
7.6 3."
7.1 7.7 7.
7.8 60m 74 8.4 F
8.0 Wind Direction (Deg)
(from) 10m 353 345 5
2 35m 358 355 8
3 60m 0
0 10 5
Wind Direction Var. (Deg) 10m 15.2 15.5 15.5 15.3 60m 13.2 13.7 13.1 13.0 Vert. Temp. Diff. (Deg F)10-35m
+0.20
+0.20
+0.20
+0.20 10 60m
+0.75
+0.75
+0.75
+0.70 10-85m
+1.00
+1.00
+1.00
+1.00 Dew Point (Den F) 10m 75 73 75 73 Ref. Temp. (Deg 1 l
10m 75 75 75 75 Precipitation (Inches) 0.3 0.3 0.3 0.3 Stability Clans F
F F
F 92-FE 6.
5
l SECTION 7.0 i
OtLSITE RADIOLOGICAL PARAMETERS i
i i
Subsections Pane PROCESS RADIOr'IEHISTRY 7.1 PROCESS HON 11t.iS AIRBORNE 7.4 LIQUID 7.13 l
AREA RADIATION HONITORS 7.16 INPLANT SURVEYS 7.27 i
l i
1 i
92-FE 7.
0
PROCESS RADIOCIDMISTRY 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).
Containment and plant unit vent concentrations to be used throughout the Exercise are also included.
Isotopic :oncentrations are determined using the radiation monitoring system as a reference.
1 Time frames at the tup of the page are based on the time at which the sample.
is collected, not when it was analyzed.
j A time delay of one hour 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.
1 l
l l
l l
I l
l l
92-FE 7.
1
e PROCESS NADIOCHEMISTRY y
'RCS Concentraction (uC1/cc) m M
Time (relative):
H+00:00 H+00: 30 H+01:00 H+01:30 H+02:00 H+02:30 H+03:00 H+03:30+
Nuclide Kr-85m 1.0E-01 9.3E-02 7.3E-02 4.8E-02 3.2E-02 1.9E-02 Kr-87
- 6. 4 E- 02 3.5E-02 Kr-88.
1.8E-01 1.7E-01 5.1E-02 6.3E-02 5.1E-02 Xe-133 2.7E+00 3.9E+00 2.0E+00 2.5E+00 3.4E+00 4.3E+00 3.7E+00 3.6E+00 Xe-133m 6.0E-02 5.8E-02 Xe-135 5.9E-01 9.4E-01 4.6E-01 6.1E-01 8.6E-01 1.1E+00 8.6E-01 7.7E-01 Xe-135m 1.3E-01 5.8E-01 Xe-138 t
Total Noble Gas 3.82E+00 5.78E+00 2.58E+00 3.17E+00 4."lE+00 5.45E+00 4.59E+00 4.39E+00 I-131 8.6E-02 2.3E+00 3.dE+00 5.1E+00 5.1E+00 4.0E+00 3.4E+00
- 2. 7 E+ 00 I-132 1.1E-01 1.3E+00 1.6E+00 1.5E+00 1.3E+00 8.6E-01 7.4E-01 6.2E-01
[
I-133 1.2E-01 2.1E+00 3.2E+00 4.0E+00 3.9E+00 2.9E+00 2.2E+00 1.7E+00 I-134 9.8E-02 1.9E-01 1.1E-01 3.2E-02 I-135 8.6E-02 1.1E+00 1.6E+00 1.6E+00 1.4E+00 8.8E-01 5.9E-01 3.9E-01 Total Icilge 5.00E-01 6.99E+00 1.03E+01 1.22E+01 1.17E+01 8.64E400 6.93E+00 5.41E+00 DEI 1.29E-01 3.04E+00 4.92E+00 6.39E+00 6.35E+00 4.89E+00 4.09E+00 3.25E+00 Particulate i
Cs-134 9.3E-03 4.2E-01 6.9E-01 1.1E+00 1.5E+00 1.3E+00 1.1E+00 9.5E-01 Cs-136 2.1E-03 7.7E-02 1.2E-01 1.8E-01 2.AE-01 2.2E-01 1.9E-01
'1.6E-01 Cs-137 6.0E-03 2.5E-01 4.0E-01 6.2E-01 8.5E-01 7.3E-01 6.3E-01 5.6E-01 Cs-138 8.6E-02
'8.6E-02.
2.3E-02 Total Particulate 1.03E-01 8.33E-01 1.23E+00 1.90E+00 2.59E+00 2.25E+00 1.92E+00 1.67E+00 Gross Total Activity 4.42E+00 1.36E+01 1.41E+01 1.73E+01 1.86E+01 1.63E+01 1.34E+01 1.15E+01 t0 l
e PROCESS RADIOCHEMISTRY
=vs Cont ainmet Atmosphere Concentration tuC1/cc)
Time (Relative):
H+00:00 H+00:30 H+01:00 H+01:30 H+02:00 H+02:30 H+03:00 H+03:?O+
Nuclide Kr-85m 1.61E-05 3.03E-05 3.50E-05 Kr-87 1.03E-05 1.11E-05 Kr-88 2.90E-05 5.48E-05 2.52E-05 Xe-133 4.42E-04 1.13E-03 1.30E-03 2.53E-03 4.38E-03 8.40E-03 7.19E-03 7.01E-03 Xe-133m 9.69E-06 1.90E-05 1.96E-05 Xe-135 9.47E-05 3.00E-04 3.00E-04 6.11E-04 1.15E-03 2.12E-03
- 1. 74 E-03 1.47E-03 Xe-135m 2.00E-05 1.92E-04 Xe-138 Total Noble Gas 6.22E-04 1.74E-03 1.68E-03 3.14E-03 5.53E-03 1.05E-02 8.93E-03 8.48E-03 1-131 3.90E-11 3.70E 10 7.00E-10 9.99E-10 2.00E-09 4.00E-09 2.96E-09 2.92E-09 I-132 3.59E-10 1.80E-09 8.89E-10 1 80E-09 1.67E-09 1.52E-09 1.38E-09 I-133 8.51E-11 7.96E-10 1.49E-09 2.13E-09 4.27E-09 4.27E.39 3.14 E-09 3.01E-09 I-134 2.95E-10 1.31E-09 I-135 7.18E-11 6.48E-10 1.19E-09 1.70E-09 3.41E-09 3.33E-09 2.16E-09 1.05E-09 Total Iodine 1.96E-10 2.47E-09 6.49E-09 5.72E-09 1.15E-08 1.33E-08 9.78E-08 8.36E-09 Particulate (no particulate less than detectable)
Cs-134 Cs-136 Cs.-137 Cs-138 Co-58 Co-60 Iotal Particulate Gross Total Activity 6.22E-04 1.74E-03 1.68E-03 3.14E-03 5.53E-03 1.05E-02 8.93E-03 8.48E-03
?
w O
FROCESS MONITORS AIRBORNE Time-related inplant airborne 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 i
particulates, lodines or noble gases.
For the process monitor data it is 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.
i I
l 1
92-FE 7.
4
PROCESS MONITORS AIRBORNE Time Relative (H+00:00)
GTRE 21A/B Unit Vent Eff.
P (uCi/cc) 2.0E-13 I
7.1E-13 G
9.0E-07 GilRE 10A/B Radwaste Building Eff.
P (uCi/cc) 1,0E-12 1
1.0E-11 G
2.0E-06 ABRE 114 MSRV Monitor S/G A (mR/hr) 4.0E-01
~
ABRE 113 S/G B (mR/hr) 4.0E-01 ABRE 112 S/G C (mR/hr) 4.0E-01 ABRE 111 S/G D (mR/hr) 4.0E-01 FCRE 385 Aux. Feed Pump Turbine (mR/hr) 4.0E-01 GLRE 60 Aux. Bldg. Vent Ex.
P (uCi/cc) 2.0E-10 GKRE 41 Access Control Vent P (uCi/cc) 3.0E-11 GGRE 27 Fuel Bldg. Vent Ex.
P (uC1/cc) 3.2E-10 I
1.4E-11 G
2.1E-07 GGRE 28 P (uCi/cc) 3.1E-10 1
1.3E-11 G
2.0E-07 GERE 92 Condenser Air Discharge G (uCi/cc) 2.0E-06 GTRE 22 Containment Purge Ex.
P (uC1/cc) 1.0E-12 I
1.0E-12 G
1.0E-07 GTRE 33 P (uCi/cc) 1.0E 12 I
1.0E-12 G
1.0E-07 GHRE 22 Radwaste Bldg. Vent P (uCi/cc) 1.0E-11 GHRE 23 Gas Decay Tank Vent Ex.
G (uCi/cc) 2.2E-06 GRRE 04 Control Room Supply P (uCi/cc) 3.0E-12 I
2,0E-11 G
4.0E-06 GKPE 05 P (uCi/cc) 3.0E-12 I
2.0E-12 G
4.0E-06 GTRE 31 Containment Atmosphere P (uC1/cc) 2.6E-11 I
2.0E-10 G
8.2E-04 GTRE 32 P (uC1/cc) 2.6E-11 I
2.0E-10 G
8.2E-04 GTRE 59 Ctmt. High Range Rad.
(R/hr)
<1.0E+00 GTRE 60 (R/hr)
<1.0E+00 92-FE 7.
5
PROCESS HONITORS AIRBORNE Time Relative (H+00:15)
(H+00:30)
GTRE 21A/B Unit Vent Eff.
P (uC1/cc) 2.0E-13 2.0E-13 I
7.1E-13 7.1E-13 G
9.0E-07 9.0E-07 GHRE 10A/B Radwaste Building Eff.
P (uCi/cc) 1.0E-12 1.OE-12 1
1.0E-11 1.0E-11 G
2.0E-06 2.0E-06 ABRE 114 MSRV Monitor S/G A (mR/hr) 4.0E-01 4.0E-01 ABRE 113 S/G B (mR/hr) 4.0E-01 4.0E-01 ABRE 112 S/G C (mR/hr) 4.0E-01 4.0E-01 ABRE 111 S/G D (mR/hr) 4.0E-01 4.0E-01 FCRE 385 Aux. Feed Pump Turbine (mR/hr) 4.0E-01 4.0E-01 GLRE 60 Aux. Bldg. Vent Ex.
P (uC1/cc) 2.0E-10 2.0E-10 GKRE 41 Access Control Vent P (uCi/cc) 3.0E-11 3.0E-11 GGRE 27 Fuel Bldg. Vent Ex.
P (uCi/cc) 3.2E-10 3.2E-10 I
1.4E-11 1.4E-11 G
2.1E-07 2.1E-07 GGRE 28 P (uCi/cc) 3.1E-10 3.1E-10 I
1.3E-11 1.3E-11 G
2.0E-07 2.0E-07 GERE 92 Condenser Air Discharge G (uC1/cc) 2.0E-06 2.0E-06 GTRE 22 Containment Purge Ex.
P (uCi/cc) 1.0E-12 1.0E-12 1
- 1. 0E-12 1.0E-12 G
1.0E-07 1.0E-07 GTRE 33 P (uCi/cc) 1.0E-12 1.0E-12 I
1.0E-12 1.0E-12 G
1.0E-07 1.0E-07 GHRE 22 Radwaste Bldg. Vent P (uC1/cc) 1.0E-11 1.0E-11 GHRE 23 Gas Decay Tank Vent Ex.
G (uC1/cc) 2.2E-06 2.2E-06 GKRE 04 Control Room Supply P (uC1/cc) 3.0E-12 3.0E-12 1
2.0E-11 2.0E-11 G
4.0E-06 4.0E-06 GKPE 05 P (uCi/cc) 3.0E-12 3.0E-12 I
2.0E-12 2.0E-12 G
4.0E-06 4.0E-06 GTRE 31 Containment Atmosphere P (uC1/cc) 2.6E-11 2.6E-11 I
2.0E-09 2.0E-09 G
9.0E-04 1.7E-03 GTRE 32 P (uCi/cc) 2.6E-11 2.6E-11 I
2.0E-09 2.0E-09 G
9.0E-04 1.7E-03 GTRE 59 Ctmt. High Range Rad.
(R/hr)
<1.0E+00
<1.0E+00 GTRE 60 (R/hr)
<1.0E+00
<1.0E+00 92-FE 7.
6
PROCESS MONITORS j
AIRBORNE Time Relative (H+00:45)
(H+01:00)
GTRE 21A/B Unit Vent Eff.
P (uC1/cc) 2.0E-13 2.0E-13 I
?.1E-13 7.1E-13 G
9.0E-07 9.0E-07 GHRE 10A/B Radwaste Building Eff.
P (uCi/cc) 1.0E-12 1.0E-12 I
1.0E-11 1.0E-11 G
2.0E-06 2.0E-06 I
ABRE 114 MSRV Monitor S/G A (mR/hr) 4.0E-01 4.0E-01 ALRE 113 S/G B (mR/hr) 4.0E-01 4.0E-01 ABRE 112 S/G C (mR/hr) 4.0E-01 4.0E-01 ABRE 111 S/G D (mR/lir )
4.0E-01 4.0E-01 FCRE 385 Aux. Feed Pump Turbine (mR/hr) 4.0E-01 4.0E-01 GLRE 60 Aux. Bldg. Vent Ex.
