ML20076K994
| ML20076K994 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek, 05000355  |
| Issue date: | 10/25/1994 |
| From: | Public Service Enterprise Group |
| To: | |
| References | |
| NUDOCS 9411020264 | |
| Download: ML20076K994 (556) | |
Text
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i SCENARIO MATERIAL CONTROL FORM ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS Your signature below acknowledges the following: A. Receipt of the below listed scenario materials of the ARTIFICIAL ISLAND EMERGENCY PLAN ANNUAL EXERCISE 1994 CONTROL #
- 1. EXERCISE SCENARIO DATA BOOK B. I understand the above scenario material is CONFIDENTIAL and shall not be transmitted or discussed with any individual who is not identified as either a member of the scenario development team or a designated referee or evaluator. (see approved list in enclosed Section 4.1, Referees / Scenario Development Assignment List)
C. I shall keep this scenario material LOCKED UP when not under my direct control. D. I shall IMMEDIATELY REPORT any loss or suspected l compromise of the contents of this material to the Head Referee or the EP Manager listed below. Craig Banner (Head Referee) 609-339-1157 Tom DiGuiseppi (EP Manager) 609-339-1517 Your name (Print): Signature (Date): / / 94 cc: material recipient file - scenario control 1994 c:\pw\ scenario \ control.94 (!, h OIf
ARTIFICIAL ISLAND ANNUAL EXERCISE 1994 ("% TABLE OF CONTENTS Pace Section Title 1.0.0 1.0 Participant's Schedule Exercise Scope and Objectives 2.0.0 2.0 3.0 Guidelines and Player Information - Index 3.0.0 3.1 Exercise Guidelines 3.2 Player Instructions 3.3 Participating Locations 3.4 Player Participant Evaluation Forms 3.5 Exercise Sign-in Sheet Forms 4.0.0 4.0 Referee / Observer Information - Index 4.1 Referee and Player Assignments 4.2 Referee / Observer Instructions 4.3 Observation Sheets 4.4 Phone Lists 5.0.0 5.0 Scenario Overview - Index 5.1 Scenario Synopsis / Narrative 5.2 Scenario Timeline O' 5.3 Major Observable Onsite Events 5.4 Onsite Actual vs. Simulated Events 5.5 Radiological Assumptions
5.6 Comparison
Scenario vs. Industry Events Exercise Message Forms 6.0.0 6.0 Supplemental Scenarios 7.0.0 7.1 8.0.0 8.0 Operational Data Spreadsheet 9.0 Onsite Radiological & Chemistry Data - Index 9.0.0 9.1 Sample Analysis Data 9.2 RMS Data and Plant Vent Flows 9.3 Inplant Survey Maps and Data 9.4 Onsite Survey Map and Plume Data Offsite Radiological Data - Index 10.0.0 10.0 10.1 Offsite Plume Maps 10.2 Plume Centerline Data 10.3 Specific Location Data 10.4 Met Forecast Data O , TOC Rev. 0 1 l
F' SECTION 1.0 i ARTIFICIAL ISLAND j ANNUAL EXERCISE- 1994. PARTICIPANT'S SCHEDULE-Thursday - Oct. A. OSC Referees / Observers Initial Briefina, book distribution ! and OSC Supplemental Scenario walkthroughs. i Time: 0900 - 1300 Location: Hope Creek TSC (lunch provided) j B. PSEEG Re'ferees/ Observers Initial Briefinc & book ; distribution. (other than OSC Referees) Time: 1430 - 1600 l Location: NDAB (TB2) Conference Room 9 i Monday - Oct. 24 ! A. NRC Exercise Briefina (Banner, Dior, Reece) ; Time: 1300 - 1500 Location: EP Conference Room I B. NRC Exercise Team Access Training & Tour Time: 1500 - 1600 Location: Processing Center /EP Conference Room t Tuesday - Oct. 25 i A. PSE&G Referees / Observers Assemble prior to exercise. Times: Locations: Simulator - Simulator Referees Only 0700 - O. . 0730 .- TSC - All Onsite Referees 0900 - EOF - All Offsite Referees . 8 0 - Ons [ft hmes- 0 30 - Cont ol Ro m S a f HC TSC Locations: Hope Creek Simulator C. Artificial Island Annual Exercise i Time: 0830 - 1530 ENC f Location: Hope Creek Station, Simulator, EOF, 1 I D. Exercise Particicants' Criticue by Players, Referees, and Observers. Immediately following exercise termination. Time: Location: Various ERFs Wednesday - Oct. 26 A. PSE&G Lead Referees' Criticue Time: 0800 - 1100 Location: EP Conference Room B. PSEEG Referee, Management and Player's Critique Time: 1300 - 1400 Location: Processing Center Room 1 NRC Critique EP Staff, PSE&G Management) C. 1400(NRC,
- 1500Lead Refs,ing PSE&G Critique)
O (follow , Time: 1 Location: Processing Center Room 1 1.0.0 Rev. 1 i i l
C (,)T SECTION 2.0 PUBLIC SERVICE ELECTRIC AND GAS COMPANY ARTIFICIAL ISLAND HOPE CREEK GENERATING STATION 1994 ANNUAL EMERGENCY PREPAREDNESS EXERCISE SCOPE AND OBJECTIVES SCOPE: The 1994 Annual Exercise of the Artificial Island Emergency Plan will simulate accident events at the Hope Creek Generating Station culminating in a radiological release. The exercise will involve events that test the effectiveness of PSE&G's Emergency Preparedness Program and integrated capabilities of the State of Delaware in protecting the health and safety of the general public from a radiological emergency at Artificial Island. The exercise will begin on Tuesday morning, October 25th and will conclude that afternoon. s This is an announced full participation exercise The thatofwill State be Delaware evaluated by the NRC and FEMA Region III. g'~') will fully participate in this exercise and the State of New Jersey Current will participate but are not being evaluated by FEMA. plans call for participation by the NRC as outlined in NUREG-0728, NRC Incident Response Plan. To improve realism and to minimize the distraction to the control Room Operators on duty, this exercise will be conducted from Allthe other Hope Creek Simulator.at PSE&G's Nuclear Training Center. emergency response activities will take place in the designated response facilities of the emergency plan. If the Hope Creek Simulator is at any time determined by the l Referees to be providing erroneous or unrealistic operational data ' it shall be necessary to direct the Simulator Staff to freeze or shutdown the simulator for the remainder of the exercise to prevent negative training of the Hope Creek Operators. i l If shutdown of the simulator is necessary, the exercise shall continue through the use of preplanned and prepared operational 2.0.0 es 'r,J
( 'f SECTION 2.0 PUBLIC SERVICE ELECTRIC AND GAS COMPANY ARTIFICIAL ISLAND HOPE CREEK GENERATING STATION 1994 ANNUAL EMERGENCY PREPAREDNESS EXERCISE SCOPE AND OBJECTIVES SCOPE: (continued) data, message forms, and other scenario control techniques in order to support demonstration of exercise objectives in all other Emergency Response Facilities. a To establish the scope and boundaries of the exerciseThe scenario, objectives definitive set of objectives has been developed. were used to ascertain the required inputs to the exercise sequence of events and to establish evaluation critique areas to be observed during the exercise. OBJECTIVES: f-~. A. Emercency Response Facilities 1. Demonstrate the activation and staffing of emergency response facilities.
- 2. Demonstrate communication capabilities between emergency response facilities.
- 3. Demonstrate adequacy of facilities and displays to support emergency operations.
B. Event Classification and Notifications
- 1. Demonstrate proficiency in recognizing and classifying emergency conditions in accordance with the Hope Creek Event Classification Guide (ECG) and the ability to implement Emergency Plan Implementing Procedures (EPIP's).
- 2. Demonstrate the capability of the Hope Creek Generating Station to perform timely notifications to the States of New Jersey and Delaware.
() 2.0.1
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m/ SECTION 2.0 PUBLIC SERVICE ELECTRIC AND GAS COMPANY ARTIFICIAL ISLAND HOPE CREEK GENERATING STATION 1994 ANNUAL EMERGENCY PREPAREDNESS EZERCISE SCOPE AND OBJECTIVES
- 3. Demonstrate the ability to communicate technical information between emergency response facilities and to the NRC utilizing the Emergency Notification System (ENS).
- 4. Demonstrate the capability to formulate around the clock emergency response duty rosters to allow the extended activation of the emergency response facilities.
C. Emeraency Manaaement 1. Demonstrate the capability of the Artificial Island Emergency Response Organization to implement the (s) Artificial Island Emergency Plan and Procedures. ( , 2. Demonstrate the ability to turnover Emergency Coordinator responsibilities between the Senior Nuclear Shift Supervisor, Emergency Duty Officer (EDO), and the Emergency Response Manager (ERM).
- 3. Demonstrate the ability of key emergency personnel to initiate and coordinate timely and effective decisions with respect to a radiological emergency and clearly demonstrate command and control functions as applicable.
4. Demonstrate effective organizational control and integrated radiological emergency response including: 4.1 Deployment of field monitors. 4.2 Receipt and analysis of radiological data.
- 5. Demonstrate that emergency management personnel (ERM and EDO) identify changing (degrading, improving) plant conditions and brief facility personnel concerning the degraded or improved plant status.
2.0.2 l
.['y 5) SECTION 2.0 PUBLIC SERVICE ELECTRIC AND GAS COMPANY ARTIFICIAL ISLAND HOPE CREEK GENERATING STATION 1994 ANNUAL EMERGENCY PREPAREDNESS EXERCISE SCOPE AND OBJECTIVES
- 6. Demonstrate the ability of the Emergency Response Organization to interface with the NRC Site Response Team.
D. Accident Assessment 1. Demonstrate the ability of emergency response personnel to communicate with and control field teams along with receiving and assessing radiological data from the field teams and installed radiation monitors within the plant. 2. Demonstrate the ability of emergency response personnel based to make Protective Action Recommendations (PAR's) on plant conditions and/or dose assessment. g V( w E. Public Information and Media Relations 1. Demonstrate the staffing of the Emergency News Center (ENC) by Artificial Island emergency response personnel and facility activation. 2. Demonstrate the capability to issue coordinated periodic public information bulletins. 3. Demonstrate the ability to provide rumor control and response to inquiries from the general public and media, as applicable, in a coordinated fashion. I t '
- 4. Demonstrate the abilit he N ws M dia i accurate briefings to i F. Onerations and Onerations Supoort !
l 1. Demonstrate the Control Room Staff's ability to recognize ) operational symptoms and plant parameters l indicative of degrading plant conditions and take appropriate corrective actions. I 2.0.3 I
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( SECTION 2.0 PUBLIC SERVICE ELECTRIC AND GAS COMPANY ARTIFICIAL ISLAND HOPE CREEK GENERATING STATION 1994 ANNUAL EMERGENCY PREPAREDNESS EXERCISE SCOPE AND OBJECTIVES 2. Demonstrate proper communications methods and ability to complete timely notifications to offsite agencies. 3. Demonstrate the ability to implement protective actions for site personnel.
- 4. Demonstrate command and control functions within the Operations Support Center (OSC).
5. Demonstrate the ability to properly set up, staff and operate the OSC. 6. Demonstrate the ability of OSC dispatched teams to respond to assigned tasks. rs E,] G. Health Physics and_Excosure Control 1. Demonstrate the decision making process for limiting exposure of emergency workers. 2. Demonstrate methods and resources for if distributing appropriate, dosimetry knd thyroid blocking agents, to emergency workers. 3. Demonstrate adequate health physics support for OSC teams deployed in areas of radiological concern. ! H. Enaineerina and Technical Support 1. Demonstrate the ability to develop alternative methods or equipment alterations in response to accident affected plant systems or components. l 2. Demonstrate the ability to assess plant operational i data and provide recommendations concerning accident mitigation or engineering based PAR's. O 2.0.4 i
I I /~} l \_) SECTION 2.0 l PUBLIC SERVICE ELECTRIC AND GAS COMPANY ARTIFICIAL ISLAND HOPE CREEK GENERATING STATION 1994 ANNUAL EMERGENCY PREPAREDNESS EXERCISE SCOPE AND OBJECTIVES 3. Demonstrate the ability to identify or recognize when fission product boundaries are failed. '
- 4. Demonstrate the ability to estimate fuel damage using the data available.
I. Security 1. Demonstrate effective site security operations and the ability to establish and control security access as defined in Security's Emergency Plan Implementing Procedures. () J. Exercise Control and Evaluation 1. Demonstrate the ability to control the scenario in accordance with the prescribed timeline. 2. Demonstrate the ability of the exercise referees to provide scenario data and address questions which pertain to data without prompting the players.
- 3. Demonstrate the ability to adequately critique the exercise performance.
Prepared By: - m L >~w Adm3,rf. -() Nuclear'Onsite Emerg. Prep. Approved By: O h
~ Emergency pepas'e'dness Manager I
( l 2.0.5 l 1 l 1
SECTION 3.0 , ARTIFICIAL ISLAND ANNUAL EXERCISE GUIDELINES AND PLAYER INFORNATION PAGE # SECTION # SECTION NAME 3.1.0 3.1 EXERCISE GUIDELINES 3.2.0 7 3.2 PLAYER INSTRUCTIONS 3.3.0 3.3 PARTICIPATING LOCATIONS i 3.4.0 3.4 PLAYER PARTICIPANT'S EVALUATIONS 3.5.0 3.5 EXERCISE SIGN-IN SHEETS i f 1 I i O . I i 1 3.0.0
SECTION 3.1 .O ARTIFICIAL ISLAND / AuNcAL ExEaCIsE O EXERCISE GUIDELINES I. Purpose This document provides guidance for conducting the It provides methods Artificial Island Annual Exercise. for demonstrating emerger :y response capability and conducting the exercise. II. Concept of Operations and Control of the Exercise Public Service Electric and Gas Company (PSE&G) will supply official exercise referees and observers for each location where an emergency response may be demonstrated. Prior to the exercise, the referees and observers will receive an extensive exercise briefing and be provided with the appropriate locations, maps, timelines, and observation checklist (s) corresponding to their assignments. Referees will hand out messages and/or If cueunplanned cards and will make judgement decisions as required. situations arise, they w O their assigned Emergency Response Facility advice and resolution of the problem. (ERF) Lead for referees are designated for Simulator, TSC, OSC, EOF, ENC, and Control Point. The head referee, stationed as the lead referee in the TSC, will be in overall command of conducting the exercise. All requests for modification or holding periods must be cleared through the Head Referee. As initiating events are provided, the Plant Staff will determine the nature of the emergency andThisimplement will include appropriate emergency plan procedures. , a determination of the emergency classification inPlayers accordance with the Event Classification Guide. should notify the lead referee at the appropriate ERF prior to formal escalation or de-escalation of theIf the proposed clas emergency classification. change is within 15 minutes of the scenario timeline or 3.1.0 0
will not have any adverse effect on the scenario, Required the notification (,_) referee will allow play to proceed. E\ / for changes in event classification shall be completed in accordance with the Event Classification Guide. The hypothesized emergency will continue to develop based on data and information provided to emergency response As the situation develops, information will be personnel. forwarded to appropriate personnel for the determination of actions to be taken in response to hypothesized emergency. If a conflict exists between the scenario (hypothesized) data and the actual (simulator driven) data, the scenario data shall be utilized. Certain inconsistencies (suchmay as radiation level, be intentional and equipment availability, etc.) required to provide an exercise basis which will test emergency response to the maximum extent The lead feasible in the referees limited will havetime theframe of the authority to exercise. resolve or explain any inconsistencies or problem which may occur during the exercise. III. General Guidance for the Conduct of the Exercise Participants shall avoid taking any actions during the exercise which would actually reduce plant or public f-w safety. The potential for creating a real radiological ( ' 'f emergency or endangering the public shall be specifically avoided. 1.0 Simulating Emergency Actions Since the exercise is intended to provide demonstration of actual abilities as closely as is ] j reasonably possible, the participants All should act as actual they would during a real emergency. actions shall be taken where possible. Simulation will be utilized only when it is not feasible to perform the actual action. (Refer to Section 5.4) l l Actual evacuation of a segment of the general public for exercise purpose is undesirable due to the l' unnecessary public hazard created and great public inconvenience of such action. No actual evacuations of the public are planned. 3.1.1 0
1 2.0 Avoiding Violation of Laws ! h (_,) Intentional violation of laws is not justifiable during any exercise. To implement this guideline, the following actions must be taken prior to conduct i all exercises:
- a. All observers and potential drill participants must be specifically informed of the need to avoid intentional violation of all Federal, State, and local laws, regulations, ordinances, statutes, and other legal restrictions. The orders of all police, sheriffs, and other authorities should be followed as would normally be the case.
- b. Drill participants shall not direct illegal actions be taken by other drill participants or members of the general public.
- c. Drill participants should not intentionally take illegal actions when being called out to participate in an exercise. Specifically, local traffic laws such as speed laws shall be observed.
,-~ 3.0 Avoiding Personal and Property Endangerment s' Participants and observers shall be instructed to avoid endangering property (public or private), other personnel responding to the exercise, members of the general public, animals, and the environment. 4.0 Action to Minimize Public Inconvenience It is not the intent, nor is it desirable or feasible to effectively train or test the public response during the conduct of radiological emergency exercises. Public inconvenience is to be minimized. The action of Federal, State, County and municipal agencies, and nuclear power plant operators receivethe continuous public notice and scrutiny; therefore, conduct of an exercise could arouse public concern that an actual emergency is occurring. In order to minimize public inconvenience and concern, the following actions are being included in the exercise plan: I 3.1.2 1 1 1
- a. A few days prior to the exercise, the public
/~ within the affected area will be informed of the ( ,N) impending conduct of a radiological emergency exercise. Press releases from Public Service Electric & Gas (PSE&G) will be used to accomplish this. Prior to the exercise the public shall be informed of the following as a minimum:
- 1. The purpose of the exercise and that it is a routine function not intended to inconvenience the public unnecessary.
- 2. The exercise requires no public action or involvement.
- 3. The exercise will be conducted at a preselected time during a specifically stated time period.
- 4. The siren system will not be activated,
- b. Emergency Response Personnel should make every effort to prevent the public from being misinformed about the nature of the exercise.
Therefore, it is important to inform members of the public that an exercise is in progress and that their involvement is not required, whenever [s direct public contact occurs in the field. In \2 t addition, it is important to preface, interject, and conclude conversations that"This can be overheard is a drill." by the public with the words, Conversations that can be monitored by the public include those on telephones, radios, loudspeakers, telegraphs, etc. 5.0 Maintaining Emergency Readiness During the performance of an exercise the ability to recognize a real emergency, terminate the exercise, and respond to the new situation must be maintained. Therefore, the exercise scenario and actions of the participants shall not include any actions which affect or degrade the condition of systems, equipment or supplies, or affect the detection, assessment, or response capability to radiological or other emergencies.
