ML20128B516
| ML20128B516 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 07/15/1992 |
| From: | SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| Shared Package | |
| ML20128B514 | List: |
| References | |
| NUDOCS 9212040006 | |
| Download: ML20128B516 (224) | |
Text
{{#Wiki_filter:- - - - - - - - - - - - - - _ _ O I ANNUAL Exeacise i July 15,1992 I O V. C. Summer Nuc ear Station 4 pro:888u889k
Table of Contents O Exercise Logistics 1 Scope arid Objectives 2 Narrative Summary 4 Time Line 7 Chronological Listing of Major Events 8 Release information 10 Inoperable Equipment 11 Event Listings and Classifications 12 Messanes 26 Group Packages 35 Health Physics Data 60 Chemistry & Release Data 90 Plant Status and RMS Data 157 ControllerInformation 209 e i
i e EXERCISE LOGISTICS
- 1. Pre exercise information provided to participating players by letter
- 11. Allowed Simulation A. Changeout of RM-A3 and RM A4 filters B. Use of silver zeolite filters C. Wearing of plastic anti contamination clothing D. Hooked up of Scott Air Pack air supply i E. Wearing of anti contamination clothing outside of the RCA i
) R. Any other actions that could adversely affect personnel safety, plant i operations, or public relations. j lit. Critiques A. Area Critiques To be held in each major area with controllers and participants O immediately upon termination of exercise B. Controller Critique To be held at 1:00 p.m. on July 16,1C92 in the Security Building Meeting Room. All lead controllers shall attend. C. Formal NRC Critique To be held at 1:00 p.m. on July 17,1992 in the NOB Cafeteria. All lead controllers shall attend. I I
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VIRGIL C. SUMMEk NUCLEAR STATION SCOPE AND OBJECTIVES On July 15, 1992, between the hours of 1800 and 2400, a Radiological Emergency Exercise will be conducted at the Virgil C. Summer Nuclear Station (VCSNS) to test the integrated capability of the emergency organizations and a major portion of the Emergency Plan's basic elements. The simulated emergency will require mobilization and response of on-site and off-site company personnel to verify their capability in an actual emergency. The exercise will not require the full participation of local and state government emergency personnel. This is a utility-only exercise. The specific elements of the VCSNS Radiation Emergency Plan which will be ) exercised include: Accident assessment and classification Managerial direction and control Technical Support Center operations Operations Support Center operations Emergency Operations Facility operations
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News Media Center operations (Utility only) Site evacuation, personnel accountability and access control Public alerting and notification procedures (simulated activation of the siren system) Radiological monitoring and dose assessment The objectives of the Radiological Emergency Exercise for South Carolina Electric & Gas Company (SCE&G) personnel are:
- 1. Test the ability of Operations personnel to effectively asses and respond to an abnormal operating condition which may produce an off-site radioactive release.
- 2. Test the abilities of Health Physics and Environmental Monitoring personnel, operating under emergency conditions, to monitor and assess radiological dose rates; to determine specific contamination levels, airborne and/or surface deposited concentrations; and, to assess specific indications (including their rates to change) that may be used for initiating emergency measures. This constitutes one of the Semi-Annual Health Physics Drills and the Annual Radiation Monitoring Drill.
- 3. Test the effectiveness and operability of VCSNS's site warni-o and evacuation procedures.
- 4. Test the effectiveness of VCSNS's emergency communicatior.3 systems between the VCSNS and federal, state and local governments and field monitoring teams. This section constitutes the Annual Communications Drill.
- 5. Test the operations of the Technical Support Center and the Operations Support Center and the ability of staffing personnel to respond to an -
emergency condition. 2
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T=40, Operators should be isolating the 'C' Steam Generator. 'C' Main Steam Isolation Valve will be closed during this procedure. At T=45, while isolating 'C' Steam Generator, the 'C' Steam Generator to Turbine-Driven Emergency Feed Pump Isolation Valve (XVG 02802B) cannot be closed from the Main Control Board. An Operator should be sent to locally investigate and close this valve. At T=55, the Contrcl Room receives a report from an Operator, at XVG 02802B, that the valve cannot be manually closed locally. (This is due to a failure of the Limitorque linkage to engage.) At approximately T=60, the Turbine-Driver' imergency Feed Pump starts due to low levels in 'A' and 'B' Steam Generators which will occur during rapid plant cooldown. The Turbine-Driven Emergency Feed Pump will come up to minimal speed and cannot be controlled frv the Main Control Board. This will be due to an I/P converter problem , 'n the pump's governor. The Turbine-Driven Emergency Feed Pump steam exhaust boot will come loose from the piping when the pump starts. This will fill the room with contaminated steam. When the pump is secured, the steam will be removed by the room's normal ventilation. At T=90, the 115 Kv Parr Line will de-energize. Tnis will result in a loss of ' A' Train off-site power; and because the ' A' Diesel Generator is still inoperable, the IDA Switchgear will be de-energenized. This should be classified as a Site Area Emergency. At T=140, the Main Condenser Vacuum will be restored. This will allow use of the Main Condenser for further cooldown of the plant, if desired. ! At T=180,- the Corporate Dispatcher will call the Control Room and report that the Relay Department has replaced a distance relay on the 115Kv line at Parr. l The 115Kv line is ready to be re-energized. This will allow restoration of I 'A' Train, off-site power. 5
At T=190, ' A' Train, off-site power will be restored by energizing the 115Kv (Parr) line. This will allow the Off-Site Emergency Coordinator to begin recovery planning and possible de-escalation of the Emergency classification. At T=210, the exercise will be terminated. J d O 1 O 6
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i e 4 4 VIRGIL C. SUMMER NUCLEAR STATION j b( ) SCOPE AND OBJECTIVES
- 6. Test the ability of the Operations Scoport Center to effectively dispatch and track the progress of emergency repair teams and to report team status and results.
- 7. Test the ability of Operations Support Center personnel to efficiently and effectively repair damaged equioment under emergency co.:ditions.
- 8. Test the operations of the Emergency Operations Facility with respect to physical facilities, communications, emergency equipment, operations and
- assistance provided to VCSNS.
- 9. Test the operations of the News Media Center and the ability of staffing l personnel to respond to an emergency condition with respect to public j information and news media interface.
l 10. Ensure that emergency response personnel are f amiliar with their duties
- and responsibilities, thus identifying and deficiencies in personnel training, i
- 11. Test the adequacy and operability of emergency equipment and identify any deficiencies in the quantity or quality of equipment.
- (~ ) 12. Utilize the training simulator in the exercise with real-time station N- / operating information and to provide more realism in the simulated
- emergency condition.
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- 13. Test the flow of information between emergency response facilities and personnel. (1991 drill action item, identified by utility) 2 3
1 1 l NARRATIVE SUtHARY Prior to the commencement of this drill, the plant has Reactor Coolant System activity of 3E4 pci/gm and .1 gallon per minute 'C' Steam Generator tube leakage. The plant is in a 'B' Train maintenance week. 'C' Charging / Injection Pump is Red Tagged Out for an internal inspection. At T=0, a -light plane, which had been inspecting power transmission lines, . crashes in the Switchyard. The plane strikes a lightning arrestor and two phases of Bus Number 3. Tt.is results 'n busses Numbe ? and 3 de-energizing. This is a loss of 'B' Trair off-site power. The pilot of the plane is killed by the crash. 'B' Diesel Generator starts and loads re-energizing 'B' Train safeguards power. The plant's secuencer will comm?nce loading of safeguards equipment to the Diesel Generator. During the loading of equipment, the sequencer will fail to start 'B' Service Wate.r Pump. The Reactor Operator will oe able to str' L 'B' Service Watcc Pump manually at the Main Control Board. These events should be classifiad as an Alert Condition by the Shif t Supervisor. At T=15, the Control Room receives a D'4IMS alarm on 'C' Steam Generater.
'C' Steam Generator develops a tube leak which steadily increases to 500 gallons per minute over a 20-minute period.
At approximately T=30, the plant should Safety Inject due to a low pressurizer pressure signal. The 'A' Diesel Generator will come up to speed, but will not field flash, due to broken generator excitor brushes. At T=30, the 'C' Steam Generator tube leak will steady out at 500 gallons per minute. At T=40, the Main Control Room will lose Main Condenser vacuum indication. This will prevent the use of the condenser steam dumps for plant cooldown. A release to the environment will commence, due to the use of the Steam Generator power-operated relief valves. The loss of condenser vacuum indication will be due to a bad card in the racks. Also, at approximately 4
'C' S/G to Turbine Driven Emergency Fuel Pump isol viv fails to close :
DMIMS Alarm
',C' 5/G leak increasing Light Plane 'C' S/G leak crash. Loss of steadies at
'B' Train of f-site 500 gpm Power
'A' D/G TDEFP starts, N:oin Condenser Begin
.1 gpm 'C' S/G will not cannot control speed, vacuum signal recovery leak field flash exhaust boot ruptures restored planning s
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-30 -15 0 15 30 45 60 75 90 105 120 135 150 165 180 195 2' O S inj,afe,ty Loss of 115 kv 115 kv Power ection Power is restored Loss of Main Condenser vacuum signal. Requ. ires cooldown Drill with S/G PORV,s Terminated e e O
Chronological Listing of Major Events O EAL Time Event Classification Predrill - 'C' Chg/Inj pp red tagged out
'B' Train Maint. Week
- Failed Fuel Action Plan #2, 3 E-2 yCi/gm
- 2 mph vind from 90' 740 T=-20 -
.1 gpm tube leakage 'C' S/G 800 T=0 - Light plane crash in switchyard. Bus #2 and Alert Bus #3 de-energizes. Rcsults in a loss of 'B' Train off-site power.
'B' D/G starts and loads
- Sequencer fails to start 'B' Service Water Pump O
(requires operator action to start 'B' SW pump) 815 T=15 - DMIMS Alarm 'C' S/G
'C' S/G tube leak ramps in over 20 minutes to 500 GPM 830 T=30 - SI due to lo Pressurizer Pressure signal
'A' D/G Generator Excitor Brushes broken.
Generator will not field flash. 835 T=35 -
'C' S.G tube leak steady at 500 gpm 840 T=40 - Loss of main condenser vacuum signal due to a bad card in the racks. Requires plant cool ,
down using PORV's (release to environment) )
'C' MSIV is closed to isolate 'C' S/G 845 T=45 -
'C' S/6 to TDEFP isol v1v (28028) fails to close from the MCB l 8
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Chronological Listing of Major Events O (V EAL Time Event Classification 855 T=55 - 2802B won't close locally. Limitorque fails to engage. 900 T=60 - TDEFP comes up to minimal speed and will not control (pump started due to rapid cool down of S/G's and resultant 'A' and 'B' S/G Lo levels). I/P converter problem on governor.
- TDEFP steam exhaust boot ruptures - fills room with contaminated steam 930 T=90 - Loss of 115 kV line. Loss of ' A' Train off- Site Area site power. (Total loss of off-site Pwr) 10A Emergency de-energized while 'A' D/G is inoperable 1020 T=140 -
Main Condenser vacuum indication restored 1100 T=180 - Dispatcher calls the Control Room. Reports
" Relay Dept has replaced a distance relay and 115 kV line from Parr is ready to be restored".
(This will allow restoration of 'A' Train off-site power.) 1110 T=190 - Off-site power restored to 115 kV - line ('A' Train off-site power). Begin recovery planning. 1130 T=210 - Exercise termination
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RELE ASE INFORM ATION h I. Meteorological Conditions A. Wind Speed 2 MPH B. Wind Direction 90 Degrees C. Stability Classification F D. 10-60 Delta T in Deg C 2.0
- 11. Release Scenario - Multiple Release from Main Steam A. First Release, Puff from C S/G PORV
- 1. Start Time T = + 30 minutes
- 2. Duration 10 minute',
- 3. Flow Rate 30% PORV Design Flow
- 4. Curie Content lodine 428 uCi/sec Particulate 0.644 uCi/sec Gas 4.02E + 4 uCi/sec Note: Values in uCi/sec, not Ci/sec B. Second Release, Steam Operated Emergency Feed Water Pump
- 1. Start Time T = + 60 minutes
- 2. Duration 30 minutes
- 3. Flow Rate 50% Terry Turbine Steam Flow
- 4. Curie Content lodine 428 uCi/sec Particulate 0.690 uCi/sec Gas 1.00E t 5 uCi/sec Note: Valuesin uCi/sec, nat Ci/sec C. Filtered No D. Monitored (List) RM-G19C 111. RCSLeakage A. Origin 'C' S/G Tube B. Leakage Rate Transition from 0.1 to 500 GPM over 20 Minutes then 500 GPM C. Curie Content Normal RCS Coolant Activity with lodine Spike After Safety injection IV. Maximum Dose Rates in Environment See sheets titled " Projected Off-Site Doses" h
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INOPERABLE EQUIPMENT V,r3 J Pre Exercise XPP0043A 'C' Chatging/ injection Pump Internalinspection T = 0 To Term Off-Site Power from Bus #2 and Bus #3 Plane crash T = 30 To Term
- 'A' DG Diesel Generator 'A' Will not field flash
- T = 40 to T = 140 i
Steam Dump system to Main Condenser Loss of vacuum signal T = 45 To T = 195 XVG02802B 'C' Steam Header to Turbine Driven Will not close Emergency "eed Pump T = 60 to T = 120 Turbine Driven Emergency Fuel Pump Steam exhaust boot rupture I/P converter problem i T = 90 To 180 XSW1DA Loss of 115 kv power Distance relay failure 1 i 11
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~.,Isring,AND CLASSIFlcpTIONS 1
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$ 1 CLASSIFICATIONS O
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l 9 EVENT TIME EVENT LOGISTICS T=-20 1. Activation Method
.1 gpm 'C' S/G Tube Leakage EMERGENCY CLASSIFICATION None II. EFFECT ON SCENARIO ,
Cause an evaluation of plant ooeration DIRECTI0t' Upgrade Unchanged X
~
Downgrade INITIATING CONDITION III. ANTICIPATED CORRECTIVE ACTIONS None Controlled plant shutdown after evaluation of S/G leakage 9 13
O E_ VENT TIME EVENT LOGISTICS T=0 1. Activation Method Plane crash in swltchyard EMERGENCY CLASSIFICATION Alert TI. EFFECT ON SCENARIO A. Loss of 'B' train off-site power B. Fatality C. Fire in switchyard OIRECTION Upgrade X Unchanged Downgrade INITIATING CONDITION Air craft crash on facility III. ANTICIPATED CORRECTIVE ACTIONS Verify 'B' D/G starts and loads. Dispatch operator to 'B' D/G
-Dispatch Fire Brigade to switchyard
, Dispatch First Responder to switchyard l ~ Dispatch Security Officer to switchyard i lO ! 14
l EVENT TIME EVENT LOGISTICS T=0 1. Activation Method
'B' Train Sequencer fails to load 'B' Service Pump EMERGENCY CLASSIFICATION Alert II. EFFECT ON SCENARIO Loss of 'B' Train Service Water DIRECTION Upgrade Unchanged X Downgrade INITIATING CONDITION Same III. ANTICIPATED CORRECTIVE ACTIONS A. Reactor Operator manually starts 'B' Service Water Pump from the Main Control Board B. I & C investigates 'B' train Sequencer O
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EVENT TIME EVENT LOGISTICT
- f T=15 I. Activation Method A. DMIMS Alarm 'C' S/G Tube leak 'C'
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B. S/G EMERGENCY CLASSIFICATION l Alert II. EFFECT ON SCENARIO f
- A. Loss of one fission product barrier B. Contaminated secondary system i (potential release)
OIRECTION Upgrade Unchanged X Downgrade O INITIATING CONDITION III. ANTICIPATEP CORRECTIVE ACTIONS Same A. Isolate 'C' S/G B. Controlled shutdown and plant cooldown ( 16 l
O EVENT TIME EVENT LOGISTICS T=30 I. Activation Method 1
'A' DG failure !