P (uC1/cc) 2.0E-10 2.0E-10 GKRE 41 Access Control Vent P (uCJ/cc) 3.0E-11 3.0E-11 GGRE 27 Fuel Bldg. Vent Ex.
P (uci/cc) 3.2E-10 3.2E-10 I
1.4E-11 1.4E-11 G
2.1E-07 2.1E-07 GGRE 28 P (uCi/cc) 3.1E-10 3.1E-10 I
1.3E-11 1.3E-11 G
2.0E-07 2.0E-07 GERE 92 Condenser Air Discharge G (uC1/cc) 2.0E-06 2.0E-06 GTRE 22 Containment Purge Ex.
P (uCi/cc) 1.0E-12 1.0E-12 I
1.0E-12 1.0E-12 G
1.0E-07 1.0E-07 GTRE 33 P (uCi/cc) 1.0E-12 1.0E-12 I
1.0E-12 1.0E-12 G
1.0E-07 1.0E-07 GHRE 22 Radwaste Bldg. Vent P (uC1/cc) 1.0E-11 1.0E-11 GHRE 23 Gar Decay Tenk Vent Ex.
G (uCi/cc) 2.2E-06 2.2E-06 GKRE 04 Control Room Supply P (uCi/cc) 3.0E-12 3.0E-12 I
2.0E-11 2.0E-11 G
4.0E-06 4.0E-06 GKPE 05 P (uCi/cc) 3.0E-12 3.0E-12 I
2.0E-12 2.0E-12 G
4.0E-06 4.0E-06 GTRE 31 Containment Atmosphere P (uci/cc) 2.6E-10 2.6E-10 I
6.0E-09 6.0E-09 G
1.7E-03 1.7E-03 GTRE 32 P (uC1/cc) 2.6E-10 2.6E-10 I
6.0E-09 6.0E-09 3
1.7E-03 1.7E-03 GTRE 59 Ctmt. High Range Rad.
(R/hr)
<1.0E+00
<1.CE+00 GTRE 60 (R/hr)
<1.0E+00
<1.0E+00 92-FE 7.
7
PROCESS HONITORS AIRBORNE Time Relative (H+01:15)
(H+01:30)
GTRE 21A/B Unit Vent Eff.
P (uCi/cc) 2.0E-13 I
7.1E-13 G
9.0E-07 9.0E-07 GHRE 10A/B Radwaste Building Eff.
P (uCi/cc) 1.0E-12 I
1.0E-11 G
2.0E-06 2.0E-06 ABRE 114 MSRV Monitor S/G A (mR/hr) 4.0E-01 4.0E-01 AERE 113 S/G B (mR/hr) 4.0E-01 4.0E-01 ABRE 112 S/G C (mR/hr) 4.0E-01 4.0E-01 ABRE 111 S/G D (mR/hr) 4.0E-01 4.0E-01 FCRE 385 Aux. Feed Pwnp Turbine (mR/hr) 4.0E-01 4.0E-01 GLEE 50 Aux. Bldg. Vent Ex.
P (uCi/cc) 2.0E-10 GKRE 41 Access Control Vent P (uC1/ce) 3.0E-11 i
GGRE 27 Fuel Bldg. Vent Ex.
P (uC1/cc) 3.2E-10 3.2E-10 I
1.4E-11 1.4E-11 G
2.1E-07 2.1E-07 GGRE 28 P (uC1/cc) 3.1E-10 3.1E-10 I
1.3E-11 1.3E-11 a
G 2.0E-07 2.0E-07 GERE 92 Condenser Air Discharge G (uCi/cc) 2.0E-06 GTRE 22 Containment Purge E(.
P (uCi/cc) 1.0E-12 1.0E-12 I
1.0E-12 1.0E-12 i
G
- 1. 0E. 0 7 1.0E-07 GTRE 33 P (uCi/cc) 1.0E-12 1.0E-12 I
1.0E-12 1.0E-12 G
1.0E-07 1.0E-07 GHRE 22 Radwaste Bldg. Vent P (uCi/cc) 1.0E-11 CHRE 23 Gas Decay Tank Vent Ex.
G (uCi/cc) 2.2E-06 GKRE 04 Centrol R3om Supply P (uCi/cc) 3.0E-12 3.0E-12 1
2.0E-11 2.0E-11 G
4.0E-06 4.0E-06 GRPE 05 P (uC1/cc) 3.0E-12 3.0E-12 1
2.0E-12 2.0E-12 G
4.0E-06 4.0E-06 GTRE 31 Containment Atmosphere P (uCi/cc) 2.6E-10 2.6E-10 I
6.0E-09 6.0E-09 G
3.2E-03 3.2E-03 GTRE 32 P (uC1/cc) 2.6E-10 2.6E-10 I
6.0E-09 6.0E-09 G
3.2E-03 3.2E-03 GTRE 59 Ctmt. High Range Rad.
(R/hr)
<1.0E:00
<1.0E+00 GTRE 60 (R/hr)
<1.0E+00
<1.0E+00 92-FE 7.
8
PROCESS MONITORS AIRBORNE Time Relative (H+01: 45)
(H+02:00)
GTRE 21A/B Unit Vent Eff.
P (uCi/cc)
I G
9.0E-07 9.0E-07 GHRE 10A/B Radwaste Building Eff.
P (uCi/ce)
I G
2.0E-06 2.0E-06 ABRE 114 MSRV Monitor S/G A (mR/hr) 4.0E-01 4.0E-01 ABRE 113 S/G B (mR/hr) 4.0E-01 4.0E-01 ABRE 112 S/G C (mR/hr) 4.0E-01 4.0E-01 ABRE 111 S/G D (mR/hr) 4.0E-01 4.0E-01 FCRE 385 Aux. Feed Pump Turbine (mR/hr) 4.0E-01 4.0E-01 GLRE 60 Aux. Bldg. Vent Ex.
P (uC1/cc)
GKRE 41 Access Control Vent P (uCi/cc)
GGRE 27 Fuel Bldg. Vent Ex.
P (uCi/cc) 3.2E-10 3.2E-10 1
1.4E.11 1.4E-11 G
2.1E-07 2.1E-07 CGRE 28 P (uC1/cc) 3.1E-10 3.1E-10 I
1.3E-11 1.3E-11 G
2.0E-07 2.0E-07 GERE 92 Condenser Air Discharge G (uC1/cc)
GTRE 22 Containment Purge Ex.
P (uC1/cc) 1.0E-12 1.0E-12 I
1.0E-12 1.0E-12 G
1.0E-07 1.0E-07 GTRE 33 P (uci/cc) 1,0E-12 1.0E-12 I
1.0E-12 1.0E-12 G
1.0E-07 1.0E-07 GHRE 22 Radwaste Bldg. Vent P (uCi/cc)
GHRE 23 Gas Decay Tank Vent Ex.
G (uCi/cc)
GKRE 04 Control Room Supply P (uCi/cc) 3.0E-12 3.0E-12 I
2.0E-11 2.0E-11 G
4.0E-06 4.0E-06 GKPE 05 P (uCi/cc) 3.0E-12 3.0C-12 I
2.0E-12 2.0E-12 G
4.0E-06 4.0E-06 GTRE 31 Containment Atmosphere P (uCi/cc) 2.6E-10 2.6E-10 I
8.0E-09 1.0E-08 G
4.2E-03 5.2E GTRE 32 P (uCi/cc) 2.6E-10 2.0E-10 I '
8.0E-09 1.C -08 G
4.2E-03 5.2E-03 GTRE 59 Ctmt. High Range Rad.
(R/hr) si.0E+00 3.0E+00 GTRE 60 (R/hr) s;.0E+00 3.0E+00 92-FE 7.
9
PROCESS MONITORS AIRBORNE Time Relative (H+02:15)
(H+02:30)
GTRE 21A/B Unit Vent Eff.
P (uCi/cc)
I G
9.0E-07 9.0E-07 GHRE 10A/B Radwaste Building Eff.
P (uC1/cc)
I G
2.0E-06 2.0E-06 ABRE 114 MSRV Monitor S/G A (mR/hr) 4.0E-01 5.0E+0 ABRE 113 S/G B (mR/hr) 4.0E-01 5.0E+0 ABRE 112 S/G C (mR/hr) 4.0E-01 5.0E+0 ABRE 111 S/G D (mR/hr) 4.0E-01 5.0E+0 FCRE 385 Aux. Feed Pump Turbine (mR/or) 4.0E-01 4.0E-01 GLRE 60 Aux. Bldg. Vent Ex.
P (uCi/cc)
GKRE 41 Access Control Vent P (uCi/cc)
GGRE 27 Fuel Bldg. Vent Ex.
P (uci/cc) 3.2E-10 3.2E-10 I
1.4E-11 1.4E 11 G
2.1E-07 2.1E-07 GGRE 28 P (uCi/cc) 3.1E-10 3.1E-10 I
1.3E-11 1.3E-11 G
2.0E-07 2.0E-07 GERE 92 Condenser Air Discharge G (uci/cc)
GTRE 22 Containment Purge Ex.
P (uCi/cc) 1.0C-12 1.0E-12 I
1.0E-12 1.0E-12 G
1.0E-07 1.0E-07 GTRE 33 P (uC1/cc) 1.0E-12 1.0E-12 I
1.0E-12 1.0E-12 G
1.0E-07 1.0E-07 GHRE 22 Radwaste Bldg. Vent P (uC1/cc)
GHRE 23 Gas Decay Tank Vent Ex.
G (uCi/cc)
GKRE 04 Control Room Supply P (uCi/cc) 3.0E-12 3.0E-12 I
2.0E 11 2.0E-11 G
4.0E-06 4.0E-06 GKPE 05 P (uC1/cc) 3.0E-12
'3.0E-12 I
2.0E-12 2.0E-12 G
4.0E-06 4.0E-06 GTRE 31 Containment Atmosphere P (uCi/cc) 2.6E-10 2.6E-10 I
2.0E-08 2.5E-08 G
1.2E-02 1.0E-02 GTRE 32 P (uCi/cc) 2.6E-10 2.6E-10 1
I 2.0E-08 2.5E-08 l
G 1.2E-02 1.0E-02 GTRE 59 Ctmt. High Range Rad.
(R/hr) 3.0E+00 5.0E+00 GTRE 60 (R/hr) 3.0E+00 5.0E+00 l
92-FE 7,
lo l
I i
I
PROCESS HONITORS AIRBORNE Time Relati;e (H+02:45)
(H+03:00)
~
GTRE 21A/B Unit Vent Eff.
P (uCi/cc)
I G
9.0E-07 9.0E-07 GHRE 10A/B Radwaste Building Eff.
P (uC1/cc) 1 G
2.0E-06 2.0E-06 ABRE 114 MSRV Moni+.or S/G A (mR/hr) 6.0E+0 1.2E+01 ABRE 113 S/G B (mR/hr) 6.0E+0 1.2E+01 ABRE 112 S/G C (mR/hr) 6.0E+0 1.2E+01 ABRE 111 S/G D (mR/hr) 6.0E+0 1.2E+01 FCRE 385 Aux. Feed Pump Turbine (mR/hr) 4.0E-01 4.0E-01 GLRE 60 Aux. Bldg. Vent Ex.
P (uCi/cc)
GKRE 41 Access Control Vent P (uCi/cc)
GGRE 27 Fuel Bldg. Vent Ex.
P (uCi/cc) 3.2E-10 3.2E-10 I
1.4E-11 1.4E-11 G
2.1E-07 2.1E-07 GCRE 28 P (uC1/cc) 3.1E-10 3.1E-10 1
1.3E.11 1.3E-11 G
2.0E-07 2.0E-07 GERE 92 Condenser Air Discharge G (uci/cc)
GTRE 22 Containment Purge Ex.
P (uCi/cc) 1.0E-12 1.0E-12 I
1.0E-12 1.0E-12 G
1.0E-07 1.0E-07 GTRE 33 P (uC1/cc) 1.0E-12 1.0E-12 I
1.0E-12 1.0E-12 G
1.0E-07 1.0E-07 GHRE 22 Radwaste Bldg. Vent P (uCi/cc)
GHRE 23 Gas Decay Tank Vent Ex.
G (uCi/cc) l GKRE 04 Control Room Supply P (uCi/cc) 3.0E-12 3.0E-12 I
2.0E-11 2.0E-11' G
4.0E-06 4.0E-06 GKPE 05 P (uC1/cc) 3.0E-12 3.0E-12 I
2.0E-12 2.0E-12 G
4.0E-06 4.0E-06 GTRE 31 Containment Atmosphere P (uci/cc) 2.6E-10 2.6E-10 I
1.3E-08 1.3E-08 G
9.6E-03 8.8E-03 f
GTRE 32 l
'P (uC1/cc) 2.6E-10 2.6E-10 1.3E-08 1.3E-08 9
9.6E-03 8.8E-03 GTRE 59 Ctmt. High Range Rad.
(R/hr) 5.0E+00 5.0E+00 GTRE 60 (R/hr) 5.0E+00 5.0E+00 l
1 92-FE 7.
11 l
I l
PROCESS HONITORS AIRBORNE Time Relative (H+03:15)
(H+03:30+i GTRE 21A/B Unit Vent Eff.