-3.1.3
(~T O
I The exercise will be terminated should a situation develop at the station which could adversely affect (/} the licensee's ability to protect public health and ( safety. All messages about real events shall be clearly identified as such. For example, precede a real message with "THIS IS NOT, repeat THIS IS NOT A DRILL". IV. Emergency Response Implementation and Operations 1.0 Initial Notification Initial notification will be made in accordance with the Event Classification Guide (ECG). 2.0 Plant Operations It should be emphasized that the exercise will in no way interrupt normal plant operations, production, and safety. The responses of operations support personnel and plant operators will be simulated when taking action to combat the emergency. To avoid distracting the actual control room staff, the Simulator will be utilized for all drill activities which would involve control room personnel with the and enabling of () exception of PA (page announcement) PASS sampling. 3.0 Environmental Monitoring Teams The Nuclear Generating Station will dispatch field monitoring teams. The referees will provide hypothesized field data which will be used to determine radiation readings at preselected locations. However, these teams will be equipped with the necessary equipment to enable them to i determine actual area gamma dose rates and airborne The monitoring teams l radiciodine concentrations. will not be suited up in anticontamination clothing, j but will have such equipment at their disposal. f 4.0 Public Notification Actual emergency message transmissions via the Emergency Broadcast System (EBS) will not occur. 3.1.4 I v 1
- ' 5.0 Public Information
- t' The Emergency News Center (ENC) will be activated for the Artificial Island Exercise. 6.0 Communications Communications between the exercise participants will occur in accordance with the appropriate Emergency Should any primary Plan Implementing Procedures. communication path become inoperative or prove inadequate, backup means of communice. tion will be utilized as appropriate. V. Closeout of the Exercise The exercise will be terminated by the joint concurrence of the PSE&G Head Referee and Lead NRC Inspector after the major objectives have been demonstrated. SIX3-1.DRL
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H94-06 Rsv. O ARTIFICIAL ISLAND ANNUAL EXERCISE 1994 PLAYER INSTRUCTIONS
- 1. Know the drill organization.
shall aggressively work to mitigate the EJavers - consequences of the simulated emergency. (includes NRC Region I Incident Response Team) Referees - shall control the exercise events to ensure objectives are met, including safe performance. shall assess the response HRQ Evaluators capabilities of/ the Observers - players, the facilities, the plan and procedures as well as the scenario and drill control of the referees.
- 2. Wear your player identification.
are issued by the
- 3. Drill messages, written or verbal, referees as needed to keep the exer initial
- 4. Players may ask referees for information, conditions, symptoms o etc, which would normally be available to them.
You must comply with all reasonable directions of the () (. j 5. referees for your safety and that of others. If you disagree with the referee's direction, consult with 6. the lead referee in your facility for a ruling. 7. Don't be overly concerned with scenario details that appear unrealistic. (Drillsmanship) 22 Dgt " simulate" vour actions unless directed by the 8. referee or if actually performing that action will potentiallyask affect theplant status Referee or personnel to repeat safety.aWhen or reconsider in doubt, direction given to you. Speak up when communicating with other players and 9. occasionally think out loud so the referees and evaluators can follow your actions and thoughts.
- 10. Play as if the simulated radiation levels of the exercise scenario were actually present. Take every opportunity to demonstrate your knowledge of ALARA and radiation protection principles. ,
- 11. Da Dat allow your performance to be distracted by non-drill participants.
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- 12. Complete possible.
all of the documentation as thoroughly as(this includf log books, etc.) [N forms, tagging requests, EPIPs, ; (_,1 3.2.0 , 1
H94-06 Rav. O ARTIFICIAL ISLAND 1 /~N ANNUAL EXERCISE 1994
' PLAYER INSTRUCTIONS (cont'd)
- 13. Keep a list of items that you feel should be addressed to improve your emergency preparedness, drill effectiveness, or any problems encountered that may require corrective actions. Your solutions are welcomed as well, but at the least we need to identify the problems.
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- 14. A critiaue for all participants in each facility will follow immediately after the exercise ends and should last about 60 minutes allowing everyone the opportunity for feedback, both positive and areas of concern.
This is a drill", in all verbal j
- 15. Remember to say, "d write " Drill" on all documents used.
communications an Control Room Staff players will participate from the Simulator. An Artificial Island phone number has been set 16. up (x3339) along with a radio base station in the Simulator to facilitate communications. The PA System is n21 operable in or from the Simulator. l I NETS phone numbers for the Control Room have been l programed to transfer automatically to the Simulator. l Scenario data is generated and provided by different means l
- 17. Some inconsistencies during the course of the exercise.ask the lead referee in I s' are unavoidable. If in doubt, your facility which data to use and which to ignore.
Egr ihm most part, operational parameters will be generated live off the Simulator while radiological data is " canned" or prepared ahead of time in order to facilitate control and distribution throughout the ten mile radius surrounding Artificial Island and onsite. SOME FINAL REMINDERS FOR THE BAKE OF SAFETY When enterina the ECA for drill related activities you are I 18. required to abide by all normal radiation protection rules. I Abso:.utely De one, including Referees or Observers, is permntted to disregard normal station rules of any kind. CAUTION: DO NOT ENTER REAL HIGH RADIATION AREAS OR CROSS ANY REAL STEP-OFF PADS FOR DRILL ACTIVITIES.
- 19. Follow all industrial safety rules including use of hard hats, safety glasses, hearing protection, etc.
- 20. D2 ngt open any electrical panels, breakers, or cabinets or otherwise physically come in contact with plant
(( equipment that may affect your safety or the plant status. 3.2.1 ,
. .- . . . . . ~. - _. -
H94-06 Rev. O ARTIFICIAL ISLAND ANNUAL EXERCISE 1994 PLAYER INSTRUCTIONS (cont'd) i 21. Immediately contact thA duty SNSS if any real plant problems are discovered. The drill may be suspended at any time at the direction of the duty SN88 gr Head Referee-11 a real operational problem develops. Players and referees will be notified to back away until such time as the duty SNSS determines that the drill may continue.
- 22. EKIS Tagging! If any real (not scenario related) oroblems with eauioment gr plant systems you are working with-or take a moment to properly document around are detected,in accordance with plant procedures those discrepancies and ensure that the duty operations Staff is notified.
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6 l 3.2.2
CONTROL ROOM STAFF - HOPE CREEK SIMULATOR SPECIAL INSTRUCTIONS (V~}
- 1. NETS phones are programed to bvoass @ Hope Creek"This is a drill", when Control Room. Be sure to say, radio, or PA system.
communicating over the phones, Otherwise, regard yourself to be in your Control Room. 2. Radio in thg Simulator is live and may used as you would your Control Room Radio.
- 3. QID Extension live Artificial 3339 Island on the phone Communications Console is a extension.
4. Plant EA announcements that you must make for drill purposes will kg relaved by a designated individual (drill controller) in the Control Room onsite. 5. You are eqected to respond to all Simulated events as you would in a real emergency within the Simulator, a) Follow your EOPs and other approved procedures. b) Communicate as you do during your Simulator training, but try to OVERCOMMUNICATE to the extent that the Simulator Referees are always aware of the actions you intend to take in time for them to intervene as needed to support the scenario. /'T Communicators, CM1 and CM2, are eqected to obtain data (j 6. from the Simulator boards unless directed otherwise. (some data must be mocked up; radiological readings, Met data, H2/02 concentrations, etc.) When directina thg QEQ or other players outside the 7. Control Room to take actions for dr.ll purposes, be sure to pref ace your directions by saying, " Simulate", as in
" Simulate racking out the Breaker."
Also remind the player to Itensure they may be have a referee necessary for the with them in the field. player to stop by the OSC area and ask for a referee if the OSC has not yet been activated.
- 8. The Shift Rad Pro Tech will not participate in theSimulator with the scenario from the RM-11 terminal.Disrecard any radio and back panels with the exception of alarms.
The RMS Trouble Overhead Annunciator will be used as for changes in the RMS data off the RM-11. 9. MET data is provided in book form emulating the computer screen located in the Control Room. /~N 3.2.3
CONTROL ROOM STAFF - HOPE CREEK SIMULATOR , SPECIAL INSTRUCTIONS (cont'd) l / '\ \_) 8IMULATOR LIMITATIONS / DRILL SCENARIO CONSTRAINTS that will Plant components (pumps, valves, pipes, etc.) 1. fail for scenario purposes will be programed or controlled to fail by the Simulator referee at the appropriate times. As long as the Simulator is live, you need to respond in accordance with your training and procedures to the alarms and indications that you see. Occasionally, the referee may interject an event or - modify the displayed spptoms using a message form if I simulation is not possible. I I
- 2. 11 thg Simulator grgshes or your actions are causing i plant parameters to deviate significantly from thedata for any reason, expected Cplanned) Play referee wall be directed to FREEEE the program.will then continu 4
us back on the scenario timeline. i a) Back track may be used to reset conditions. b) Time out may be called with the simulator reinitialized at a later time period in the scenario with an appropriate " interim briefing" (']/ provided by the referees as to what was postulated s, to have occurred up to that point. c) Dark boards The simulator may be turned off and left off with play continuing using paper message forms and prepared operational data forms. FREEEE periods for the simulator & Dgt stop the rest NOTE: of the drill from proceeding. It is an internal control for our use in keeping the operational data consistent with the prepared radiological data. You shall continue to play and verbally describe to the referees what actions you would be taking. d) When in FREEEE, continue to follow your EOPS, communicate with other facilities as if nothing has happened unless a large step change in theKeep the operational data needs to be explained. drill going unless the simulator referee specifically allows you to relax or take a break. 3. Some individual carameters may hg mocked un
~
in ifa they are manner required to respond (for scenario control)that is incansistent wl For example;
- radiological data N
- meteorological data
- Drywell Rydrogen/Orygen Concentrations 3.2.4 1
1 I CONTROL ROOM STAFF - HOPE CREEK SIXULATOR r~N SPECIAL INSTRUCTIONS (cont'd i I
- some indications of Containment failure, release into the Reactor Bldg
- some tvoes of component failures (specific OSC i objectives may dictate)
- RCS break locations and/or sizes
- peak values of critical parameters that assume worst case conditions and therefore exceed design bases (scenario license invoked)
- 4. If you suspect a real oroblem with a Simulator indication you may call an I&C Technician to come to the control Room from the OSC.
For scenario control, tell thg Referee of your intended request and atoSimulator staffthe troubleshoot personnel problem.Elll role play tha lig Tech.
- 5. Other limitations:
- Bldg Watches; cannot directly contact EOs except by phone or radio since PA is not connected to the Island.
- OSCC interface must be strictly by phone
- EC turnover by phone only
- SRPT interface with Control Room Staff, phone only; r's NOTE: A referee will ROLE PLAY the SRPT at times
(' ,) during the exercise to provide the SNSS (EC) with SSCL Radiological Information for review and approval. OPPORTUNITIES
- 1. IMPROVED PLANT SAFETY: Ability to conduct Emergency Plan drills from outside of the real control room.
- 2. Better realism for Control Room Staff during periods of live simulator action.
- 3. Improved realism for the TSC and EOF staffs also through the SPDS link from the Simulator since they can see the operational data changing instantaneously.
(D V 3.2.5
H94-06 Rsv. O HOPE CREEK SHIFT PERSONNEL DRILL PLAYERS r'~h
.)
pFECIAL INSTRUCTIONS In addition to the normal player instructions, please keep the following in mind. 1. Control Room Staff players will be participating from the Hope Creek Simulator at the Training Center. If you need to speak with the SNSB or any of his Control Room Staff you can use the NETS phones to call the CR and the calls will be forwarded automatically to the Simulator g you may use the DID phones to call 3339. (no prefix is needed)
- 2. If you need to go to the Control Room for any reason, a referee stationed there will assist you as needed by either role playing the SNSS or directing you to call the simulator. For example:
EDO should call the Simulator to speak with the SNSS for EC turnover briefing. OSC Coordinator should call the SNSS at Simulator to ensure team priorities are correct. s 3. Scenario problems will be addressed by the Head Referem
) located in the TSC.
Real amargency. situations, should they arise, should DQt be reported via NETS to the Control Room. Use the plant 4. PA system Be sure or DID phones."This is Dg1 a drill !" to emphasize,
- 5. SPDS in the TSC and EOF should be live (real time) off the Hope Creek Simulator model during all or most of the drill.
- 6. The Simulator operational data may differ from that expected or predicted when the radiological data was generated. _D2 D21 let any potential discor.nects in the data throw you or let it drag down your performance.
- 7. Simulation may be temporarily frozen at the Simulatorbut from time to time in an effort to control the data, keep in mind that the drill continues even during the those periods unless the Head Referee specifically stops the drill for some other reason.
- 8. When the drill begins (very shortly), you are on shift, at work in your normal work locations and ready to respond. That is, you should have your normal tools and gear with you, as appropriate, to your normal assignent.
The emergency plan depends on our being ready to ('N dispatch emergency teams quickly. \~) 3.2.6
H94-06 Rav. O BOPE CREEK 8EIFT PERSONNEL DRILL PLRYERS (cont'd)- O Exception: NEO's should begin the drill in the OSC area-unless directed otherwise by a referee for prestaging. This is to facilitate communications with the SNSS in - the simulator. If-during the course of the
- 9. EMIS Taaaina Reminder:. i drill, any problems with equipment or plant systems you are working with or around are detected, take a moment '
to properly document those discrepancies'in accordance. , with plant procedures and ensure that the duty l Operations Staff is notified. t 6 i O . l f f f 3.2.7 l 1
SECTION 3.3 l ARTIFICTAL ISLAND '\ ANNUAL EZERCISE PARTICIPATING LOCATIONS PAGE # LOCATIONS' 3.3.1 A. SITE MAP OF GENERATING STATION 3.3.2 B. TRAINING SIMULATOR (NTC) 3.3.3 C. OPERATIONS SUPPORT CENTER (OSC) 3.3.4 D. TECHNICAL SUPPORT CENTER (TSC) 3.3.5 E. MAP LOCATIONS OF NUCLEAR TRAINING CENTER & EMERGENCY NEWS CENTER 3.3.6 F. EMERGENCY OPERATIONS FACILITY (EOF) 3.3.7 G. EMERGENCY NEWS CENTER (ENC) (GREATER SALEM COMMUNITY CENTER) d O I 3.3.0 1 l i
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@ DID x3155 z
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PAGE COMMUNICATIONS MANUALS AND SUPPLY CLOSET HONE UHF TE RADIO JACK p < O 3.3.3 FAc7 l l
' l HOPE CREEK ,
n GENERATING STATION O SUPPORT CENTER TECHNICAL cAmNETS c0MMUNicATIONS A. CODE-A-PHONE
- 1. ADMIN - ECG & AIEPIP WORK FILES NET 3 x5207 DID x3593 XEROX & CAX SUPPUES P.A. SYSTEu
- 2. COMMUNICATORS -
NETS a5212 DID m3295 B. STORAGE NETS x5213 DlD x3595 C. STATUS BOARD STORAGE E. MISCELLANEOUS ESSX x7963 NAWAS NRC/ ENS (FTS) F. ENGINEERING SUPPLfES NRC/ ENS (FTS) MISCELLANEOUS ADMIN SUPPUES 3, TELECOPtER - G. ADMIN SUPPUES TRANSMITTING NETS x5208 ADMIN KITS w RECFMNG - NETS x5216 H. MANUALS 'C 4 TSS - 8. RAD PRO LOCKER = NETS x5201 DID x3597 J. ENGINEERING DRAWINGS = NETS a5206 ESSX x6101 = 5 Ot0 x3543 NEC E O =
- 6. EDO - ENS 700-361-7139 DID x3397 i NETS x5200 NRC/MCL (FTS) HPN 700-361-7135 I NETS x5217
- 7. RAC -
NETS x5202 NETS x5204 PMCL 700-361-7137 RSCL 700-361-7136 1 '
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7 - DID m3261 Ei.iX 6492 70 -361- 1 8 ; NRC/HPN (FTS) NETS x5218 7 l Q1
- 8. RAD ASSESS. - C NETS a5203 OtD m3468 r--
XERg-NRC/PMCL (FTS) D u CHEMtSTRY - 3 NETS x5205 DID m3297
- 9. SECURITY -
2 b ( ( NETS x5214 DrD x3253 U ' C
- 10. NETS x5215 -
- 11. OPS /ENG - 4' NETS x5211 DID x3002 ESSX x7962 OPS /ENG -
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- 12. TSS NETS x5210 STATUS 4
- 13. OPS /ENG - BOMDS NETS x5209 DtD x3035 a g g NETS x5219 R -
EDO W NRC/RSCL (FTS)
- 14. oSC RActO uoNiTon
- 15. NRC/HPN (FTS) 6
- 16. NRC/LAN (FTS) 0 0 C
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ROOM
- A* COMMUNtCATIONS (CONT I ROOM "C" COMMUNfCAWit{$
ROOM " A" COMMUNICATIONS LOCKER A CABINET 0 13. NETS x5021 ESSX x8519 LOCKER R DID x3763 SALEM & HOPE CREEK ECG WORK DID x3995
- 1. NETS x5005 FILES NETS x5006 NRC/PMCL (FTS)
DID x3992 CABINET P
- 2. NETS x5001 SALEM & HOPE CREEK AIEPIP WORK LOCKER F NETS x5002 DID m3993 14. NETS x5022 DID x3788 ESSX x7455 FILES DID x3789 NETS x5003 NETS x5023 NETS x5004 ESSX x7466 ESSX x7650 X m7468 poou g- coyuuNicAT10Ns p 15. NETS x5007 DID x3765 LOCKER 0 COLUMN NETS x5020 DID x3991
- 3. NETS x5000 DID m3989 10. NETS x5008 ESSX x7511 - ESSX x7580 DID m3761 ESSX x7877 NETS x5009 16. NETS x5017 NRC/MCL (FTS) LOCKER L NETS x5018
- 4. NETS x5011 NETS x5010 11. NETS x5015 DID m3766 NETS x5019 ESSX x7517 DID x3889 x5016 ESSX x8520 NRC/RSCL (FTS)
D x3907. 3916, 3932 /EN NRC/HPN - (FTS) CONrrprNCF ROOVs
- 6. NETS x5012 DID x3762 NRC/LAN - (FTS)
NETS x5037 ESSX x7518 010 m3994 17. NETS x5038 ESSX x7508 12. NETS x5024 18. NETS x5036
- 7. NETS x5013 NETS x5025 ESSX x7728 NETS x5014 ESSX x7519 DID m3960 NETS x5032 h[\ NAWAS NRC/ ENS (FTS)
NETS x5042 NRC/ITS KED
- 8. TRANSMITTING TELECOPIER NETS x5034 PMCL 700-361-3876 MCL 700-361-3872 ENS 700-361-3874 LAN 700-361-3875 FAC2
- 9. RECIEVtNO TELECOPIER HPN 700-361-3871 RSCL 700-361-3873 i NETS x503$
f 3.3.6 i
PSE&G - EMERGENCY NEWS CENTER [] U MEDIA INFO. LINE ROOM MAIN ENTRANCE ENC STAFF PE T NS
,[ wp pg p KITCHEN MEDIA MONITOR ROOM DINING ROOM STAFF MEN WOMEN NRC/ FEMA ROOM RESTROOMS ENC MEDIA INFO LINE RM: ENTRANCE NETS - N/A (609)273-0062, 0188, 0282, 0386, 0479, 0586 NEW JERSEY STAFF WRITERS RM: ROOM NETS - 5315, 5316, 5317, DIRECTOR 5319, 5326 (609)273-0607, 0695, 0792 ENC 0881, 8129=(FAX) CONFERENCE MEDIA MONITOR RM: ROOM NETS - 5302 j NRC/ FEMA RM ; NElS - 6310, 5311, 5312, i 5308 f (609)273-0992, 1049, 1179 DE. RM NEW JERSEY RM:
NETS - 5320, 5321, 5322, (609)273-1263, 1395, 8092 8185. 7968 __, , DELAWARE RM: I NETS - 5323, 5324 (609)273-1474, 1593, 8004 PSE&G ENC PSE&G OPERATIONS RM: MEDIA ROOM NETS - 5300/ ENC MGR 5301/ OPS SPVR 5303/LD TECH 273-2263, 2488, 2539, 2690, 2691, 2774 5313/COM TECH 273-2787. 2873, 3156, 3257, 3379, 3380 5314/SPKR PHONE 273-3689, 3793, 4388, 5895, 5928, 5997 5318/ FAX 273-6340, 6387, 6475, 6593, 6874, 6694 (609)273-1961, 2261, 1948 273-7596, 7624, 7689, 7719, 7789, 7882 7 273-7935, 6673 ENC CONFERENCE RM: NETS - 5327 -- NETS - N/A (609)273-1690, 1702, 1883 TC RM 3.3.7
SECTION 3.4 PLAYER PARTICIPANT'S EVALUATION REPORT Drill Type: Artificial Island innual Exercise Drill Number: H94-06 . Date: October 25. 1994 . Your Emergency Position
Title:
OSC TSC CP EOF ENC Facility: (circle one) SIM Summary 21 Comments /Deficiences/Succestions Positive Observations: Facility /Bquipment problems: Procedura problems: O Scenario problems: Other comments / concerns / suggestions,etc:
?