EMERGENCY CLASSIFICATION l Alert II. EFFECT ON !.CENARIO Loss of back-up power source for 'A' Train DIRECTION Upgrade Unchanged X Downgrade INITIATING CONDITION III. ANTICIPATED CORRECTIVE ACTIONS Same Dispatch Electricians to investigate 0 17
l l l EVENT :4E EVENT LOGISTICS T=40 1. Activation Method Loss of Steam Dump to Main Condenser capability EMERGENCY CLASSIFICATION l Alert II. EFFCCT ON SCENARIO A. Must cooldown plant using Steam Generator power operator relief valves. B. Opens a release path to the environment. DIRECTION Upgrade N Unchanged X l Downgrade INITIATING CONDITION III. ANTICIPATED CORRECTIVE ACTIONS Same Dispatch I & C Technicians to investigate t iO 18 w s , ,m -r-p-- r y e-- + v .- 9p vm+k---y7 y - w=-
O EVENT TIME EVENT LOGISTICS T=45 1. Activation Method ! XVG028028 fails to close from the Main I Control Board l EMERGENCY CLASSIFICATION Alert II. EFFECT ON SCENARIO A. Cannot isolate 'C' S/G B. Potential relea.se path DIRECTION Upgrade Unchanged X Downgrade INITIATING CONDITION III. ANTICIPATED CORRECTIVE ACTIONS Same A. Dispatch an operator to close the valve locally. B. Dispatch mechanics to investigate failure l 19 l l
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h EVENT TIME EVENT LOGISTICS i ' T=60 1. Activation Method Cannot control the Turbine Driven Emergency Fuel Pump from the Main Control Board 4 EMERGENCY CLASSIFICATION ,l l Alert
- II. EFFECT ON SCENARIO 4
A. Only one Emergency Feed pump l cvailable DIRECTION Upgrade Unchanged X Downgrade INITIATING CONDITION III. ANTICIPATED CORRECTIVE ACTIONS Same Dispatch I & C Technicians to investigate 20
O EVENT TIME EVENT LOGISTICS T=60 1. Activation Method Turbine Driven Ernargency feed Pump Steam Exhaust Boot ruptures. EMERGENCY CLASSIFICATION Alert II. EFFECT ON SCENAR;0 A. Only one Emergency feed pump available B. Fill room with contaminated steam C. Environmental Release Path DIRECTION Upgrade Unchanged X Downgrade INITIATING CONDITION III. ANTICIPATED CORRECTIVE ACTIONS Same A. Mechanics must dress in anti-contamiantion clothing to repair boot. B. I & C Technician must dress in anti-contamination clothing to repair I/P converter O 21 , l __ _ - - - _ _ _ - _ _ - _ _ - - - - - _ - )
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{ EVENT TIME EVENT LOGISTICS Y=90 I. Activation Method j l Relay Failures on 115 kv line, i 1 i EMERGENCY CLASSIFICATION i Site Area Emergency II. EFFECT ON SCENARIO l A. Loss of 'A' Train off-site po.ser B. Loss of all off-site power C. 10A de-energized while ' A' 0/G is inoperable (loss of 'A' Train Power) i DIRECTION i i Upgrade X d O Unchanged b Downgrade
- INITIATING CONDITION III. ANTICIPATED CORRELTIVE ACTIONS Rapid failure of several steam A. Call dispatcher to investigate
, generator tubes with loss of 4 off-site power. B. Send electricians to 115 kv equipment to investigate 1 ! 22
4 EVENT TIME EVENT LOGIS, TICS T=140 1. Activation Method Main Londenser Vacuum signal restored. EMERGENCY CLASSIFtCATION Site Area Emergency
- 11. EFFECT ON SCENARLQ A. Allows alignment of Steam Dumps to the Main Condenser B. Terminates a release path DIRECTION Upgrade .
Unchanged X Downgrade INITIATINC CONDITIE III. ANTICIPATED CORRECTIVE ACTIONS 4 Same A. Align Steam Dump to the Main Condenser for Turtner plant cooldown. 23
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(_
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1 1 O l iV ' ) EVENT TIME EVENT LOGISTICS T=180 1. Activation Method l 115 kv line Distance relay repaired EMERGENCY f:LAS$1FICATION 4 Site Area Emergency
- 11. EFFECT ON SCENARIO Will ellow restoration of ' A' Train
< offsite power ] l DIRECTION Upgrade Unchanged X Downgrade INITIATING CONDITION 111. ANTICIPATED CORRECTIVE ACTIONS Same Restnre power from 115 kv line i 4 1 0 24
O EVENT TIME EVENT LOGISTICS T=190 1. Activation Method 115 kv line energized
- EMERGENCY CLASSiflCATLON O Site Area Energency Recovery II. [FFECT ON SCENARIO Restoration of offsite power to ' A' Train DIRECTION Upgrade Unchanged Downgrade X INITIATING CONDITION Ill. ANTICIPATED CORRECTIVE ACTIONS Restoration of offsite power Begin recovery planning to 'A' train O
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4 4O 4 J i ) i i i MESSAGES i 1 !O 1 i lO 26
T=0 h Message To: Any Security Officer in the AAP Hessage frcn: Security Controller LOCATION: j HESSAGE: You have just heard a loud crash in the switch yard cutside the Protected Area. l 1 W O 27
NJ T = 15 (approximate) Contingency Message To: Communicator / Security Shif t Leader Message from: Communicator Controller / Security Controller LOCATION: TSC / Security Central MESSAGE: If of f site assistance is requested, simulate call to fairfield Co. Dispatcher. Fire Protection Controller will provide information on simulated volunteer Fire Department actions to Securitv Officer on the scene. W Y j , y l l 28
T = > 60 O i tsage To: First Person near Turbine Driven Emergency Fuci Pump Room A stage from: Controller near room LOCATION: 412 Intermediate Building HESSAGE: You see steam coming from (point to Turbine Driven Emergency fuel Pump Room's fire Damper) h W O 29
O T = 90 Nessage To: _ Alarm Station Operator 7 Nessage from: Security Controller ; LOCATION: TSC / Security Central MESSAGE: You have just received the following error messages: ALER UPS (ASB) - Battery Charger Power failure (70) EP03 Security Inverter XIT 5936 (UPS A), ASB, ELV 436, Area 30-UPSA Battery Charger AC Power Monitor ALER UPS(ASB) - Battery Charger Power Failure (70) EPO4 Security Inverter XIT 5937 (UPS B) ASB, ELV 436, Area 30 UPSB Battery Charger AC Power Monitor ALER Inverter Operating In Other Than Auto Mode (94) EP01 Security-Inverter XIT 5909, SB, ELV 436, Area 24 5909 Inverter Auto Prsition Relay SLER Inverter Operating In Other Than Auto Mode (94) EP02 Security Inverter XIT 5910. AB, ELV 388, Area 29 5910 Inverter Auto Position Relay l O 30 _ ._.-.2, ,_._,_.-_-_.--a..._._-... - . _ . _ _ _ _ . _ - , . . _ _ . . , . _ _ _ , -.,_. . - .. -
1 T = 92 O Message To: Control Room Message from: Simulator Controller 1 LOCATION: Simulator ~ HESSAGC: This is the Dispatcher. The OCB at Parr Substation has opened and will not reclose. <l a l O 4 P I '1 O 31
O T = 120 Message To: Control Room Message from: Simulator Cor. troller LOCATION: Simulator MESSAGE: This is the Olspatcher. No line problems have been found by the Transmission Department's inspection. I am calling in the Relay Department to check protective relaying at the Parr Substation. O V l l I 1 (~h l l l 32
T = 180 O Message To: Control Room Supervisor on Dispatcher Phone Message from: Simulator Controller LOCATION: Simulated Control Room HESSf4E: This is the Dispatcher. A distance relay on the 115 kv line at Parr has been replaced. I am ready to energize the 115 kv line. J O 1 2 33
O j T = 190(approximate) Message To: Control Room q Hessage from: Simulator Controller LOCATION: Simulator HESSAGE: This is the Dispatcher. The 115 KV line from Parr is energized. 4 !o l O l 34 l
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FIRE BRIGADE h 1 - Controller / Fire Brigade T=0 I. EVENT A. A light single engine plane has crashed in the switchyard. B. Small fire occurs on impact with lightninc rod protector and plane. C. There is no flammable liquid fire due to tie plane being out of fuel. D. Place Roscoe Fog Machine west of the Relay House in the switchyard area and start the machine to generate smoke. This will be the indication of the small fire created when the plane crashed.
- 11. INVESTIGATIVE ACTIONS A. Report of smoke in the switchyard.
B. Control R mn makes announcement and activates the Fire Brigade in accordancc with EPP-013. C. Fire Brigade Leader (FBL) respond- to the switchyard with appropriate keys for entering switchyard. D. FBL begins initial assessment of the scene and communicates with Control Room by two way radio, of a small plane crash with a small fire with light smoke inside the switchyard. E. FBL observes a decapitated victim on the ground within 20 feet of the crashed nlane and relays this info by two way radio to the Control Room. Ill. REPAIR ACTIVITIES A. FBL determines the security fence around the switchyard is not energized and unlocks a: cess gate for entry. B. FBL establishes a command post of the relay house. C. FBL requests Fire Brigade Members (fBM) to bring Fire Preplans for the switchyard area (FPP-055). D. FBL should request Fairfield County Coroner and FAA, be dispatched to the crash scene (simulated). E. FBMs arrive with Fire Preplans and FBL's equipment. FBL may extinguish the fire prior to the arrival of FBM's. F. FBL directs FBMs to use a dry chemical extinguisher to extinguish the small fire around the plane. G. FBL requests blanket be brought to cover the victim as found. The victim should not be moved until directed by the County Coroner. H. Fire is extinguished as determined by FBL.
- l. FBL request continuous Fire Watch and security be established to this area.
IV. FOLLOW UP ACTIONS A. Coroner arrives and takes charge of the victim (simulated -information provided by Fire Protection Controller). B. FAA arrives to begin investigation into the cause of crash (simulated). C. All Fire Brigade equipment is replaced. D. FBL requests FPO to replaced used portable extinguishers from hose house # (actual). E. FBL complete Fire Report per FPP-002, 36
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- - Fawfield No.1 8942 Main Transformer
ELECTRICAL MAINTENANCE 1 Controller /1 Man 30 minutes
- 1. EVENT A. Plane Crash in switchyard
- 1. Loud noise from switchyard
- 2. Smoke in switchyard
- 3. Security reports crash 4: Security opens switchyard gates
- 5. Pilotdead B. Loss of power on Bus #2 and Bus #3
- 1. Plane struck solid bus bars 01,02 & 03 from Fairfield 2, Plane struck lightning arrestor next to Fairfield OCB's ll. INVESTIGATIVE ACTIONS A. Operator and Security respond to switchyard- (Controller use draw:ng in scenario to exhibit damage)
- 1. Fairfield bus bar 02 is in contact with the stee support structure
- 2. Fairfield bus bar 03 is in contact with the ground
- 3. OCB 8942, Switch 8943 and switui 8941 have no damage O B.
- 4. There is a small fire in tfie plane wreckage May call for Fire Brigade, First Responder, or Offsite Fire Department til. REPAIR ACTIVITIES A. Report the damage to the Emergency Director B. Security cordons off the area C. Pilot dead i D. No immediate repair activities can be accomplished.
l IV. FOLLOW UP ACTIONS Report to the OSC l 41 t
E LECTRICAL M AINTEN ANCE 1 Controller /2 Men 90 rninutes
- l. EVENT A. XVG028028 M5 will not close from th? Main Control Board B. Valve will not close from local handwheel ll. INVESTIGATIVE ACTIONS A. Electrical Team dispatched from OSC (may be concurrent with operators and mechanics)
- 1. Obtain tools from shop
- 2. Report to valve B. !nitial inspection reveals the valve motor runs but valve does not stroke C. Request to manually stroke the valve locally valve handwheel turns but stem does not move D. Inspection determines this is a mechanical problem.
- 1. Electricians may be asked to assist in removal of the valve operator 9 motor.
Ill. REPAIR ACTIVITIES Mechanical repair required IV. FOLLsW UP ACTIONS A. Assist mechanics'/,".n retest of valve
- 1. MEG
- 2. Bridge
- 3. Running current B. Report results to the OSC 9
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I i 'I ELECTRICAL MAINTENANCE 1 Controller (not necessarily Electrical) 90 minutes 0 Electricians Duration: Approxiniately 1.5 hours ,
- l. EVENT l A. Loss of 115 KV line (55F) from Parr Substation. This causes total loss of " A" train offsite power and 1DA bus due to "A" diesel generator inoperable.