I P (uC1/cc)
I G
9.0E-07 9.0E-07 GURE 10A/B Radwaste Building Eff.
P (uCi/cc)
I G
2.0E-06 2.0E-06 i
A3RE 114 MSRV Monitor S/G A
-(mR/hr) 1.4E+01 1.3E+01 ABRE A13 S/G B (mR,ar) 1.4E+01 1.3E+01 ABRE 112 S/G C (mR/hr) 1.4E+01 1.3E+01 ABRE 111 S/G D (mR/hr) 1.4E+01 1.3E+01 FCRE 385 Aux. Feed Pump Turbine (mR/hr) 4.0E-01 4.0E-01 GLRE 60 Aux. Bld. Vent Ex.
P (uCi/cc)
GKRE 41 Access Control Vent P (uCi/cc)
GGRE 27 Fuel Bldg. Vent Ex.
P (uC1/cc) 3.2E-10 3.2E-10 I
1.4E-11 1.4E-11 G
2.1E-07 2.1E-07 CGRE 28 P (uC1/cc) 3.1E-10 3.1E-10 1
1.3E-11 1.3E-11 G
2.0E-07 2.UE-07 GERE 92 Condenser Air Discharge G (uC1/cc)
GTRE 22 Containment Purge Ex.
P (uCi/cc) 1.0E-12 1.0E-12 1
1.0E-12 1.0E-12 G
1.0E-07 1.0E-07 GTRE 33 P (uCi/cc) 1.0E-12 1.0E-12 I
1.0E-12 1.0E-12 G
1.0E-07 1.0E-07 GHRE 22 Radwaste Bldg. Vent P (uCi/cc)
GHRE 23 Gas Decay Tank Vent Ex.
G (uCi/cc)
GKRE 04 Control Room Supply P (uCi/cc) 3.0E-12 3.0E-12 I
2.0E-11 2.0E-11 G
4.0E-06 4.0E-06 GKPE 05 P (uC1/cc) 3.0E-12 3.0E-12 i
I 2.0E-12 2.0E-12 l
G 4.0E-06 4.0E-06 l
GTRE 31 Containment Atmosphere P (uC1/cc) 2.6E-10 2.6E-10 I
1.3E-08 1.3E-08 G
8.3E-03 7.6E+03 GTRE 32 P (uCi/cc) 2.6E-10 2.6E-10 i
I 1.3E-08 1.3E-08 G
8.3E-03 7.6E+03 GTRE 59 Ctmt. High Range Rad.
(R/hr) 3.0E+00 3.0E+00 GTRE 60 (R/hr) 3.0E+00 3.0E+00 l
l 92-FE
- 7. 12 l
[
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 cocunon name, n
92-FE
- 7. 13
PROCESS HOKITORS LIQUID Time Relacive (H+00:00)
(H+00:15)
LERE 59 Turbine Bldg. Drain (uCi/cc) 6.00E-07 6.00E-07 HFRE 45 Sec. Liquid Wasta Discharge (uCi/cc) 5.5CE-09 5.50E-09 FBRE 50 Aux. Steam Cond.
(uC1/cci Recovery Tank 4.00E-07 4.00E-07 AERE 4A Service Water Return (uCi/cc) 4.00E-08 4.00E-08 AERE 4B (uCi/cc) 4.00E-08 4.00E-00 i
EFRE 35 Essential Service Water (uC1/cc) 5.00E-07 5.00E-08 EFRE 36-(uci/cc) 5.00E-07 5.00E-08 EGRE 09 CCW Train A (uCi/cc) 4.50E-07 4.50E-07 EGRE ;0 CCW Train B (uC1/cc) 4.50E-07 4.50E-07 SJRE 02 S/F Liquid (uC1/cc) 3.00E-07 3.00E-07 BMRE 25 S/G Blowdown Process (uCi/cc) 3.50E-07 3.50E-07 BMRE 52 S/F Blowdown Discharge (uCi/cc) 3.50E-07 3.50E-07 SJRE 01 CVCS Letdown (uCi/cc) 2.30E+00 4.40E+00 HERE 16 Boron Recycle Distillate (uCi/cc) 5.00E-07 5.00E-07 HERE 18 Liquid Waste Discharge (uci/cc) 3.00E-05 3.00E-05 Time Relative (H+00:30)
(H+00:45)
LERE 59 Turbine Bldg. Drain (uCi/cc) 6.00E-07 6.00E-07 HFRE 45 Sec. Liquid Waste Discharge (uCi/cc) 5.50E-09 5.50E-09 FBRE 50 Aux. Steam Cond.
(uC1/cc)
Recovery Tank 4.00E-07 4.00E-07 AERE 4A Service Water Return (uci/cc) 4.00E-08 4.00E-08 AERE 4B (uci/cc) 4 00E-08 4.00E-08 EFRE 35 Essential Service Water (uCi/cc) 5.00E-07 5.00E-07 EFRE 36 (uC3/cc) 5.00E-07 5.00E-07 EGRE 09 CCW Train A (uCi/cc) 4.50E-07 4.50E-07 EGRE 13 CCW Train B (uC1/cc) 4.50E-07 4.50E-07 i
SJRE 02 S/F Liquid (uCi/cc) 3.00E-07 3.00E-07 BMRE 25 S/G Blowdown Process (uci/cc) 3.50E-07 3.50E-07 BMRE 52 S/F Blowdown Discharge (uC1/cc) 3.50E-07 3.50E-07 SJRE 01 CVCS Letdown (uC1/cc) 1.40E+01 1.40E+01 HERE 16 Boron Recycle Distillate (uCi/cc) 5.00E-07 5.00E-07 l
HERE 18 Liquid Waste Discharge (uci/cc) 3.00E-05 3.00E-05 l
l i
92-FE
- 7. 14 l
PROCESS MONITORS LIQUID Time Relative (H+01:00)
(H+01:15+)
LERE 59 Turbine Bldg. Drain l(uCi/cc) 6.00E-07 6.00E-07 HFRE 45 Sec. Liquid Waste Discharge (uci/cc) 5.50E-09 5.50E-09 FBRE 50 Aux. Steam Cond.
(uC1/cc)
Recovery Tank 4.00E-07 4.00E-07 AERE 4A Service Water Return (uCi/cc) 4.00E-08 4.00E-08 AERE 4B (uCi/cc) 4.00E-08 4.00E-08 EFRE 35 Essential Service Water (uC1/cc) 5.00E-07 5.00E-08 EFRE 36 (uCi/cc) 5.00E-07 5.00E-08 EGRE 09 CCW Train A (uCi/cc) 4.50E-07 4.50E-07 EGRE 10 CCW Train B (uCi/cc) 4.50E-07 4.50E-07 SJRE 02 S/F Liquid (uci/cc) 3.00E-07 3.00E-07 BMRE 25 S/G Blowdown Process (uC1/cc) 3.50E-07 3.50E-07 BHRE 52 S/F Blowdown Discharge (uC1/cc) 3.50E-07 3.50E-07 SJRE 01 CVCS Letdown (uC1/cc) 1.40E+01 1.70E+01 HERE 16 Baron Recycle Distillate (uCi/cc) 5.00E-07 5.00E-07 HBRE 18 Liquid Waste Discharge (uC1/cc) 3.00E-05 3.00E-05 92-FE
- 7. 15
AREA RADIATION HONITORS 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.
92-FE
- 7. 16
AREA RADIATION MONITORS Relative (H+00:00)
(H+00:15)
SDRE01 Radwaste Bldg. Corridor. Basement (West)
(mR/hr) 0.2 0.2
'~SDRE02 Radwaste Bldg. Corridor Basement (Central)
(mR/hr) 0.2 0.2 SDRE03 Radwaste Bldg. Corridor. Basement (East)
(mR/hr) 0.2 0.2 SDRE04 Radwaste Bldg. Corridor. 2000' ele. (West)
(mR/hr) 0.2 0.2 SDRE05 Radwaste Bldg. Corridor. 2000' ele. (Central)
(mR/hr) 0.2 0.2 SDRE06 Solid Radwa5'e Area. 2000' ele.
(mR/hr) 0.2 0.2 SDRE07 Radwaste B.'
Truck Space. 2000' ele.
(mR/hr) 0.2 0.?
SDRE08 Radvaste Bldk. Sample Laboratory (mR/hr) 0.2 0.2 SDRE09 Rapygggygggy,gggvekm. Corridor.
(mR/hr) 0.2 0.2 SDRE10 Rapygggyggg9,VggveRm. Corridor.
(mR/hr) 0.2 0.2 SDRE11 Radwaste Bldg. HVAC Filter Unit (mR/hr) 0.2 0.2 SDRE12 Aux. Bldg. Corridor. Basement (1974' ele. SE)
(mR/hr) 25.0 25.0 SDRE13 Aux. Bldg. Corridor. Basement (1974' ele. NE)
(mR/hr) 25.0 25.0 SDRE14 Aux. Bldg. Corridor, basement (1974' ele. N)
(mR/hr) 25.0 25.0 SDRE15 Aux. Bldg. Corridor. Basement (1974' ele. W)
(mR/hr) 25.0 25,0 SDRE16 Aux. Bldg. Corridor. Basement (1974' ele. SW)
(mR/hr) 25.0 25.0 SDRE17 NopgggggagggvyPipeTunnel&PersonnelAccess (mR/hr) 0.5 0.5 SDRE18 Aux. Bldg. Ground Floor Corridor (2000' ele. N)
(mR/hr) 25.0 25.0 SDRE19 Aux. Bldg. Ground Floor Corridor (2000' ele. SE)
(mR/hr) 25.0 25.0 SDRE20 Aux. Bldg. Valve km. Corridor (2000' ele. S)
(mR/hr) 25.0 25.0
_SDRE21 Aux. Bldg. Valve Rm. Corridor (2000' ele. S)
(mR/hr) 25.0 25.0 SDRE22 Aux. Bldg. Ground Floor (2000' ele. SW)
(mR/hr) 25.0 25.0 SDRE23 Aux. Bldg. Ground Floor (2000' ele. W)
(mR/hr) 25.0 25.0 SDRE24 Aux. Bldg. Sampling Room (2000' ele. Central)
(mR/hr) 50.0 50.0 SDRE21 Aux. Bldg. Vent Filter (mR/hr) 5.0 5.0
~ SDRE26 kHR Heat Exchanger Outside (2026' ele.)
(mRfhr) 25.0 25.0 SDRE27 Cont. Purge Exhaust Filter Unit (2047' ele.)
(ml.hr) 5.0 5.0 SDRE28 Cont. Personnel Hatch (2047' ele.)
(mR/hr) 50.0 50.0 SDRE29 Hot Machine Shop (mR/hr) 0.2 0.2 SDRE30 Hot Instrument Shop
('mR / hr )
0.2 0.2 SDRE31 Control Bldg. Hot Lab (mR/hr) 0.2 0.2 SDRE32 Control Bldg. Corridor (mR/hr) 0.2 0.2 SDRE33 Control Room (2047' ele.)
(mR/hr) 0.2 0.2 SDRE34 Cask Handling Area (2000' ele.)
(mR/hr) 0.5 0.5 SDRE35 New Fuel Storage (2026' ele. W)
(mR/hr) 0.5 0.5 SDRE36 New Fuel Storage Corridor (2026' ele.)
(mR/hr) 0.5 0.5 SDRE37 Spent Fuel Pool Area (mR/hr) 0.5 0.5 SDRE38 Spent Fuel Pool Area (mR/hr) 0.5 0.5 SDRE39 Seal Table Area (2026' ele. N)
(mR/hr) 200.0 200.0 SDRE40 Peggggp91kEC'SN)HatchAreaInside e
(mR/hr) 400.0
-400.0 SDRE41 Containment Bldg. (2047.6' ele. NW) tr.h/hr) 40.0 40.0 SDRE42 Containment Bldg. (2047.6' ele. E)
(mR/hr) 40.0 40.0 SDRE43 Technical Support Center (mR/hr) 0.2 0.2 l
SDRE44 Emergency Operations Facility (mR/hr) 0.2 0.2 S2hE47 PASS Sampling Room (2000' ele. Aux. Bldg.)
(mR/hr) 50.0 50.0 l
l l
92-FE
- 7. 17
AREA RADIATION MONITORS I'**
Relative (H000:30)
(H+00:45)
SDRE01 Radwaste Bldg. Corridor. Basement (West)
(mR/hr) 0.2 0.2 SDRE02 Radwaste Bldg. Corridor. Basement (Central)
(mR/hr) 0.2 0.2 SDRE03 Radwaste Bldg. Corridor. Basement (East)
(mR/hr) 0.2 0.2 SDRE04 Radwaste Bldg. Corridor. 2000' ele. (West)
(mR/hr) 0.2 0.2 SDRE05 Radwaste Bldg. Corridor 2000' ele. (Central)
(mR/hr) 0.2 0.2 SDRE06 Solid Radwaste Area. 2000' ele.
(mR/hr) 0.2 0.2 SDRE07 Radwaste Bldg. Truck Space. 2000' ele.