Submitted by: (continue on back (optional) if needed) O 3.4.0
SECTION 3.4 PLAYER PARTICIPANT'S EVALUATION REPORT Drill Type: Artificial Island Annual Exercise October 25, 1994 Drill Number: H94-06 . , Date: . Your Emergency Position
Title:
SIM OSC TSC CP EOF ENC Facility: (circle one) Summary 21 Comments /Deficiences/Succestions Positive Observations: Facility / Equipment problems: Procedure problems: O Scenario problems: other comments / concerns / suggestions,ete: Submitted by: (continue on back (optional) if needed) O 3.4.0 l l l
SECTION 3.4 / PLAYER PARTICIPANT'S EVALUATION REPORT Drill Type: Artificisi Island Annual Exercise Drill Number: H94-06 . Date: October 25. 1994 .
)
Your Emergency Position
Title:
I OSC TSC CP EOF ENC Facility: (circle one) SIM Summary 21 Comments /Deficiences/Succestions Positive Observations: l I l Facility / Equipment problems: i f I Procedura problems: Scenario problems: , l l i I Other comments / concerns / suggestions,etc: Submitted by: (continue on back (optional) if needed) O 3.4.0
l 1 SECTION 3.4 PLAYER PARTICIPANT'S EVALUATION REPORT Drill Type: Artificial Island innual Exercise October 25, 1994 . Drill Number: H94-06 . Date: Your Emergency Position
Title:
SIM OSC TSC CP EOF ENC Facility: (circle one) Summary 21 Comments /Deficiences/Succestions Positive Observations: P Facility / Equipment problems: Procedure problems: i Scenario problems: i Other comments / concerns / suggestions,ete: P h Submitted by: (continue on back (optional) if needed)
/'T 3.4.0
(_)
SECTION 3.4 PLAYER PARTICIPANT'S EVALUATION REPORT Drill Type: Artificial Island Annual Exercise October 25, 1994 . Drill Number: H94-06 . Date: Your Emergency Position
Title:
SIM OSC TSC CP EOF ENC Facility: (circle one) Summary 21 Comments /Deficiences/Succestions Positive Observations: Facility / Equipment problems: L Procedure problems: i O i Scenario problems: t other. comments / concerns / suggestions,etc: l Submitted by: (continue on back (optional) if needed) O 3.4.0 l l l i
I SECTION 3.4 l PLAYER PARTICIPANT'S EVALUATION REPORT Drill Type: Ar_tificial Island Annual Exercise Drill Number: H94-06 . Date: October 25. 1994 . Your Emergency Position
Title:
SIM OSC TSC CP EOF ENC Facility: (circle one) Summary af Comments /Deficiences/Succestions Positive Observations: Pacility/ Equipment problems: Procedure problems: O V Scenario problems: Other comments / concerns / suggestions,ete: 1 Submitted by: (continue on back (optional) if needed) O 3.4.0
EXERCISE SIGN-IN SHEET Drill Type: Artificial Island Annual Exercise I Facility: SIM OSC TSC CP EOF ENC
-Drill Number: H94-06 hrs. Date: October 25, 1994 Time: to
)
Social Security 1. Print Name Emergency Plan l Number 2. Signature Position / Title 1
- 1. ,
I 2. 1. 2. 1. 2. 1.
- 2. ,
1 0 2. 1. 2. 1. 2. 1. 2. 1. 2. 1.
- 2. l 1.
2. 3.5.0
EXERCISE SIGN-IN SHEET
,~r
-* Drill Type: Artificial Island Annual Exercise OSC TSC CP EOF ENC H94-06 Facility: SIM Drill Number: hrs. Date: October 25. 1994 Time: to Emergency Plan Social Security 1. Print Name Position / Title Number 2. Signature 1. 2. 1. 2. 1. e 2. 1. 2. 4
- 2. t 1.
2.
- 1. I 2.
1. l 2. 1.
- 2. _
1. 2.
- 1. l 2.
3.5.0 l i
l SECTION 4.0 ARTIFICIAL ISLAND ANNUAL EXERCISE REFEREE /OB8ERVER INFORNATION PAGE # SECTION # SECTION MAME 4.1.0 4.1 Referee / Observer,& Player Lists 4.2.0 4.2 Referee / Observer Instructions 1 4.3.0 4.3 Referee Evaluation Sheets & Report 4.4.0 4.4 Phone Lists (NETS, DID, ESSX) :
?
n O . 4.0.0 (
l ARTIFICIAL ISLAND ANNUAL EXERCISE (H94-06) OCTOBER 25, 1994 f REFEREE / OBSERVER ASSIGNMENT LIST REV. 2 NAME LOCATION / DUTIES BOOK HO t l MITCH DIOR SIML - LEAD REF - SNSS & CR OVERALL ,
- 1. SIML - OPERATIONS /OSC INTERFACE '
- 2. DAVE FAWCETT SIML - OPERATIONS / SIMULATOR CONTROL
- 3. DENNIS KABACHINSKI SIML - OPERATIONS /EOPS
- 4. MARTY LICHTNER SIML - COMMUNICATIONS /RMS DATA S. BILL WECKSTEIN CR - SIMULATOR / PLANT INTERFACE N/A TBA - D. POWELL OSC - LEAD REF - OSCC & OSC OVERALL
- 6. MARK AZZARO OSC - RAD PRO - RPS EXP CONTROL i
- 7. LARRY ZITKEVITZ OSC - TEAM ACTIVITIES HARLAN HANSON, JR.
8. OSC - TEAM ACTIVITIES i
- 9. BILL SUTTON OSC - TEAM ACTIVITIES
- 10. -TERRY O'BRIEN OSC - TEAM ACTIVITIES
- 11. WAYNE BOOZ - TEAM ACTIVITIES JOHN DILKS OSC
- 12. OSC - TEAM ACTIVITIES
- 13. BOB STAMATO - TEAM ACTIVITIES DEVON PRICE OSC I
- 14. OSC - TEAM ACTIVITIES
- 15. BRIAN SEBASTIAN - FIRE BRIGADE ACTIVITIES JOHN CARLIN OSC E 16.
50HN HARRIS CP - LEAD REF - RPS INP & CP OVERALL i 17.
'OAVE MASON CP - RAD PRO ACTIVITIES
- 18. CP - CHEM / PASS ACTIVITIES
- 19. MIKE ADZIMA !
- HEAD REF - EDO/TSS & TSC OVERALL ,
O20. CRAIG BANNER RAY REECE TSC TSC - RAD PRO ACTIVITIES
?
- 21. TSC - RAD PRO ACTIVITIES ,
- 22. JOHN MOLFFR - ONSITE FIELD TEAM ACTIVITIES MIKE KULIG TSC
- 23. - ENGINEERING ACTIVITIES BILL BERG TSC
- 24. TSC - CORE DAMAGE ASSESSMENT
- 25. FRANK SAFIN - COMMUNICATIONS / ADMIN SUPPORT 4
GEORGE THOMSON TSC '
- 26. TSC - SECURITY ACTIVITIES
- 27. JOE LOEB l BARRY WEIGER MGH - SECURITY CENTER ACTIVITIES
- 28. ;
EOF - LEAD REF - EOF OVERALL
- 29. JIM SCHAFFER BOB YEWDALL EOF - DOSE ASSESSMENT ;
- 30. EOF - RAD PRO ACTIVITIES OVERALL
- 31. JOHN TREJO - ENGINEERING / TECH SUPPORT GARY NAYLER EOF I
- 32. EOF - COMMUNICATIONS /NRC INTERFACE
- 33. BOB MALONE PHIL DUCA EOF- - SITE SUPPORT ACTIVITIES i
- 34. EOF - ADMIN SUPPORT '
- 35. KAREN ROOTS EOF - OFFSITE FIELD TEAM
- 36. LUCIUS CLARK JEANNE HEDGE EOF - OFFSITE FIELD TEAM 37.
MICHAELE CAMP ENC - LEAD REF - ENC OVERALL
- 38. ENC - OPERATIONS / COMMUNICATIONS
- 39. TOM BROWN - OPERATIONS / GOVT RELATIONS ENC
- 40. BILL STEWART ENC - MEDIA MONITORS l
- 41. DAWN DRUMMOND-WOLFROM JOHN MOONEY ENC .- MEDIA INTERFACE 42.
DEL - DELAWARE LEAD REFEREE OVEFALL STEVE STASOLLA ( 43.
- 44. MARY ANN QUINN NJ - BNE REFEREE 4.1.0
HOPE CREEK GRADED EXERCISE (H94-06) 7g DRILL PLAYER ASSIGNMENT LISTING (v) NAME LOCATION / POSITION NO. SIM - SNSS
- 1. K. Krueger SIM - NSTA-
- 2. R. Cummins SIM - NSS
- 3. S. Dennis SIM - NCO
- 4. G. Schmelz SIM - NCO '
- 5. M. Roman SIM - Communicator (CM1)
T. Catalano 6. J. Price SIM - Communicator (CM2) 7. OSC - Coordinator
- 8. S. Miller OSC - Maintenance Sup. (Mech.)
- 9. J. Lewis OSC - Shift Control Tech Elec
- 10. A. Vegliante OSC - Cont Tech Elec
- 11. G. Parris, Jr. OSC - I & C Supervisor
- 12. B. Booz OSC - Nuc Tech Machinist
- 13. G. Scimeca OSC - Shift I & C Tech
- 14. G. Pison OSC - Cont Tech I & C
- 15. T. Quirk OSC - Operations Supervisor
- 16. E. Bubier OSC - Equipment Operator
- 17. C. Hernandez OSC - Equipment Operator
- 18. E. Schilling OSC - Equipment Operator
- 19. T. Kretzer OSC - Radwaste Operator
- 20. TBA - O'Malley OSC - Rad Pro Supv Exp Cont
- 21. T. Wallender OSC - Fire Brigade Supv N 22. H. Thompson OSC - Fire Brigade
- 23. T. Denny OSC - Fire Brigade
- 24. P. Uhland OSC - Fire Brigade
- 25. F. Schemeley OSC - Fire Brigade
- 26. B. Schmid OSC - Fire Brigade
- 27. G. Fitton OSC - Fire Brigade
- 28. J. Hagen OSC - Fire Brigade
- 29. A. Knight OSC - Duty Storekeeper
- 30. D. Buck F. Mauro OSC - Planner
- 31. OSC - Administrative Clerk
- 32. M. MacWatters OSC - Nuc. Tech Welder
- 33. D. Brown OSC - Relay Supervisor
- 34. T. Fries OSC - Relay Technician
- 35. B. Solomen CP - Rad Pro Supv In Plant
- 36. G. Parkhurst CP - Chem Supv
- 37. T. Lake CP - Chem Tech / PASS
- 38. S. Poinsett CP - Chem Tech / PASS
- 39. M. Fagan CP - Shift Rad Pro Tech
- 40. B. Humphries CP - Rad Pro Tech
- 41. W. Wagner CP - Rad Pro Tech
- 42. R. McCarthy CP - Rad Pro Tech
- 43. T. Rollins CP - Rad Pro Tech
- 44. C. Roller
( 4.1.1 (
HOPE CREEK GRADED EXERCISE (H94-06) DRILL PLAYER ASSIGNMENT LISTING NO. NAME LOCATION / POSITION
- 45. T. McCleave CP - Rad Pro Tech e
- 46. J. Seymour CP - Rad Pro Tech
- 47. J. Fitzpatrick TSC - Salem Rad Pro Tech TSC - Salem Rad Pro Tech -)
- 48. G. Ondricek, Jr. i
- 49. M. Trum TSC - EDO
- 50. B. Gary TSC - RAC ;
- 51. L. Wagner TSC - TSS TSC - Admin Support Supy
- 52. M. Vest
- 53. A. House TSC - EPA TSC - Security Liaison
- 54. TBA - Renwick TSC - Chemistry Supervisor
- 55. G. Slaby TSC - Rad Pro Supv. - Offsite .
- 56. C. "inne
- 57. J. Iannucci TSC - Rad Pro Tech
- 58. L. Riley TSC - Rad Pro Tech
- 59. R. Harrington TSC - Rad Pro Tech
- 60. P. Opsal TSC - Tech Supp Team Leader TSC - Electrical Engineer
- 61. V. Rao
- 62. R. Masten TSC - Mechanical Engineer
- 63. J. Hawrylak TSC - Controls Engineer
- 64. R. Schmidt TSC - Core Thermal Engineer
- 65. C. Brennan TSC - Nuclear Fuels Engineer
- 66. D. Fisher TSC - Communicator
- 67. R. Lickliter TSC - Communicator L. Dyer TSC - Admin Support 68.
K. Master TSC - Admin Support
- 69. ;
TSC - Admin Support O 70. 71. L. S. Locke Delp Maier TSC - Admin Support (TDR) TSC - Admin Support (RP) i
- 72. L.
- 73. TBA - Renwick TSC - Security Force Member 1
- 74. L. Miller EOF - ERM
- 75. M. Simpson EOF - RSM '
- 76. J. Bailey EOF - TSM
- 77. B. McKeever EOF - ASM
- 78. C. Bauer EOF - SSM
- 79. B. Billings EOF - Rad Assess Staff
- 80. D. Branham EOF - Rad Assess Staff
- 81. J. Russell EOF - Rad Assess Staff
- 82. D. Parks EOF - Rad Assess Staff i i
- 83. D. Granberg EOF - Rad Assess Staff '
- 84. F. Quick EOF - Rad Assess Staff
- 85. D. Tisdel EOF - Field Team Comm i
- 86. J. Beattie EOF - Off Site Team
- 87. T. Migdal EOF - Off Site Team
- 88. A. Wesolek EOF - Off Site Team
- 89. J. Livermore EOF - Off Site Team EOF - Licensing Support
- 90. C. Manges, Jr.
- 91. W. DeNardi EOF - System Engineer i
- 92. M. Idell EOF - System Engineer
- 93. W. Maher EOF - System Engineer
- 94. A. Johnson EOF - System Engineer
- 95. B. Bovankovich EOF - System Engineer ]
4.1.2 ! j
HOPE CREEK GRADED EXERCIDE (H94-06) DRILL PLAYER ASSIGNMENT LISTING NO. NAME LOCATION / POSITION
- 96. C. Atkinson EOF - Controls Engineer EOF - Electrical Engineer
- 97. J. Bussman
- 98. P. Fallin EOF - Admin Support ,
- 99. D. Wyckoff EOF - Admin Support EOF - Admin Support 100. A. Lloyd EOF - Admin Support 101. C. Tolley EOF - Admin Support 102. L. Veasey EOF - Admin Support - RP 103. A. Gross EOF.- Personnel Supervisor 104. D. Hitchner EOF - Purchasing Support 105. M. Klessel 106. R. Gehret, Jr. EOF - Material Control EOF - SSM. Ops Staff 107. W. Chausse 108. E. Dean EOF - SSM. Staff (CM1) 109. R. Rudy EOF - SSM Staff (CM2) 110. M. Ivanick EOF - Security Liaison 111. D. Burgin EOF - EPA 112. T. DiGuiseppi EOF - EPC 113. TBA - Renwick EOF - Security Force Member #1 114. TBA - Renwick EOF - Security Force Member #2 115. R. Bell EOF - Public Info Liaison 116. T. Chipko EOF - Telecommunications Supp 117. M. Sesok EOF - A.E. Co-owner Rep.
118. B. Burricelli ENC - Company Spokesperson 119. B. Gorman ENC - ENC Manager ENC - PIM/Comm Supervisor 120. C. Florentz ENC - Lead Tech Adv. 121. L. Aversa 122. R. Bashall ENC - Tech Advisor 123. R. Bravo ENC - Tech Advisor 124. F. Centore ENC - Staff Writer 125. P. Lanning ENC - Staff Writer 126. F. Davis ENC - Media Monitor 127. E. Kidd ENC'- Media Monitor 128. P. Travers ENC - Industry Coord , 129. E. McManus ENC - Rumor Control Coord ! 130. R. Sutton ENC-- Media Info Supervisor l 131. M. Haberland ENC - Media Info'Line Operator , 132. V. Moniz ENC - Media Info Line Operator ! 133. C. Vitale ENC - Media Info Line Operator 134. D. Straubmuller ENC - Ops Supervisor 135. D. Cheeseman ENC - Admin Supp , 136. D. Fedosick ENC Admin Supp l 137. A. Shimp ENC -- Admin Supp 138. K. Leach ENC - Admin Supp 139. M. Rodriques ENC - Admin Supp 140. F. Smith ENC -' Admin Supp 141. J. Garofalo ENC - Gov. Affairs Coordinator 342. P. Jefferson ENC - Audio Visual Serv Coord 143. TBA - Renwick ENC - Security Force Member #1 144. TBA - Renwick ENC - Security Force Member #2 145. TBA - Renwick ENC - Security Force Member #3 0 146. J. Dotterer 147. TBA - Weckstein ENC - Computer Analyst E}1-RMCSpokesperson 4.1.3 1 1
SECTION 4.2 /^N i ) ARTIFICIAL ISLAND ANNUAL EXERCISE REFEREE AND OBSERVER INSTRUCTIONS 1. Referees are assigned by PSE&G to all key functionalthey In addition, areasare to control and evaluate the exercise. into the field (onsite and prepared offsite) to accompany team;to provide data and event messages that support the overall exercise scenario. Observers may also be assigned to provide additional feedback regarding the effectiveness of the exercise and the plan.
- 2. Onsite with theReferees and Observers Head Referee will coordinate in the Technical their activities Support Center. If unable to contact the Head Referee, then contact the OSC Lead Referee.
Offsite Referees and Observers will contact the EOF Lead Referee.
- 3. Message forms and simulated operational / radiological data are used to initiate, modify, and complete the events that comprise the overall scenario.
() Three kinds of messages are used: Contro111na messaces used as the primary means of implementing scenario events by presenting postulated alarms or indications to the appropriate player (s) to supplement or augment Simulator or field indications. Continaency messaces used at the discretion of the Head Referee in order to maintain the scenario timeline or prompt specific response activities that were planned to be evaluated (exercise objectives related). Dark Board messaaes used at the discretion of the
- Simulator Lead Referee if the simulator is not in service.