B. Communications established between the Control Room and the Dispatcher.
- CC'N TROLLER MESSAGE: T = 92 (to Control Room) by Simulator Controller The l OCB at Parr Substation has opened and will not reclose.
- 11. INVEST!GATIVE ACTIONS ,
T A. (Cohtroller message to Control Room) Dispatcher calls in transmission crew to " ride the line" between Part and the VCSN substations. B. T r 1:0 (Controller message to Control Rom by Simuiator Controller) No Ilrue problems found by Transmission Crew's inspection. C. (Controlier message to Control Room) Dispaicer calls in Rclay , Department to check protective rebying at Parr Substation. D. (Controller message to Control Room at approximately T = 160) - ,
- Dispatcher contacts Control Room, Relay Department has found a distance -
1 y relay with a bad capacitor. This distance relay has caused the OCB to open. ; lit. REPAIR ACTIVITIES A. Relay Department repairs and tests distance relay. Dispatcher is notified that repair and testing is complete. B. T = 180 (Controller message to Control Room by Simulator Controller)- Dispatcher notifies Control Room reparis are complete and the OCB is to be , closed momentarily. IV. FOLLOW UP ACTIONS NOTE: T = 190 (Controller Message to Control Room from Simulator Controller)ffsite "A" train o power.- The 115 KV line (ESF) from Parr is energelzed, re V l. O 43
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E LECT RICAL M AINTENANCE 180 minutes h 1 Controller /2 Men
- 1. EVENT
< A. 'A' Diesel Generator starts (from a Safety Inicction Signal), Main Control Board " Field Failure" Annunciator Alarm
- 1. Operations does operator actions to try to restore 'A' Diesel Generator
- a. Check generator voltage (0 voltage on motor)
- o. Momentarily field flash
- c. Depress excitor shutdown i d. Depress excitor reset
- e. Turn field flash to flash for 10 seconds
- 2. " Field Failure" Annunciator is stillin with no voltage on the generator II. INVESTIGATIVE ACTIONS
- A. Electrical Maintenance dispatched from the OSC
- 1. Obtain tools from shop
- 2. Obtain drawing and procedure from Document Reference Center
- 3. Report to D.G.
R. Possible Causes are:
- t. Failure of field to flash
- 2. Facit5 the field circuitry
- 3. Relay failure
- 4. Request for D.G. to remain running or be restarted C. Check for voltage at F( + ) and F[-] in XEX4201 when the field is flashed
- 1. There is voltage (250 vdc) between F[ + ) and F(-) in XEX4201 when the field is flashed
- 2. Problem not found, eliminate possible causes 1 & 2 above D. Check the junction box for connection of field flash circuit to the brushes
- 1. The connection is found to be good E. Inspect the excitor brushes
- 1. Request D.G. be shut down and Red Tagged out
- 2. Copper leads from the brush riggings are broken on one pair of brushes,of the same polarity ill. REPAlR ACTIVITIES A. Report results to the OSC B. Obtain additional tools / materials from warehouse C. Obtain brushes from the warehouse D. Brushes m?t be seated and installed E. A continuity check should be performed before the screens are reinstalled on the west end of the generator IV, FOLLOW UP ACTIONS A. Notify OSC repairs are complete B. Should not be completed prior to termination of drill 44
1 l & C MAINTENANCE T = 40 1 Controller / 2 Men 90 minutes <
- l. EVENT: LOSS OF MAIN CONDENSER DUMP AVAILABILITY A. Permissive C 9 B. XCP 611413 annunciator light dim C. Main Condenser vacuum indication: 3" vacuum absolute [27" HG), as indicated by IP103006 & IPl03016 II. INVESTIGATIVE ACTIONS i
A. OSC dispatches 2 i & C technic;ans to investigate B. Technicians investigate drawings and procedures
- 1. VC5 IPT03006 CO,VC5 IPT03016 CO
- 2. B 208 063-MB01/ M B04/ MB098/ MB 16 A/ MB 11 B/ MB08B/ MB 10B/ MB07B/
MB050/ MB06B/ MB128/
- 3. ICP-140.012,ICP 140.013 C. Determhe problem to be either.
- 1. PB 3006Ain XPN6003 LCabinet 11 O' 2. PB 3016A in XPN6003 Cabinet 11
- 3. PB 3006A & PB 3016A trip at 5" Condenser vacuum. These bistables close contacts in series to enable condenser dump valves.
111. REPAIR ACTIVITIES l A. Take voltar)e readings in Cabinet 11 l 1. PB 3006 loop is normal: l 9:000 vdc at output 3 & Sig common of NMA P4 4006 C11-122 bistable PB 3006A, C11 123 output B1 on (tripped / normal read) close contacts mad with DMM at 78 D1-1&2, OVDC read with DMM on 200 vdc scale.
- 2. PB 3016A card power lamp is o". 9:000 vdc at output 3 & sig common of NMA P4 3016 C11-526 U? tab e ?B 3016A,C11-546 car powerlamp is out and none of bistable outpa amg l on. A blown fuse is suspected.
- 3. Inform OSC of findings May install a jumper across C11 TB01-16 & 17 or XPN7033 TB301-1&2 if desired.
- 4. Obtain fuse from warehouse: Fuse #54-2763-0491-13 Loc. C KD-8-K-8 NAC# 03-0645-9061-13 Loc. C AK-6-J-1 Note: May rob fuse from card to use if unable to ;ecate fuses.
- 5. Install fuse (if vacuum card installed, calibrate card per ICP 140.013)
- 6. Condenter vacuum availability is restored IV. FOLLON UP ACTIONS A. Inform OSC of job completion B. Retur n to OSC 45
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I & C MAINTENANCE T = 60 1 Controlier / 2 Men 60 minutes I. EVENT A. Turbine L) riven Emergency Feed Pump comes up to minimal speed and will i not control B. The Steam Exhaust Boot on the Turbine Driven Emergency Feed Pump ruptures 1; This fills the room with contaminated steam.
- 2. The steam is removed by the room's ventilation when t" oump is secured.
- 3. The room is contaminated
- 4. This is a mechanical repair activity ll. INVESTIGATIVE ACTIONS A. OSC dispatches 2 I&C technicians B. Technicians investigate procedures
- 1. ICP 195.021 C. Technicians investigate drawings
- 1. D 302 011
( D. Technicians investigate Tech Manual
- 1. IMS 948-425
- 2. IMS 94B 1241 E. Determine the aroblem to be in the Turbine's Governor or I/P converter.
Need to go to t1e Turbine for further investigation. 111. REPAIR ACTIONS A. Obtain tools & equipment
- 1. Current source, DMM,30 psiindicator from l&C shop
- 2. Various hand tools from hot tool room B. Dress out in anti contamination clothing required C. Attempt to calibrate I/P Transducer (15Y02034). Can not be calibrated.
Output remains at full supply air signal des site ad ustment attem ats. D. Determine problem to be 1/P transducer fai ed hig'1 [l5YO2034) T lis is a clogged screen on the vent port.
- 1. Operations can controllocally,if desired
- 2. Inform OSC and Operations E. Obtain new 1/F transducer from warehouse (if repair is desired).
- 1. Calibrate transducer
- 2. Installtransducer
- 3. Have Operations verify stroke / operation of the I/P transducer from the Main Control Board I IV. FOLLOW UP ACTIONS d A. Inform OSC of job complete B. Return to OSC l
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r i I & C MAINTENANCE. Ta0 1 - Controller / 2 Men 60 minutes
- l. EVENT: SEQUENCER FAILS TO START 'B' SERVICE WATER PUMP
- 11. INVESTIGATIVE ACTIONS f
A. OSC dispatches 2 l&C technicians to investigi B. Technicians investigate drawings 1MS 28 09 .3,1MS 28 031 1 through 4, 1MS 28 321 through 3,1MS 28112 5,1MS 28 0971 through 5,1MS 28-112 3 j C. Technicians investigate Tech Manual IMS 94B 452 ! D. Technicians investigate orocedure ICP 200.001 E. 'E' Service Water Pump is initiated b sea uencer step 3. At XPN6025, the step 3 actuation lamp is illuminated.y'B' KVAC Chilled Water Pump is initiated by the same step. This pump was started by the se Suspect that contact 4 & 3 of output relay 43 failed to close.quencer. Ill. REPAIR ACTIONS A. Measure 125 vdc across contacts 4 & 3 on K 43 or TBS 11 & 12, shows contacts open. These are normally open contacts that close to start Service O B. Water Pump B when the sequencer reaches step 3. Inform OSC l 1. of problem
- 2. May provide closure by placing a jumper across TBS 11 & 12 if desired.
C. Obtain relay from warehcuse
- 1. Part # 54 7602 0095-00
- 2. Location C-LT 2 5 3 D. Replace relay Removing relay will stop 'B' Chill Water Pump < Will need to jumper TBS 7
& 8 or have OP s take pump to manual prior to removing relay.
IV. FOLLOW UP ACTIONS A. Inform OSC of job complete B. Return to OSC 4 1 O . 49
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1 i MECHANICAL MAINT EN ANCE T = 45 1 - Controller / 2 Men 150 minutes
- 1. EVENT XVG02802B MS (M AIN STEAM ISOLTO TURB DRIVEN EMER FEED PUMP FROM
'C' HDR) CANNOT BE CLOSED FROM THE MAIN CONTROL BOARD
- 11. INVESTIGATIVE ACTIONS 4
A. Operator dispatched from OSC to close valve locally
- 1. Operator arrives at valve
- 2. If Ops attempt to close valve from Main Control Board:
[ Controller Message] You hear the motor running; valve will not operate
- 3. Operator attempts to close valve with handwheel
[ Controller Message)
- Handwheel operates, no movement on valve
- 4. Operator reports situation to OSC lil, REPAIR ACTIONS A. Repair team dispatched to make repairs j
O 1. Obtain tools from shop
- 2. Obtain procedure ano drawing.
B. Disassemble operator
; 1. Remove operator from valve
- 2. Disassemble operator
- 3. Electricians may be required to de term operator 4 [ Controller Message, upon inspection of worm gear]
Worm gear is stripped.
- a. Report findincjs to OSC
- b. If repair is desired:
i
- 1) Repair
- 2) Obtainoperator parts from warehouse (worm gear,d,' grease, g and gaskets)[
- 3) Install operator & I5 #
4
- 4) Re term operatorif required (elect)
C. If valve closure & block is desired:
- 1. Obtain materials to make locking device
- 2. Force valve closed and installlocking devde
- 3. Report condition to OSC
- 4. Continue to repair operator as ci: .itribed previously if directed by OSC i
IV. FOLLOW UP ACTIONS ~ A. May attempt to stroke valve locally or from Main Control Board (if operator repaired) i B. Inform OSC repair / closure is complete
- J C. Return to OSC 51
O CLUTCH KEY SLOT ,- UPPER DRNE SLEEVE BEARING CONE (64)
, BEVEL GEAR
- CLUTCH RETURN SPRING (43)
- CLUTCH RING (28)
LUBRICATION PO9T 0 / CONDUlT PLUG ' 4 ( WORM GEAR (7)
/ .
8 ARING NE 66) u --rx r E'iWIf"' \/ e /N i Figure 17-49 Drive Sleeve Installation O 52.
MECH ANICAL MAINTENANCE - T = 60 1 - Controller / 2 Men 60 minutes-
- 1. EVENT TURBINE DRIVEN EMERGENCY FEED PUMP 5 TEAM EXHAUST BOOT SLIPS-AWAY FROM BOTTOM CLAMP
- 11. INVESTIGATIVE ACTIONS A. Heavy steam reported in Turbine Driven Emergency Feed Pump Room.
B. Team dispatched from OSC C. Team must dress in anti-contamination clothing D. Team enters room and proceeds to pinpoint source of steam E. If Turbine is still_ operating:
' Controller Mesugeh Vou see steam coming from (point to turbine steam exhaust area);
[ Controller Message, upon a team membe 'bserving the Turb, disch, piping): The boot has slipped away from the bot' -lamp ill. REPAIR ACTIONS A. Inform OSC of situation (request the turbine be' secured for repair,if , running)
- 8. Obtain tools to make repair (screwdriver, flashlight, caulking gun and
, caulking, cleaning equipment) from hot tool room. C. Reattach boot-to piping with caulking and clamp _ IV. FOLLOW UP ACTIONS A. Inform OSC repairs are complete - B. Return to OSC 0 53
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O ANNUAL EXERCISE - SECURITY CHECKLIST ACCIDENT ACTIONS Receive report of accident. Officers dispatched to scene. First person on scene performs " quick check" on victim, notified CR. Officers lend assistance as directed by on scene personnel. Officers establish cordon and secure scene. Receive report from SS of responding off site support service. Implement SPP-108 Fire, Explosion of Similar Disturbance. ALERT DECLARED Implement SPP-114 SF Responsibilities During Emergencies ATTACHAENT 4 (All Posts). IfTSC is activated, contact administrative supervisor and request switchboard operator. g Update status board at portal (s). RECEIPT OF SCS ERROR MESSAGES Notify SSL. Contact Control Room. Dispatch Response. Implement SPP-119, Loss or Degradation of Physical Security Systems. Implement SPP-118, Security Notification. SITE AREA EhERGENCY DECLARED Implement SPP-114 ATTACHMENT 4 (All Posts). Implement SPP-114 ATI'ACHMENT 6 (APS at AAP). Implement SPP-114 ATTACHAENT 7 (APS at PAP). Update status board at portal (s). 54
SPP.114 ATTACHMENT 4 Page 1 of 3 Revition 10 (] V EMERGENCY SECURITY ACTIVITIES CHECKLIST EMERGENCY ~ NORMAL EMERGENCY EMERGENCY TASK / COMME NT REFERENCE CLASS POST POST COMPtf7E (LOCATION) ALL CLASSES 55L *CAS 1. Noufy secunty force of situauon SPP-118
- 2. Initiate secunty notification. SPP 118
- 3. Coorcinate security activities with IED/ED or 5.3.1 Security Supervisor .