(mR/hr) 0.2 0.2 SDRE08 Radwaste Bldg. Sample Laboratory (mR/hr) 0.2 0.2 SDRE09 Rapygggygggy,gggveRm. Corridor, (mR/hr) 0.2 0.2 SDRE10 Rapggg{ypggp,gggveRm. Corridor.
(mR/hr) 0.2 0.2 SDRE11 Radwaste Bldg. HVAC Filter Unit (mR/hr) 0.2 0.2 l SDRE12 Aux. Bldg. Corridor. Basement (1974' ele. SE)
(mR/hr) 25.0 25.0 SDRE13 Aux. Bldg. Corridor. Basement (1974* ele. NE)
(mR/hr) 25.0 25.0 SDRE14 Aux. Bldg. Corridor. Basement (1974' ele. N)
(mR/hr) 25.0 25.0 SDRE15 Aux. Bldg. Corridor. Basement (1974' ele. W)
(mR/hr) 25.0 25.0 SDRE16 Aux. Bldg. Corridor. Basement (1974' ele. SW)
(mR/hr) 25.0 25.0 SDREl?
Nopyggg9ag}gvyPipeTunnel&PersonnelAccess (mR/hr) 0.5 0.5 SDRE18 Aux. Bldg. Ground Floor Corridor (2000' ele. N)
(mR/hr):
25.0 25.0 25.0 25.0 SDRE19 Aux. Bldg. Ground Floor Corridor (2000' ele SE)
(mR/hc)
SDRE20 Aux. Bldg. Valve Rm. Corridor (2000' ele. S)
(mR/hr) 25.0 25.0 SDRE21 Aux. Bldg. Valve Rm. Corridor (2000' ele. S)
(mR/hr) 25.0 25.0 SDRE22 Aux. Bldg. Ground Floor (2000' ele. SW)
(mR/hr) 25.0 25.0 SDRE23 Aux. Bldg. Ground Floo_r (2000* ele, W)
(mR/hr) 25.0 25.0 SDRE24 Aux. Bldg. Sampling Room (2000* ele. Central:
(mR/hr) 50.0 50.0 SDRE25 Aux. Bldg. Vent Filter (mR/hr) 5.0 5.0 SDRE26 RHR Heat Exchanger Outside (2026' ele.)
(mR/hr) 25.0 25.0 SDRE27 Cont. Purge Exhaust Filter Unit (2047' ele.)
(mR/hr) 5.0 5.0 SDRE28 Cont. Personnel Hatch (2047' ele.)
(mR/hr) 50.0 50.0 SDRE29 Hot Machine Shop (mR/hr) 0.2 0.2 SDRE30 Hot Instrument Shop (mR/hr) 0.2 0.2 SDRE31 Control Bldg. Hot Lab (mR/hr) 0.2 0.2 SDRE32 Control Bldg. Corridor (mR/hr) 0.2 0.2 SDRE33 Control Room (2047' ele.)
(mR/hr) 0.2 0.2 SDRE34 Cask Handling Area (2000' ele.)
(mR/hr) 0.5 0.5 SDRE35 New Fuel Storage (2026' ele. W)
(mR/hr) 0.5 0.5 SDRE36 New Fuel Storage Corridor (2026' ele.)
(mR/hr) 0.5 0.5 SDRE37 Spent Fuel Pool Area (mR/hr) 0.5 0.5 SDRE38 Spent Fuel Pool Area (mR/hr) 0.5 0.5 SDRE39 Seal Table Area (2026' ele. N)
(mR/hr) 200.0 200.0 SDRE40 Pe{ggg991ggcegg)HatchAreaInside e
(mR/hr) 400.0 400.0 SDRE41 Containment Bldg. (2047.6' ele. NW)
(mR/hr) 40.0 40.0 SDRE42 Containment Bldg. (2047.6' ele. E)
(mR/hr) 40.0 40.0
- bn643 Technical Support Center (mR/hr) 0.2 0.2 SDRE44 Emergency Operations Facility (mR/hr) 0.2 0.2 SDRE47 PASS Sampling Room (2000' ele. Aux. Bldg.)
(mR/hr) 50.0 50.0 92-FE 7.
18
AREA RADIATION MONITORS Time Relative (H001:00)
(Ht01:15)
SDRE01 Radwaste Bldg. Corridor Basement (West) l(mR/hr) 0.2 0.2
_5DRE02 Radwaste Bldg. Corridor, Basement (Central)
'(mR/hr) 0.2 0.2 SDRE03 Radwaste Bldg. Corridor, Basement (East)
(mR/hr) 0.2 0.2 SDRE04 Radwaste Bldg. Corridor, 2000' ele. (West)
(mR/hr) 0.2 0.2 SDRE05 Radwaste Bldg. Corridor, 2000' ele. (Central)
(nR/hr) 0.2 0.2 SDRE06 Solid Radwaste Area, 2000' ele.
(mR/hr) 0.2 0.2 SDRE07 Radwaste Bldg. Truck Space, 2000' ele.
(mR/hr) 0.2 0. 2'~
SDRE08 Radwas te Bldg. Sample laboratory (mR/hr)
O.2 0.2
~~'
SDRE09 Rapygggypggp,gggveSm. Corridor, (mR/hr) 0.2 0.2 SDRE10 Ragggggyggg9,gggvekm. Corridor, (nG /hr) 0.2 0.2 SDRE11 Radwaste Bldg. HVAC Filter Unit (mR/hr) 0.2 0.2 SDRE12 Aux, b1dg. Corridor, Basement (1974' ele. SL)
(mR/hr) 25.0 25.0 SDREla Aux. Bldg. Corridor, Basement (1974' ele. NE)
(mR/hr) 25.0 25.0 SDRE14 Aux. Bldg. Corridor. Basement (1974' ele. N)
(mR/hr) 25.0 25.0 "
SDRE15 Aux. Bldg. Corridor. Basement (1974' ele. W)
(mR/hr) 25.0 25.0 SDRE16 Aux. Bldg. Corridor, Basement (1974' ele. SW)
(mR/hr) 25.0 25.0
,jjggagggvyPipeTunnel&PersonnelAccess SDRE17 N
(mR/hr) 0.5 0.5 SDRE18 Aux. Bldg. Ground Floor Corridor (2000* ele. N)
(mR/hr) 25.0 25.0 SDRE19 Aux. Bldg. Ground Flour Corridor (2000' ele. SE)
(mR/hr) i!.0 25.0 SDRE20 Aux. Bldg. Valve Rm. Corridor (2000' ele. S)
(mR/hr) 2a.0 25.0 SDRE21 Aux. Bldg. Valve Rm. Corridor (2000' ele. S)
(mR/hr) 25.0 25.0 SDRE22 Aux. Bldg. Ground Floor (2000' ele. SW)
(mR/hr) 25.0 25.0 SDRE23 Aux. Bldg. Ground Floor (2000' ele. W)
(mR/hr) 25.0 25.0 SDRE24 Aux. Bldg. Sampling Room (2000* ele. Central)
(mR/hr) 50.0 50.0 SDRE25 Aux. Bldg. Vent Filter (mR/hr) 5.0 5.0 SDRE26 RHR Heat Exchanger Outside (2026' ele.)
(mR/hr) 25.0 25.0 SDRd27 Cont. Purge Exhaust Filter Unit (2047' ele.)
(mR/hr) 5.0 5.0 SDRE28 Cont. Personnel Hatch (2047' ele.)
(mR/hr) 50.0 50.0 SDRE29 Hot Machine Shop (mR/hr) 0.2 0.2 SDRE30 Hot Instrument Shop (mR/hr) 0.2 0.2 SDRE31 Control Bldg. Hot Lab (mR/hr) 0.2 0.2 SDRE32 Control Bldg. Corridor (mR/hr) 0.2 0.2 SDRE33 Control Room (2047' ele.)
(mR/hr) 0.2 0.2 SDRE34 Cask Handling Arca (2000* ele.)
(mR/hr) 0.5 0.5 SDRE35 New Fuel Storage (2026' ele. W)
(mR/hr) 0.5 0.5 SDRE36 New Fuel Storage Corridor (2026' ele.)
(mR/hr) 0.5 0.5 SDRE37 Spent Fuel Pool Area (mR/hr) 0.5 0.5 SDRE38 Spent Fuel Pool Area (mR/hr) 0.5 0.5-SDRE39 Seal Table Area (2026' ele. N)
(mR/hr) 200.0 200.0 SDRE40 Pegggg991ggcegg)HatchAreaInside e
(mR/hr) 400.0 400.0 SDRE41 Containment Bldg. (2047.6' ej e.
NW)
(mR/hr) 40.0 40.0 SDRE42 Containment Bldg. (2047.6' ele. E)
(mR/hr) 40.0 40.0 SDRE45 Technical Support Center (mR/hr) 0.2 0.2 l
S DRE 4 '.
Emergency Operations Facility (mR/hr) 0.2 0.2 SDRE47 PASS Sampling Room (2000' ele. Aux. Bldg.)
(mR/hr) 50.0 50.0 i
l l
92-FE 7.
19
AEFA RADIATION MONITORS Relative (H+01:30)
(H+01:45)
SDRE01 Radwaste Bldg. Corridor, Basement (West)
(mR/hr) 0.2 0.2 SDRE02 Radwaste Bldg. Corridor, Basement (Central)
(mR/hr) 0.2 0.2 SDRE03 Radwaste Bldg. Corridor. Basement (East)
(mR/hr) 0.2 0.2 SDRE04 Radwaste Bldg. Corridor. 2000' ele. (West)
(mR/hr) 0.2 0.2 SDRE05 Radwaste Bldg. Corridor. 2000' ele. (Central)
(mR/hr) 0.2 0.2
' SDRE06 Solid Radwaste Area, 2000* ele.
(mR/hr) 0.2 0.2 SDRE07 Radwaste bldg. Truck Space, 2000' ele.
(mR/hr) 0.2 0.2
~ bRE08 Radwaste Bldg. Sample Laboratory (mR/hr) 0.2 0.2 S
SDRE09 Rapygg[ygfgy,gggveRm. Corridor, (mR/hr) 0.2 0.2 10 Rapgg,gygfgy,,g,yekm. Corridor, (mR/hr) 0.2 0.2 SDRE11 Radwaste Bldg. HVAC Filter Unit (mR/hr) 0.2 0.2 SDRE12 Aux. Bldg. Corridor. Basement (1974' ele. SE)
(mR/hr) 25.0 25.0 SDRE13 Aux. Bldg. Corridor, Basement (1974' ele. NE)
(mR/hr) 25.0 25.0 SDRE14 Aux. Bldg. Corridor. Basement (1974' ele. N)
(mR/hr) 25.0 25.0 SDRE15 Aux. Bldg. Corridor, Basement (1974' ele. W)
(mR/hr) 25.0 25.0 SDRE16 Aux. Bldg. Corridor, Basement (1974' ele. SW)
(mR/hr) 25.0 25.0
$DRE17 Nop{gj{9aggg,vyPipeTunnel&PersonnelAccess (mR/hr) 0.5 0.5 SDRE18 Aux. Bldg. Ground iToor Corridor (2000* ele. N)
(mR/hr)-
'25.0 25.0 SDRE19 Aux. Bldg. Ground Floor Corridor (2000' ele. SE)
(mR/hr) 25.0 25.0 SDRE20 Aux. Bldg. Valve Rm. Corridor (2000' ele. S)
(mR/hr) 25.0 25.0 SDRE21 Aux. Bldg. Valve Rm. Corridor (2000' ele. S)
(mR/hr) 25.0 25.0 SDRE22 Aux. Bldg. Ground Floor (2000' ele. SW)
(mR/hr) 25.0 25.0 SDRE23 Aux. Bldg. Ground Floor (2000' ele. W)
(mR/hr) 25.0 25.0 SDRE24 Aux. Bldg. Sampling Room (2000' ele. Central)
(mR/hr) 100.0 100.0 SDRE25 Aux. Bldg. Vent Filter (mR/hr) 5.0 5.0 SDRE26 RHR Heat Exchanger Outside (2026' ele.)
(mR/hr) 25.0 25.0 SDRE27 Cont. Purge Exhaust Filter Unit (2047' ele.)
(mR/hr) 20.0 20.0 SDRE28 Cont. Personnel Hatch (2047' ele.)
(mR/hr) 50.0 50.0 SDRE29 Hot Machine Shop (mR/hr) 0.2 0.2 SDRE30 Hot Instrument Shop (mR/hr) 0.2 0.2 SDRE31 Control Bldg. Hot Lab (mR/hr) 0.2 0.2 SDRE32 Control Bldg. Corridor (mR/hr) 0.2 0.2 SDRE33 Control Room (2047' ele.)
(mR/hr) 0.2 0.2 SDRE34 Cask Handling Area (2000' ele.)
(mR/hr) 0.5 0.5 SDRE35
-New Fuel Storage (2026' ele, W)
(mR/hr) 0.5 0.5 SDRE36 New Fuel Storage Corridor (2026' ele.)