These messages provide alarms and indications that the CR Staff would normally observe if the simulator was in use. Messages are expected to be provided to the designated drill player at the time specified on the form. Although generally self suff$cient, the referee may follow-up with an explanation of the message to ensure that it is understood. l l Referees will not initially provide information to the ! players regarding scenario development or the resolution of problem areas encountered. The players are eqected to obtain information through their own organization and exercise their own judgment in determining response actions and resolving problems. In the event of incorrect or incomplete responses, or if the 4.2.0 i
1 l REFEREE AND OBSERVER INSTRUCTIONS (cont'd) e of how to proceed, the ( ') playerindicateslackofknowledkththenecessaryinstructions referee will prompt the player w or contingency messages and will note the deficiency for later I critique. l
- 4. The scenario events are hypothetical. Any portions of the scenario depicting plant system operational transients are simulated events. No Control Room actions, or reactions involving operation of plant systems, or affecting generation capability will be initiated. All exercise scenario messages will begin and end with the words, "THIS IS A DRILL".
Referees stationed at areas vital to maintaining generating capability should be especially aware, and take extra precautions, in issuing messages or giving instructions regarding the scenario events.
- 5. Where practical, operational and radiological data will be displayed on the Simulator in real time or in hard copy format at locations where the data would normally be available to the player during a real emergency. Referees will control the use of this information to ensure that the correct data is displayed at the correct time and to provide interpolated data between prepared time intervals.
73 6. Players may occasionally insist that certain parts of the scenario are unrealistic. The lead referees have the \ l' v authority to clarify any questions regarding scenario However, in some cases, it may be necessary to content. exercise " scenario license" to preserve the continuity of the drill and meet the objectives of the exercise. Players are expected to demonstrate good drillsmanship by accepting the referee's decision and continue to play while ! noting their concerns for resolution at the critique.
- 7. Prior to drill commencement, lead referees shall establish I communications with their counterparts in each facility. l All referee watches and clocks shall be synchronized with the l Simulator to ensure the proper control of messages and l data per the timeline of the scenario.
l
- 8. OSC Referees and those observers or evaluators who intend to follow team activities must be prepared ahead of time to do i so. ( i.e. Vital Area access, RWP sign-in, hard hats and !
glasses if needed, etc.)
- 9. Scenario problems not covered in this exercise manual must l be referred to the Head Referee for resolution if they are in any way affecting the safe or effective conduct of this exercise.
a meal may be provided by
- 10. For drills exceeding however, there four hours,ific is no spec meal time break in the r3 PSE&G,io.
scenar All participants, including referees, should be ( ')
' allotted time for their meal as time permits, but not to 4.2.1
REFEREE AND OBSERVER INSTRUCTIONS (cont'd) / interfere with the exercise. 11. NRC Region I Incident Response Team members are regarded as players during the course of this exercise and will be evaluated by the NRC exercise evaluators. l l DO's 1. Know the overall Referee / Observer organization. Know especially the Lead Referee in your facility or area.
- 2. Remember Scenario time, that there are two clocks: starting at 00:00 and real clock time. l 3.
Identify the players you are controlling or observing. l Identify yourself to the players as their referee / observer. 4. Ensure all participants wear ID provided (i.e. shirts, hats)
- 5. Determine the phone (or radio for field teams) that you will use to maintain communications with your lead referee.
6. position yourself to maximize your effectiveness in iesuing messages and controlling the responses of the recipients. Refer
- 7. Keep the play on schedule by issuing messages on time.
r' to the overall scenario timeline. , (-)T 8. Make sure the players understand what the message is trying to convey, but d2 D21 prompt what is expected of the player to perform. l 9. Allow the players reasonable flexibility to do their and functions and demonstrate their skill, knowledge, ) l initiative. !
- 10. Remember to call the Head Referee If report if playersac!
to necessary, l may affect the overall scenario timeline. intervene with the pl on track, "for scenario control". (NRC/ FEMA) . Make
- 11. Identify yourself to any Federal evaluatorsthem reasonably aw as you control the scenario. I
- 12. Make notes on good and bad things that happen. Not as the plan. Attempt to assess the causes of poor performance and use the observation checklists.
13. Attend the post drill critique session to provide your comments and recommendations to the Lead Referees. Remember, if a real emergency or operational problem occurs, ('} 14. call off your portion of the exercise and notify the Head (m/ Referee immediately! 4.2.2
_- . . . ~ - -- . - ._ .. . REFEREE AND OBSERVER INSTRUCTIONS (cont'd) f- !
~
DO's (cont'd) ! l
- 15. Ensure that actual problems with plant equipment or structures that are discovered during the exercise, if any, are identified to the duty SNSS and documented by the players if necessary (EMIS tagging).
i DON'Ts r
- 1. Don't leave your post at key times.
- 2. Don't prompt the players except through use of approved j messages.
- 3. Don't coach the players.
- 4. Don't criticize or praise the player's actions during the .
play of the drill. !
- 5. Don't allow the players to introduce events or modify the data.
In other words, don't deviate from the scenario timeline jf unless such actions are expressly permitted by the Head. Referee. l Don't allow the player's actions, or your own, to violate O 6. normal plant rules regarding security, safety, or radiological controls. i Always exercise your authority as a referee to ensure plant and personnel safety. .That is controlling, not prompting. q
- 7. Don't allow the players to be distracted by the presence of observers or evaluators. These participants may wish to ask ;
questions of the players in order to better understand the ! actions they are observing. ; Such questions are permissible ~, but should be directed first to the referee who may provide the answer or at least participate in the interview with the player to ensure there : is no misunderstanding.
- 8. Don't forget that the NRC Region I Incident and are Response not privy Team to the scenario. ;
members are players also, As players they are encouraged to interact with.our emergency ' response players as an integrated team. 4
-i 4.2.3
SECTION 4.3 ARTIFICIAL ISLAND ANNUAL EZERCISE REFEREE ODBERVATION SHEETS Paae # 4.3.1 Control Room' Command and Control / Operations 4.3.2 Control Room Notifications and Communications 4.3.3 TSC Command and Control / Security 4.3.4 TSC Technical Support i 4.3.5 TSC Radiological Assessment / Chemistry Response 4.3.6 TSC Notification and Communication / Administration Support 4.3.7 OSC Command and Control / Operations / Communications 4.3.8 OSC Support Personnel 4.3.9 Chemistry Sampling and Analysis Teams 4.3.10 Control Point Command and Control / Operations / Communications 4.3.11(a) Inplant Radiation Monitoring Teams 4.3.11(b) Onsite Fadiation Monitoring Teams 4.3.11(c) Offsite Radiation Monitoring Teams 4.3.12 EOF Radiological Assessment 4.3.13 EOF Technical Assessment 4.3.14 EOF Command and Control / Operations / Security 4.3.15 EOF Communications / Administrative Support 4.3.16 ENC Public Information and Media Relations 4.3.17 Exercise Control and Evaluation 4.3.18 Observation / Evaluation Sheet (Referees / Observers) 4.3.20 Controller Critique Guidelines (~)
- 4.3.0
1 f l 4.3.1 OB8ERVATION CBBCKLIST I Area / Function Observed: Control Room Co==and and Control /Onerations s Exercise Date: ; Name: i' (check one) Adeauate Inadeauate ,
' Exercise Obiectives to be demonstrated ,
A.2 Provide technical and operational information concerning plant status / .. prognosis to appropriate TSC and EOF emergency personnel. B.1 Recognizing and classifying emergency conditions. I C.1 Implement appropriate Emergency Plan ; procedures. ; C.2 Transfer responsibilities of Emergency Coordinator. I C.3 Command and control of Control Room emergency response. O C .4 Establishing and directing OSC team priorities through the OSCC. C.5 Identify changing plant conditions and brief Control Room personnel concerning degraded or improved plant status. i C.6 Ability of the Control Room Staff to ; interface with the NRC Site Response Team. I Recognizing operational symptoms and F.1 parameters indicative of degrading plant conditions. }. 4 Signed: ,
?
Note: Use the back of this sheet to give details on any i
" inadequate" demonstrations of objectives.
I Return completed checklist to the Emergency Preparedness Manager,- 'i MC-M37. , 4.3.1 l i
.1
.,.-,,,w- .,m_ , . _ y. - . , _ . -
O 4.3.2 OBSERVATION CHECKLIST Area / Function Observed: Control Room Notifications and Communications Exercise Date: Name: (check one) Adecuate Inadeauate Exercise Obiectives to be demonstrated r A.2 Communications capabilities between Emergency Response Facilities. ' B.1 Implement notifications and data communications in accordance with procedures. B.2 Capability to perform timely notifications , to the States of New Jersey and Delaware. B.3 Capability to notify and communicate with the NRC via secondary phone lines. F.2 Proper communciations methods _and timely notifications to offsite agencies. O r Signed: 1 Note: Use the back of this sheet to give details on any , l
" inadequate" demonstrations of objectives. l l
l Return completed checklist to the Emergency Preparedness Manager, MC-W37. 4.3.2
i l l 4.3.3 OBSERVATION CHECKLIST ( TSC Command end Control / Security Area / Function Observed: Exercise Date: Name: (check one) Adecuate Inadecuate Exercise Obiectives to be demonstrated A.1 Activation and staffing of the Technical _ Support Center. B.1 Recognizing and classifying emergency conditions. C.1 Implement appropriate Emergency Plan procedures. C.2 Transfer responsibilities of Emergency Coordinator. C.3 Command and control of TSC emergency response. r)r Effective organizational control and (_ C.4 integrated emergency response. C.5 Identify changing plant conditions and brief TSC personnel concerning degraded or improved plant status. C.6 Ability of the TSC Staff to interface with the NRC Site Response Team. I.1 Establishing and controlling security access onsite and maintaining personnel accountability within the Protected Area. Signed: Note: Use the back of this sheet to give details on any
" inadequate" demonstrations of objectives.
Return completed checklist to the Emergency Preparedness Manager, MC-N37, i 4.3.3 l
4.3.4 OBSERVATION CHECKLIST Area / Function Observed: TSC Technical Suncort/Encineerina Name:
Exercise Date: (check one) Adecuate Inadecuate Exercise Obiectives to be demonstrated B.3 _ Communicate technical information between emergency response facilities. C.1 Implement appropriate Emergency Plan procedures. H.1 Develop alternative methods or equipment alterations in response to accidents affecting plant systems or components. H.2 Assess plant operational data and provide recommendations concerning accident mitigation and engineering based PAR's when appropriate. H.3 Identify or recognize when fission , ~s product boundaries are breached. H.4 Estimate fuel damage using available data should core damage, occur. Signed: Note: Use the back of this sheet to give details on any
" inadequate" demonstrations of objectives.
Return cor.pleted checkligt to the Eastgency Preparedness Manager, MC-M37. i l O 4.3.4 I
x a . , . . . m - . e nor, - + . - - -n, . -. :. . ~ . . . ~ . . . . . - + a - a. a .. I i 4.3.5 OBSERVATION CERCKLIST i Area / Function Observed: TSC Radioloaical/Chemictry f Exercise Date: Nrme: .i l (check one) Adecuate Inadeauate ! Exercise Obiectives to be demonstrated C.1 Implement appropriate Emergency Plan I procedures l C.4 Coordinate, control, and deploy ; radiological monitoring teams. f D.1 Communicate monitoring teams withandandreceipt controland fieldanalysis of field data. I
.D.2 Determine recommendations of PAR's l-based on dose projections or plant ,
chemistry. G.1 Decision making for limiting exposure of emergency response personnel. O G .2 Perform dose assessment and effectively distribute dosimetry and thyroid blocking agents, if appropriate. Signed: Note: Use the back of this sheat to give details on any
" inadequate" demonstrations of objectives. >
j Return completed checklist to the Ezergency Preparedness Manager, ? MC-M37. i 4.3.5
)
l 3 I 6 em :, ,
i ,O 4.3.6 OBSERVATION CHECKLIST Area / Function Observed: TSC Notifications / Communications / Admin. Suonort f Exercise Date: f Name: ! (check one) Adecuate Inadecuate Exercise Obiectives to be demonstrated A.2 Communications capabilities between emergency response facilities. A.3 Facilities and displays to support emergency operations. B.2 Capability to perform timely notifications to the States of New Jersey and Delaware. B.3 Communicate technical information between emergency response facilities. B.3 Capability to notify and communicate with the NRC via the Emergency Notification System (ENS). ( ) B.4 Capability to formulate around the clock emergency response duty rosters to allow extended activation of emergency response. F.2 Proper communciations methods and timely notifications to offsite agencies. Signed: Note: Use the back of this sheet to give details on any
" inadequate" demonstrations of objectives.
Return completed checklist to the Emergency Preparedness Manager, MC-N37. 4.3.6
O 4.3.7 OBSERVATION CHECKLIST OSC Command and control / Operations / communications Area / Function Observed: Exercise Date: Name: (check one) Adecuate Inadecuate Exercise Obiectives to be demonstrated , A.2 Communications capabilities between ; emergency response facilities. B.3 Communication of technical information between the OSC and other ERFs. C.1 Implement appropriate Emergency Plan , procedures. F.4 Command and control functions within the OSC. F.5 Properly set-up, staff, and operate the OSC. F.6 Coordinate the dispatch of OSC teams Og to meet SNSS priorities. G.3 Adequate health physics support for ' OSC dispatched teams deployed in areas 3 of radiological concern. i Signed: C Note: Use the back of this sheet to give details on any
" inadequate" demonstrations of objectives.
l Return completed checklist to the Emergency Preparedness Manager, ! MC-N37. ! 4.3.7
l (- 4.3.8 OBSERVATION CHECKLIST Area / Function Observed: OSC Suncort Personnel , Name: Exercise Date: (check one) Adecuate Inadeaunte Exercise Obiectives to be demonstrated F.3 Implement protective actions for site personnel dispatched from the OSC. ' F.5 Properly set-up, staff, and operate the OSC. F.6 Capability of dispatched OSC teams . to respond as directed by the OSCC. G.3 Adequate health physics support for OSC dispatched teams deployed in areas of radiological concern. O Signed: Note: Use the back of this sheet to give details on any
" inadequate" demonstrations of objectives. ;
f Return completed checklist to the Emergency Preparedness Manager, MC-N37. I 4.3.8
5 4.3.9 OBSERVATION CHECKLIST Area / Function Observed: Chemistry Samolina and Analysis Exercise Date: , Name: (check one) Adecuate Inadeaunte Exercise Obiectives to be demonstrated : A.2 Provide technical information concerning plant status /chemi~stry to the TSC. C.1 Implement appropriate Emergency Plan procedures. G.3 Adequate health physics support for Chemistry sampling teams deployed in areas of radiological concern. O Signed: Note: Use the back of this sheet to give details on any
" inadequate" demonstrations of objectives.
Return completed checklist to the Emergency Preparedness Manager, MC-N37. O 4.3.9
i O 4.3.10 OB8ERVATION CHECKLIST T Control Point Command and Control / Communications Area / Function Observed: i Exercise Date: Name: i (check one) Adecuate Inadeauate f Exercise Obiectives to be demonstrated l A.2 Communications capabilities between : emergency response facilities. : B.3 Communication of technical information between the CP and other ERFs. c.1 Implement appropriate Emergency Plan procedures. C.3 Command and control of Control Point ! emergency response. G.2 Methods and resources for distributing ; dosimetry and thyroid blocking agent to emergency responders, if appropriate. ( ) G.3 Adequate health physics support for OSC dispatched teams deployed in areas ; of radiological concern. i t Signed: ; Note: Use the back of this sheet to give details on any
" inadequate" demonstrations of objectives. ;
i. Return completed checklist to the Emergency Preparedness Manager, MC-N37. s 4.3.10
\
-() 4.3.11(a) OBSERVATION CHECKLIST I l Area / Function Observed: Inolant Monitorina Teams Exercise Date: Name: (check one) Adecuate Inadeounte . Exercise Obiectives to be demonstrated C.1 Implement appropriate Emergency Plan procedures. F.6 Coordinate the dispatch of OSC and CP teams to meet SNSS priorities. G.2 Methods and resources for distributing dosimetry and thyroid blocking agent to emergency responders, if appropriate. G.3 Adequate health physics support for OSC dispatched teams deployed in areas of radiological concern. O Signed: Note: Use the back of this sheet to give details on any ,
" inadequate" demonstrations of objectives.
Return completed checklist to the Emergency Preparedness Manager, MC-N37. O 4.3.11
i O 4.3.11(b) OBSERVATION CHECKLIST Area / Function Observed: Onsite Monitorina Teams Exercise Date: Name: (check one) Adecuate Inadecuate , Exercise Obiectives to be demonstrated C.1 Implement appropriate Emergency Plan t procedures. D.1 Communicate radiological data from the field to the TSC and respond to control. G.2 Methods and resources for distributing dosimetry and thyroid blocking agent to emergency responders, if appropriate. D O > t Y Signed: Note: Use the back of this sheet to give details on any
" inadequate" demonstrations of objectives.
Return completed checklist to the Emergency Preparedness Manager, MC-N37. 4.3.11(b) i i l
(~\ V 4.3.11(c) OBSERVATION CHECKLIST } Area / Function Observed: Offsite Monitorina Teams J Exercise Date: Name: (check one) Adecuate Inadeavate Exercise Obiectives to be demonstrated 1 C.1 Implement appropriate Emergency Plan procedures. D1 Communicate radiological data from the field to the EOF and respond to control. G.2 Methods and resources for distributing dosimetry and thyroid blocking agent to emergency respo.nders, if appropriate. f~ ( Signed: Note: Use the back of this sheet to give details on any
" inadequate" demonstrations of objectives.
Return completed checklist to the Emergency Preparedness Manager, MC-N37. 4.3.11(c) O 1
O 4.3.12 OBSERVATION CHECKLIST , Area / Function Observed: EOF Radioloaical Assessment Exercise Date: Name:' l (check one) Adeaunte Inadeauate Exercise Obiectiv.gs to be demonstrated , c.1 Implement appropriate Emergency Plan i procedures, C.4 Coordinate, control, and deploy radiological monitoring teams. D.1 Communicate monitoring withand teams andreceipt controland fieldanalysis of field data. D.2 Determine recommendations of PAR's based on dose projections or plant chemistry. , G.1 Decision making for limiting exposure of emergency response personnel. ( G.2 Perform dose assessment and effectively distribute dosimetry and thyroid blocking agents, if appropriate. I Signed:
)
l Note: Use the back of this sheet to give details on any
" inadequate" demonstrations of objectives.
Return completed checklist to the Emergency Preparedness Manager, MC-N37. d O 4.3.12 ; l
.- l
~~ 4.3.13 OBSERVATION CHECKLIST Area / Function Observed: EOF Technical Assessment /Encineerina Exercise Date: Name: (check one) Adecuate Inadesuate Exercise Obiectives to be demonstrated B.3 Communicate technical information between emergency response facilities. c.1 Implement appropriate Emergency Plan procedures. H.1 Develop alternative methods or equipment alterations in response to accidents affecting plant systems or components. H.2 Assess plant operational data and provide recommendations concerning accident mitigation and engineering based PAR's when appropriate. Identify or recognize when fission O H.3 product boundaries are breached. Signed: Note: Use the back of this sheet to give details on any
" inadequate" demonstrations of objectives.