- 4. Report terminauon of any post /pattof NOTE immediately to TSC 5.3.3.C
- 5. Direct merease in freovency of communi
. _ . . . ... . . ... . . . . . . . ,. . . cation..checks. . . . . .
as necessary. SITE AREA SSL . . ..
*CAS 6. Assist ED in site evacuation.
GENERAL J
- 7. Direct required compensatory or support 5.3.1 actions,
- 8. Complete personnel accountacility (30 Attachments mmutes after evacuation) 6&7
- 9. Report missing personnel to ED/IED 5.3.1
- 10. Initiate secunty force recall. as required SPP 118
*May be located elsewhere depending upon situation.
ALL CLASSES CAS CAS AOS AOS 1. Initiate secunty communicauon log. N/A ASO ASO 2. Receive location of secunty shift personnel 5.2,4 and submit report 01 AAP APS.
- 3. Increase communication checks with security N/A v posts whendirected
$A_5, }AS 4 Disseminate situation reports to security SPP-118
*ASO *ASO posts.
- 5. Notify ACPand PAP APS ofi ncoming N/A emergency response personnel and vehicles.
- 6. Assist SSL as directed.
*SAS operator performs tasks as directed t
PATROLS PATROLS l ALL CLASSES PA.1 PA 1 Continue normal patrol activities 5.3.3 C j PA-2 PA unless otherwise cirected ! RCA PA 2. WHEN DIRECTED patrol accessible areas of CAP OCA
. . . _ . .. . _ . - . . . .. . . . _ . . . . . OCA. . . OR
_ . assistin
.peratingo ACP (CAP).
SITE AREA PA.1 . . _ . . PA
- 3. Screen respective patrol areas and verify all 5.3.3 C 2.a GENERAL PA.2 PA non-essential personnel have evacuated.
PA 3 PA 4 Contmue normal patrol activities and report 5.3.3 C2.b any deviations immediately to CAS.
- 5. WHEN DIRECTED, fire FOUR red signal flares 5.3.3.C2.c over Lake Monticello (PA-1)
- 6. Locate and direct evacuauon of personnelin l 5.3.3 C.1
- l. OCA, venfy Gates 4 and 16 are secure, and conduct other activities as directed by the SSL. (CAP) b u
55
SPP-114 ATT/.CHMENT 4 Page 2 of 3 Revision 10 EMERGENCY SECURITY ACTIVITIES CHECKLIST EMERGENCY NORMAL EMERGENCY EMERGENCY TASK / COMMENT REFERENCE cowLtTE CLASS POST POST (LOCATION) AAP AAP ALL CLASSES APS LT 1. Prepare for personnel accountabilsty. Attachment 6 ACO APS 2. Locate visitors. N/A . BCO ACO 3. Receive secunty personnet status report from 5.2.4 ECO BCO CAS. P50 ECO (NOTE: Report missmg officers to SSL) PSO SITE AREA AP5 LT 1. Upon notificaton, deny access to PA EXCEPT 5.1.3 GENERAL ACO APS as approved by IED/ED or DA Attachment 6 BCO ACO 2. If SCS fails initiate manuallogging Step 3 ECO BCO procedures Attachment 6 PSO ECO 3. Receive essential personnel accountability Step 6 PSO report from T5C Admm Suov, secunty Attachment 6 personnel status report from CAS. ano accountability overlay from PAP.
- 4. Report missmg personnel to security Step 7 Supervisor m TSC. Attachment 6
- 5. Request missmg personnel (badge ir and Step 7 name) to report their location to AAP using Attachment 6 station paging system.
- 6. Five mmutes after STEP 5. report any pers.ans Step 8 not located to Security Supervisor in TSC. Attachment 6 PAP PAP 1. Prepare for personnel accountability Attachment 7 ALL CLASSES APS APS 2. Locate visitors. N/A ACO ACO 3. WHEN DIRECTED or at ALERT, dispatch 5.3.3.A BCO BCO officer (s)(ACO and Comp) to establi<h EOF ECO ECO security posts (NOTE: Requ FOU< !ficars:
P50-1 P50-1 request SSL to recall personnelif rew. > <d.) P50-2 PSO-2 4 WHEN DIRECTED, dispaten officer (P50-2) to 53.3.B V50 V50 establish ACP. COMP COMP 5. WHEN DIRECTED or at ALERT, process 5.3.3. A emergency vehicles and personnel and 5.4 provide vehicle escort. SITE AREA APS APS 6. Upo nouficauon, deny access to PA. 5.1.3 GENERAL SCO BCO 7. If 5C5 fails, initiate manuallogging Step 3, _O ECO procedures. Attachment 7 ECO P50-1 8. Inicate accountabihty procedures. Steps 15 P50-1 V50 Attachment 7 P50-2 9. Provide compieted accountability overlay to Step 6 VSO AAP NLT 20 mmutes after notification of Attachment 7 COMP evacuauon.
- 10. Report badge number of any person exitmg Step 7 PAPto AAP APS after overlay es disoattned Attachment 7 O
56
SPP.114 ATTACHMENT 4 Page 3 of 3 Revision 10 O V EMERGENCY SECURITY ACTIVITIES CHECKLIST EMERGENCY NORMAL EMERGENCY EMERGENCY TA5K/ COMMENT REFERENCE COMPLETE CLASS POST POST (LOCATIONI AAP ACP 1 WHEN DIRECTED, deny personnel / vehicle Attachment 8 ALL CLASSE5 '50 access to the OCA EXCEPT for authorized personnel
- NOTE: if not already manned, PAP PSO-2 establishes post. CAP provides assistance wnen available.
NTC EOF 1. Establish access control under direct ALERT '50 50 supervision of Secunty Coorcinator 50 SO ' NOTE: Existing NTC post dunng backshifts, WP nights, and hohdays PAP ACO and COMP may be dispatched initially until security recall can be etfected. NOTE Normal duty assignments designated to fill emergency posts are for planning purposes only and may be altered during implementation due to available manpower or operational O requirements necessary to fulfill regulatory V commitments g' 57 l l
i are.... ATTACHMENT 6 Page1of1 Revision 10 SITE EVACUATION PERSONNEL ACCOUNTABILITY 0 POST: ACCESS PORTAL SUPERVISOR LOCATION: AUXILIARY ACCESS PORTAL (AAP) INSTRUCTIONS: Follow these steps to ensure personnel accountability during a site evacuation. STEP 1 Receive notification of a site evacuation. Write down time. STEP 2 Evacuate non essential personnel through the AAP exit portal (s). Collect badges in basket (s). Do not card out or slot badges. (NOTE: Post secunty officer (s) at turnstile with basket (s) to collect badges.) STEP 3 Following announcement of an evacuation, personnel requesting access to the PA will be dealt with on a case-by-case basis through the Security Supervisor in the T5C, or,in his absence, directly through the ED/IED. NOTE: Should the Security Computer System become inoperative during an emergency event, the entry and exit of all personnel, except emergency response personnel, to orfrom the PA should be recorded using an Access Control Log (SSA Form 417 - ATTACHMENTI) after the evacuation of non essential personnel has been completed. STEP 4 Using the white " Security Evacuation Badge Accountability Roster" LINE THROUGH badge numbers present on the badge board including terminated and purged badge slots. (NOTE: Step 4 can begin simultaneously with step 1). While this is l I being accomplished, direct an appropriate number of security officers to check EVERY AAP PArbadge slot from the opposite side of the badge board to ensure that no badges are incorrectly slotted. STEPS Line through badge numbers collected in the basket, placing badges in the second basket as the badge numbers are called out and lined through. These badges should then be activated in exit cardreader and slotted on the badge boards as soon as possible. NOTE: REMEMBER,line through the badge numbers of security officers present in the AAP and those reported by CAS as present in the PA. STEP 6 Receive the plastic overlay templates from the Administrative Supervisor and PAP. Place them over the AAP " Security Evacuation Badge Accountability Roster"and tape them in place, Badge numbers that are unaccounted for will be those that are nollined throuch. STEP 7 Immediately upon completion of Step 6, call the Security Supervisor in the TSC and simutaneously CIRCLE the missing badge numbers on the top plastic overlay and report missing personel. WHEN DIRECTED, initiate actions to locate missing badges / personnel and initiate the following announcement over the station paging system.
" ATTENTION, THE FOLLOWING PERSONNEL REPORT YOUR LOCATION TO SECURITY h l1,trn ATTHE PR;ieAiiY%CCE55 PORTAL FOR ACCOUNTABILITY (NAME AND BADGE i
NUMBER OF ALL UNACCOUNTED FOR PERSONNEL" (repeat the announcement.) STEP 8 If the unaccounted for personnel have not repor:ed their whereabouts after approximately five minutes, the SSL shall report the names of the individual (s) who cannot be located to the Secunty Supervisor in the TSC OR directly to the ED/IED, if { } appropnate. 58
t i SPP 114 ATTACHMENT 7 ' Page l of 1 Revision 10 Q SITE EVACUATION PERSONNEL ACCOUNTABILITY POST: ACCESS PORTAL SUPERVISOR LOCATION: PRIMARY ACCESS PORTAL (PAP) INSTRUCTIONS: Follow these steps to ensure personnel accountability during a site evacuation. STEP 1 Receive notification of a site evacuation. Write down time. STEP 2 Evacuate non-essential personnel through the PAP exit portal. Collect badges in basket. Do not card out or slot badges. (NOTE: Post secunty officer at turnstile (s) with basket to collect badges.) STEP 3 Following announcement of an evacuation, personnel requesting access to the PA will be dealt with on a case-by case basis thru the Security Supervisor in the TSC or in his absence, directly through the ED/IED. NOTE: Should the Security Computer System become inoperative during an emergency event, the entry and exit of aJ personnel, except emergency response personnel to or from the PA shall be recorded using an Access Control Log (SSA Form 417 - Attachment I) after the evacuation of non-essential personnel has been completed. STEP 4 Usin a grease pencil on the " Security Evacuation Badge Accountability Roster" (plah,ci overlay) LINE -THROUGH badge numbers present or' the badge-boar including terminated an( purged badge slots. (NOTE: Step 4 can begin simultaneously with Step 1). While this is being accomplished, direct an appropriate number of secunty officers to check EVERY PAP badge slot from the ornosite side of the badge board to ensure that no badges are incorrectly slotted, STEP 5 Line through badge numbers collected in the basket, placing badges in the second basket as they are called out and lined through. These badges should then be activated in exit cardreader and slotted on the badge boards as soon as possible. NOTE: REMEMBER, line through the badge numbers of security force officers present in the PAP. STEP 6 Deliver the completed plastic overlay to the APS at the AAP. Step 6 should be completed within 20 minutes of Step 1. STEP 7 Any personnel who attempt to exit the PAP after the initial report is submitted should be reported to the APS immediately. 59
4AJ._4m..A=.6.W. .4ma_-._aha, e-s_s.4,A,.--c.J. =m.--....e a m. 4 w mp -mua_2 - __ -_ w -,., m.-.,.4__-, ,- - - - - --_ ---.- - - - - - _ , , _ _ _ l l I 1O ( l I i i i H EALTH PHYSICS i i DATA l !O l l i i i k
^
i !O i ! 60 f
Health Physics Data / Overview Pre-Drill - Failed fuel Action Plan 2 T = -20 (1940) - Approx,0.1 gpm tube leakage "C" Steam Generator Steam Generator Blow down to hot well
- Wind 2 mph @ 90 at = 2' "B" Train Week Plant Operation @ 99.8 for last 160 days.
T = 0 (2000) - Light plane crash in switchyard. Loss of 'B' Train safeguards power.
** - All dose rates normal T = 15 (2015) -
DMIMS Alarm 'C' S/G
'C' S/G Tube leak from 0.1 gpm, to 500 gpm over next 20 minutes.
** - Dose rates in IB and TB increasmg (RM A9 increasing)
(Shift HP to start offsite dose calculation) T = 30 Dose Rates: in MR/Hr.
'C' Main Steam Line -
- 70 - G/A A& B Main steam Line -
*5 Cond. Shell -
- 20 - G/A 3 to 0.5 S/G Blowdown Ht. Ex. Area -
- 50 - G/A 10 TB 412 -
G/A 0.5 to 5 TB 436 - G/A 0.5 to 5 TB 436 - G/A 0.5 to 10 MSR's 436 -
- 50 IB 436 E. Penn -
2 to 15 Si(Low Pzr. Level) S/G Blowdown Isolated PORV's Open - (30% Ct 10 minutes) T = 35 (2035) - Tube Leak Steady @ 500 gpm 'C' 5/G
=T = 40 (2040) - Main Cond. Vacuum Switch Problem
@ requires plant cooldown using PORVs
@ bottle up 'C; S/G close MSlV T = 45 (2045) -
TDEFP (18412) Isolation Valve (28028) fails to close from the Main Control Board. T = 60 (2100) - _TDEFP starts due to rapid cooldown of 5/G's and low levels on A and B S/G's. CTDEFP Steam exhaust boot ruptures 50% to atmosphere 50% to room 18412 T = 90 (2130) - StopRelease TDEFP Loss of 115 kv line
- A Train Off-site Power (Loss of all Off-site Power)
*
- Dose Rates in for 18412
- TDEFP Room 8000 mR/Hr O/S Room 5000
*
- Air Sample in IB 412 1 E-1 pCi/CC Part 9E + 0 pCi/CC 12 1 E + 0 pCi/CC Gas
*
- Contamination 18412 G/A MRAD / Swipe T = 190 (2310) Offsite Power Restoration to 'A' Train T= (2340) Begin Recovery planning End of Drill 61
,O *g
SUMMARY
OF ANALYSIS BETA DOSE RATE Calculate Open Window = Closed Window x 1.35 For All Dose Rates in Intermediate Bldg. >T = 60 No Beta Detected Before T = 60 Beta Dose Rate in Steam Leaks in Turbine Bldg. After T = 20 to T = 60 Calculate Open Window = Closed Window x 1.35 No Beta Detected in Any Other Areas At Anytime. t. l l
'C' SG Blowdown Activity mci /mi For an ISOTOPES Specific Activity multiply in concentration in the RCS time 0.25.