(mR/hr) 0.5 0.5 SDRE37 Spent Fuel Fool Area (mR/hr) 0.5 0.5 SDRE38 Spent Fuel Fool Area (mR/hr) 0.5 0.5 SDRE39 deal Table Area (2026' ele. N)
(mR/hr) 200.0 200.0 SDRE40 Pe{3gp991pgcegg)MatchAreaInside (mR/hr) 400.0 400.0 l
SDRE41 Containment Bldg. (2047.6' ele. NW)
(mR/hr) 60.0 60.0 l
SDRE/ 2 Containment Bldg. (2047.6' ele. E)
(mR/hr) 60.0 60.0 SDRE43 Technical Support Center (mR/hr) 0.2 0.2 l
SDRE44 Emergency Operations Facility (mR/hr) 0.2 0.2 i
SDRE47 PASS Sampling Root (2000' ele. Aux. Bldg.)
,(mR/hr) 100.0 100.0 92-FE
- 7. 20 t
l l
AREA RADIATION HONITORS Tims Relative l(H+02:00)
(H+02:15)
SDRE01 Radwaste Bldg. Corridor, Basement (West)
(mR/hr)~
0.2 0.2 SDRE02 Radvaste Bldg. Corridor, Basement (Central)
(mR/hr) 0.2 0.2~
SDRE03 Radwaste Bldg. Corridor, Basement (East)
(mR/hr) 0.2 0.2 SDRE04 Radwaste Bldg. Corridor, 2000' ele. (West)
(mR/hr) 0.2 0.2 SDRE05 Radwaste Bldg. Corridor, 2000' ele. (Central)
(mR/hr) 0.2 0.2 SDRE06 Solid Radwaste Area. 2000' ele.
(mR/hr) 0.2 0.2 SDRE07 Radwaste Bldg. Truck Space. 2000' ele.
(mR/hr) 0.2 0.2
$DRE08 Radwaste Bldg. Sample Laboratory (mk/hr) 0.2 0.2 SDRE09 Raggaggygggy,gggveRm. Corridor, (mR/hr) 0.2 0.2 SDRE10 Rapgg,gypfgy,gg,7ekm. Corridor, (mR/hr) 0.2 0.2 SDREll Radwaste Bldg. HVAC Filter Unit (mR/hr) 0.2 0.2 SDRE12 Aux. Bldg. Corridor. Basement (1974' ele. SE)
(mR/hr) 25.0 25.0 SDRE13 Aux. Bldg. Corridor. Basement (1974' ele. NE)
(mR/hr) 25.n 25.0 SDRE14 Aux. Bldg. Corridor, Basement (1974' ele. N)
(mR/hr) 2 5'. e 25.0 SDRE15 Aux. Bldg. Corridor, Basement (1974' ele, W)
(mR/hr) 25.0 25.0 SDRE16 Aux. Bldg. Corridor, Basement (1974' ele. SW)
(mR/hr) 25.0 25.0 SDRE17 Nop{ggggagggvyPipeTunnel&PersonnelAccess (mR/hr) 0.5 0.5 SDRE18 Aux. Bldg. Ground Floor Corridor (2000' ele. N)
(mR/hr) 25.0 25.0 SDRE19 Aux. Bldg. Ground Floor Corridor (2000' ele. SE)
(mR/hr) 25.0 25.0 SDRE20 Aux. Bldg. Valve Rm. Corridor (2000' ele. S)
(mR/hr) 25.0 25.0 SDRE21 Aux. Bldg. Valve Rm Corridor (2000' ele. S)
(mR/hr) 25.0 25.0 SDRE22 Aux. B ld g. Ground Floor (200u' ele. SW)
(mR/hr) 25.0 25.0 SDRE23 Aux. Bldg. Ground Floor (2000' ele. W)
(mR/hr) 25.0 25.0 SDRE24 Aux. Bldg. Sampling Room (2000' ele. Central)
(mR/hr) 100.0 100.0 i SDRE25 Aux. Bldg. Vent Filter (mR/hr) 5.0 5.0 SDRE26 RHR Heat Exchanger Outside (2026' ele.)
(mR/hr) 25.0 25.0 SDRE27 Cont. Purge Exhaust Filter Unit (2047' ele.)
(L1/hr) 20.0 20.0 SDRE28 Cont. Personnel Hatch (2047' ele.)
(mR/hr) 50.0 50.0 SDRE29 Hot Machine Shop (mR/hr) 0.2 0.2 SDRE30 Hot Instrument Shop (mR/hr) 0.2 0.2 SDRE31 Control Bldg. Hot Lab (mR/hr) 0.2 0.2 SDRE32 Control Bldg. Corridor (mR/hr) 0.2 0.2 SDRE33 Control Room (2047' ele.)
(mR/hr) 0.2 0.2 SDRE34 Cask Handling Area (2000* ele.)
(mR/hr) 0.5' O.5 SDRE35 New Fuel Storage (2026' ele. W)
(mR/hr) 0.5 0.5 SbRE36 New Fuel Storage Corridor (2026' ele.)
(mR/hr) 0.5 0.5 SDRE37 Spent Fuel Fool Area (mR/hr) 0.5 0.5 SDRE38 Spent Fuel Pool Area (mR/hr) 0.5 0.5 SDRE39 Seal Table Area (2026' ele. N)
(mR/hr) 200.0 200.0 SDRE40 Pe{ggggglggcegg)HatchAreaInside e
(mR/hr) 400.0 400.0 SDRE41 Containment Bldg. (2047.6' ele. NW)
(mR/hr) 100.0 100.0 SDRE42 Containment Bldg. (2047.6* ele. E)
(mR/hr) 100.0 100.0 SDRE43 Technical Support Center (mR/hr) 0.2 0.2 SDRE44 Emergency Operations Facility (mR/hr) 0.2 0.2 SDRE47 PASS Sampling Room (2000' ele. Aux. Bldg.)
(mR/hr) 100.0 100.0 92-FE
- 7. 21
AREA RADIATION HOKITORS Relative (H+02:30)
(H+02:45)
-$bRE01 Radwaste Bldg. Corridor, Basement (West)
(mR/hr) 0.2 0.2 SDRE02 Radwaste Bldg. Corrldor. Basement (Central)
(mR/hr) 0.2 0.2
~
SDRE03 Radwaste Bldg. Corridor, Basement (East)
(mR/hr) 0.2 0.2 SDRE04 Radwaste Bldg. Corridor. 2000' ele. (West)
(mR/hr) 0.2 0.2 SDRE05 Radwaste Bldg. Corridor 2000' ele. (Central)
(mR/hr) 0.2 0.2 SDRE06 Solid Radwaste Area. 2000' ele.
(mR/hr) 0.2 0.2 SDRE07 Radwaste Bldg. Truck Space, 2000' ele.
(mR/hr) 0.2 0.2 SDRE08 Radwaste Bldg. Sample Laboratory (mR/hr) 0.2 0.2 SDRE09 Rapyasgygggy,gggveRm. Corridor, (mR/hr) 0.2 0.2 DRE10 Rapygggygggp,gggyeRm. Corridor, (mR/hr) 0.2 0.2 SDRE11 Radwaste Bldg. HVAC Filter Unit (mR/hr) 0.2 0.2 SDRE12 Aux. Bldg. Corridor, Basement (1974' ele. SE)
(mR/hr) 60.0 90.0 SDRE13 Aux. Bldg. Corridor, Basement (1974' ele. NE)
(mR/hr) 55.0 85.0 SDRE14 Aux. Bldg. Corridor, Basement (1974' ele. N)
(mR/hr) 40.0 50.0 SDRE15 Aux. Bldg. Corridor, Basement (1974' ele. W)
(mR/hr) 30.0 35.0 SDRElb Aux. Bldg. Corridor. Basement (1974' ele. SW)
(mR/hr) 30.0 33.0 SDRE17 Noprgg{9agggvyPipeTunnel& Personnel Access (mR/hr) 35.0 45.0 SDRE18 Aux. Bldg. Ground Floor Corridor (2000' ele. N)
(mR/hr)
- 0.0 50.0 SDRE19 Aux. Bldg. Ground Floor Corridor (2000* ele. SE)
(mR/hr) 37.0 45.0 SDRE20 Aux. Bldg. Valve Rm. Corridor (2000' ele. S)
(mR/hr) 30.0 33.0 SDRE21 Aux. Bldg. Valve Rm. Corridor (2000* ele. S)
(mR/hr) 30.0 33.0 SDRE22 Aux. Bldg. Ground Floor (2000' ele. SW)
(mR/hr) 28.0 29.0 SDRE23 Aux. Bldg. Ground Floor (2000' ele. W)
(mR/hr) 28.0 29.0 SDRE24 Aux. Bldg. Sampling Room (2000' ele. Central)
(mR/hr) 200.0 250.0 SDRE25 Aux. Bldg. Vent Filter (mR/hr) 35.0 60.0 SDRE26 RHR Heat Exchanger Outside (202b' ele.)
(mR/hr) 58.0 85.0 SDRE27 Cont. Purge Exhaust Filter Unit (2047' ele.)
(mR/hr) 44.0 63.0 SDRE28 Cont. Personnel Hatch (2047' ele.)
(mR/hr) 80.0 100.0 SDRE29 Hot Machine Shop (mR/hr) 0.2 0.2 SDRE30 Hot Instrument Shop (mR/hr) 0.2 0.2 SDRE31 Control Bldg. Hot Lab (mR/hr) 0.2 0.2 SDRE32 Control Bldg. Corridor (mR/hr) 0.2 0.2 SDRE33 Control Room (2047' ele.)
(mR/hr) 0.2 0.2 SDRE34 Cask Handling Area (2000' ele.)
(mR/hr) 0.5 0.5 SDRE35 New fuel Storage (2026' ele. W)
(mR/hr) 0.5 0.5 SDRE36 New Fuel Storage Corridor (2026' ele.)
(mR/hr) 0.5 0.5 SDRE37 Spent Fuel Pool Area (mR/hr) 0.5 0.5 SDRE38 Spent Fuel Pool Area (mR/hr) 0.5 0.5 SDRE39 Seal Table Area (2026' ele. N)
(mR/hr)
>10000.0
>10000.0 SDRE40 Pe{ggg99,pgceg.}) Hatch Area Inside 1
(mR/hr)
>10000.0
>10000.0 SDRE41 Containment Bldg. (2047.6' ele. NW)
(mR/hr)
>10000.0
>10000.0 SDRE42 Containment Bldg. (2047.6' ele. E)
(mR/hr)
>10000.0
>10000.0 SDRE43 Technical Support Center (mR/hr) 0.2 0.2 SDRE44 Emergency Operations Facility (mR/hr) 0.2 0.2 SDRE47 PASS Sampling Room (2000* ele. Aux. Bldg.)
(mR/hr) 200.0 250.0 i
i 92-FE
- 7. 22 l
l i
AREA RADIATION HOKITORS A""
Relative (H+03:00)
(H+03:15)
SDRE01 Radwaste Bldg. Corridor, Basement (West)
(mR/hr) 0.2 0.2 SDRE02 Radwaste Bldg. Corridor. Basement (Central)
(mR/hr) 0.2 0.2 SDRE03 Radwaste Bldg. Corridor. Basement (East)
(mR/hr) 0.2 0.2 SDRE04 Radwaste Bldg. Corridor. 2000* ele. (West)
(mR/hr) 0.2 0.2 SDRE05 hadwasue Eldg. Corridor. 2000' ele. (Central)
(mR/hr) 0.2 0.2 SDRE06 Solid Radwaste Area. 2000' ele.
(mR/hr) 0.2 0.2 SDRE07 Radwaste Bldg. Truck Space. 2000' ele.
(mR/hr) 0.2 0.2
~
SDRE08 Radwaste Bldg. Sample Laboratory (mR/hr) 0.2 0.2 SDRE09 Rapygsgygggy,gggveRm. Corridor.
(mR/hr) 0.2 0.2 l SDBE10 Rapggggygggy,{g,7ekm. Corridor' i
(mR/hr) 0.2 0.2 SDRE11 Radwaste Bldg. HVAC Filter Unit (mR/hr) 0.2 0.2 l SDRE12 Aux. Bldg. Corridor. Basement (1974* ele. SE)
(mR/hr) 340.0 410.0 SDRE13 Aux. Bldg. Cortidor. Basement (1974' ele. NE)
(mR/hr) 335.0 405.0 SDRE14 Aux. Bldg. Corridor. Basement (1974' ele. N)
(mR/hr) 150.0 180.0 SDRE15 Aux. Bldg. Corridor. Basement (1974* ele. W)
(mR/hr) 72.0 98.0 SDRE16 Aux. Bldg. Corridor, Basement (1974' ele. SW)
(mR/hr) 70.0 93.0 SDRE17 Nopfggggag}gvyPipeTunnel&PersonnelAccess (mR/hr) 110.0 130.0 SDREla ~ Aux. Bldg. Ground Floor Corridor (2000* ele. N)
(mR/hr) 150.0 180.0 SDRE19 Aux. Bldg. Ground Floor Corridor (2000' ele. SE)
(mR/hr) 140.0 170.0 SDRE20 Aux. Bldg. Valve Rm. Corridor (2000' ele. S)
(mR/hr) 70.0 95.0 SDRE21 Aux. Bldg. Valve Rm. Corridor (2000' ele. S)
(mR/hr) 70.0 93.0
[ SDRE22 Aux. Bldg. Ground Floor (2000' ele. SW)
(mR/hr) 60.0 75.0
.(SDRE23 Aux. Bldg. Ground Floor (2000' ele. W)
(mR/hr) 60.0 75.0 SDRE24 Aux. Bldg. Sampling Room (2000' ele. Central)
(mR/hr) 325.0 350.0 SDRE25 Aux. Bldg. Vent Filter (mR/hr) 260.0 310.0 SDRE26 RHR Heat Exchanger Outside (2026' ele.)