Return completed checklist to the Emergency Preparedness Manager, MC-N37. , O 4.3.13
O 4.3.14 OBSERVATION CHECKLIST EOF Command and Control / Operations / Security i Area / Function Observed: Exercise Date: Name: (check one) Adecuate Inadeuuate Exercise Obiectives to be demonstrated A.1 Activation and staffing of the Emergency Operations Facility. B.1 Recognizing and classifying emergency conditions. 1 C.1 Implement appropriate Emergency Plan procedures. C.2 Transfer responsibilities of Emergency coordinator. C.3 Command and control of EOF
~
emergency response. C.4 Effective organizational control and integrated emergency response. C.S Identify changing plant conditions and brief EOF personnel concerning degraded or improved plant status. C.6 Ability of the EOF. Staff to interface with the NRC Site Response Team. D.2 Determination of PAR's based on plant conditions and/or dose projections. I.1 Establishing and controlling security access to the EOF. Signed: Note: Use the back of this sheet to give details on any
" inadequate" demonstrations of objectives.
Return completed checklist to the Emergency Preparedness Manager, MC-N37. 4.3.14
(3 \-) 4.3.15 OBSERVATION CHECKLIST Area / Function Observed: EOF Communications / Admin. Succort Name: Exercise Date: (check one) Adecuate Inadecuate Exercise Obiectives to be demonstrated A.2 Communications capabilities between emergency response facilities. A.3 Facilities and displays to support emergency operations. B.2 Capability to perform timely notifications to the States of New Jersey and Delaware. B.3 Communicate technical information between emergency response facilities. B.3 Capability to notify and communicate with the NRC via the Emergency Notification System (ENS). /~D B.4 Capability to formulate around the clock (_s/ emergency response duty rosters to allow extended activation of emergency response. F.2 Proper communciations methods and timely notifications to offsite agencies. Signed: Note: Use the back of this sheet to give details on any
" inadequate" demonstrations of objectives.
Return completed checklist to the Emergency Preparedness Manager, MC-N37.
~.
\_/ 4.3.15 1
-- -- .- . = . _ __.
{ l 4.3.16 OBSERVATION CHECKLIST ) Area / Function Observed: ENC Public Information and Media Relations Exercise Date: ! Name: (check one) Adecuate Inadeauate , Exercise Obiectives to be demonstrated , A.2 Communications capabilities between emergency response facilities. A.3 Facilities and dis' plays to support emergency operations. C.1 Implement appropriate Emergency Plan procedures. E.1 Activation'and staffing of the Emergency News Center (ENC). E.2 Ability to issue coordinated periodic public information bulletins. Ability to provide rumor control and response to inquiries from the general OE.3 public in a coordinated fashion. and E.4 Ability to provide clear, timely,dia. accurate briefings to the news me F I.1 Establish and control security access to the ENC. Signed: Note: Use the back of this sheet to give details on any
" inadequate" demonstrations of objectives.
Return completed checklist to the Emergency Preparedness Manager, MC-N37. l O 4.3.16 f l l l l l l
.. - - _= ...-- -
D 4.3.17 OBSERVATION CHECKLIST Area / Function Observed: Exercise Control and Evaluation Exercise Date: Name: (check one) Adecuate Inadeauate Exercise Obiectives to be demonstrated J.1 Ability to control the scenario in accordance with the prescribed timeline. J.2 Ability to provide scenario data and address questions which pertain to the data without prompting. J.3 Ability to adequately critique the exercise performance. O Signed: l Note: Use the back of this sheet to give details on any l
" inadequate" demonstrations of objectives. l I
I Return completed checklist to the Emergency Preparedness Manager, MC-N37. I I l l l ( 4.3.17 l l
SECTION 4.3 REFEREE / OBSERVER DRILL EVALUATION REPORT Name: Exercise / Drill Date: Oct. 25, 1994 OSC TSC CP EOF ENC Location: (circle one) SIM Exercise / Drill
Title:
Artificial Island Annual Exercise (H94-06) Drill Commenced: Drill Terminated: (time) (time) Note: Refer to Critique Guidelines and Exercise / Drill Objectives OBSERVATIONS - Performance of area observed to include drillsmanship. Areas of Good Performance by personnel: (continue on back, if needed) O Areas of Poor or Questionable Performance: (cont'd on back, if need) (
,ontinued on next page) f Signature:
Title:
Phone: 4.3.18 ; O ; i 1
REFEREE / OBSERVER DRILL EVALUATION REPORT (cont'd) Facility / Equipment problems or concerns: i P Proced.re problems or concerns: O l b (continued on next page) Signature: , Phone:
Title:
O 4,3,19a f ;
REFEREE / OBSERVER DRILL EVALUATION REPORT (cont'd) (j Scenario problems or concerns: Other problems or comments: (items that don't fit above categories) rs ( ) %.J l i i (continued on back, if needed) i l Signature: Phone:
Title:
4.3.19b ) N \ (G
i O EMERGENCY PLAN DRILL / EXERCISE CONTROLLER CRITIQUE GUIDELINES I AREAS TO CRITIOUE EMERGENCY RESPONSE ORGANIZATION 1. A. Staffing (full response, timely) Facility set up (automatic, timely) B. C. Command and control (clear, positive, proactive) D. EC turnover (effective, timely)
- 2. CLASSIFICATIONS AND NOTIFICATIONS Classifications (appropriate, timely)
A. B. Notifications to site personnel (clear, timely) C. Notifications to States / Agencies (clear, timely) COMMUNICATIONS to the point) 3. A. Within Group / Facilityfrequent, (clear, frequent, complete) B. Between ERFs (clear, C. Equipment (telephones, telecopiers, radios, PA)
- 4. PROCEDURE COMPLIANCE A. Procedural guidance is sufficient?
Procedures (available, complied with) B. C. Procedure forms, lists, data tables (up to date)
- 5. EXPOSURE CONTROL Exposure minimized when possible (ALARA)
A. B. Rad monitoring equip./ dosimetry (operable, available) C. Protective Action Decisions / Recommendations (correct)
- 6. EMERGENCY MITIGATING ACTIONS A. Mitigating actions taken were proper B. Developing problems were anticipated (what if thinking)
C. Priorities established (clear, SNSS directed, revised as needed)
- 7. FACILITIES A. Functional for response objectivescalibrated, operable)
B. Supplies / Equip. (available, C. Reference documents (available, up to date)
- 8. SCENARIO CONTROL comprehensive)
A. Scenario Scenario events (realistic, challenging,isplayed data (consistent, sufficient, d well) B. 9. DRILLSMANSHIPReferees A. prepared (scenario control, player interaction) B. C. Players maintained involvement with drill eventsPlant safety plant operation was adequately addressed) D. Critique (problems identified, feedback, praise, player input, attendance forms)' 4.3.20
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LEAD REFEREE'S NOTE: 1. Take control of the critique meeting Cut someone Do not allow it to develop into a gripe session.if necessary. It will benefit off (politely) group and they will respect you for it.
- 2. Seek suggested solutions to problems identified.
as 3. Provide positive feedback (praise for good performance) well as raising items of concern.
- 4. Distribute and collect participant evaluation report forms.
- 5. Collect all attendance forms distributed.
- 6. Limit the participant critique to 60 minutes.
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ESSI 1 Telephonee operate commerciotty from Area code 201. NOAA - 24 Hr. Emergency Weather Service (609) 261-6604 2 NOAA - Daekup Emergency Weather Service (609) 261-660 National Earthquake Center (303) 273-8500 i _ _ . _ _ . _ . . . . _ _ _ _ . _ _ _ _ . _ _ . _ . _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ % __m _-W
~O SECTION 5.0
-ARTIFICIAL ISLAND ANNUAL EXERCISE 1994 SCENARIO OVERVIEW t
PAGE # l SECTION # SECTION NAME Scenario Synopsis 5.1.0 5.1 5.2.0 5.2 Scenario Timeline 5.3.0 5.3 Major Observable Onsite Events 5.4.0 5.4 Onsite Actual vs. Simulated Events Radiological Assumptions 5.5.0 l 5.5 l
5.6 Comparison
Scenario vs. Industry- 5.6.0 1 Events t CAUTIOMs O THIS SECTION IS FOR REFEREE / EVALUATOR REFERENCE ONLY ! SCENARIO INFORMATION AND DATA REQUIRED BY THE PLAYERS SHALL BE PROVIDED AND CONTROLLED FROM SECTIONS 6, 7, 8, 9 & 10 BY THE REFEREES. 5.0.0
I
.l 1
1 I H94-06 i REV. 3 l i SECTION 5.1- j ARTIFICIAL ISLAND ANNUAL GRADED EXERCISE ! OCTOBER 25, 1994 SCENARIO SYNOPSIS [ I INITIAL CONDITIONS: Salem 1 is currently at 100% power. ; Salem 2 is currently at 85%-Power, with power ascension in progress following repairs to the #21 Main Feed Pump. l i Hope Creek is at 95% Power, End of Life (EOL) Core, Step #743 ! of the pull sheet, with a coastdown in progress. The unit has : been on line for the past 9 months. l All Major Equipment is Operable with the following exceptions:
"B" CRD Pump (1B-P-207) is Cleared and Tagged to replace i the pump motor, which failed during the night shift. ;
Repairs are in progress and are expected to be completed on l the day shift tomorrow.
"A" Core Spray Loop is Cleared and Tagged for a scheduled !
preventative maintenance outage. Tech Spec LCO 3.5.1 was -i entered at 0607 yesterday morning, October 24. Work is in progress and should be completed by the end of swing shift tomorrow. ;
"A" RACS Pump (1A-P-209) is Cleared and Tagged to repair -
l the pump discharge check valve (1-ED-V013) and replace the ] pump outboard bearing. The pump was found to be rotating backwards due to the discharge check being stuck open. Work is in progress and is expected to be completed by swing i shift today. l l Reactor Coolant System (RCS) chemical sample analysis indicates several fuel pins are leaking, causing a minor increase in Reactor Coolant Activity. The leakage started one month ago and the Nuclear Fuels Group estimates approximately 0.01% clad defects currently. The leaking fuel pins are suspected to be manufacturing imperfections and will be replaced during the upcoming Refuel Outage. RCS activity is still well below Tech Spec Limits. HTV RMS is inoperable 5.1.1
H94-06 REV. 2 f O) Scenario Synopsis The exercise will begin at 08:30 with the Hope Creek Control Room Staff having completed shift turnover and prestaged in the Simulator Control Room. At 08:33, the Control Room Crew will receive indication that Non-Essential 480 VAC Unit Substation (USS) 10-B-130 has been lost. The Unit Substation has overheated and is on fire. The loss of this Unit Substation among other things will cause a Loss of AC Power to various Condensate and Extraction Steam System Valves, that will become significant later in the scenario. In addition, the "B" Feedwater HeaterAs String will isolate, as Feedwater Temperature power is lost to the Control Panel. begins to decrease, Reactor Power will increase. The NSS Will refer to OP-AB.ZZ-0118, Loss of Feedwater Heaters and directs a Reactor Power decrease. Smoke from the fire is beginning to fill the Turbine Building, Elevation 120' in the Electrical Switchgear Area. The fire is limited to the 10-B-130 Unit substation, but burns for greater than 10 minutes.
- UNUSUAL EVENT should be declared by the SNSS based on
\' ECG Section 14A, (Fire within a permanent plant structure lasting for greater than 10 minutes). At 08:55, Fire Protection personnel will successfully extinguish the fire at 10-B-130 Unit Substation. Damage assessment will commence as soon as the area has been cleared of smoke. At 09:01, the Loose Parts Monitor Overhead Alarm will annunciate in the Main Control Room. The #5 Jet Pump Riser will fail, as the elbow / mixer section (Ram's Head Assembly) suddenly separates from the top of the Jet Pump riser, resulting in a rapid decrease in flow in the #5 Jet"B"Pump, as well as a decrease in Total Jet Pump Flow in the Reactor Recirc Loop. As Core Flow decreases, a decrease in Reactor Power occurs. The NSS will direct actions in accordance with OP-AB.ZZ-lli, Jet Pump Failure. He will direct the NCO to validate the indications and refer to Tech Spec 3.4.1.2, which requires the plant to be in Hot Shutdown within 12 Hours. This failure will create the presence of several small Loose Parts in the Reactor Coolant System, that will become significant later in the exercise. 5.1.2 O
H94-06 REV. 2
)
At 09:28, level in the #6C Feedwater Heater (FWH) will begin to increase as the result of a large tube leak. As level in the Heater continues to increase, a Heater Trip signal will be initiated. However, due to the previous loss of power to the extraction and condensate system valves, remote isolation of the #6C FWH is not possible from the Control Room. The NSS will again refer to OP-AB.ZZ-0118, Loss of Feedwater Heaters and dispatch an operator to attempt to locally isolate the #6C FWH. At 09:41, the Control Room receives indication that Main Turbine Vibration has begun to increase. This increase in vibration is due to postulated water induction into the Main Turbine, due to a inability to isolate the #6C FWH, combined with a failure of the Bleeder Trip Valve associated with the
#6C FWH. The water induction allows water to impinge on Turbine Blading and results in a subsequent imbalance of the Main Turbine.
The NSS will refer to OP-SO.AC-0001, Main Turbine Operation, which will require the Main Turbine be tripped due to the high vibration conditicn immediately when vibration reaches 12 mils. At 09:47, before Main Turbine Vibration increases above 6 mils, the Main Turbine will trip on Low Bearing Oil Pressure, g s) as the Bearing Oil Supply Header fails due to the increased ( Main Turbine Vibration. The Reactor Scrams and all Control Rods fully insert into the Reactor. At 09:48, two Main Turbine Blades will be thrown through the East Side Wall of the Turbine Building and travel into the Hope Creek Switchyard, and impact with '.ne 13.8 KV Ring Bus, Sus Section 2. This section of the 13.8 KV yard is destroyed and is not recoverable for the' duration of the exercise. At 09:42, the Primary Condensate Pump suction header, located on Elevaticn 54' of the Turbine Building ruptures due to the induced vibratitu from the failure of the Main Turbine and Condenser, resulting in a complete loss of Feedwater and condensate.
- ALERT should be declared by the SNBS based on ECG Section 13E, (Turbine Rotating Component Failure with casing penetration).
As Main Condenser Vacuum rapidly degrades, the MSIVS will close. RCIC will be used for Reactor Water Level Control. HPCI will be used for Reactor Pressure Control. 5 .1.' 3 .r t 1 l I 1 l
~ . . _ . - .
- l E94-06 ,
REY. 2 l !"~ \us)
-In response to Fire Alarms, the Control Room dispatches Site 1 Z
Protection There are per FP-EO.ZZ-0001(jo)r, no explosions or ma Control fires fromRoom Fire this Response. event. l There are small fires burning on Elevation 137' of the l Turbine Building, which are brought under control within 15 l l minutes. 1 Section 2, Station Service i Due to the loss of 13.81BX502 KV Bus and 1BX503 will deenergize, Transformers 1BX501, resulting in a fast transfer of the associated loads to the "A" side Station Service Transformers. All loads successfully i fast transfer, with the exception of the "B" 4160 VAC Vital "B" Bus (10-A-402). The alternate Feeder Breaker for the Vital Bus fails to close due to a Diesel Emergency breaker malfunction. Generator (EDG) will be l As a result, the "B" ): started and load onto the "B" Vital Bus. At 10:02, a small leak (less than 3 GPM) will develop just 4 downstream of Instrument Root Valve 1BB-V-600 and associated Excess Flow Check Valve 1BBXV-3734B, which is associated "B" with ) the #5 Jet Pump Flow Instrumentation, as well as the ' Channel Fuel Zone Instrument. The Control Room will not receive indication of the leak at this time. ; The leak has been caused by a small piece of the #5 Jet Pump beam, which is impacting against the instrument line and is f-- e causing oscillatory vibration of the instrument line. The leak is located in the South Pipe Chase, Reactor Building, Elevation 102'. The significance'of this small leak is that it will prevent manual operation of several valves after 10:51, for which remote operation will be lost, due to the loss of motive power. Since the leak is initially less than 3 GPM, the EFCV will not automatically close. During this time, the leak is only detectable if entryclosure If manual into theofSouth PipeisChase the EFCV is attempted, it attempted. will close. At 10:22, the "B" Emergency Diesel Generator (EDG) Lube Oil Suction line will develop a large, unisolable leak between the Lube Oil Reservoir and the Engine Driven Lube Oil Pump, ' resulting in a trip of the "B" EDG. Loss of the "B" EDG causes the the "B" 4160 VAC Vital "B" Bus to RHR deenergize, resulting in a Loss of AC Power to the
" B" Service Water Pump, "B" SACS Pump, "B" & "F" FRVS Pump, Recirc Fans and the "B" FRVS Vent Fan.
5.1.~4 O
H94-06 REV. 2 L' including In addition, several valves will lose motive power,an the "B" the "B" Core Spray Injection Valve (1BEHV-F005B) LPCI Injection Valve (1BCHV-F017B). If not done during the Unusual Event, at approximately 10:30, the OSC should be activated. All inplant activities will be controlled by the OSC Coordinator under direction from the SNSS. At 10:51, the leak in the South Pipe Chase will create an "D" LPCI Injection Overload Valve / Power Failureascondition (1BCRV-F017D), the valveon the experiences an motor internal South Pipe short due toThe Chase. theControl currentRoom steamwillenvironment in the of receive indication this condition. This is the first indication the Control Room receives that there may be a leak in the South Pipe Chase. This condition will prevent the valve from stroking open electrically upon a valid LPCI initiation signal.
"B" LPCI The "B" Core Spray Injection Valveare also(1BEHV-F005B) and effected by harsh Injection (lBCHV-F017B) However, no alarms will environment in the South Pipe Chase.
Vital Bus is currently be received, since the "B" deenergized. At approximately 11:00, the TSC should be activated.
'] Emergency Coordinator duties will be transferred from the y ,/ SNSS to the Emergency Duty Officer (EDO)
At 11:02, the leak in the South Pipe Chase will exceed 5the GPM and the Excess Flow Check Valve will close, isolating "B" Channel Fuel leak. Reactor Water Level indication on the Zone instrument will be lost. At 11:33, the Loose Parts Monitor Overhead Alarm reflashes, as a large piece of the failed #5 Jet Pumps Elbow / Mixer Section, which had been wedged between the tops of Jet Pumps
#6 & 7 and the Reactor Vessel Wall, has come loose and has been drawn into the "B" Recirc Pump Suction Piping.
At 11:35, the "B" Reactor Recirc Pump Suction Piping as the loose part impacts experiences a catastrophic failure, the suction piping. The impact results in an unisolable failure of the suction piping. Reactor Water Level rapidly decreases to the Top of Active Fuel and then slowly recovers. Drywell Pressure rapidly increases and then stabilizes at approximately 20 PSIG. Reactor Pressure rapidly decrease, resulting in the isolation of the HPCI and RCIC Systems. 5.1.5 O
H94-06 REV. 2 (n (
- DITE AR E EMERGENCY should be declared by the Emergency Duty Officer (EDO) based on ECG Baction 1D, (Loss of Coolant Accident Greater than Makeup Capacity).