Dose Rates from blowdown sample l # of ML's Mr/Hr 1 4.4 Contact
.3 12"
.04 3' 10 44. Contact
, 3 12"
.4 3' l
V 62
SUMMARY
OF ANALYSIS INTERMEDIATE BUILDING Air Activity - 412 elevation General Area - T = 0 to T = 60 - No detectable General Area > T = 60 to Termination of Drill (pCi/ml) Gas - 1.28 E + 0 lodine - 9.15 E + 0 Particulate - 1.36 E-1 Air Activity-436 elevation General Area - T = 0 to T = 65 - No detectable General Area > T = 65 to Terminstion of Release from 412 (pCi/ml) Gas - 1 E-2 lodine Particulate - 9E2 1 E-3 h Contamination: 412 elevation Smears taken before release - No detectable Smears taken after release Approx.T = 60 Smear / Swipe = 1000 MR/Hr. East Side,800 MR/HrWest Side TDEFP Rm Smear / Swipe 6000 MR/Hr. Contamination: 436' elevation Smears taken from T = 0 to T = 65 - No detectable Smears taken after T = 65 Smear / Swipe by opening to 412 500 MR/Hr. l 63
1 1 1 1 1 1 4 h General Area Smear / Swipe 50 to 300 Mr/Hr to 0,5, Mr/Hr by doors to Turbine Building i i , k 1 i l l C . 9 i 64
SUMMARY
OF ANALYSIS TURBINE BUILDING General Area - Gas - <LLD Ir, dine - Not Detected Particulate - Not Detected H3 Not Detected
@ Steam Leak - (>T = 20 to T = 80)
Gas - 1 E-6 lodine - 1 E-9 480 NCPM on LUDLUM/10 min. samples Particulate - 2 E-10 80 NCPM/ min H3 Not Detected Contamination: Smears taken in water >T = 20 to termination of drill 300 to 800 cpm above Bkg. Smears taken in other areas - No detectable k O I 65
I i All DTE RATES IN cR/Hr (close windca) TB 412 G/A TB 436 G/A TB 463 G/A 13 436 G/A 436 E PENN. TDE - W l E W i E W E U sfe<m
-.. .. q .-..-..---....---..-q.....--.a.-------'.--..- -----.... .....E.... ....- .--.k.c.":-
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2 65 T-50 I " I "
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O CHEMISTRY AND O RELEASE DATA O 90
i 4 Projected Off-Site Doses O Release l EDAP Expected Dose Assessment (Scenario 10 Minute PORV Release) The scenarlo involves a steam release from "C' S/G PORV at 30% flow for 10 minutes immediately following the Safety injection. Since this release occurs early in the scenario (T = 30) and is of such short duration, accurate quantification of this release is not expected. However, the following two sets of results give the most likely outcome of dose assessment calculation performed for this release:
- 1) *C' S/G steam flow should Indicate about 2.66E+5 Lb/Hr (885,000 Lb/Hr design flow times 30%), if the calculations for this plum are performed after the release is terminated, the resultant average hourly steam flow should be 2.21'd+4 Lb/Hr for the 2 hour dose calculation period. Steam pressure should be about 1000 psi and RM G19C should read about 5 mR/Hr (expected simulator output).
Meteorological conditions are as indicated on the pre-drill data sheets. RESULTS: " ALERT" with the following dose assessment: 2 Hour Dose Assessment in Rem Miles Whole Body Thyroid 1 2 7.7E 3 3.2 E-3 3.3E 1 1.4E 1 h 5 9.7E-4 4.2E T 10 4.2E-4 1.8E 2
- 2) If the dose assessment is performed during the release, the Indicated PORV steam flow of 885,000 Lb/Hr will result in the following very conservative results.
These results are high due to the assumption that the release will continue for the entire 2 hour assessment period. RESULTS " GENERAL EMERGENCY" with the following dose assessment: 2 Hour Dose Assessment in Rem Miles Whole Body Thyroid PAGs 1 3.1E 1 1.3 E + 1 Shelter 2 1.3E 1 5.6E+0 Shelter 5 3.9E 2 1.7E + 0 None 10 1.7E 2 7.2E-1 None l 91
O noi.... ii ! EDAP Expected Dose Assessment (Scenario 30 Minute Terry Turbine Release) ! This scenarlo involves a 30 minute Terry Turbine (Steam Operated Emergency Feed Water Pump) run at 100% design steam flow. The release is reduced to 50% design steam flow due to a rupture in the turbine steam exhaust trunk boot. This has the effect of dumping half of the steam to the Terry Turbine Room and half to the atmosphere. Therefore, the indicated 'C' S/G steam flow is twice the steam release rate. Three possible dose assessments can be made depending on the data available at the time of the assessment.
- 1) "C" S/G steam flow should Indicate about 25 000 Lb/Hr at about 1000 psi.
RM G19C should indicate about 5 mR/Hr. Meteorology same as Release 1. RESULTS: " ALERT" with the following dose assessment: 2 Hour Projected Dose Assessment Miles Whole Body Thyroid - 1 8.9E 3 4.5E 1 2 3.7E-3 1.9E 1 5 1.1E 3 5.7E 2 10 4.8E-4 2.5E 2 ~ 0 2) If the dose assessment is performed using field team " call in" data, the T following results would be expected based on a sample taken at 1/2 mile on the plume center line. Air sample (280 liters,10 cubic feet) reads 300 NCPM on the lodine cartridge and <100 NCPM on the particulate filter. The general area open window dose rate reading is ~ 10 mR/Hr (9.7). The meteorological conditions are the same as Release I. RESULTS: " ALERT" with the following dose assessment:- 2 Hour Projected Dose Assessment Miles Whole Body Thyroid 1 1.1 E-2 1.7E-1 2 4.6E-3 7.2E 2 5 1.4E-3 2.2E 2 10 6.0E-4 9.3E 3 O 92-
- 3) If the dose assessment is performed using the laboratory results of the field team samples, the following rMults are expected. Sample results indicate 1.72E 7 uCl/ml Total lodine and 2.41E 5 uCl/ml Total Noble Gas. All other parameters are as before. The resultant calculations give a release rate of 3.66E 4 Cl/sec lodine and 5.13E 2 Cl/sec Noble Gas.
RESULTS: " ALERT" with the following dose assessment: 2 Hour Projected Dose Assessment Miles Whole Body Thyroid 1 2.2E 3 2.1 E 1 2 9.2E 4 8.6E 2 5 2.8E-4 2.6E-2 10 1.2E 4 1.1 E 2 4 O O 93
Reactor Coolant Radiochemistry - At Start Of Annual Exercise Nuclide uCl/ml 1131 2.50E-2 1-132 1.41 E-2 1-133 1.11 E 2 1-134 2.83 E-2 1-135 1.35 E-2 Kr-85 0.00E + 0 Kr-85m 4.02E-2 Kr-87 5.32E 2 Kr-88 6.96E-2 Xe-131m 0.00E+0 Xe-133 2.49E-1 Xe-133m 1.04E-2 Xe-135 2.30E-1 l Xe-135m 3.24E-1 Xe-138 3.01 E-1 l O Sr/v-80 Te-132 0.00E + 0 5.82E-4 Cs-134 0.00E + 0 Cs-136 0.00E+ 0 Cs-137 0.00E + 0 Cs-138 8.67E-2 Na-24 1.42E-2 Ru-106 1.47E-2 Mn-56 1.67E 2 Mn-54 5.31 E-4 Ce-144 2.42E-3 l l l l O l 94
A i
- Reactor Coolant Radiochemistry - After Si for Annual Exercise h Nuclide uCl/mi 1-131 2.50E + 0 l-132 1.41 E+ 0 1-133 1.11 E + 0 1-134 2.83E + 0 1-135 1.35 E + 0 Kr-85 0.00E + 0 i Kr-85m 4.02E-2 i Kr-87 5.32 E-2 i Kr-88 6.96E-2 Xe-131m 0.00E+0 Xe-133 2.49E-1 Xe-133m 1.04E-2 Xe-135 2.30E-1 Xe-135m 3.24E-1 Xe-138 3.01 E-1 Sr/Y 90 Te-132 0.00E + 0 5.82E-4 Cs-134 0.00E + 0 Cs-136 0.00E + 0 Cs-137 0.00E + 0 Cs-138 8.67 E-2 Na-24 1.42 E-2 Ru 106 1.47E-2 Mn-56 1.67 E-2 Mn-54 5.31 E-4 Ce-144 2.42E-3 l
l O l l 95
Steam Generator Radiochemistry - At Start Of Annual Exercise Controler Sheet Nuclide uCl/ml 1-131 2.1'7 E-5 l-132 1.23 E-5 l-133 9.66E-6 l134 2.46E-5 i 1-135 1.17E 5 del = 2.62E-5 Kr-85 0.00E+ 0 Kr-85m 0.00E + 0 Kr-87 0.00E+ 0 Kr-88 0.00E+ 0 Xe-131m 0.00E+0 Xe-133 0.00E+ 0 Xe-133m 0.00E+0 Xe-135 0.00E + 0 l Xe-135m 0.00E+0 Xe-138 0.00E + 0 O Sr/v-90 Te-132 0.00E + 0 1.50E-6 Cs-134 0.00E + 0 Cs-136 0.00E + 0 Cs-137 0.00E+ 0 Cs-138 2.23E-4 Na-24 3.66E-5 Ru-106 3.79E-5 I Mn-56 4.30E-5 Mn-54 1.37E-6 Ce-144 6.24E-6 Total Particulate = 3.50E-4 O 96
i l Reactor Coolant Radiochumistry - At Start Of Annual Exercise Controler Sheet h Nuclide uCl/ml 1-131 2.50E 2 1-132 1.41 E-2 . I 1-133 1.11 E-2 1-134 2.83 E-2 1135 1.35 E-2 DEI = 3.01E-2 Kr-85 0.00E + 0 Total lodine = 9.20E-2 i Kr-85m 4.02E-2 Kr-87 5.32E 2 Kr-88 6.96E 2 Xe-131m 0.00E+0 Xe-133 2.49E-1 Xe-133m 1.04E-2 Xo-135 2.30E-1 Xe-135m 3.24E-1 Xe-138 3.01 E-1 Total Gas = 1.28E+0 Sr/Y-90 0.00E + 0 Te-132 5.82 E-4 Cs-134 0.00E + 0 Cs-136 0.00E+ 0 Cs-137 0.00E + 0 Cs-138 8.67E-2 Na-24 1.42 E-2 Ru-106 1.47 E-2 Mn-56 1.67 E-2 Mn-54 5.31 E-4 Ce-144 2.42E-3 Total Particulate = 1.36E-1 O 97
l Reactor Coolant Radiochem!stry - After Si for Annual Exercise Controler Sheet Nuclide uCl/ml 1-131 2.50E + 0 1-132 1.41 E + 0 l-133 1.11 E + 0 1-134 2.83 E + 0 1-135 1.35 E + 0 DEI = 3.01 E+0 Kr 85 0.00E + 0 Total lodine = 9.15E+0
- Kr-85m 4.02E-2 Kr-87 5.32E-2 Kr-88 6.96E-2 Xe-131m 0.00E+0 Xe-133 2.49E 1 Xe-133m 1.04E-2 Xe-135 2.30E-1 Xe-135m 3.24E-1 Xe-138 3.01 E-1 Total Gas = 1.28E+0 O
l srev-90 0.00E+ 0 Te-132 5.82 E-4 Cs-134 0.00E+ 0 Cs-136 0.00E + 0 Cs-137 0.00E + 0 Cs-138 8.67E-2 Na-24 1.42 E-2 Ru-106 4.47E-2 Mn-56 1.67E 2 Mn-54 5,31 E-4 Ce-144 2.42E-3 Total Particulate = 1.36E-1 lO l 98
1 i PORV Release - Controler Shoot h Release Start Time (T) = +30 Clock Time ~20:30 Release Duration = 10 minutes at 30% PORV Flow lodine Release Rate = 428 uCl/sec = 4.28E 4 Cl/sec i Particulate Release Rate = 0.644 uCl/sec = 6.44E-7 Cl/sec i Gas Release Rate = 4.02E+4 uCl/sec = 4.02E 2 Cl/sec j Radionuclide Release Rates: (uCl/sec) 1131 1.16E +2 1-132 6.55 E + 1 1-133 5.16E+1 1-134 1.32E + 2 1-135 6.28 E + 1 Kr-85 0.00E + 0 Kr-85m 1.27 E + 3 Kr-87 Kr-88 1.68E + 3 2.19E + 3 h Xe-131m 0.00E+0 Xe 133 7.84 E + 3 Xe-133m 3.28E+2 Xe-135 7.25E + 3 Xe-135m 1.02E+4 Xe-138 9.48 E + 3 Sr/Y-90 0.00E+ 0 Te-132 2.76E-3 Cs-134 0.00E+ 0 l Cs-136 0.00E + 0 Cs-137 0.00E + 0 Cs-138 4.11 E-1 Na-24 6.73E-2 Ru-106 6.97E-2 Mn-54 2.52 E-3 Mn-56 7.92E-2 Ce-144 1.15 E-2 g 99
Terry Turbine Release - Controler Sheet Release Start Time (T) = +60 Clock Time ~21:00 Release Duration = 30 minutes at 50% Terry Turbine Flow lodino Release Rate = 458 uCl/sec = 4.58E 4 Cl/sec Particulate Release Rate = 0.690 uCl/sec = 6.90E-7 Cl/sec Gas Release Rate = 1.00E+5 uCl/sec = 1.00E-1 Ci/sec Radionuclide Release Rates: (uCl/sec) 1-131 1.25 E+ 2 1-132 7.02E+ 1 1-133 5.53E+1 1-134 1.41 E + 2 1-135 6.72E + 1 Kr-85 0.00E + 0 Kr-85m 3.15E+ 3 O Kr-87 4.16E + 3 Kr-88 5.45E + 3 Xe-131m 0.00E+0 Xe-133 1.95E+4 Xe-133m 8.14E+2 Xe-135 1.80E + 4 Xe-135m 2.54E+4 Xe-138 2.36E+4 Sr/Y-90 0.00E + 0 Te-132 2.96E-3 Cs-134 0.00E+ 0 Cs-136 0.00E+ 0 Cs-137 0.00E+ 0 Cs-138 4.40E-1 Na-24 7.21 E-2 Ru-106 7.47E 2 Mn-54 2.70E-3 Mn-56 8.48E-2 O C.-144 1.23 E-2 100 ___ _ -- 1
i
*C" Steam Generstar & Blowdown Sarnple Cecc.treekm.