(mR/hr) 310.0 370.0 SDRE27 Cont. Purge Exhaust Filter Unit (2047' ele.)
(mR/hr) 225.0 270.0 SDRE28 Cont. Personnel Hatch (2047' ele.)
(mR/hr) 448.0 520.0 SDRE29 Hot Machine Shop (mR/hr) 0.2 0.2
]SDRE30 Hot Instrument Shop (mR/hr) 0.2 0.2 3DRE31 Control Bldg. Hot Lab (mR/hr) 0.2 0.2 SDRE32 Control Bldg. Corridor (mR/hr) 0.2 0.2 SDRE33 Control Room (2047' ele.)
(mR/hr) 0.2 0.2 SDRE34 Cask Handling Area (2000' ele.)
(;.R / hr )
0.5 0.5 SDRE35 New Fuel Storage (2026' ele. W)
(mR/hr) 0.5 0.5 SDRE36 New Fuel Storage Corridor (2026' ele.)
(mR/hr) 0.5 0.5 SDRE37 Spent Fuel Pool Area (mR/hr) 0.5 0.5 SDRE38 Spent Fuel Pool Area (mR/hr) 0.5 0.5 SDRE39 Seal Table Area (2026' ele. N)
(mR/hr)
>10000.0
>10000.0 SDRE40 Pe{ggg991pgcegg)HatchAreaInside (mR/hr)
>10000.0
>10000,0 SDRE41 Containment Bldg. (2047.b' ele. NW)
(mR/hr)
>10000.0
>10000.0 SDRE42 Containment Bldg. (2047.6' ele. E)
(mR/hr)
>10000.0
>10000.0 SDRE43 Technical Support Center (mR/hr) 0.2 0.2 SDRE44 Emergency Operations Facility (mR/hr) 0.2 0.2 SDRE47 PASS Sampling Room (2000' ele. Aux. Bldg.)
(mR/hr) 325.0 325.0 92-FE 7, 23
AREA RADIATION HONITORS 1**
Rela ti v_e (H+03:45)
(H+04:00)
')RE01 Radwaste Bldg. Corridor, Basement (West)
(mR/hr) 0.2 0.2 SDRE02 Radwaste Bldg. Corridor. Basement (Central)
(mR/hr) 0.2 0.2 SDRE03 Radwaste Bldg. Corridor Basement (East)
(mR/hr) 0.2 0.2 SDRE04 Radwaste Bldg. Corridor. 2000' ele. (Wert)
(mR/nr) 0.2 0.2 SDRE05 Radwaste Bldg. Corridor, 2000' e)e. (Centraj)
(mR/hr) 0.2 0.2 SDRE06 Solid Radwaste Area, 2000' ele.
(mR/hr) 0.2 C.2
~~
SDRE07 Baiwaste Bldg. Truck Space. 2000' ele.
(mR/hr) 0.2 0.2 SDRE08 Radwaste Bldg. Sample Laboratory (mR/hr) 0.2 0.2 SDRE09 Ragggsgygggp,gggveRm. Corridor, (mR/hr) 0.2 0.2 SDRE10 Ragggggy gggy,g,ye Rm. Corridor, i
(mR/hr) 0.2
0.2 SDRE11
Radwaste Bldg. HVAC Filter Unit (mR/hr) 0..
0.2 SDRE12 Aux. Bldg. Corridor, Basement (1974' ele. SE)
(mR/hr) 525 0 365.0 SDRE13 Aux. Bldg. Corridor Basement (1974' ele. NE)
(mR/hr)
$ f7. 0 360.0 SDRE14 Aux. Bldg. Corridor. Basement (1974' ele. N)
(mR/hr) f s.0 160.0 SDRE15 Aux. Bldg. Corridor Basement (1974' ele. W)
(mR/hr) 75.0 70.0 SDRE16 Aux. Bldg. Corridor. Basement (1974' ele. SW)
(mR/hr) 71.0 65.0 SDRE17 Nop{ggg9agggvyPipeTunnel&PersonnelAccess (mR/hr) 180.0 110.0 SDRE18 Aux. Bld g. Ground Floor Corridor (2000* ele. N)
(mR/hr) 225.0 160.0 SD5E19 Aux. Bldg. Ground Floor Corridor (2000* ele. SE)
(mR/hr) 210.0 150.0 SDRE20 Aux. Bldg. Valve Rm Corridor (2000' ele. S)
(mR/hr) 71.0 65.0 SDRE21 Aux. Bldg. Valve Rm. Corridor (2000' ele. S)
(mR/hr' 70.0 64.0 SDRE22 Aux. Bldg. Ground Floor (2000' ele. SW)
(mR/ht) 65.0 54.0 SDRE23 Aux. Bldg. Ground Floor (2000' ele. W)
(mR/hr) 65.0 54.0 SDRE24 Aux. Bldg. Sampling Room (2000' ele. Central)
(mR/hr) 400.0 335.0 SLRE25 Aux. Bldg. Vent Filter (mR/hr) 405.0 280.0
~3bRE26 RHR Heat Exchanger Outside (2026' ele.)
(mR/hr) 475.0 330.0 SDRE27 Cont. Purge Exhaust Filter Unit (2047' ele.)
(mR/hr) 345.0 240.0 SDRE28 Cont. Personnel Hatch (2047' ele.)
(mR/hr) 650.0 475.0 SDRE29 Hot Machine Shop (mR/hr) 0.2 0.2 SDRE30 Hot Instrument Shop (mR/hr) 0.2 0.2 SDRE31 Control Bldg. Hot Lab (mR/hr) 0.2 0.2 SDRE32 Control Bldg. Corridor (mR/hr) 0.2 0.2 SDRE33 Control Room (2047' ele.)
(mR/hr) 0.2 0.2 SDRE34 Cask Handling Area (2000' ele.)
(mR/hr) 0.5 0.5 SDRE35 New Fuel Storage (2026' ele, W)
(mR/hr) 0.5 0.5 SDRE36 New Fuel Storage Corridor (2026' ele.)
(mR/hr) 0.5 0.5 SDRE37 Spent Fuel Pool Area (mR/hr) 0.5 0.5 SDRE38 Spent Fuel Pool Area (mR/hr) 0.5 0.5 SDRE39 Seal Table Area (2026' ele. N)
(mR/hr)
>10000.0
>10000.0 SDRE40 Pe{ggg991ggcegg)hatchAreaInside e
(mR/hr)
>10000.0
>10000,0 SDRE41 Ccntainment Bldg. (2047.6' ele. NW)
(mR/hr)
>10000.0
>10000.0 SD:
2 Contain.nent Bldg. (2047.6' ele. E)
(milhr)
>10000.0
>10000.0 SDRE43 Technical Support Center (mR/hr) 0.2 0.2
~
SDRE44 Emergency Operations Facility (mR/hr) 0.2 0.2 SDRE47 PASS Sampling Room (2000' ele. Aux. Bldg.)
(mR/hr) 400.0 335.0 92-FE
- 7. 24
AREA RADIATION MONITORS Time Relative (H+04: 15)
(H+04: 30)
SDRE01 Radwaste Bldg. Corridor. Basement (West)
(mR/hr) 0.2 0.2
_SDRE02 Radwabte Bldg. Corridor, Basement (Central)
(mR/hr) 0.2 0.2 SDRE03 Radwaste Bldg. Corridor, Basement (East)
(mR/hr) 0.2 0.2 SDRE04 hadwaste Bldg. Corridor. 2000' ele. (West)
(mR/hr) 0.2 0.2 SDREOS Radwaste Bldg. Corridor, 2000" ele. (Central)
(mR/hr) 0.2 0.2 SDRE06 Solid Radwaste Area, 2000* sle.
(mR/hr) 0.2 0.2 SDRE07 Radwaste Bldg. Tr'stk Space, 2000' ela.
(mR/hr) 0.2 0.2 SDREOS Radwaste Bldg. Sample Laboratory (mR/hr) 0.2 0.2 SDRE09 Rapygggyggg9,gggvekm. Corridor, (mR/hr) 0.2 0.2 SDRE10 Rapygggygggy,gggveRm. Corridor, (mR/hr) 0.2 0.2 SDRE11 Radwaste Bldg. HVAC Filter Unit (mR/hr) 0.2 0.2 SDRE12 Aux. Bldg. Corridor. Basement (1974' ele. SE)
(mR/hr) 330.0 310.0 SDRE13 Aux. Bldg. Corridor, Basement (1974' ele, NE)
(mR/hr) 325.0 305.0 SDRE14 Aux. Bldg. Corridor. Basement (1974' ele. N)
(mR/hr) 150.0 140.0 SDRE15 Aux. Bldg. Corridor. Basement (1974' ele. W)
(mR/hr) 68.0 65.0 SDRE16 Aux. Bldg. Corridor. Basement (1*/4' ele. SW)
(mR/hr) 64.0 61.0 SDRE17 Nop{ggggagggvyPipeTunnel&PersonnelAccess (mR/hr) 95.0 85.0 SDRE18 Aux. Bldg. Ground Floor Corridor (2000' ele. N)
(mR/hr) 150.0 140.0 SDRE19 Aux. Bldg. Ground Floor Corridor (2000' ele. SE)
(mR/hr) 140.0 130.0 SDRE20 Aux. Bldg. Valve Rm. Corridor (2000* ele. S)
(mR/hr) 64.0 61.0 SDRE21 Aux. Bldg. Valve Rm. Corridor (2000' ele. S)
(mR/hr) 63.0 60.0 SDRE22 Aux. Bldg. Ground Floor (2000' ele. SW)
(mh/hr) 53.0 52.0 SDRE23 Aux. Bldg. Ground Floor (2009' ele. W)
(mR/hr) 53.0 52.0 SDRE24 Aux. Bldg. Sampling Room (2000' ele. Central)
(mR/hr) 320.0 315.0 SDRE25 Aux. Bldg. Vent Filter (mR/hr) 250.0 230.0 SDRE26 RHR Heat Exchanger Outside (2026' ele.)
(mR/hr) 300.0 280.0 SDRE27 Cont. Purge Exhaust Filter Unit (2047' ele.)
(mR/hr) 220.0 205.0 SDRE28 Cont. Personnel Hatch (2047' ele.)
(mR/hr) 440.0 415.0 SDRE29 Hot Machine Shop (mR/hr) 0.2 0.2 SDRE30 Hot Instrument Shep (mR/hr) 0.2 0.2 SDRE31 Control Bldg. Hot Lab (mR/hr) 0.2 0.2 S>RE32 Control Bldg. Corridor (mR/hr) 0.2 0.2 SDRE33 Control Room (2047' ele.)
(mR/hr) 0.2 0.2 SDRE34 Cask Handling Area (2000* ele.)
(mR/hr) 0.5 0.5 SDRE35 New Fuel Storage (2026' ele, W)
(mR/hr) 0.5 0.5 SDRE36 New Fuel Storage Corridor (2026' ele.)
(mR/hr) 0.5 0.5 SDRE37 Spent Fuel Pool Area (mR/hr) 0.5 0.5 SDBE38 Spent Fuel Pool Area (mR/hr) 0.5 0.5 5DRE39 Seal Table Area (2026' ele. N)
(mR/hr)
>10000.0
>10000.0 SDRE40 Pegggggplpgcegg)HatchAreainside (mR/hr)
>10000.0
>10000.0 SDRE41 Containment Bldg. (2047.6' ele. NW)
(mR/hr)
>10000,0
>10000.0 SDRE42 Containment Bldg. (2047.6' ele.
E>
( r.k / hr )
>10000.0
>10000.0 SDRE43 Technical Support Center (mR/hr) 0.2 0.2 SDRE44 Emergency Operations Facility (mR/hr) 0.2 0.2 SDRE47 PASS Sampling Room (2000' ele. Aux. Bldg.)
(mR/hr) 320.0 315.0 92-FE
- 7. 25
I AREA RADIATION MONITORS Relative l(H+04:45)
(H005:000)
SDRE01 Radwaste Bldg. Corridor, Basement (West)
(mR/hr) 0.2 0.2 SDRE02 Radwaste Bldg. Corridor, Basement (Central)
(mR/hr) 0.2 0.2 SDRE03 Radwaste Bldg. Corridor, Basement (East)
(mk/hr) 0.2 0.2 SDRE04 Radwaste Bldg. Corridor, 2000' ele. (West)
(mR/hr) 0.2 0.2 SDRE05 Radwaste Bldg. Corridor, 2000' ele. (Central)
(mR/hr; 0.2 0.2 SDRE06 Solid Radwaste Area, 2000' ele.
(mR/hr) 0.2 0.2 SDRE07 Radwaste Bldg. Truck Space, 2000' ele.