Upon receipt of the LOCA signal, the "D" Core Spray Pump, "C" and "D" RHR Pumps will start. However, only the "C" RHR Pump will inject to the Reactor Vessel, as the injection valves associated with the other pumps can not be opened. In addition, the "A" RHR Pump, which was running in Torus Cooling, will trip approximately 1 minutes after the LOCA signal is received. All Primary Containment Isolation Valves will close on the LOCA signal, with the exception of the Drywell Atmospheric Gaseous Radioactivity Monitoring Inboard Isolation Valve, ISKHV-5018, which fails to fully close and indicates dual position in the Main Control Room. A Bailey Logic Card has failed, preventing remote valve closure from the Main Control Room. Attempts to manually close 1SKHV-5018 will be unsuccessful due to a failure of the Motor Operator declutch lever. The manual isolation valve associated with the penetration can not be closed due to a bent stem. As Reactor Coolant continues to enters the Drywell Air Space, ()i \ insulation and lagging material are blown throughout the Drywell. This generates a large amount of debris that is then directed from the Drywell into the Suppression Chamber. As the Low Pressure ECCS Pumps start, plugging of the respective pump suction strainers begins to occur. "C" RHR Pump Flow (only pump injecting to the RPV) decreases from 10000 GPM to 3000 GPM. At approximately 12:15, the "C" RHR pump will trip due to an overcurrent condition, as a result of continued pump cavitation due to low suction pressure. Pump motor amps, which initially decreased when suction strainer plugging started, have begun to experience significant fluctuations over the past few minutes, as the pump becomes air bound. The pump shaft heats up and begins to bind, resulting in a pump trip on overcurrent. Between 12:15 and 12:30, the Emergency Operations Facility (EOF) will be activated. Emergency Coordinator duties will be transferred from the EDO to the Emergency Response Manager (ERM). 5.1.6 / \ k
H94-06 REV. 2 fV CRD Pump and Fire Water available By 12:16, with only the "A" for injection to the Reacter; Reactor Water Level decreasesFuel Damage will to below the Top of the Active Fuel (TAF). begin to occur at this time. Between 12:30 and 12:45, Reactor Water Level will continue to slowly decrease. DAPA is increasing from 124 R/HR to 211 R/HR. The Emergency Coordinator may declare a General Emergency, based on his judgement that the potential exists for a Loss of Primary Containment Integrity. At 13:15, the Control Room receives indication that Area Radiation Levels in the Reactor Building'are increasing. FRVS Effluent quickly exceeds the release limit. Drywell Pressure is decreasing at a greater rate than previously observed. The breach of Primary Containment is due to the failure of the Drpell Atmospheric Gaseous Radioactivity sample line on Elevation 162' of the Reactor Building. The failure has occurred due to a previous failure of the heat trace associated with the piping. The buildup of moisture has resulted in corrosive environment. When the LOCA occurred in the Drywell, the pressure surge significantly weakens a number of piping welds. In addition, OSC personnel who are working to close the upstream manual valve (1-SK-V004) have s used excessive force in the attempt to close the valve. This i causes an already weakened weld joint to fail. This failure l allows the Drywell atmosphere to communicate directly with the Reactor Building. A radiological release to the atmosphere has commenced ; through the FRVS Vent. . Monitored Release Path : RPV --> "B" RECIRC SUCTION PIPING --
> DRYWELL --> RZ BLDG --> FRV8 VENT
- GENERAL EMERGENCY should be declared by the Emergency Response Manager (ERM) based on ECG Section 1E, (Loss of Coolant Accident with Failure of ECCS Systems to or ,
perform, or with potential Containment Failure) ECG Section 6A/B/C, (Fission Product Boundary Failure). 1 i 5.1.7
H94-06 REV. 2 ,m At 13:46, the "C" RHR Pump will be available for a. restart. The effects of Suction Strainer plugging will be minimal at this time. At 14:11, "B" EDG repairs will be completed. The "B" Vital Bus will be reenergized. With power available to the "B" Vital Bus, the "B" RHR Pump will be restarted. At 14:49, an OSC team will complete successful repair of the failed Bailey Logic Card for the 1SKHV-5018, allowing the valve to fully close, thereby stopping the release of fission products into the Reactor Building. At about 15:30, Emergency Conditions have stabilized. The release into the Reactor Building has ceased and the FRVS Vent Release Rate is decreasing. Although a General Emergency should be maintained at this time, the drill may be terminated by the HEAD REFEREE (with concurrence of the Lead NRC Inspector). Exercise termination requires that all major drill objectives have been achieved and the ERM is satisfied that stable conditions exist.
/**
5.1.8 O \.J
- T RADIOLOGICAL RELEASE
'-- FRVS VENT FAN EXIIAUST
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ARTIFICIAL ISLAND ANNUAL EXERCISE (1194-06) SIMPLIFIED DIAGRAM OF RELEASE PAT!! 5.1.9
*'s f)
O sJ V ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MAJOR EVENTS TIMELINE DRILL NUMBER: H94-06 REAL DRILL RECEIVER EXPECTED ACTION TIME TIME MESSAGE EVENT
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HOPE CREEK ShlFT PERSONNEL 1. LEAD REFEREE WILL HOLD AN INITIAL 08:00 00:00 01 INITIAL CONDITIONS - BRIEFING FOR ON CONDliiuNS BRIEFING FOR ALL DRILL SHIFT DRILL PLAYERS. PLAYERS.
- 2. ENSURE KEY PLAYERS AND REFEREES ARE AVAILABLE TO START THE DRILL.
SNSS (HOPE CREEK) 1. HOPE CREEK CONTROL ROOM IS AWARE 08:20 00:20 02 DRILL PAGE ANNOUNCEMENT FOR BOTM SALEM OF THE DRILL. AND HOPE CREEK.
- 2. DRILL CONTROLLERS ARE READY TO START THE DRILL.
CONTROL ROOM STAFF 1. CREW RECOGNIZES THAT 10-B-130 HAS 08:33 00:33 030 DARK BOARD MESSAGE FOR THE LOSS OF BEEN LOST AND STABILIZES PLANT. 10 8-130 UNIT SUBSTATION DUE TO A FIRE.
- 2. CREW RECOGNIZES THE PRESENCE OF A FIRE, REFERS TO FIRE RESPONSE MANUAL AND DISPATCHES THE FIRE BRIGADE.
- 3. NSS RECOGNIZES LOSS OF THE "B" FEEDWATER HEATER STRING AND REFERS TO OP-AB.ZZ-0118, LOSS OF FEEDWATER HEATERS AND UP-AB.ZZ-0204, POSITIVE REACTIVITY ADDITION.
CONTROL ROOM STAFF 1. CREW RECOGNIZES THAT A FIRE MAS 08:33 A :33 04 THE 10-8-130 UNIT SUBSTATION FIRE HAS STARTED IN THE TURBINE BUILDING, RESULTED IN AN OVERHEAD ALARM BEING ELEVATION 120'. RECEIVED IN THE MAIN CONTROL ROOM.
- 2. SNSS CONTACTS FIRE PROTECTION THIS MESSAGE CONTAINS THE ASSOCIATED TO RESPOND.
FIRE COMPUTER ALARM POINT THAT MUST BE
- 3. NSS REFERS TO PREFIRE PLAN ISSUED TO CONTROL ROOM SHIFT PERSONNEL FRH-II-452 (TURBINE BUILDING, VMEN THE OVERHEAD ALARM IS RECEIVED.
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N O ARTIFICIAL ISLAND EMERGENCY PREPAIEDNESS n b MAJOR EVENTS TIMELINE t DRILL NUMBER: H94-06 REAL DRILL EXPECTED ACTION EVENT RECEIVER TIME TIME MESSAGE ======================e=====================
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THE (MIT SUBSTATION. EQUIPMENT OPERATOR 1. THE OPERATOR DISPATCHED TO THE 00:50 10 THE "A" REACTOR RECIRC PUMP MG SET 08:50 10-C-184 PANEL ACKNOWLEDGES THAT VENT FAN (1A V-107) HAS TRIPPED ON LOW THE "A" REACTOR RECIRC PUMP MG SET FLOW DUE TO THE LOSS OF POWER FROM VENT FAN IS TRIPPED AND THAT THE 10-B-130 UNIT SUBSTATION.
"B" VENT HAS STARTED.
- 2. THE OPERATOR PROVIDES THE INFORMATION TO THE CONTROL ROOM (SIMULATOR)
USING DID PHONE EXTENSION 3339. CONTROL ROOM STAFF 1. CREW DISPATCHES AN AVAILABLE 00:54 10C CONTINGENCY MESSAGE TO DISPATCH AN 08:54 EQUIPMENT OPERATOR TO MONITOR EQUIPMENT OPERATOR TO MONITOR REACTOR REACTOR RECIRC PUMP MG SET LUBE Olt RECIRC PUMP MG SET LUBE CIL TEMPERATURES TEMPERATURES. FOLLOWING THE POWER REDUCTION. FIRE BRIGADE TEAM LEADER 1. THE FIRE BRIGADE ACKNOWLEDGES THAT 08:55 00:55 11 10-8-130 UNIT SUBSTATION FIRE IS THE FIRE IS EXTINGUISHED. SUCCESSFULLY EXTINGUISHED BY THE
- 2. FIRE BRIGADE COMMENCES ACTIONS TO FIRE BRIGADE. BEGIN CLEARING SMOKE FROM THE AREA. ,
SNSS 1. SNSS SNOULD REFER TO ECG SECTION 14.A 00:59 11C CONTINGENCY MESSAGE TO DECLARE AT 08:59 AND DECLARE AN UNUSUAL EVENT. UNUSUAL EVENT.
- 2. SNSS IMPLEMENTS APPROPRIATE ECG ATTACHMENTS AND EPIPS.
EQUIPMENT OPERATOR 1. THE OPERATOR DISPATCHED TO THE 01:00 12 SOME VALVES ASSOCIATED WITH THE STEAM 09:00 STEAM SEAL EVAPORATOR PANEL SEAL EVAPORATOR HAVE LOST POWER DUE TO j ACKNOWLEDGES THAT LOCAL INDICATIONS l THE LOSS OF 10-8-130. ARE NORMAL AND THE STEAM SEAL EVAPORATOR 15 FUNCTIONING PROPERLY. 5.2.4
~ . . - _ _ __ . _ _ _ - _ _ _ _ - - _ _ _ _ _ _ _ - _ _ _ _ - _ - _ - _ _ _ . .__ _ - - _ _ __ _ _ - _ _ - _
T. ARTIFICIAL ISLAND EMERGENCY PREPAIEDNESS MAJOR EVENTS TIMELINE DRILL NUMBER: H94-06 REAL DRILL EXPECTED ACTION EVENT
- RECEIVER TIME TIME MESSAGE
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- 2. THE OPERATOR PROVIDES THE INFORMATION TO THE CONTROL ROOM (SIMULATOR)
USING DID PHONE ENTENSION 3339. NSS 1. NSS CONTACTS THE REACTOR ENGINEER TO 09:00 01:00 12C CONTINGENCY MESSAGE TO CONTACT THE REVIEW THERMAL LIMITS AND PROVIDE REACTOR ENGINEER TO CHECK THERMAL GUIDANCE ON FURTHER REACTIVITY LIMITS AND PROVIDE FURTHER GUIDANCE MANIPULAfl0NS. ON REACTIVITY MANIPULATIONS. EQUIPMENT OPERATOR 1. THE EQUIPMENT OPERATOR ACKNOWLEDGES 01:00 13 MESSAGE FOR EQUIPMENT OPERATOR 09:00 THE STATUS OF THE SERVICE AIR DISPATCHED TO CHECK THE STATUS OF THE COMPRESSORS AND WOTIFIES THE CONTROL SERVICE AIR CPOMPRESSORS. ROOM. SNSS 1. SNSS DOES NOT IMPLEMENT ASSEMBLY / 01:01 13C CONTINGENCY MESSAGE TO PREVENT THE 09:01 ACCOUNTABILITY AT THIS TIME. SNSS FROM IMPLEMENTING ASSEMBLY / f,CCOUNTABILITY AT THIS TIME. CONTROL ROOM STAFF 1. CREW RECOGNIZES THAT INDICATED FLOW 09:01 01:01 130 DARK BOARD MESSAGE FOR THE #5 JET PUMP THROUG4 THE #5 JET PUMP HAS DECREASED RISER SECTION FAILURE. 2. CREW RECOGNIZES THE POSSIBLE ! PRESENCE OF A LOOSE PART IN THE REACTOR VESSEL DUE TO RECEIPT OF THE LOOSE PARTS MONITOR OVERHEAD ALARM.
- 3. CREW DISPATCHES AN EQUIPMENT OPERATOR TO VALIDATE THE LOOSE PARTS MONITOR ALARM.
- 4. NSS DIRECTS THE DA!LY JET PM SURV (OP-ST.88-001) BE PERFORMED TO ASSESS THE OPERABILITY OF THE #5 JET PUMP.
5.2.5 p. _ _ . _ _ _ _ _ _ . . _ _ _ _ _ _ . _ _ . _ . _ . _ _ _ _ _ _ _ _ _ _ _ __ __ _ _ . ~ . . -- ,m...- _
. ~ .-. , - _ - , _ -
ARTIFICI AL ISLAND EMElItGENCY PREPAKEDNESS MAJOR EVENIS TIMELINE DRILL NUMBER: M94-06 REAL DRILL EXPECTED ACTION EVENT RECEIVER TIME TIME MESSAGE
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EQUIPMENT OPERATOR 1. EQUIPMENT OPERATOR MONITORS REACTOR 04:02 01:02 16 "A" AND "B" REACTOR RECIRC MG SET RECIRC PUMP MG SET LUBE OIL LUBE O!L TEMPERATURES. TEMPERATURES.
- 2. EQUIPMENT OPERATOR NOTIFIES THI CONTROL ROOM.
- 1. CREW REFERS TO OP-50.SC-0001, LOOSE CONTINGENCY MESSAGE TO DISPATCH A4 CONTROL ROOM STAFF 09:06 01:06 14C PARTS MONITORING SYSTEM OPERAfl0N EQUIPMENT OPERATOR TO THE UPPER RELAY AND DISPATCHES AN EQUIPMENT OPERATOR ROOM TO VALIDATE THE LOOSE PARTS TO VALIDATE THE ALARM IN ACCORDANCE MONITOR ALARM.
Wi1H THE PP00EDURE. T. CREW PERFORMS OP-ST.BB-0001, 09:08 01:08 15C CONTINGENCY MESSAGE TO PERFORM THE DAILY CONTROL ROOM STAFF DAILY JET PUMP SURVEILLANCE, IN JET PUMP SURVEILLANCE TO DETERMINE THE ORDER TO DETERMINE THE OPERABILITY OPERABILITY OF THE #5 JET PUMP. OF THE #5 JET PUMP.
- 2. CREW DETERMINES THAT THE #5 JET PUMP IS th0PERABLE.
- 3. NSS REFERS To TECH SPEC 3.4.1.Z AND COMMENCES A REACTOR SHUTDOWN. !
CONTROL ROOM STAFF 1. THE CONTROL ROOM STAFF ACKNOWLEDGES 01:09 15D DARit BOARD MESSAGE FOR START OF THE 09:09 THAT THE "C" TUR8INE BUILDING "C" TURBINE BUILDING CHILLER. CHILLER HAS STARTED AND 15 DPERATING SATISFACTORILY. EQUIPMENT OPERATOR 1. EQUIPMENT CPERATOR PROPERLY 09:10 01:10 T6 VALIDATION OF THE LOOSE PARTS MONITOR IMPLEMENTS TtE VAllDAtl04 PROCEDURE ALARM. 3 CHANNELS ARE FOUND TO BE IN FOR THE LOOSE PARTS ALARM AND ALARM. NOTIFIES THE CONTROL ROOM (SIMULATOR) 0F HIS FINDINGS. 5.2.6 y qp eg n y -re,+--- -
*ee-?+ g up - - -
cx 0m O% U AR11FICI AL ISLAND EMERGE *4CY PREPA::EDi:ESS MAJOR EVENTS i!MELINE DRILL NUMBER: H94-06 REAL DRILL RECEIVER EXPECTED ACTION EVENT TluE TIME MESSAGE ============================================
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CONTROL ROOM STAFF 1. CREW CONTACTS THE SYSTEM ENGINEER 01:15 16C CONilNGENCY MESSAGE TO CONTACT THE 09:15 FOR THE LOOSE PARTS MONITORING SYSTEM ENGINEER FOR THE LOOSE PARTS SYSTEM TO ENSURE CORRECT VALIDATION MONITOR SfSTEM TO ENSURE CORRECT ALARM OF THE AL ARM. VALIDATION.
- 1. THE EQUIPMENT OPERATOR RECORDS EQUIPMENT OPERATOR 01:16 17 THE NSS HAS DIRECTED THE CONTROL ROOM THE JET PUMP DIFFERENilAL PRESSURE 09:16 OPERATORS TO PERFORM OP-ST.BB-0001, DATA PROVIDED BY THE REFEREE IN THE JET PUMP OPERABILITY SURVEllANCE. PROCEDURE.
AN EQUIPMENT OPERATOR IS DISPATCHED TO 2. THE OPERATOR CONTACTS THE CONTROL THE LOWER RELAY ROOM TO OBTAIN ROOM AND PROVIDES THE INFORMATION INDICATION OF DIFFERENTIAL PRESSURE FOR TO THE CREW. EACH OF THE 20 JET PUMPS. SNSS/NSS 1. THE SNSS DOES NOT SCRAM THE REACTOR 01:17 17C CONTINGENCY MESSAGE TO PREVENT MANUAL AND COMMENCES A CONTROLLED REACTOR 09:17 SCRAM OF THE REACTOR. SHUTDOWN WITH REACTOR POWER REDUCTION NOT EXCEEDING 15%/MOUR. FIRE BRIGADE TEAM LEADER 1. THE FIRE BRIGADE ACKNOWLEDGE THAT 01:17 18 WITH THE 10-B-130 UNIT SUBSTATION FIRE MOST OF THE SMOKE IS CLEARED. 09:17 EXTINGUSHED FOR THE PAST 20 MINUTES, THE FIRE BRIGADE HAS BEEN ABLE TO CLEAR MOST OF THE SMOKE FROM THE AREA SO THAT DAMAGE ASSESSMENT CAN COMMENCE. SNSS 1. THE SNSS DISPATCHES THE SHIFT 01:22 18C CONTINGENCY MESSAGE TO DISPATCH THE ELECTRICIAN TO PERFORM DAMAGE 09:22 SHIFT ELECTRICI AN TO PERFORM A DAMAGE ASSESSMENT ON 10-B-130 UNIT ASSESSMENT OF THE 10-B-130 UNIT SUBSTAil0N. SUBSTATION. REACTOR ENGINEER 1. REACTOR ENGINEER SUCCESSFULLY OBTAINS 01:23 19 REACTOR THERMAL LIMITS P1 EVALUATION 09:23 5.2.7
U V ARTIFICIAL ISLAND EMERGE %CY PIEPAIED%ESS MAJOR EVENTS TIMELINE DRILL NUMBER: H94-06 REAL DRILL EXPECTED ACTION EVElfi RECEIVER TIME TIME MESSAGE =================e==========================
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A P1 AND REVIEW THERMAL LIMITS AND DATA FOR RiACTOR EN',1NEER. THEN CONT ACTS THE CONTROL ROOM (SIMULATOR) WITH THE RESULTS.