Note *A*& T SEs activitics remain comtant at presfrill va!wes Cmcentratsons in S?G Bkew in oCi/mi Drin Time T= Nuclide 20 30 40 50 to 120 1s3 I-131 147E-01 1.00E + 00 13RE + 00 199E + 00 179E +00 6 66E + 00 1.0SE + 01 I I32 221E43 6.09E 03 7.97E43 1.14E42 1.46E42 237E42 309E42 I-133 1.9'tE43 538E43 767E43 1.16E42 135E42 3 69E 42 601E42 1-134 4.91E43 124E42 130E42 1.98E 42 232E 02 148E42 IE2E42 1-135 126E43 6.44E 03 8.70E43 1.29E42 170E42 364E42 5 33F42 Kr45 0.00E +00 0.00E + 60 0.00E + 00 0 OcE +00 000E +00 0 00E + 00 000E + Ge Kr45m 152E M 3.72E M 363EM 1.53E M 144EM 195E 06 2.53E 06 Kr-87 532E46 4.86E M 4.43EM 405E M 3.69E 06 114E 06 124E 06 Kr48 6 42E46 616E E $ 92E46 568EM 5.45E46 4 27E M 335E M Xe-131m 0.00E + 00 0 00E +00 0 00E+00 0 00E + 00 0 00E+ 00 0 00E + 00 000E 400 g Xe-133 2.49E45 2.48E45 2.48E45 1.03EM 2.4SE45 193EM 2 4SE45 1.03E46 146E45 101E M 145E45 100E46
- Xe-133m 1.04E46 1.03E46 Xe-135 124E45 221E-05 119E45 116E45 113E45 1.%E45 1.fnE 05 Xe-135m 124E45 107E45 132E45 840E46 536E M 360E47 142E45 Xe-138 1.13E45 6.89E46 4 21E46 2.3 FEM 1.58E M 826E48 433E49 Sr\Y-90 0 00E +00 0.00E + 00 0 00E +00 0.00E+ 00 0 00E+ 00 0.00E + 00 0enE+00 Te-132 1.05E44 114E44 4.19E44 6.27E44 836E44 1.97E43 119E43 Cs-134 0 00E+ 00 0.00E + 00 0 00E+00 0.00E + 9) 0 00E+00 0 00E +00 0 00E +00 Cs.136 0 006 + 00 0 00E + 00 0 00E+00 0 00E + 00 0 00E + 00 0 00E+no 0 enE +00 Ca-137 0 00E +00 0 OnE + 00 0 00E +00 0 00E + 00 0.00E + 00 000E + 00 0 00E + 00 Cs.138 1.57E42 178E42 4 08E42 4.93E42 5.25E42 143E 02 133E 62 Ns-24 153E43 7.52E 43 9.9RE43 1.49E42 1.96E42 4 46E42 6.95E42 Re.106 2.66E43 7.97E 43 1.07E42 1.60E42 113E42 5 07E42 827E 42 Mn-56 176E43 7.92E43 1.01E42 1.46E42 1.85E42 33FE42 4.22E 42 Mn-54 9.60E45 2.88E44 3 85E44 178E44 7.69E44 1.83E43 199E43 Ce-144 438E44 131E43 1.75E43 263E43 151E43 835E43 13tE42 Rb48 0 00E+00 0 00E+00 0 00E+00 0.00E + 00 0 00E +00 0 00E +00 0 00E +00 Mo 99 0.00E + 00 0 00E + 00 0 00E + 00 0 00E + 00 0 00E + 00 0 00E 4 00 000E+00 9 O O
l l A V Environmental Monitoring Team Controller instructions This exerciso consists of two distinct releases. Providing data which is not misleading will be a difficult task, if within close proximity of the site, some indications which may not be ask for (such as sound or sight of steam release or increased background on instruments) will need to be volunteered by the controller. Note that after plum passage, instrument backgrounds will be elevated by about 10% of the ground or surface contamination count rates. During plum passage, dose rates given in the attachment will affect f1M.14 backgrounds by a factor of about 16,000 cpm per mR/Hr. The first plum requires only 10 minutes to pass and the second plum requires 30 minutes to pass. Instrument reading and count rates and their time dependence are vital to cunveying the nature of the releases. Since the first plum arrives at the 1/2 mile point only 60 minutes into the drill, environmental monitoring teams will probably not be in place to intercept and measure the airbome component. During setup of the equipment,it may not become obylous that the area is already contaminated to low levels. However, if a frisker ?: moved close to a contaminated surface, an audible response would be noted by team personnel, and should be simulated by the controller to provide information which would be obylous in a real situation. Note thrit all drill data has been decay corrected and is in units suttable to give to the environmental monitoring teams. Field readings for air samples should be ratioed if the sample is sized differently than the standard (10 cutt), if the monitoring team la significantly off the plum center line, both altborno and surface contamination may be ratloed by the values in the distribution charts (ratios obtained using the airborne lodino distribution chart may be applied equally to the readings for lodine, particulate and gas). However, those charts were provided for the controller's use in getting a better feel for the scenarlo. As such, these charts do not contain the correct units to give directly to the monitoring team. To use these charts, ratio the center line value to the value at the appropriate distance from center line and adjust the applicable centerline instrument readings. Use this technique only if absolutely necessary to maintain reality and ensure that the dose assessment controller is notified so that appropriate adjustments can be made in the gamma spectral analysis results. If soll or water samples are taken the correct Instrument reading will be background. If vegetation samples are taken contact the dose assessment controller for instrument readings. In any of the i above cases, contact the dose assessment controller so that appropriate gamma spectral analysis results can be provided. 102
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PLANI aI4YUS FUWM TIME: l'J : t u i + .7 $T "11 T/ MOT-4 (WR) c17.4 F LE100WN 102.* hPM T/ HOT-9 (kR) c 17. 4 y CMAR6tNG es.r GPM T/ MOT-C (WR) 617.6 F TOTAL SEAL 27.1 GPM T/CbLO-A (WR) 555.0 F stAL RfN 3 . L1 GPM#ra# T/ COLD-8 (m') 55#.4 F NOAH TE VT.5 4 1/ COLD-C (WR) 557.5 F SI FLOW .O GP9 RCS PPESS 2235.7 PSI 6 RWST LivEL WS.S t PIR LEVEL 59.9 1 ACCUM A LVL 10.1
- BORON CONC 9F6.3 PPM PRESS 632.6 PSIG RCS SUBC00LLD -24.1 8 ACCOM w LVL ov.4 %
Rx POWtR 100.6 & PRcSS 631., Phtu S/G-A LVL (kR) 62.V E ACCU 9 C LvL /1.1 3 S/G-3 LVL (WR) 62.9 E Pa c SS 634.4 PSib
$/G-C LVL (WR) 62.V 2 R.V. LEVEL 120.0 t S/G-4 PRESS 9 3 3.0 PSIG R.W. PRESS .* PS16 S/G-9 PRESS v32.0 Pi!G d.d. ItMP 116.9 F S/6-C PRESS 934.2 PSIG R.B. SU9P .1 FT FW PUMP A 3.932 MPPM R.9. 44 CONC .0 2 FW PUMP d 3.Sid MPPM R.U. $8"AT NO FW PUMP C 4.031 1PpH R.H. !$0L NO S/b-A FFW 1$3 g d 6PM FMA$t A NO O NO VtMT NO S/G-3 tFW 163,7 6PM RCPeg ggqqgqq g g g S/G-C EFw 162.2 iPM RHR PUMP RUN 9 CONT STOR TK 52.4 FT C/S PUMP RUN A COND STS A'/ A IL ABL E Ah O O O
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.j ,, GAS T.$E+0S CPM NM-A10 WASTE gas VISCH gas e.it+04 LP4 RM-A9 -COND OfF GAS Re-All AUN WLOG VENTILAY!UN i RMA11.1' 436'0EMIN AdE4 GAS't PART 4.VE+02 CPM RMA11.2 All Hg ANEA GAS S PAWT 4.fE*Ut LPM R9411.3 397 W60T ANEA. IGAS'6 PART 4.VE+04 CPM HMA11.4 3/4 WMUT-uM4 GAS & PA4T 4.vE+92 (PM l RM411.5 456 00404 SYS 6AS t PaRT 4.WE*02 CPM WM A11.0 412 W.EVAP COMP GAS & PART 4.vE+0E tem l #4A11.7 364.CHG/S!/eECOL, GAS S PART 4.vE*04 CPM dMA11.8 463 PER ACCESS GAS 4 PARI 4.YE+02.tPM '
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'RM411.11 463 dMT ROO*S 6Ah & PART 4.vE+04 CPM 'NMA11.12 612 #ESIM HAND 645 s pad 1 6.vt+Ut LP9
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i I RADIATION MON 1 Top!NG SY5ftM l i TIME: 10 : t *J i T of ++ MIM 1 RM-G1 CONTROL ROOM t.0E-01 d81HR RM-L1 NCS LETDOWN 1.4E+04 (P1 l RM-G2 PADIOCHEM LAH 4.1E-01 M4/HR l 1.dE-01 MRrHe 4M tta CoaPONtNT CooLINw 1.)t*Ut t'a
- RM-65 SAMPLIN. 800=
RM-64 HOT MACHINE SMOP 1.vE-01 MR/HR R1-L2B CohPONENT C00LIN6 1.)f*04 LP9 RM-G5 R d PER ACCESS 2.SE+03 MR/HR RM-Go R B REFUEL OWIDGE 7.VE+01 MR/HR RM-L3 SYM GEh h D SAMPLE 4. t E +'13 ( 8 9 RM-G7 R 9 HIGH RANGE $.UE-01 R/MR NM-L4 SPtNT futt COOLING 1.1t*0) LPM RM-GR FH9 Rg!DGE 4.9E-01 Mw/Hs 2.1E-01 MRtHH RM-LS Liu WASTE Ett e.35+U) LFa RM-G9 AUK BLDb DEMIN RM-G10 Aur ALDG wGDT i.0E-01 14/d2 RM-Lo BORON aECVCLt 4.1E*U3 trM R M- Gi l AUA BLOG DROM AREA 1.YE-01 MR#HR NUCLEAR 8 0 t.UE+0g (PM RM-G12 AUA BLDG H V 1ANC 2.CE-01 MR/HR RM-L/ AUX 9LDG CHARuf PMP 0.0E+00 MR/HR RM-L8 TURD RM SUMP U.UE*UU tPM RM-G13 RM-G14 R e IN CORE 4.9E+01 MS/HR RM-Lv WASTE DISCHARGE v.eE+0) LPM U.UE+00 MS/HR WM-L1U STM GEN d D plSCMAMGL 4.UE*0) LF9 RM-G15 MOWABLt M0k110R RM-616 TURBINE BLDG 2.1E-01 Ak/4R METEOROLOGICAL IN70RMAY"UM 5.1E+01 MR/HR WIND SPEED 11.4 *PM RM-GITA R e MANIP CRANE (3U.3 Otb RM-G178 R B MANIP CRANE 8.0E+01 MA/HR WIND DIPtCTION 5.1E-01 N/M4 OtLTA i 10-01 00.0 DLs t RM-G16 4 L' HIGN RANGt 0% 2.tE-01 ME/HR DELTA T 10-40 JU.o oEh
- as aM-G19A STM LINE A 2r9U00.0 (fa RM-G198 STM LINE B 1.YE-01 MRIHR MAIN PLANT vtNI tLod RM-G19C STM LINE C 2.1E-01 Mo/HR
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Na- Plagi $TafuS 73RM Nd 46' itME: 10:45 i * /d *t M A N T/ HOT-A (WR) 617.3 f LtioudN 103.1 GPM T/ HOT-d (WR) 617.5 F CHA86thG dt.T GPM T/ MOT-C (WR) 017.5 F TOTAL Stat 27.3 GPM 1/ COLD-A (dR) 555.3 F SEAL RIN 3.0 GPMtPMP T/CGLD-9 (WR) 557.T F 10aN Y( 97.s
- T/ COLD-C (WR) 557.7 F SI FL0d .0 GPM RCS PRESS 4245.6 P5IG RWST LEVEL v3.5
- PIR LEVEL 60.5 t ACCum A LVL TO 4 2 dORON CONC 9T6.3 PPM PRESS 633.9 PSlu RCS SubC00 LED -24.5 F aCCum b Lvt 69.)