(mR/hr) 0.2 0.2 SDRE08 Radwaste Bldg. Sample Laboratory (mR/hr) 0.2 0.2 SDRE09 Rapygsgygfg9,VggveRm. Corridor, (mR/hr) 0.2 0.2 S
10 Raggg,gygfgg,egeyeRm. Corridor, (mR/hr) 0.2 0.2
_SDREll Radwaste Bldg. HVAC Filter Unit (mR/hr) 0.2 0.2 SDRE12 Aux. Bldg. Corridor, Basement (1974' ele. SE)
('t/hr) 295.0 288.0 SDRE13 Aux. Bldg. Corridor. Basement (1974* ele. NE)
(mR/hr) 290.0 283.0 SDRE14 Aux. Bldg. Corridor, Basement (1974' ele. N)
(mR/hr) 130.0 125.0 SDRE15 Aux. Bldg. Corridor. Basement (1974' ele. W)
(mR/hr) 63.0 60.0 SDRE16 Aux. Bldg. Corridor. Basemert (1974' ele. SW)
(mR/hr) 59.0 56.0 SDRE17 Nop{gg{9agggvyPipeTunnel&PersonnelAccess (mR/hr) 80.0 75.0 SDREle Aux. Bldg. Ground Floor Corridor (2000' ele. N)
(mR/hr) 130.0 125.0 SDRE19 Aux. Bldg. Ground Floor Corridor (2000' ele. SE)
(mR/hr) 122.0 119.0 SDRE20 Aux. Bldg. Valve Rm. Corridor (2000* ele. S)
(mR/hr) 59.0 56.0 SDRE21 Aux. Bldg. Valve Rm. Corridor (2000' ele. S)
(mR/hr) 57.0 54.0 SDRE22 Aux. Bldg. Ground Floor (2000* ele. SW)
(mR/hr) 48.0 47.0 SDRE23 Aux. Bldg. Ground Floor (2000' ele. W)
(mR/hr) 48.0 47.0 SDRE24 Aux. Bldg. Sampling Room (2000* ele. Central)
(mR/hr) 310.0 305.0 SDRE25 Aux. Bldg. Vent Filter (mR/hr) 220.0 215.0 SDRE26 RHR Heat Exchanger Outside (2026' ele.)
(mR/hr) 270.0 265.0 SDRE27 Cont. Purge Exhaust Filter Unit (2047' ele.)
(mR/hr) 195.0 190.0 SDRE28 Cont. Personnel Hatch (2047' ele.)
(mR/hr) 400.0 390.0 SDRE29 Hot Machine Shop (mR/hr) 0.2 0.2 SDRE30 Hot Instrument Shop (mR/hr) 0.2 0.2 SDRE31 Control Bldg. Hot Lab (mR/hr) 0.2 0.2 SDRE32 Control Bldg. Corridor (mR/hr) 0.2 0.2 SDRE33 Control Room (2047' ele.)
(mR/hr) 0.2 0.2 SDRE34 Cask Handling Area (2000' ele.)
(mR/hr) 0.5 0.5 SDRE35 sNew Fuel Storage (2026' ele. W)
(mR/hr) 0.5 0.5 SDRE36 New Fuel Storage Corridor (2026' ele.)
(mR/hr) 0.5 0.5 SDRE37 Spent Fuel Pool Area (mR/hr) 0.5 0.5 SDRE38 Spent Fuel Pool Area (mR/hr)
U.5 0.5 SDRE39 Seal Table Area (2026' ele. N)
(mR/hr)' *10000.0
>10000.0 SDRE40 Pegggg9elkEC'SE) Hat h Area Inside e
(mR/hr)
>10000.0
>10000.0 SDRE41 Containment Bldg. (2047.6' ele. NW)
(mR/hr)
>10000.0
>10000.0 SDRE42 Containment Bldg. (2047.6' ele. E)
(mR/hr)
>10000.0
>10000.0 SDRE43 Technical Support Canter (mR/hr) 0.2 0.2 SDRE44 Emergency Operations Facility (mR/hr) 0.2 0.2 SDRE47 PASS Sampling Room (2000* ele. Aux. Bldg.)
(mR/hr) 310.0 305.0 92-FE
- 7. 26
_... ~, -. -..
1 INPIANT SURVrYS RADIATIOh Inplant survey map data is provided in the following subsection.
Data is provided for each floor level of the auxiliary, fuel and diesel generator buildings.
Radiation data is provided in the units as indic6ted.
The data is deoignated by a letter and corresponds to the circled letter zones on ths map.
)
Radiation levels indicated with a < sign indicate areas where readings will generally be below the lower level of detectability for instruments used in determining radiation levels.
Area radiation monitors are designated on the maps as the menitor number preceeded by a 'SD*.
The data for these monitors is provided in the area radiation mo.
e ' ring data.
92-FE
- 7. 27
en s as m i. erv s/es I
I C~") i g
SD 18 SDIS
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AUX. BLDS 1974'-0" (RADIATION LEVELS INDICATED ARE IN R/HR)
Time:
H+00:00 - 02:15 H+02:30+
l (A) Corridor Area 0.025 0.700 (B)
Pump Room Areas 0.050 0.250 (C) Boric Acid Tank Areas
<0.002 0.050 (D) Corridor Area 0.025 0.080 (E) Aux FW Pump Area
<0.002 0.220 92-FE
- 7. 20 m~
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(A) RHR Encapsulation Areas 1.0 1.700 l
(B) Corridor Area 0.050 0.250 (C) Corridor Area 0.050 0.150 i
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92-FE
- 7. 29
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Time:
H+00iO3 - 02:15 H+02:30+
(A)
Pipe Penetration Areas 0,300 0.800 (B) Corridor Area 0.025 0.200 (C) RHR Heat Exchange Areas 0.200 0.300 (D) Sampling / PASS Areas 0.200 0.300 (E) Feedwater Pump Room
<0.002 0.075 92-FE
- 7. 30
_ _. _ _ -.. _ _... _ _ _ _ _ _.. _ _ _. _. _ _ _. _. _..... ~. _. _. _ _
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(RALIATION LEVELS INDICATED ARE IN R7HR)
Time:
H400iOO - 02i,Q H+02:30+
(A)
Elect. Penetration Areas 0.100 0.500 (B) Corridor Area 0.020 0.500 (C) CCV Pump Areas 0.010 0.280 (D) Main IV Pump Areas 0.010 0.410 92-FE
- 7. 31
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(RADIATION LEVELS INDICATED ARE IN R/HR)
Time H+00100 - 02:15 H+02:30+
(A)
Personnel Hatch Area 0.050 0.100 (B) Aux Bldg Roof Area
<0.002 0.100 (C)
Ctmt Purge Exhaust Area 0.005 0.375 (D)
Ctat Purge-Supply Area 0.005 0.380 (E) CR Filtration Area
<0.002 0.100 (F) MSIV Area 0.020 0.150 i
5 l
92-EE
- 7. 32
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A N
PUEL RDO. 2000'-0" (RADIATION LEVELS INDICATED ARE IN R/HR)
All levels of the Fuel Building show radiation levels-to be <0.002 R/hr throughout the duration of the exercise.
l l
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L 92-FE
- 7. 33
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N FUEL KDS. 2099'-0" (RADIATION LEVELS INDICATED ARE IN R/HR)
All levels of the Fuel Building show radiation levels to be <0.002 R/hr throughout the duration of the exercise.
92.FE
- 7. 34
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All levels of the Fuel Building show radiation levels to be <0.002 R/hr throughout the duration of the exercise.
92-FE 7.
35
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enn e>ou.e, sev un 1111.
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(RADIATION LEVELS INDICATED ARE IN-R/HR)
Times (ALL TIMES)
(A) General Floor Area
<0.002 (B) General Floor Area
<0.002 l
92-FE
- 7. 36
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I SECTION 8.0 i
0FFSITE RADIO!AXIICAl, PARAMETERS 92-FE 8.
O
i 1
0FFSITE RADIO!,0GICA1 PARAMETERS A map of the area surrounding WCGS is included in the field team kits.
Field teams may be directed to the predesignated monitoring locations indicated on the map or to other locations, however, no offsite radioactive plume will be observed since there is no release of radioactive materials from the plant.
92.FE.
8.
1
SECTION 9.0 CONTR04f"R ASSIGNMDf75 AND INSTRUCTIONS Sut>seet1ons f_gyz ASSIG MENTS 9.1 IN'iTRUCTIONS 9.2 l
I 97-FE 9.
0
.QpNTROLLP3 ASSIGNMENTS AS SIG!IMENT HAME Lead Controllers Mark Schreiber Ken Craichead Lisa Herhold CR Lead Controller Glenn Reeves CR Operations Paul Sudnak (UE)
CR Communications /HP/ Chemistry Randy Skiles CR Plant Teams (3 - dispatched from Duane Smith computer room)
Barry Brooks Art Mah TSC Lead Controller / Communications Larry Stevens TSC Dose Assessment Ralph Lonsdon TSC Engineering Ken Gross (UE)
TSC Rad. Team Skip Holman OSC Lead Controller Lee Noblen OSC Health Physics Carolyn Criaui OSC Onsite Teams (4)
Royce McMahon Alex Hawley Bud Freeman Pete DeBlenk PASS Team Bruce Reischmann OSC Offsite Monitoring Teams (2)
Jeff Walton Sue Burkdo11 Security Accountability Controller Pete Lutze EOF Lead Controller / Communications Britt McKinney EOF Engineering Dan Dullum EOF Dose Assessment Bill Ketchum EOF Rad Team Craic Swarteendruber Public Information Controller Mona Crimsley County EOC Brian Vinrenried State EOC Sheila Teal The Control Room Simulator and NPIS computer will be opert ed by Dale Moses, Dave Fehr, and Glenn Reeves.
92-FE 9.
1
CONTRot.l.13 INSTRUCT)ONS 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.
i m
92-FE 9.
2
CONTROLLER INSTRUCTIONS A.
Contro11ere shall pre-position themselves in the appropriate emergency response f acility no later than 30 minutes prior to the cocunencement of Exercise activities.
B.
Controllers must Controller.
couply with instructions from the Exercise Lead C.
Prior to the commencement of Exercise activities, controllers shall test Exercise Lead Controller.telecongnunications to ensure operable communicatio D.
Prior to the conenencement 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.
information messages, mustController messages, specifically scenario, on prior to issuance.
be approved by the facility Lead Controller 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 t'e appropriate players.
11.
Information regarding scenario event s 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 Greek participants.
1 i
l t
92-FE 9.
3
.._._m.._
i SECTION 10.0 JNAltlATOR ASSIC24DITS AND INSTRUCTIONS Subs ect ionti faggt Evaluator Assigreents 10.1
[
Evaluator Instructions 10.2 s
Evaluation Checklists 10.4 Evaluation Summary 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 /
Jeint Radiological Honitoring Team 10.16 Emergency Operations Facility 10.10 county EOC 10.21 State EOC 10.22 Evaluation Log Sheets 92-FE 10.-
0
~.
WAI.UATOR ASSIGNMMTS M S TGNMENT NAME Lead Evaluator Mark Schreiber CR Evaluator lef f Pantian CR Plant Teams (dispatched from computer room)
Rich Meister TSC Lead Evaluator Ed Peterson TSC Doge Assessment ray Rwan TSC Engineering Een Frederickson TSC Communications Mindy sadovski TSC Rad. Team Ray Ryan OSC Lead Evaluator
,Gn} ton Holman OSC llealth Physics Gren McClelland OSC Onsite Teams (4)
Dave Donohoe RoRet Guard Cliff Blow fich Gerdes PASS Team fruce Reischmann OSC Offsite Monitoring Teams (2)
Jeff Walton Sue Burkdoll Security Acccuntability Evaluator Montie McKinney EOF Lead Evaluator Tarry Damashek EOF Engineering Terry Carrett EOF Dose Assessment Chris Reekte EOF Rad Team Chrin Reekte EOF Communications Jeanne DaRenette Public Information Mons Crimeley County EOC Brian Winrenried State EOC Sheila Teal i
l l
92-FE 10.
1
l t
EVAL,UATOR INSTRUCTIONS Evaluator instructions defining the types of interactions and conduct expected from evaluators are included in the following subsection.
All instructions included in the following subsection must be adhered to since evaluators may at times have a direct input into the success of the
- Exercise, i
92'.FE 10.
2-h-.
nw y
EVALUATOR INSTRUCTIONS A.
Evaluators shal.
re-position themselves in the appropriate emergency response facility no later than 30 minutes prior to the commencement of Exorcise activities.
B.
Evaluators must comply with instructions from the Exercise Lead Evaluator.
C.
Prior to the commencement of Exercise activities, evaluators shall synchroni.ze 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 carefully note the arrival and departure times for players, the times at which major activities or milestones occur, at.3 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.
J.
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.
All facility Lead Evaluators whall submit a formal critique to be completed following the terminstion of Exercise activities.
The format of the critique will be as follows:
1.)
Summary of Events and Overall Evaluation 2.)
Timeline of Activities 3.)
List of Observations. Improvement Items and Deficiencies J.
The facility Lead Evaluators shall ensure that -layers' psperwork, loge, notification forms, etc. produced in the.ourse of Exercise activities are turned into the Exercise Lead Evaluator during the controller / evaluator critique.