- 2. THE REACTOR ENGINEER PROVIDES REACTIVITY CONTROL GUIDANCE TO THE CREW.
$NSS/NSS
- 1. THE SNSS/NSS REFERS TO TECH SPEC 01:30 19C CONTINGENCY MESSAGE FOR THE SNS$/ MSS 09:30 3.4.1.2 AND DIRECTS THE REACTOR TO DIRECT THE INITIATION OF A REACTOR SHUTDOWN.
SHUTDOWN IN ACCORDANCE WITH TECH SPEC
- 2. THE SNSS/ MSS NOTIFIES THE OPS MANAGER 3.4.1.2 DUE TO A FAILURE OF THE #5 JET AND LOAD DISPATCHER OF THE IMPENDING
) PUMP. SHUTDOWN. (THESE INTERFACES WILL BE ROLE PLATED BY A SIMULATOR REFEREE)
- 1. CREW RECOGNIZES THE HIGH LEVEL
! 09:30 01:30 190 DARK BOARD MESSAGE FOR THE #6C FEEDWATER CONTROL ROOM STAFFCONDITION IN THE #6C FEEDWATER HEATER TUBE LEAK RESULTING IN A HIGH HEATER AND ATTEMPTS 10 ISOLATE THE LEVEL IN THE #6C FEEDWATER HEATER. FEEDWATER HEATER TO PREVENT WATER INDUCTION INTO THE MAIN TURBINE.
- 2. NSS REFERS TO OP-AB.ZZ-0118, LOSS OF FEEDWATER HEATERS.
11C SYSTEM ENGINEER 1. SYSTEM ENGINEER PROPERLY VALIDATES 01:30 20 VALIDATION OF THE LOOSE PARTS MONITOR 09:30 LOOSE PARTS MONITOR ALARM AND ALARM. 3 CHANNELS ARE FOUND TO BE IN NOTIFIES THE SNSS. ALARM. CONTROL ROOM CREW 1. THE CREW ACKNOWLEDGES THAT THE 01:32 20D DARK BOARD MESSAGE FOR FAILURE OF THE 09:32 #6C FEEDWATER HEATER CONDENSATE
#6C FEEDWATER HEATER CONDENSATE INLET VALVE MOTOR HAS TRIPPED INLET TO CLOSE ON DEMAND, AS THE 04 THERMAL OVERLOAD AND DISPATCHES MOTOR BREAKER TRIPS ON THERMAL OVERLOAD.
5.2.8
~
D d ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MAJOR EVENTS TIMELINE DRILL NUMBER: H94 06 I DRILL EXPECTED ACTION REAL RECEIVER ,===================== f MESSAGE EVENT TIME TIME
============ ============ ============ ============================ AN OPERATOR TO INVES ATTEMPT TO CLOSE THE VALVE MANUALLY.
- 1. EQUIPMENT OPERATOR ATTEMPTS TO EQUIPMENT OPERATOR 01:33 21 ATTEMPT TO MANUALLY CLOSE THE #68 MANUALLY CLOSE THE #6B FEEDWATER 09:33 FEEDWATER HEATER CONDENSATE UUTLET VALVE HEATER CONDENSATE OUTLET VALVE.
15 NOT SUCCESSFUL, AS A SIGNIFICANT l AMOUNT OF RESISTANCE IS ENCOUNTERED WHILE THE EQUIPMENT OPERATOR ATTEMPTS TO MANUAL CLOSE THE VALVE.
- 1. THE SNSS DOES NOT SCRAM THE REACTOR SNSS/NSS i
01:33 21C CONTINGENCY MESSAGE TO PREVENT MANUAL AND COMMENCES A CONTROLLED REACTOR 09:33 SCRAM OF THE REACTOR. SHUTDOWN WITH REACTOR POWER REDUCTION NOT EXCEEDING 15%/MOUR. SHIFT ELECTRICIAN
- 1. SHIFT ELECTRICI AN SHOULD REPORT THE 01:37 22 DAMAGE ASSESSMENT MESSAGE FOR 10-8-130. DAMAGE TO THE SNSS (EC) WITH AN 09:37 ESTIMATE OF TIME TO REPAIR AND REQUEST DIRECTION ON WHETHER OR NOT TO PROCEED WITH REPAIRS. (AT THIS TIME, NORMAL WORK PROCEDURES ARE TO BE FOLLOWED.
CONTROL ROOM STAFF
- 1. THE CREW DISPATCHES AN EQUIPMENT 01:37 22C CONTINGENCY MESSAGE TO DISPATCN AN OPERATOR TO THE "C" FEEDWATER NEATER 09:37 "C" FEEDWATER EQUIPMENT OPERATOR TO THE CONTROL PANEL.
HEATER CONTROL PANEL. MAINTENANCE TEAM- 1. MAINTENANCE TEAM ACKNOWLEDGES THAT 01:40 ?3 MESSAGE FOR SUCCESSFUL HOOKUP OF THE THE TEMPORARY AIR COMPRESSOR HAS 09:40 TEMPORARY AIR COMPRESSOR. BEEN HOOKED UP AND INFORMS THE-
' CONTROL ROOM (SIMULATOR).
5.2.9 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ - - _ _ - - , - - _ _ ,-~ _ _ . - - . - .- - - . --- . _ _ _ _ _ _ _ _ _ _ __,
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O ARTIFICIAL ISLS.ND EMERGENCY PIEP MEDIESS MAJOR EVENTS TIMELINE o DRILL NUMBER: H94-06 REAL DRILL EXPECTED ACTION EVENT RECEIVER TIME TIME MESSAGE
============ ============ ============ ========================================= ======
r0UIP*ENT OPERATOR 1. EQUIPMENT OPERATOR ATTEMPTS TO 09:45 01:45 26 ATTEMPT TO MANUALLY CLOSE THE #6C MANUALLY CLOSE THE #6C FEEDWATER FEEDWATER HEATER EXTRACTION STEAM HEATER EXTRACTION STEAM ISOLAft0N ISOLATION VALVE IS NOT POSSIBLE DUE TO VALVE. THE INACCESSABILITY OF THE VALVE.
- 1. NSS ENTERS E0P-101, RPV CONTROL AND CONTROL ROOM STAFF 09:47 01:47 27D ALSO MONITORS KET CTMT. PARAMETERS.
A TURBINE TRIP HAS OCCURRED DUE TO LOW
- 2. NCO's PERFORM POST SCRAM ACTIONS, USE BEARING OIL PRESSURE. THE REACTCR HAS RFP FOR LEVEL CONTROL AND TURBINE SCRAMMED. ALL CONTROL RODS HAVE FULLY BTPASS VALVES FOR PRESSURE CONTROL.
INSERTED INTO THE REACTOR.
- 3. SNSS SHOULD REFER TO ECG.
- 1. NSS ENTERS E0P-101, RPV CONTROL AND CONTROL ROOM STAFF 09:47 01:47 280 ALSO MONITORS KEY CTMT. PARAMETERS.
A TURBINE TRIP HAS OCCURRED DUE TO LOW 2. NCO's PERFORM POST SCRAM ACTIONS, USE BEARING OIL PRESSURE. THE REACTOR HAS , RFP FOR LEVEL CONTROL AND TURBINE SCRAMMED. ALL CONTROL RCDS HAVE FULLY BTPASS VALVES FOR PRCMSURE CONTROL. INSERTED INTO THE REACTOR.
- 3. SNSS SHOULD REFER su LLG.
CONTROL ROOM STAFF 1. THE CREW RECOGNIZES THE FAST TRANSFER 01:48 29D DARK BOARD MESSAGE FOR LOSS OF THE 09:48 OF LOADS FROM THE "B" SIDE STAfl04 13.8 KV RING BUS SECTION 2, ALONG WITH "A" SIDE SERVICE TRANSFORMERS TO THE A FAILURE OF THE ALTERNATE FEE. DER FOR STATION SERVICE TRANSFORMER. THE 10-A-402, "B" 4160 VAC VITAL Bus
- 2. THE CREW RECOGNIZES THE LOSS OF THE TO CLOSE ONTO THE BUS.
"B" 4160 VAC VITAL BUS.
- 3. THE CREW ATTEMPTS TO MANUALLY START THE "B" EDG FROM THE CONTROL ROOM.
i CONTROL ROOM STAFF 1. THE CREW RECOGNIZES THE FAST TRANSFER 01:48 30D DARK BOARD MESSAGE FOR LOSS OF THE 09:48 OF LOADS FROM THE "B" SIDE STATION 13.8 KV RING BUS SECTION 2, ALONG WITH "A" SIDE SERVICE TRANSFORMERS TO THE A FAILURE OF THE ALTERNATE FE DER FOR 5.2.11
O ARTIFICI AL ISLAND EMEKGENCY PREPMEDNESS ' O MAJOR EVENTS TIMELINE _ DRILL NUMBER: H94-06 REAL DRILL EXPECTED ACTION EVENT RECEIVER TIME TIME MESSAGE
==============e============== ============================================
==========e= ============ ========== == =========================================
, STATION SERVICE TRANSFORMER.
THE 10-A-402, "B" 4160 VAC VITAL BUS
- 2. THE CREW RECOGN!ZES THE LOSS OF TPC TO CLOSE ONTO THE BUS.
"B" 4160 VAC VITAL BUS.
- 3. THE CREW ATTEMPTS TO MANUALLY START THE "B" EDG FROM THE CONTROL ROOM.
EQUIPuENT OPERATOR 1. EQUIPMENT OPERATOR PROVIDES 09:48 01:48 31 WHILE ATTEMPTING TO MANUALLY CLOSE THE INFORMATION TO THE SNSS.
#6C FEEDWATER HEATER CONDENSATE INLET VALVE, THE OPERATOR OBSERVES TUR8INE BLADING PENETRATING THE EAST WALL OF THE TURBINE BUILDING.
- 1. NSS ENTERS E0P-101, RPV CONTROL AND CONTROL ROOM ST AFF 09:49 01:49 31D ALSO MONITORS KEY CTMT. PARAMETERS.
A TURBINE TRIP HAS OCCURRED DUE TO LOW
- 2. NCO's CONTROL REACTOR WATER LEVEL BEARING OIL PRESSURE. THE SUBSEQUENT USING MPCI AND OR RCIC. SRVS ARE VIBRATION DUE TO WATER IMPINGEMENT USED FOR PRESSURE CONTROL.
' 04 THE TURBINE BLADING CAUSES A FAILURE OF THE MAIN CONDENSER ALONG WITH A RUPTURE OF THE PRIMART CONDENSATE PUMP SUCTION HEADER.
- 1. NSS ENTERS E0P-101, RPV CONTROL AND CONTROL ROOM STAFF 09:49 01:49 32D ALSO MONITORS KET CTMT. PARAMETERS.
A TUR8INE TRIP HAS OCCURRED DUE To LOW
- 2. NCO's CONTROL REACTOR WATER LEVEL BEARING OIL PRESSURE. THE SUBSEQUENT USING HPCI AND OR RCIC. SRVS ARE VIBRATION DUE TO WATER IMPINGEMENT USED FOR PRESSURE CONTROL.
ON THE TUR8INE SLADING CAUSES A FAILURE OF THE MAIN CONDENSER ALONG WITH A RUPTURE OF THE PRIMARY CONDENSATE PUMP SUCTION HEADER.
- 1. SNSS DIRECTS NCO TO MAKE'PAGE 09:50 01:50 33 SECURITY HAS JUST NOTIFIED THE SNSS 'THAT MGM SECURITY SUPERVISOR S.2.12
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V g ARTIFICIAL ISLt.ND EMERGEECY P;EPAIED%ESS b\ i MAJOR EVENTS TIMELINE DRILL NUMBER: H94-06 REAL DRILL EXPECTED ACTION RECEIVER EVENT TIME TIME MESSAGE _ ..____;2 ================ ============================================
============ ============ ============ ==================._____.__============== ===
OPERATOR TO PERFORM DAMAGE ASSESSMENT IN THE TURBINE BulLDING. ASSESSMENT IN THE TURBINE BUILDING. CONTROL Ro0M CREW 1. THE CREW DISPACHES AN EQUIPMENT 01:59 36C CONTINGENCY MESSAGE TO PERFORM DAMAGE 09:59 OPERATOR TO PERFORM DAMAGE ASSESSMENT IN THE SWITCHYARD. ASSESSMENT IN THE HOPE CREK SWITCHYARD. CONTROL ROOM CREW
- 1. THE CREW DISPACHES AN EQUIPMENT 01:59 37C CONTINGENCY MESSAGE TO DETERMINE THE OPERATOR TO THE "B" VITAL BUS 09:59 REASON FOR THE LOSS OF THE "B" VITAL SWITCHGEAR TO INVESTIGATE THE BUS. REASON FOR THE FAST TRANSFER FAILURE.
EQUIPMENT OPERATOR
- 1. SNSS REFERS TO ECG FOR EVENT 02:04 38 THE MAIN TUR8INE FAILURE HAS RESULTED DECLARATION AFTER RECEIVING A 10:04 IN 2 TUR8INE BLADES PENETRATING THE COMPLETE DESCRIPTION OF THE DAMAGE TUR8tNE CASING AND EAST WALL OF THE THAT HAS OCCURKED IN THE SWITCHYARD.
TUR81NE BUILDING. THE BLADES IMPACT 2. SNSS 08TAINS C*TIONAL INFORMATION 13.8 KV BUS SECTIONS 2 AND 8, RESULTING FROM EQUIPMit > W'RATORS DISPATCHED IN A LOSS OF THE "B" SIDE STATION TO DETERMINE r*' ' 4 TENT OF DAMAGE SERVICE TRANSFORMERS. AND FAST TRANSFER TO THE PLANT. TO THE "A" SIDE. EQUIPMENT / FIRE PROT. OPERATOR 1, SNSS REFERS TO ECG FOR EVENT 02:04 39 THE MAIN TUR8INE FAILURE HAS RESULTED DECLARATION AFTER RECEIVlWG A 10:04 IN 2 TUR81NE SLADES PENETRATING THE COMPLETE DESCRIPTION OF THE DAMAGE TUR8INE CASING AND EAST WALL OF THE THAT HAS DCCURRED IN THE TUR81NE SLDG TUR8INE SUILDlWG. THERE IS DAMAGE TO 2. SNSS OSTAINS ADDITIONAL INFORMATION THE MAIN CONDENSER AND OTHER COMPONENTS FROM EQUIPMENT OPERATORS DISPATCHED IN THE TUR8INE BUILDING. TO THE SWITCHYARD TO DETERMINE THE EXTENT OF, DAMAGE TO THE PLANT. 5.2.14 _ _ . _ _ . _ _ _ _ ________m-_m_ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ - - , , _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ __ _ m_ - _.__ _ _ ___ _ _ _ _ _ _ _ _______m-
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* ~
ARilFICIAL ISLAND EMERGE %CT PREPAREDNESS MAJOR EVENTS TIMELINE DRILL NUMBER: M94-06 l REAL DRILL EXPECTED ACTION EVENT RECEIVER TIME TIME MESSAGE
=========================m===============
============================= =================================
============ ============ ============
CONTROL ROOM CREW 1. THE CREW DISPACHES THE FIRE BRIGADE 10:04 02:04 39C CONTINGENCY MESSAGE FOR FIRE BRIGADE TO RESPOND TO THE FIRES IN THE TO RESPOND TO SMALL FIRES IN THE TURBINE BUILDING. l TURBINE BUILDING. THE MAIN TURBINE FAILURE HAS RESULTED EQUIPMENT / FIRE PROT. OPERATOR $. SNSS REFERS TO ECG FOR EVENT 10:05 02:05 40 DECLARATIDN AFTER RECEIVING A IN 2 TURBINE BLADES PENETRATING THE COMPLETE DESCRIPTION OF THE DAMAGE TURBINE CASING AND EAST WALL OF THE THAT HAS OCCURRED IN THE TURBINE BLDG TURBINE BUILDING. THERE IS DAMAGE TO
- 2. SNSS DBTAINS ADolTIONAL INFORMATION THE MAIN CONDENSER AND OTHER COMPONENTS FROM EQUIPMENT OPERATORS DISPATCHED IN THE TURBINE BUILDING. TO THE SWITCHYARD T3 DETERMINE THE
- EXTENT OF DAMAGE TO THE PLANT.
THE MAIN TURBINE FAILURE HAS RESULTED EQUIPMENT / FIRE PROT. OPERATOR $. SNSS REFERS TO ECG FOR EVENT. 10:05 02:05 41 DECLARATION AFTER RECEIVING A IN 2 TURBINE BLADES PENETRATING THE COMPLETE DESCRIPTION OF THE DAMAGE TUR8INE CASING AND EAST WALL Of THE THAT HAS OCCURRED IN THE TURBINE SLDG TUR81NE BUILDlWG. THERE IS DAMAGE To 2. SNSS DBTAINS ADDITIONAL INFORMAT10N THE MAIN CONDENSER AND OTMER COMPONENTS FROM EQUIPMENT OPERATORS DISPATCMED IN THE TbR81NE SUILDING. TO THE SWITCHYARD TO DETERMINE THE EXTENT OF DAMAGE TO THE PLANT. THE MAIN TURBINE FAILURE MAS RESULTED EQUIPMENT / FIRE PROT. OPERATOR $. SMSS REFERS TO ECG FOR EVENT 10:05 02:05 42 DECLARATION AFTER RECEIVING A IN 2 TURBINE BLADES PENETRATING THE COMPLETE DESCRIPfl0N OF THE DAMAGE TUR8INE CASING AND EAST WALL OF THE THAT NAS OCCURRED IN THE TUR81NE SLDG TURBINE BUILDING. THERE IS DAMAGE TO
- 2. SNSS OBTAINS ADDITIONAL INFORMATION THE MAIN CONDENSER AND OTHER COMPONENTS FROM EQUIPMENT OPERATORS DISPATCHED IN THE TUR8INE BUILDING. TO THE SWITCHYARD TO DETERMINE THE EXTENT OF DAMAGE TO THE PLANT.
b 5.2.15 4 ____________.__._______m________________ __ _ _ _ _ _ _ _ _ _ - _ r , . . _ . . . . . . - _ . . _ _ . _
h U ARTIFICIAL ISLAND EMEICE%CT P!EPAIEDNESS MAJOR EVENTS TIMELINE DRILL NUMBER: H94-06 REAL DRILL EXPECTED ACTION RECElvER MESSAGE EVENT .======== .,====.. . .. .......... ............. TIME TIME
====....=33. === 3.====.. ..c=======.. ==============...=............ .... ==== .============
- 1. SHIFT ELECTRICIAN ACKNOWLEDGES THAT 10:07 02:07 43 FAILURE OF THE ALTERNATE FEEDER BREAKER SHIFT ELECTRICIAN THE NORMAL AND ALTERNATE FEEDER To CLOSE ONTO THE "B" VITAL BUS. BREAKER FOR THE "B" VITAL BUS ARE TRIPPED.
- 1. CONTROL ROOM CREW DISPATCHES CONTROL ROOM STAFF 02:10 43C CONTINGENCY MESSAGE TO DISPATCH AN AN EQUIPMIENT OPERATOR TO OPEN THE 10:10 EQUIPMENT OPERATOR TO SECURE THE BREAKERS FOR THE DC OIL PUMPS TURBINE GENERATOR AND RFPT DC OIL LOCATED IN THE TURBINE BUILDING.