- RK P0dtR -130.4 4 PRtS$ 032.4 Pb1G S/G-A LVL (WR) 62.1 % aCCUM C LVL T1.5 %
S/G-8 LVL (Wa) 62.1 4 PRkSS 635.5 PSIG S/G-C LVL (WA) 62.1
- R.V. LEVEL 140.J
- S/6-A PRESS 935.2 PSIG W.8. 'RESS 1.1 PSIb S/G-9 PRESS 934.5 PSIG N.w. TEMP 125.1 F S/G-C PRESS v36.6 PSIG 8.b. SU"a .1 FT FW PUMP A 3.97T MPPH d.u. H2 CONC . 'S &
FW PUMP B i.865 MPPM R.U. $PN4Y NO FW PdMP C 4.301 MPPH R.8. 150L NO S/b-A EFW U GPM PH4SE A NO e 40 VtWT NO S/G-9 LFW .0 hPM 4CP'$ RUhh1NG A W C 5/G-C EFW .0 $PM RHR PUM8 RUN 9 CONT STOR TK 34.2 Fi C/S PUMP NUN A COND STS AVAILARLE .a O 4
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4ADIATroN McMitowlNG svstem TIME: 10:!J f + /g e4 514 eM-A1 CONT RM SUPPLY A1W PART 3.UE+01 CPM dM-Al RA ULD6 A14 #441 (.UE*0) (PM XE $.OE+01 C8M ac v.ut+U) LPM t 5.UE+0? CPM I d.1E+03 LPM RM-At MAIN PLANT VEAT ' ART 4.OE+0! C3M as-44 Rx eLos aUnhE En* Ae1 1.uc+0e trM Xi 6.VE+di CPM st 3.tE+U9 LP9 I T.UE+01 CPM i 1.1E+0c (PM RM-ASA AUX SLDG EXP PLNM GAS 5 PART 1.1E+01 CPM RM-A6 FM9 EAM PA1T 1.1E+04 (PM At 1.lE+94 (*M eM-A5w AUa BLDG EAM PLNM GAS 1 PART 1.UE+03 CPM I /.VE*01 LPM RM-AT $AMPLING ROOM MON PART 0.0E+00 CPM kM-45 SPENT FUEL AREA PANI U.UE+UU (PM (PORTABLE) XE 0.9E+0J CPM (PONT4blE) WE U.UE*UU LPM 1 0.0E+00 CPM 1 0.UE+00 189 PM-A9 COND OFF GAS GAS 1.1E*00 CPM MM-410 d45ft GAS DISCM b45 4.1E*02 LPM RM-A11 AUX BLOG VENTILATIUN GA5 & PART 4.WE+02 CPM RMA11.2 412 HK AREA GAS 5 PART 4.YE+0g LPM AMA1t.1 436 DEMIN AREA RMA11.3 397 WGOT AREA IGAS & PART 4.YE +02 C PM NMA11.4 jf4 WMUT-RNR GAS s *A81 6.VE*04 (** DMA11.5 436 00RON STS 6AS 4 # APT 4.WE+0/ CPM RMA11.6 412 w.tWAP C0aP GAS S PA*I 4.vt+0g (P9 RMF11.7 3d6 CMG/51/4ECO GAS S PART 4.YE+02 CPM RM411.5 463 PER ACCtSS 645 6 "Adi 6.vE+Ut LPM RM411.9 436 DEM REM GAS 4 PART 4.VE*02 CPM RMA11.10 Sf6 FDT/ CHEM De GAS E PARt 4.vt+0c trM GAS 5 PART 4.vE+0g CPM RMA11.12 41/ RESIN MAND GAS E Papi 4."t+0g (PM RNA11.11 463 WMT ROOMS
' RM-All MOV ATMOS MON PART 0.UE+00 CPM RM-413 MAIN PLANT WENT 1.1 E-til MesMw m
#M-414 A p PURGE (Hg mAhGED 1.1E-01 MRIHR 9 O O
f% r (y' #ADIAI!UN M0N!IORING ST5ftM ]' (*- f!*t: 10:!) 1 + ff ++ *Le SM-G1 CONTRUL R005 4.UE-01 9R/M8 RM-L1 RCS LtIDUwN 1.ht+H6 LP* RM-62 RADIOCheM Lan 2.1E-U1 MRtHR RM-G3 SAMPLINi R00= 1.9E-01 Ma/HR RM-tta COMPONtNT Cout1No 1.st+0c (PM RM-G4 MOT MACHINE SHOP 1.9E-01 MRtHR *M-Ltw COMPONtNi CUuLINw 1.>t+94 (*M RM-65 R 8 DER ACCESS 2.5E +00 MR tH R RM-66 R H REFUEL WRIDGt 7.9E+01 MRtwd MM-Li 5TM GtN 3 D SAMPLt t.tt+03 trM RM-G7 R e HIGH RANGE 3.UE-01 R /MR - R*-L6 SPtNT FULL CUOLING 1.1T+U) (PM eM-Gd FHB HRIDGE 2.9E-01 MRtHR RM-G9 AUX OLOG DEMIN 2.1E-01 MRtHR RM-LS Lie m* Sit EfF u.3E+0s CPM RM-610 Auf BLDG wGDT t.UE-01 MRtHR RM-L6 90RON RtCTCLt 6.it+03 (PM RM-G11 AUX BLDG DRUM AREA 1.VE-01 MRtHR RM-G12 AUX BLOG H d TANK l.UE-01 MRtHR RM-tr NUCLEAR eD t.Ut*Ut tPM RM-G13 AUA BLDG CHARGt PMP 0.UE+00 MRtHR R M-L t. TURR RM SUMP U.UE+00 t#M pm-G14 R 8.IN C0HE 4.9t+01 MRtHR HM-LW wasit D15C H A RGt v.ot+03 (PM RM-G15 MOVABLE MON 1104 0.0E+03 MR/HR RM-L10 STM GEN 9 O DISCHAMGt 2.UE+03 LPM i RM-G16 TURBINE BLOG 2.1E-01 MR/dd METEOROLOGICAL INFORPAi!UN RM-GITA R U MANIP CRA%E d.1E+01 *RtHR w!kD SPEED 11.3 MPM 4M-61To R S MANIP CRANt d.UE+01 MRtHR. WIND DIRECTION 23).1 Dib RM-G18 4 e HIGH RANGt 5.1E-01 R/Ma DELTA i 10-61 -U.e ett
- RM-G17A STM LINE A 2.lE-01 MR/HR DELTA i 10-40 *U.1 Utb F RM-G19B STM LINE e '1.9E-01 MR/HR MAIN PLANT WENT Flow 249000.0 (FM RM-G19C STM LINE C 4.1E-01 MR/HR' '
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T I M O T- 4 (Wa) 017.5 F LETDOWN 103.0 G*M T/ HOT-6 (WR) 617.5 5 CHARhfMG /B.) hPM T/ HOT-C (wR) etT.S f TOTAL SEAL 27.2 GP" T/ COLD-4 (Was $$$ 3 F SEAL 374 3.J GP9/FM# f/ COLD-H (wR) 557.7 F MOAH TE 97.$ % T/ COLD-C (wR) SST.T f 11 FLOW U.0 G*9 RCS PRtS3 2265.0 *sIG #W51 LtVEL v3.5 3 PZd LEVEL 6d.4 5 ACCVM 4 LVL IV.T 2 90RON COMC VT6.3 PPM PRsSS 635.6 Phl6 ACCUM q $9.9 3 RCS SUBCOOLED -t4.3 F LVL RX POWER 100.4 x retSS 634.2 *SIG S/G-A LVL (WR) 62.0 5 ACCUM C LVL 11.6 1
$/G-8 LVL (w4) 62.1 1 PRtSS 63T.3 PSIG S/G-C LVL (WR) 62.0 E R.V. LtVEL 120.0 1 S/G-A PRESS 936.1 PSIG R.W. PRESS 1.3 PSIG S/G-d PRESS 935.4 PSIG R.9. TEMP 131.9 F S/G-C PRESS 937.2 PS!G R.B. Sua# .1 FT FW PU9P 4 4.0dj MPPH M.S. Hg CONC .J &
FW PUMP 8 3.Y76 MPPH R.H. SPRAY NO FW PLMP C 4.161 MPPM R.S. ISCL M0 Stb-A EFd .0 GPM PMASE A MO 9 MO VtNT NO S/G-4 tFW .0 6PM R(Pe1 RUNNING A 4 C S/G-C EFw .0 GPM RHM PURP RUM CONT $?OR TK $2.5 FT C/S PUMP RUM A COND Sf5 AVAILABLE a N O O O O
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#9-A4 RK t* L O G PuquE EKM *A'7 1.ut+0/ iP9 RM*A) MAIN PLANT Ve%T PART 4.UE*02 (P9 Et S.tt+09 LPM KL 6.VE*U1 CPM I 1.1E+04 (PM 1 T.UE+01 CPM RM-A6 fHe EKM PART 3.1E*04 (PM '
RM-ASA aux eLOG ERM PLNM GA$ & PART 1.1E+01 CPM at 1.tt+04 LPM 1 4.vE+01 LPM RM-AS8 AUK 9 LOG EKH P Lf4 M GAS 4 PART 1.UE+03 Cem SPENT FUfL A#tA PAPT U.UE*UU LPM RM-AT SAMPLING ROOM MON PART U.UE*00 CPM RM-45 RE U.Ut+UU tPM (PORTABLE) XE U.UE+00 CPM (PORTABLE) I 0.UE+00 CPM I U.UE+90 ten
' BAS 1.SE+06 CPM Nm-A10 waSit GAS DISCH 485 2.1E+04 LPM RM-A0 COND OFF GAS RM-A11 Aux ULDb VENTILATION amA11.2 412 HK Asta GAS 5 P A 8 7 4.vE +ff t CPM RMA11.1 4}6 DCMIN ASEA GAS C PART 4.WE+02 CPM GAS E PART 4.YE+04 (PM RM411.3 3v7 WGOT AREA 3G AS 5 PART 4.dE*02 CPM RM411.4 3/4 WNUt-eHR 645 4 PApi 4.9E*02 CP9 R9411.0 412 w.EWAP COMP EAS E PA11 4.vt+Pt lpm eMA11.3 456 a0RON Sv5 465 PtR ACCtSh GAS 5 P44[ 4,vgegg gym RMA11.5 RM411.7 356 CMG/SI / PECO GAS 5 Pant 4.vf*02 CP M R M A 11.10 Jf4 FJTtCHEM Dd 6AS 4 PATT 4.vF+04 (P=
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- 1 :a 1/ MOT-A (h4) 617.5 F LEfDOWN 1U 5.0 6*1 T/ HUT-H (WM) 617.5 8 CHaRw1NG er.1 Gee f/ HOT-C (WA) $17.5 f TOTAL 5EAL 41.1 GPM T/ COLD-A (JR) 555.4 5 SEAL RTN 3.3 6PMtPM' T/ COLD-8 (WR) 551.7 F N0aw T( v/.s x T/ COLD-C (nel 557.5 5 S1 flow 0.0 GPM RCS PRESS 2240.0 *SI6 PwST LtVcL d5.5 1 PIR LfvEL 58.4 1 aCCUM A LVL (1.1 E '
HORON CONC 976.4 PPM PRt%S 638.1 P51b RCS SubC00 LED -14.1 F ACCU 9 H LVL /0.2 3 WR P3wER 100.5 t PRESS 636.5 P516 S/G-4 LVL'(WR) 62.2 1 ACCUM C LVL /2.0 I S/G-d LWL (WR) 62.2 E PRESS 659.$ PSib S/G-C LVL (WR) 62.5 t e.V. LtWEL 120.0 1 S/G-4 PRESS 930.7 PSIG R.W. PRESS 1.4 P5I6
$/G-8 PRESS 935.1 PSIG e.9. TEMP 136.6 F '
S/G-C PRCSS 937.7 PSIG N.d. SUMP .1 FT FW PUMP A I 4.044 MPPH R.C. H2 CO%C .U 1 FW PUMP O 3.98d MPPH M.U. SPRAV NO FW PUMP C 4.150 MPPH R.B. ISOL NO S/G-A EFW .0 GPM PMASE A NO M NO VENT NO l S/G-9 EFW JO GPM RCP'S HUNNING 4 8 C S/G-C EFW .O GP4 AMA PUMP RUN CONT STOR TK 32.4 Fi C/S PUMP RUN A . COND SYS AVAILABLE N Las e i i a l
RADIAf!UN MONITO4tMb % T Sit M 9tgt; gggg) T +20 44 "IN AM-A1 CONT RM SUP'LY AI4 PART S.UE+01 CPM eM-At an eLch als PARI 2.ut+J3 LPM 4t S.UE*UI (PM (t V.UE*US LPM 1 5.UE*01 CPM 1 v.1E+03 LPM RM-43 MAIN etANT WENT PART 4.wi+02 CPM RM-A4 ## eLOG PUR6E Exh PA+t 1.Ut+04 (PM
#E 0.9E+C CPM AE 3.dE+P1 L*M 1 7.UE+0* CPM I 1.1F+04 CPM RM-A5A AUX HLDG EXH PLN4 GAS d PAH1 1.1E*01 COM RM-A6 FH4 EXH PAdf 1.1t+Ut (PM me 1.dE+04 (PM RM-ASE tux HLDG EAH PLNM GAS % PART 1.UE*03 (PM t 4.vt+01 (PM RM-17 SAMPLING A001 M04 *A8T 0.0E*00 CpH 49-A9 S*ENT FUEL APEA PA#1 U.UE+0U LPM (PORTABLE) Xt U.UE+00 CPM (PORTABLE) RE U.UE+0V LPF I U.UE*00 CPM I U.UE+00 (PM RM-49 COND OFF GAS GAS 3.3E+06 CPM RM-A10 dASTE GAS O!SCH 64h 4.1t+0t LP4 R*-411 AUX dLOG VENTILATICN RMA11.1 450 DEMIN AREA GAS % PART 4.Wi+0/ CPM RMA11.2 412 HR ANtA GAS & # arf 4.Wt*U( (PM I dMA11.4 3/4 WHUI-RWN 645 & PARY h.VE+0g (PM RNA11.3 391 WGOT AREA GAS t PART 4.9E+04 CPM RMA11.5 436 dORON SYS GAS & PA41 4.VE+92 CPM NMA11.0 412 W.tVAP Comp GAS 5 PARI 4.Yt+Ul LPM RMA11.7 388 CNG/SI/RECO GAS & PART 4.9E+02 CPM RMA11.8 463 PER ACCESS GAS & PART 4.vE*02 LP" RMA11.9 436 PEM REM GAS & PART 4.VE*Ud CPM RMA11.10 314 70T/CMEM DW GAS 5 PART 4.vt+0E (PM 9M411.11 463 WMT 900PS 6AS 5 PART 4.vt+02 CPM RMA11.12 412 PESIN HAND GAS & PARI 4.WF+0g (PM C RM-All MOV ATMOS MON PART U.UE*00 CPM RM-A13 MAIN PLANT WENT 1.1E-U1 MWsMN u
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PLANI >T a t us fo4M TIMt; 1U:4U T + 78 +4 *14 T/ MOT-A (ww) 617.3 F LFfDUdN 4o.8 GFM T/ MOT-H (WR) 611.3 i CHARGIN6 1$0.0 GPM 1/NOT*C (WR) 617.1 F ICIAL SEAL 22.4 GPM T/ COLD-A (wR) $$5.1 F bcAL 98N 3.0 GPM/P"P T/ COLD-B (WR) $$1.5 F NOAH TK v/.S 3 T/ COLD-C (WR) $57.8 F St Flow 0.0 GPM RCS PRESS 2235.4 PSIG RWST LEVEL v5.5 %
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1 I !, O i i I 4 j CONTROLLER O l INFORMATION l I l l O l 209
l EPP-024 ATTACHMErJT VI PAGE 1 OF 1 REVISION 3 SUGGESTED EXERCISE / DRILL CONTROLLER ORGANIZATION t seffseOre5 (,oordenat NLUr (m ni- OC t end T5C tead 05C tead t ot tead ianatatos leadeir leadiof thne t .d s ..ey Conteone's j Contiones Conteouer Cont olie. Controne. Assrst1E nv., uomte. Ceone, f,b> Mch R v;< F Cw,one, 75-5037 4773 75 5074 yon 227 4773 75 5053 Chern,str y (OF angwice,.ng 5.=awtatoe fiP town Mosentor Tease segue,gy T5C Engmeeving ~
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- O O
EPP-024 ATTACEMENT VII PAGE 1 OF 5 REVISION 3 O INSTRUCTIONS AND RULES POR CONTROLLERS Instructions
- 1. Personnel are assigned as controllers at all key functional areas to monitor and control the exercise. In addition, they will accompany radiological monitoring teams, plant health physics personnel, maintenance / repair 2nd fire / medical teams.