1 l
l 92-FE 10.
3 l'
I-1
_ ~.
. _ - -. = _ _. -
EVALUATION CilECKLISTS Evaluation checklists are included in the following subsection.
Checklists sre categorized by facility or response function and then into specific objectives to be demonstrated by that facility or response function.
The objectives provided in the checklists correspond to the objectives to be demonstrated as identified 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
Deficient.y:
A significant failure or inadequacy.
l' 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 "Perf ormance improvenient Request. "
Weakness:
A failure or inadequacy in any WCHOC-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.
Observation:
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 tracked through the E-Plan Action Item Tracking System.
Good Practice:
An item identified during drills and exercises which should be continued to enhance the implementation of the Emergency Planning Program.
92-FE 10, 4
- _. _ _ ~ - - -
-. = - -.. _ _ _ _ _ _._
PNAl,UAMON _ CitECKL1 STS EVA!.UATION SUbHARY Evaluator:
Assignments (Use additional pages as required)
DEFICIENCIES:
i VEAKNESSES :
IMPROVD4ENT ITDiS :
GOOD PRACTICES:
Mu 52-FE 10, 5
l l
EVALUATION CIIECKLISTS Evaluator Assignment
- Control Room Yes No N/0 juA Obiective I.1.
Accident detection and assessment a.
Did the Shift Supervisor properly evaluate the emergency?
1.2.
Emergency classification a.
Was an Alert declared promptly?
I.3.
N.tification 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 Alert?
b.
Did CR per;,nnel promptly sound the emergency alarm and announce via GAI-tronics Form EP 01-1.0-1 for the Alert?
c.
Were followup notifications made to the State and County every 30 minutes after the immediate Notification?*
I.4.
Communications a.
Were phones and GAI-tronics operable for making notifications or trans-mitting information?
b.
Were radios operable if phones were inoperable?
- After the initial Alert notification, further notifications will be made only as long as the State and County remain activated or are willing to receive the notifications.
92-FE 10.
6
EVALUATION CIIECK1.ISTS Control Room Yes No j{LQ l{]f Ohlective 7
Radiological exposure control a.
Was CR habitability established?
i t.
Did the Shift Supervisor authorize overexposure or recommend the use of KI to any WCHOC emergency worker?
c.
Was this authorization / recommendation based on criteria in EPPs 01-9.1 and 01-9.37 I.6.
Protective action recommendations a.
Did the Shift Supervisor include any protective action recommendation on the Immediate Notification Forms for the Alert?
b.
If a) is 'yes', were the recommendations based on the criteria in EPP 01-10.17 1.7 Staff augmentation a.
Did the Shift Supervisor augment the CR staff when the BOP opetator left the area?
I.8.
Shift staffing AND 11.1.
Off-. hours staffing a.
Was a complete Control Room shift complement available during the drill?
II.17.
Assembly and accountability a.
Was a complete Conttst Room shift complement initially ac;nunted for and periodically checuea during the drill?
9T.-FE 10.
7
EVALUATION CilECKLISTS Evaluator:
Assignment Security Yes No
!!Lt
!UA Objective I.1 communications a.
Were radio communications accurate and clear?
11.17.
Assembly and Accountability a.
Was there an orderly evacuation of all non-essential personnel?
b.
Did Security personnel control site access in accordance with Security procedures?
c.
Were all onsite personnel accounted for within 30 minutes post-classifi-cation of an Alert?
NOTE:
This excludes personnel on the exempt list.
d.
Did Security initiate steps to locate unaccounted-for individuals?
t f
l l
l 92-FE 10.
8
EVALUATION CHECKLISTS Evaluator:
Assignments J_echnical Support Center Yes No N/0 I!]A Oblective I.1.
Accident detection and assessment a.
When the TSC was activated was the DED aware of all significant events prior to that t!me?
b.
Did the REC promptly request that two Offsite Monitoring Teams be dispatched?
c.
Did *he DED convene regular managers' meetings and then update the balance of the TSC staff on the event status?
d.
Did the TSC personnel actively support the Control Room's efforts to identify the cause of the inci-dent and mitigate it?
e.
Did the TSC Engineering Team work with the EOF Engineering Team to determine short and long range solutions to the incident?
f.
Were ERDC Teams requested for dis-patch to problem areas promptly?
g.
Were the status boards maintained regularly and accurately?
h.
Was plant data effectively manually transmitted and tracked after the NPIS screens vent blank (simulated)?
I.2.
Emergency classification a.
Was the Site Area Emergency promptly declared by the DED7 i
92-FE 10.
9
~..-
EVALifATION CIECELISTS Technical Surrort Center Yes No 112 fila Obiective I.3.
Notification of onsite and offsite emergency responders a.
Did the TSC Communicator complete the Immediate Notification Form (Form EP 03-3.1-1) and call the appropriate personnel within appli-cable time constraints (15 min.
State, County ASAP and within one hour - NRC)?*
NOTE:
NRC communications may be performed by the ENS Communicator.
b.
Did the CR sound the Plant Emergency Alarm and announce, via GAI-tronics, Form EP 2.2-3:
- for a Site Area Emergency?
c.
Were follovup notifications made to the State and County overy 30 minutes after the Immed3'te Notification?*
d.
Were the State, County and NRC notified of TSC activation?*
1.4 Communications a.
Wero t ' e f ollowing types of communication operable during the d-ill
- I M r.v c eilos
- GAI-tronics I.5.
Radiological exposure control l-a.
Did the DED authorize overexposure-
)
or recommenti the use of KI to any WCNOC emergency worker?
- Nctifications will be made only if the State and County are activated or willing to receive the notifications.
92-FE
- 10. 10
-w
EVALUATION CIIECKLISTS Technical Supr rt Center Yes No N/O
?I / A obiective b.
Was this authorization / recommendation based on criteria in EPPs 01-9.1 and 01-9.37 c.
Was TSC habitability established and verified at least every hour?
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". *rere these r3commendati ed on discus-sions with the nu, ad 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 PARu?
I.8.
Shift staffing AND 11.6.
Off-hours staffing a.
Was the TSC activated within 60 minutes after the Alert was classified?
b.
Was a complete TSC shift comple-ment available during the drill?
- dependent on County and State extent of play.
92-FE 10, 11
EVALUATION CHECKLISTS Technical Support Ceq1er D-NIA Obiective II.17.
Assembly and accountability a.
Was a complete TSC shift comple-1 ment initially accounted for and periodically checked during the drill?
l l
[
92-FE
- 10. 12 i
EVALUATION CIIECKLTSTS Evaluator:
Assignment PASS /Onsite Survev/ERDC Team Yes No N/0 N/A obiective i
I.4.
Communic. 1
.i s a.
Vere the radios in the emergency cabinet 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.
Vere Team members supplied with correct range dosimetry and TLDs?
d.
If samples were obtained, were they handled in a way to minimize exposure?
92-FE
- 10. 13
EVALUATION CHECKLISTS Evaluator:
Assignments-operations Support Center Yes No N/0 N/A oblective I.1.
Accident detection and as essment a.
Were Onsite Survey Teams /ExDC Teams briefed on:
- radiation / contamination levels
- route to and from work area
- Dosimetry, PC, respirator requirements
- allowable doses or stay time
- air monitoring and radiological control requirements
- their team identificatioa I.4.
Communications a.
Were the Teams in radio or GAI-tronics contact with the TSC or OSC at all times?
b.
Were all the radios in the OSC emergency cabinet operable?
c.
Were phone communications avail-able__between the OSC Supervisor's office and the TSC7 I.5.
Radiological exposure control
. Was OSC habitability established then verified every hour?
b.
Were the Team members issued-adequate dosimetry for the radio-logical conditions they might encounter?
c.
Was KI recommended to be teken I
by b r.v ream member?
i d.
If c.
(s "yes", was KI readily j
avai10 ole?
92-FE
- 10. 14-
EVALUATION CHECKLISTS Operations Support Center Yes No N/O N/A obiective 1.8.
Shift staffing AND 11.1.
Off-hours staffing
- r.. Was the OSC activated within 60 mi.4utes post-classification of the Alert?
b.
Were all OSC ERO positions staffed?
II.17.
Assembly and accountability a.
Was a complete OSC shift comple-ment initially accounted for and periodically checxed during the drill?
(
92-FE
- 10. 15
_a
EVALUATION CHECKLISTG Evaluator: _,
Assignment:
Offsite Monitorine. Teams Yes No N/O N/A Obiective i
I.4.
Communications a.
Were the radies in the emergency cabinet 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 equipinent available and used?
c.
Were Team members supplied with correct range dosimetry and TLDs?
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-logicci conditions
- location to join Offsite Monitoring Team, if applicable e.
Did Team members keep their exposure ALARA by moving to low l
-background areas for counting of samples?
f.
Was dosimetry checked periodically?
92-FE
- 10. 16
EVALUATION CIIECKLISTS Offsite Monitorine Teams Yes No N/0 ljQ4 Obiective 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
/
92-FE
- 10. 17
EVALUATION CHECKLTSiS Evaluator:
Assignment:
Emercency Operations Facility les No N/0 N/A Obiective I.1.
Accident detection and assessment i
a.
When the EOF was activated, was the DEM aware of all significant events prior to that time?
b.
Did the DEM convene regular managers' meetings and then update the balance of the EOF staff on the event status?
c.
Were EOF personnel actively engaged with TSC personnel to mitigate the incident?
d.
Did the EOF Engineering Team work with the TSC Engineering Team to determine short, mid-and long range solutions to the incident?
I.3.
Notification of onsite and offsite emergency responders a.
Were followup notifications made to the State and County every 30 minutes 7*'
I.4.
Communications a.
Were the following communication lines operable:
- ERO phones
- ENS phone
- HPN phone
- Telecopier l'
l Notifications will be made only as long as the State and County l
remain activated or are willing to receive the notifications.
1 i
(
l i
92-FE
- 10. 18 i
l
EVALUATION CHECKLISTS Emere.ency Operations Facility Yes No N/O N/A obiective 1.5.
Radiological expnsure control a.
Did the DEM authorize over-exposure for any WCNOC emergency worker?
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?
d.
Was dosimetry positioned through-out the EOF 7 e.
Was dosimetry checked periodically?
I.6.
Protective action recommendations a.
Did the DEM include new protective action recommendations on the Immediate Notification Form?
b.
If a. is "yes", were these recommendations based on:
- dose calculations,
- discussions with the RAM and TRM, ot
- automatic PARS in EPP 01-10.1 c.
Were PARS posted correctly on the status boards and the notification form?
d.
Were PARS discussed with the State RAM and/or the SDEP representative?**
e.
Were changes in PARS transmitted to the State and County within 15 minutes of being made?*
Notifications will be made only as long as the State and County remain activated or are willing to accept notifications.
State officials may elect not to play and therefore may not be present.
92-FE
- 10. 19
EVALUATION CEIECKLISTS Emergency Operations Facility ies No N/0 N/A Obiective f.
Was implementation of the FARs followed up by the DD4 as to the status of their implementation?
g.
Were JRMTs awat e of the current PARS?
I.8.
Shift staffing AND II.1 Off-hours staffing a.
Was the EOF activated within 90 minutes after the Site Area Emergency classification?
b.
Was a complete EOF shift complement available during the drill?
II 17.
Assembly and accountability a.
Was a complete EOF shift comple-ment initially accounted for and periodically checked during the drill?
92-FE
- 10. 20
JVAI,UATION CIIF.CKLISTS Coffev County EOC Yes No N/0 N/A Objective 32.
Demonstrate the capability to carry out emergency response functions in an unannounced exercise or drill.
33.
Demonstrate the capability to carry out emergency response functions during an
=.
off-hours exercise or drill.
a.
Did the dispatcher use an Immediate Notification Form when the initial call came from Wolf Creek?
b.
Did the dispatcher begin his/her call list as soon as possible after receiving the Immediate Nctification?
c.
Did the dispatcher document reaching each individual on the call list and noting the ETA 7 d.
Did key players come in to the EOC in a timely fashion?
Emergency Preparedness Coordinator (EPC)
Radiological Officer (RO)
Commissioner e.
Did key players initiate their call lists as soon as possible after coming in to the EOC7 EPC RO Commissioner f.
Did each key player document reaching each individual on the call list and noting the ETA 7 EPC R0 Commissioner g.
Did the FPC contact the State and WCNOC7 92-FE
- 10. 21
EVALUATION CHECKLTSTS State EOC Yes No Nio p_LL Obiective 32.
Demonstrate the capability to carry out emergency response functions in an unannounced exercise or drill.
33.
Demonstrate the capability to carry out emergency response functions during an off-hours exercise or drill.
a.
Did the Duty Officer document when the initial call came from Wolf Creek?
b.
Did key players come in to the EOC in a timely fashion?
Duty Officer and/or his designee State Radiological Assessment Manager (SRAM) c.
Sid key players initiate their call lists as soon as possible after coming in to the EOC7 Duty Officer SRAM d.
Did each key player document reaching each individual on the call list and noting the ETA 7 Duty Officer SRAM e.
Did the Duty Officer contact the County and WCNOC7 92-FE
- 10. 22
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