- 2. The in-plant controllers will be coordinated by the Lead Controller located in the TSC (ext. 227). He will be responsible for the overall conduct of the exercise scenario. Field controllers should contact the Environmental Controller in the EOF (ext. 5074) regarding coordination problems or questions.
- 3. Message forms and simulated control room data will be used to initiate, modify, and complete the events comprising the overall scenario. Selected controllers will use the message forms to place the scenario events in effect ar.d to trigger responses from the involved emergency response O organizations. Each controller will have copies of the messages controlling the portion of the exercise scenario for which he is responsible. Evaluators will have packages sufficient to enable them to follow the scenario and facilitate evaluation of events.
Two kinds of messages will be used: O control messages are used as a primary means of starting scenario events by announcing or placing an event in effect by providing the players with scene setting information/ conditions. O Contingency messages are used by the controllers in order to maintain the scenario plan continuity or schedule. Control messages will be verbally presented to the designated exercise participant at the time specified in the event schedule. The controller may need to follow-up with an explanation of the message and .snswer questions to ensure that the participant understands the message. O I 1 211
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=_
EPP-024 ATTACHMENT VII ) PAGE 2 OF 5 REVISIF
- 4. Scenario events are hypothetical. Portions of depicting plant system cperational transients a events. No control room actions or reactions i operation of plant system or affetting generatic .411ty will be initiated. All exercise scenario messagen 11 be prefixed and/or suffixed with the words: "This is a Drill."
controllers stationed at areas vital to maintaining generating capability should take extra precautions to ensure that messages or instructions regarding scenario events do not result in adverse effects on actual plant operation.
- 5. Required controllers will have the time-related radiological parameters of the scenario. This information should be issued upon request to the appropriate participants by the controller accompanying the radiological monitoring field teams.
- 6. Some exercise participants may insist that certain parts of the scenario are unrealistic. The controllers have the authority, with approval from thJ Exercise Coordinator, to clarify any questions regarding scenario content. In some cases, it may be necessary to issue a contingency message to preserve the continuity and objectives of the drill or exercise. This must be authorized by the Exercise Coordinator er Lead Controller.
- 7. Prior to commencement, all telecommunications should be tested to ensure satisfactory communications between the lead controllers and the Exercise Controller.
- 8. All controllers will synchronize their watches to ensure that messages are delivered at the proper time. Times on messages are set relating to the beginning of the exercise, with delivery of the first message at "T=0". Frequent communications throughout the controller network is necessary to ensure time lines are maintained current in all locations.
- 9. Controllers will commence their assignments at assembly locations for players they are to observe or as directed by the lead controller.
- 10. Players are n t allowed to introduce items into the exercise or scenario,
- 11. Be sure to return all scenario packages to the Exercise Coordinator.
O 212
. . - - - _ - . _ . - . . - - _ - - - -_ _ . -~ _ . - - . - - - _- -- - --. EPP-024 ATTACRMENT VII PAGE 3 0F 5 REVISION 3 O
- 12. Lunches may be provided; however, there are no specific lunch breaks in an exercise. Participants should be relieved for lunch as time permits. Emergency team leadere should decide when team members may take a lunch break.
RULES DO's
- 1. Know the overall controller and evaluator organization.
- 2. Identify the players by name and function.
- 3. Identify yourself at all times to all players. Wear arm bands, tee-shirts, tags, or some identifier, as provided.
- 4. Locat'e the phone (or radio for field teams) you will use to maintain communications with lead controllers.
- 5. Position yourself to maximize your effectiveness in issuing nessages or observing the players.
- 6. Be sure you understand the players' scenario portion and the O overall scenario. Know precisely what level of simulation is required and allowable.
- 7. Keep the play on schedule by checking your scenario.
- 8. Issue messages on time. Make sure the players understand them.
- 9. Remember to call the Lead Controller or Exercise Coordinator to report on status of players' actions if off schedule or if in doubt about what to do. Call for advice if players depart significantly from the scenario, which may create a major delay. If necessary, intervene in player action and put players back on scenario track. Document this.
- 10. Allow the players reasonable flexibility to perform their functions and demonstrate their skill, knowledge, and initiative.
- 11. Identify the federal evaluator (s). Make sure they are reasonably aware of all your actions and those of the players.
- 12. Make notes on good and bad points of players' actions, their strengths and weaknesses, and areas for improvement. Use the critique sheets.
213
EPP-034 ATTACRMENT VII PAGE 4 OF 5 l REVISION 3
- 13. Attend the post-exercise critique session to provide your 9' comments and recommendations to the lead exercise :
coordinator.
- 14. Identify the players' leader (such as a foreman on an in-plant team or fire brigade leader). Work with them as i appropriate.
- 15. If a real emergency occurs that affects the players, call off your nortion of the exercise and notify the Lead Contrt11en or Exercise Coordinator immediately.
- 16. The federal evaluators should work through the controller.
They should not issue " surprise" mensages or direct
" surprise" actions at the players. They should work through the controller.
- 17. The player must follow the radiation protection rules.
Controllers and players entering normal nuclear station radiation areas must observe all normal radiation control picctices. However, controllers do not have to follow the radiation exposure control practices for the simulated radiation levels from the emergency exercise scenario. Don'ts
- 1. Don't leave your post at key times.
- 2. Don't prompt the players to take actions. Understand the difference between prompting and providing scenario data when players' accions are correct.
- 3. Don't give the players more information then they have earned or performed actions necessary to obtain.
- 4. Don't forget to call the lead controllers to seek advice or help, as necessary.
- 5. Don't allow the media or other external influences to distract the players. No interviews with players are allowed.
1 O 2u
EPP-024 ATTACEMENT VII PAGE 5 OF 5 REVISION 3 O CONTRCLLER SAFETY RESPONSIBILITIES
- 1. Follow safe procedures and take an active part in the task of protecting your f ellow workers and the plant.
- 2. Cooperation is necessary to protect yourcelf and others.
- 3. Follow safety rules, take no unnecessary chances, use all safeguards and safety equipment provided, and- make saf ety a part of your responsibility.
- 4. In case of accidents or injury, report promptly to the Lead controller and get first aid or medical help without delay.
- 5. Report any hazardous condition to the Lead Controller.
- 6. Cooperate in every respect with the plant safety program so the exercise may be executed in a way that ensures safety.
- 7. Know your exact duties in case of fire or an actual emergency.
,q 8. Safety takes precedence over all other requirements.
D 9 O i l 215 l
EPP-034 ATTACEMENT IX PAGE 1 OT 1 REVISION 3 DRILLIXERCISE EV AIX ATION SITEET h
- g e N A O E y T I 2 C g O E y B L G g P r s L 0 C O A E g O y O 1 R N D 0 R L y T R E D
Area / Function Evaluated Y
- 1. Physical Facilities
- 2. Resource Material Time of Evaluation
- 3. Communications Equipment From to _
- 4. Emergency Equipment Name of Evaluator
- 5. Personnel Quantity
- 6. Arca Access Control Drill / Exercise Date
- 7. Area Accountability-Initial
- 8. Area Accountability-Ongoing
- 9. Record Keeping
- 10. Interface With Other Areas la. Awareness Of Plant Conditions
- 13. Command And Control
- 13. Problem Assessment
- 14. Effective Communications
- Required Explanation Explanations O
M 216 I
EPP-024 ATTACHMENT X PAGE 1 0F 4 EIERCISE EVALUATION CRITERIA General Procedures
- 1. Each evaluator, controller, observer has been furnished and should be familiar with:
- a. Emergency Exercise Cbjectives.
- b. The specific objectives to test the Virgil C. Summer Nuclear Station. State and Local Emergency plans with the ten-mile Emergency Planning zone.
- c. The exercise scenario, initiating events, and expected courses of action to be undertaken.
- 2. A summary and description of each area's location emergency mission. and personnel and their emergency responsibilities should be discussed with the evaluators. controllers, observers.
- 3. Evaluators. controllers, observers should be at their assigned posts between 30 and 45 minutes prior to the commencement of the escrcise, even though the area being evaluated may not be activated until later in the exercise.
O 4 If controllers are to provide information (initiating events, instrumentation readings, environmental monitoring results, etc.) to the exercise participants, the information must be provided exa'tly as prescribed and exactly when prescribed. Failure to procide the information appropriately may invalidate the results of the exercise.
- 5. A Chronological Record must be kept for areas surveyed. the record should show the actual time of the event or occurrence, the result or action taken, elapsed time. (where applicable) and pertinent comments.
- 6. Controllers should offer no information, advice or assistance to the drill participants other than what is intended by the scenario. Any such requests should be declined. Controllers will only interpose themselves if the participants are taking an action that will cause the exercise to go outsiae the parameters of the anticipated time schedule and/or outcome. Examples of problems requiring such interpositions may includes a dose calculation / projection that is so grossly inaccurate that an action level other than the one postulated for the scenario would be institutedt an activity that is taking so much longer than predicted that the exercise scenario is in danger of not progressing as postulated.
U 217 i
EPP-024 ATTACHMENT X PAGE 2 OP 4 REVIS7CN - EIERCISE EVALUATION CRITERIA O Performance Evaluation Criteria To ensure validity of the evaluation, all exercise evaluators, controllers, observers must utilize the same grading criteria. The following grading standards should be utilized.
- 1. Recording Times of Actions
- a. For grading purposes, it will be assumed that onsite personnel have been alerted when the emergency siren is sounded.
- b. For calculating elapsed times, evaluators will be given the actual time the exercise is initiated. This will be T 0 on all reports. All elapsed time calculations will be based on this time, regardless of when the separate evaluated activiti,es are initiated.
- c. An emergency facility or other activity will be deemed to be in service when its personnel accountability check is completed and reported or when a formal declaration of turnover of command has been accomplished.
- d. The " Chronological Events Summary" should be the primary evaluation record.
- 2. Evaluation Standards
- a. Excellent: Personnel and equipment always functioned without error the first time, every time. There were no problems encountered, and all personnel and equipment functioned at a level much greater than could be anticipated.
- b. Good: Personnel and equipment generally performed better than expectations. Any errors or problems were minor, and easily correctable.
- c. Satisfactory: Personnel and/or equipment performed according to expectations, with some minor exceptions. Any errors noted were not severe and could be corrected without undue labor and/or expense,
- d. Poort Personnel and/or equipment generally performed below expectations and/or there were several significant deficiencies noted. The area's ability to carry out its mission was diminished.
- e. Fall Personnel and/or equipment consistently failed to perform as required and/or there were serious deficiencies noted which severely impaired the ability of the area to carry out its mission.
218
EPP-024 ATTACHMENT X PAGE 3 or 4 EXERCISE EVALUATION CRITERIA
- 3. Categories for Evaluation (1) Physical Facilities: Was the area utilized appropriate by virtue of its size and location? Was there enough furniture, ventilation, rest rooms, office supplies, etc., to support the mission? Could the area support the personnel assigned to it?
(2) Resource Materials: Were the resource materials readily availabic to assess the emergency situation and to plan corrective actions - maps, reference books, copies of emergency plans and procedures? (3) Communications Eauipment: Was the onsite, offsite, and connecting communications equipment adequate in quantity,
,.Tability and availabil.xty? Did personnel know how to utilize the equipment efficiently?
(4) Emergency Eauipment: Was emergency equipment readily available, completely operable appropriate to the task or situation, and did personnel know how to use it efficiently? Emergency equipment includes: portable (-~)g g environmental monitoring equipment; personal protective equipment - clothing, respirators; decontaminat on supplies and equipment; first aid and fir-fighting equipment; and communications equipment. (5) Personnel Quantity: Was there enough trained personnel to carry out the mission? Too few? Too many? (6) Area Access Control Did all assigned personnel respond tc their areas promptly-and stay in assigned area for the duration of the exercise? Was the area secured against unauthorized persons being present? (7) Area Accountability - Initial: Was the initial accountability done accurately and in a timely manner? (8) Area Accourij.bility - Ongoing: Was the location of personnel dispatched from the area known at all times? l (9) Recordkeeping: Was all data accurately recorded and maintained in a systematic readily rttrievable manner for further reference? l ' r\ l le/ l 219 i
EPP-024 ATTACHMENT X PAGE 4 0F 4 REVISION 3 EIERCISE EVALUATION CRITERIA (10) Interface with Other Areas and Groups: An area that performs its own mission satisfactorily but that does not interface adequately with other areas, has not performed in an overall satisfactorily manner. Any deficiencies oted in the areas interfacing with other areas should be noted. Such deficiencies may be due to inadequate communications hardaare, organizational deficiencies, or inadequacies in plans and procedures. (11) Awareness of Plant Conditions: Were personnel aware of plant conditions which may impact on their job? (12) Command and Control: Did the area carry out its mission of directing the activities of other components? (13) Problem Assessment: Was information promptly and correctly received, assessed and evaluated? (14) Effective Communications: Did the area establish and maintain communications with other components? Was the information received and/or transmitted accurate, concise, appropriate, and timely? ,
- 4. Summary
- a. Describe any problems noted by the area being evaluated, a '
description of the problem, its outcome or effect, and any recommended corrective courses of action to mitigate or correct the deficiency.
- b. After completing his evaluation report the evaluator (s) is to sign the report and promntly return it as directed.
- c. A critique of the exercise will be held with all key participants, key evaluators / controllers / observers, and NRC/ FEMA observers if present, as attendees.
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