PUMPS FOLLOWING FAILURE OF THE MAIN TURBINE.
- 1. EQUIPMENT OPERATOR N0ilFIES THE OSC 10:14 02:14 44 OPERATOR SECURES EMERGENCY DC Ott PUMPS EQUIPMENT OPERATOR THAT THE DC OIL PUMP MOTOR BREAKERS BY OPENING THE RESPECTIVE MOTOR BREAKEP.S HAVE BEEN OPENED.
$NSS
- 1. SMSS SHOULD REFER TO ECG SECTION 02:15 44C CONTINGENCY MESSAGE TO DECLARE AN 13.E AND DECLARE AN ALERT.
10:15 ALERT DUE TO TURBINE ROTATING COMPONENT 2. TSC AND OSC ACTIVATION PROCESS FAILURE WITH CASING PENETRATION. BEGINS. SNSS
- 1. SNSS DOES NOT IMPLEMENT 02:20 45C CONTINGENCY MESSAGE NOT TO IMPLEMENT ACCOUNTABILITT AT THis TIME.
10:20 ACCOUNTABILITY AT THIS TIME. CONTROL ROOM STAFF 450 THE "B" EMERGENCY DIESEL HAS TRIPPED 1. $NSS SHOULD DIRECT THE OSC TO RESPOND 10:22 02:22 AS THE RESULT OF A LARGE LEAK IN THE TO THE "B" EDG. LUBE DIL SUCTION PIPING. 2. CR STAFF CONTINUE TO FOLLOW E0Ps AND MONITOR CONTROL BOARDS.
- 3. NCO's RESPOND TO ALARMS AND EVALUATE ALL LOADS THAT HAVE BEEN LOST.
5.2.16
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============ ============ ============ ========================================= ======
REPAIRED AND IS READY TO BE PLACED IN SERVICE.
- 2. THE OSC TEAM LEADER CONTACTS THE OSCC AND PROVIDES THE INFORMATION.
CONTROL ROOM STAFF 1. CONTROL ROOM STAFF RECOGNIZES 11:02 03:02 500 DARK BOARD MESSAGE FOR "B" REACTOR ALARM FOR CLOSURE OF AN EXCESS FLOW VESSEL FUEL ZONE LEVEL INSTRUMENTATION CHECK VALVE. VARIABLE LEG EXCESS FLOW CHECK VALVE
- 2. SNSS CONTACTS THE OSCC TO DISPATCH CLOSURE DUE 10 INSTRUMENT LINE LEAK A TEAM TO THE 18C204 PANEL TO RATE EXCEEDING 5 GPM.
DETERMINE WHICH EXCESS FLOW CHECK VALVE MAS CLOSED.
- 3. NSTA AND NCO COORDINATED EFFORTS TO DETERMINE INSTRUMENTAfl0N EFFECTED BY CLOSURE OF THE EXCESS FLOW CHECK
- VALVE.
OSC TEAM 1. OSC TEAM ACKNOWLEDGES THAT THE 11:04 03:04 51 THE "D" LPCI INJECTION VALVE MOTOR "D" LPCI INJECTION VALVE MOTOR OREAKER IS TRIPPED DUE TO AN SHORT TO BREAKER IS TRIPPED AND WILL NOT GRCUND CONDITION AT THE MOTOR. THE
. RESET.
8REAKER CAN NOT BE RESET.
- 2. OSC TEAM REPORTS THE FINDINGS TO THE OSC COURDINATOR.
SNSS 1. SNSS DIRECTS OSCC TO DISPATCM AN 03:08 52C CONTINGENCY MESSAGE TO DISPATCM AN 11:08 OSC TEAM TO EXCESS FLOW CMECK VALVE OPERATOR TO EXCESS FLOW CHECK VALVE PANEL 18C204 PANEL 18C204. -:
- 2. NSTA REVIEWS P&lDS TO DETERMlWE INSTRUMENTATION EFFECTED BY THE CLOSURE OF EXCESS FLOW CHECK VALVE ,
188XV-37348. 5.2.18 _ _ . _ ..._ _ _ _ ._ __ __ _ _ _ _ . ~ . . . , _ . _ _ . _ _ _ _ _ _ _ , . . _ . ._ .
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m n U ( ARTIFICIAL ISLAND EMERGE CY PIEPAREDNESS MAJOR EVENTS TIMELINE DRILL NUMSER: H94-06 REAL DRILL RECEIVER EXPECTED ACTION MESSAGE EVENT TIME TIME
======3===========ze===========suser=====
============================= ===========================
m:========== ============ ============ MALFUNCTIONS.
- 4. NSS ASSESSES AVAILABLE INJECTION SOURCES.
CONTROL ROOM STAFF
- 1. NSS ENTERS EOP 101 AND 102 FOR 03:35 57D "B" REACTOR RECIRC PUMP SUCTION RPV CONTROL AND CONTAINMENT CONTROL.
11:35 PIPING HAS BEEN BREACHED DUE 10 IMPACT 2. SNSS NOTIFIES THE EDO AND RECOMMENDS WITH A LOOSE PART FROM THE FAILED APPROPRIATE ESCALAll0N OF THE
#5 JET PUMP. EMERGENCY CLASSIFICATION.
- 3. NCOS VERIFY PROPER RESPONSE OF .
ECCS AND NOTIFY THE NSS OF ANY MALFUNCTIONS.
- 4. NSS ASSESSES AVAILABLE INJECTION SOURCES.
's 4
CONTROL ROOM STAFF
- 1. THE CONTROL ROOM RECOGNIZES THAT THE 03:35 5m DARIC BOARD MESSAGE FOR TRIP OF THE "A" RHR HAS TRIPPED AND 15 NOT 11:35 "A" RHR PUMP DUE TO MECHANICAL BINDING AVAILABLE TO INJECT TO THE VESSEL AS A PIECE OF THE PUMP IMPELLAR HAS IN THE LPCI MODE.
BROKEN OFF AND HAS SECOME JA MED SETWEEN 2. THE SNSS DIRECTS THE OSCC TO DISPATCH THE INELLAR AND THE PUMP CASING. A TEAM TO INVESTIGATE. SNSS 1. THE SNSS DIRECTS THE OSCC TO 03:42 59C CONTINGENCY MESSAGE FOR THE SNSS TO DISPATCH A TEAM TO INVESTIGATE THE 11:42 DIRECT THE OSCC TO DISPATCH A TEAM TO "A" RHR PUMP TRIP. INVESTIGATE THE CAUSE OF THE TRIP Of THE "A" RHR PUMP. CONTROL RdOM CREW 1. CONTROL CREW RECOGNIZES THAT THE 03:45 59D DARIC BOARD MESSAGE FOR COMMENCEMENT OF "C" RHR PUMP SUCTION STRAINER IS 11:45 PLUGGING OF THE "C" RHR PUMP SUCTION BEGINNING TO PLUG. STRAlWER. 2. THE SNSS DIRECTS THE OSCC TO DISPATCH I i l- 5.2.20 h
--w + . - - w ----y. . +, , - - -w - ~+ ~ r _.
h4 u " A%TIFICIAL ISLAND EMERGENCY PREPAREDNESS MAJOR EVENTS TIMELINE DRILL NUMBER: H94-06 REAL DRILL EXPECTED ACTION EVENT RECEIVER TIME TIME MESSAGE
============ ==========================================================
A TEAM TO IMPLEMENT OP-AB.ZZ-0155, DEGRADED ECCS PERFORMANLE. OSC TEAM 1. OSC TEAM ACKNOWLEDGES THE STAit!S OF 11:47 03:47 60 THE "A" RHR PUMP MOTOR BREAKC# HAS THE "A" RHR PUMP MOTOR BREAKER AND TRIPPED 04 OVERCURRENT, DUE TO INFORMS THE OSC. MECHANICAL BINDING, AS A PIECE OF THE PUMP IMPELLAR HAS BROKEN OFF AND HAS BECOME LODGED BETWEEN THE IMPELLAR AND THE PUMP CASING.
- 1. AS PRACTICAL, RHR PUMPS CAN BE SNSS 11:49 G3:49 60C CONTINGENCY MESSAGE TO IMPLEMENT REMOVED FROM SERVICE FOR DEGRADED ECCS PERFORMANCE ABNORMAL BACRWASHING OF THE ASSOCIATED PROCEDURE.
SUCTION STRAINER.
- 1. CONTROL ROOM CREW ACKNOWLEDGES THAT 11:50 03:50 61D DARK BOARD MESSAGE FOR ATTEMPTED CLOSURE CONTROL ROOM CREW 1SKHV-5018 FAILS TO CLOSE FROM THE OF 1SKHV-5018.
CONTROL ROOM.
- 2. SNSS NOTIFIES THE TSC OF THE CONDITION AND REQUEST ENGINEERS DEVELOP A TROUBLESN00 TING PLAN.
OSC TEAM 1. IF THE SNSS RECOGNIZES THE FAILURE 03:50 62 OBSERVATION OF STATUS OF THE DRYWELL 11:50 OF THE PRIMARY CONTAINMENT ISOLAT10t! - GASEOUS ATMOSPHERIC SAMPLE SYSTEM. VALVE TO CLOSE (1SKHV-5018), THEN ME SHOULD DIRECT THE OSC TO DISPATCH A TEAM TO RESPONO. EDO / SNSS 1. DECLARE A SITE AREA EMERGENCY. 03:55 63C CONTINGENCY To DECLARE A SITE AREA 11:55 2. IMPLEMENT ECG ATTACHMENT 3. EMERGENCY.
~
~
- 3. IMPLEMENT EPIP'103H.
5.2.21 4 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ . _ _ _ ___-+_._a__ _ _ _ _ _ - __m_ - _ _ _ _ . >- _ _ _ _ _ . _ _ _ _ _ _ _ - . _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
( (D v ARTIFICIAL ISLAND EMERGE;:CY PREPAREDNESS MAJOR EVENTS TIMELINE DRILL NUMBER: H94-06 REAL ORILL EXPECTED ACTION EVENT RECEIVER TIME TIME MESSAGE
============================= ======================================
============ ============ ============ ==========s==============================
- 4. IMPLEMENT ACCOUNTABILITY (LIMITED)
CONTROL ROOM CREW 1. CONTROL CREW RECOGNIZES THAT THE 11:55 03:55 64D DARK BOARD MESSAGE FOR PLUGGING OF THE "C" RHR PUMP SUCTION STRAINER IS "C" RHR PUMP SUCTION STRAINER. PLUGGING.
- 2. THE SNSS DIRECTS THE OSCC TO DISPATCH A TEAM TO IMPLEMENT OP-AB.ZZ-0155, DEGRADED ECCS PERFORMANCE OSC TEAM MEMBERS 1. OSC TEAM DETERMihE THE SUCTION 11:56 03:56 65 "C" RHR PUMP SUCTION FRESSURE IS BELOW PRESSURE FOR THE "C" RHR PUMP.
THE NORMAL OPERATING VALUE DUE TO THE PLUGGING OF THE ASSOCIATED SUCTION STRAINER. OSC TEAM 1. IF THE CREW RECOGNIZES THE FAILURE 12:00 04:00 66 DUE TO A FAILURE OF DRYWELL GASEOUS OF THE PRIMARY CONTAINMENT ISOLATION ATMOSPHERIC SAMPLE INBOARD SUPPLY VALVE VALVE TO CLOSE, THEN AN OSC TEAM 1SKHV-5018 TO COMPLETELY ISOLATE ON THE SHOULD BE DISPATCHED TO INVESTIGATE. LOCA LEVEL 1 SIGNAL, MANUAL OPERATION IS REQUIRED. CONTROL ROOM CREW 1. SNSS CONTACTS THE OSCC TO DISPATCM 04:10 67C CONTINGENCY MESSAGE TO DISPATCH A TEAM 12:10 A TEAM. TO INVESilGATE THE FAILURE OF 1SKNV-5018 CONTROL ROOM STAFF 1. THE CONTROL ROOM RECOGNIZES THAT THE 04:13 68D DARK BOARD MESSAGE FOR TRIP OF THE 12:15 "C" RNR HAS TRIPPED AND IS NOT "C" RHR PUMP DUE TO COMPLETE PLUGGING AVAILABLE TO INJECT TO THE VESSEL 0F THE ECCS SUCTION STRAINER AS A RESULT IN TPE LPCI MODE. OF CONTINUOUS OPERATION FOR 40 MINUTES.
- 2. THE SMSS DIRECTS THE OSCC TO DISPATCH A TEAM TO INVESTIGATE.
SNSS 1. TAE SNSS DIRECTS THE OSCC TO 04:20 69C CONTINGENCY M SSAGE FOR THE SNSS TO 12:20 5.2.22
~ - -_ ._- - .___ -__ - __________ ______ _-__ -.
O G L-l ARTIFICIAL ISLAND EMERGENCY PREPAREDZESS MAJOR EVENTS TIMELINE DRILL NUMBER: H94-06 REAL ORILL EXPECTED ACTION RECEIVER MESSAGE EVENT TIME TIME
====== s=========== ============ =========================================
DISPATCH A TEAM TO INVESTIGATE THE DIRECT THE OSCC TO DISPATCH A TEAM TO "C" RHR PUMP TRIP. INVESTIGATE THE CAUSE OF THE TRIP OF THE "C" RHR PUMP. OSC TEAM
- 1. OSC TEAM ACKNOWLEDGES THE STATUS OF 04:23 70 THE "C" RHR PUMP MOTOR BREAKER HAS THE "C" RHR PUMP MOTOR BREAKER AND 12:23 TRIPPED ON OVERCURRENT, AS A RESULT 0 INFORMS THE OSC.
CONTINUED PUMP OPERATION WITH A PLUGGED SUCTION STRAINER. PUMP MOTOR CURRENT BEGAN FLUCTUATING WILDLY, RESULTING IN THE TRIP. AT APPROXIMATELY 12:45, THE DAPA DRILL REFEREES 04:45 71 REFEREE MESSAGE FOR GENERAL EMERGENCY MONITORS WILL EXCEED 200 R/HR, WHICH IS 12:45 DECLARATION. INDICATION OF A LOSS OF THE FUEL CLAD BARRIER. BASED 04 EMERGENCY COORDINATOR JtR) CEMENT, A GENERAL EMERGENCY COULD BE DECLARED AT THis TIME. IF A CENERAL EMERGENCY 15 DECLARED, THE EXPECTED PAR 15 AS FOLLOWS: EVACUATE ALL SECTORS 0 - 5 MILES CHEMISTRY SUPERVISOR - TSC 1. THE CHEMISTRf SUPERVISOR IN THE TSC 04:45 72C CDeiTINGENCY MESSAGE TO OBTAIN A PASS REQUESTS A PASS SAMPLE BE TAKEN. 12:45 SAMPLE. OSC TEAM 1. THE OSC TEAM WORKS AT CLOSING THE 04:50 73 OSC TEAM 15 HAVING SOME SUCCESS CLOSING MANUAL ISOLATION VALVE, 1-SK-YOO4. 12:50 MANUAL ISOLATION VALVE 1-St-V004. OSC TEAM 1. OSC TEAM MOTIFIES THE OSCC AND 05:00 74 A BAILEY CARD ASSOCIATED WITH ATTEMPTS TO FIND A REPLACEMENT CARD. 13:00 1SKHV-5018 HAS FAILED AND REQUIRES REPLACEMENT. 5.2.23
[ V V' fO ARTIFICI AL ISLLND EMEIGENCY PREPf. REDNESS MAJOR EVENTS TIMELINE DRILL NUMBER: H94-06 REAL DRILL EXPECTED ACTION RECEIVER EVENT TIME TIME MESSAGE ===== ============================================
======== ============ ============ =========================================
CONTROL ROOM STAFF
- 1. CONTINUE EFFORTS TO DETERMINE AND 05:15 74D RADIDACTIVE RELEASE OCCURS - AIRBORNE LOCATE THE SOURCE OF THE LINE 13:15 CONT AMINATION SPREADS THROUGHOUT RX BREAK.
BLDG. AND 15 RELEASED TO ENVIRONMENT VIA 2. SNSS INFORM EDO OF INCREASED RAD FRVS VENT. LOCAL AREA RAD MONITORS AND LEVEL AND IMOICATION OF FRVS RELEASE FRVS VENT EFFLUENT ALARMS OCCUR. 3. INFORM OSC OF RAD CONCERNS IN REACTOR BLDG.
- 4. NSS ENTERS E0P-103 (REACTOR BUILDING CONTPOL) AND E0P-104 (RADICACTIVE RELEASE CONTROL) '
- 5. NCO ENTERS ABNORMAL RELEASES OF GASEOUS RADIDACTIVITY (OP-AB.ZZ-li6)
OSC TEAM
- 1. THE OSC TEAM NOTIFIES THE OSCC 05:15 75 OSC TEAM ACTIONS INADVERTENTLY RESULT OF THE EVENTS AND IMMEDI ATELY 13:15 IN INITIATION OF A RADIOLOGICAL RELEASE. EVACUATEF THE AREA AND THE REACTOR SUILDING.
CHEMISTRY SUPERVISOR - TSC 1. PROVIDE THE RAC AND FUELS ENGINEER 05:30 76 THIS MESSAGE PROVIDES THE RESULTS OF THE WITH THE PASS RESULTS. 13:30 PASS SAMPLE TAKEN AT 12:45. RAC (RAD ASSESSMENT C00RD.) 1. RAC DIRECTS IN-PLANT RAD PRO SUPV. TO 05:30 77C CONTINGENCY MESSAGE FOR THE RAC TO TAKE FRYS EFFLUENT SAMPLE. 13:30 DIRECT THE IN-PLANT RAD PRO SUPV. TO 2. RAD PRO TECN. SAMPLES AND ANALYZES TAKE AM FRVS EFFLUENT SAMPLE. FRVS EFFLUENT. ql ERM 1. DECLARE A GENERAL EMERGENCY. 05:35 78C CONTINGENCY MESSAGE TO DECLARE A 2. IMPLEMENT ATTACHMENT 4. 13:35 GENERAL EMERGENCY BASED ON DEGRADAfl0N 3. IMPLEMENT EPIP 104H.(EPIP 401, APP.B) OF AT LEAST TWO FISSION PRODUCT 4. DEVELOPMENT OF A PAR. BARRIERS WITH POTENTIAL FOR THE THIRD
' AS A MINIMUM;
~
(FUEL CLAD). 5.2.24
J A2TIFICIAL ISLAND CMERGENCY PTEPA2EDNESS O MAJOR EVENTS TIMELING DRILL N8JMBER: H94-06 REAL DRILL EXPECTED ACTION EVENT RECEIVER TIME TIME MESSAGE
============ ============ ============ ================================= u =
SECTORS DISTANCE EVACUATE ALL 0 5 MILES EVACUATE W-WNW-WW 5-10 MILES ! SHELTER ALL REMAINING 5-10 mites SECTORS
- 1. OSC TEAM TO NOTIFY THE OSCC OF Jeg "B" EDG REPAIRS ARE COMPLETE AND IT IS OSC "8" EDG REPAIR TEAM I 14:11 06:11 79 COMPLETION.
READY AND AVAILABLE FOR RESTART.
- 2. OSCC TO INFORM SNSS THAT #8" EDG 15 I REPAIRED AND READY FOR START. i
- 3. CR CREW TO START "B" EDG.
- 1. NOTIFY THE RAC IN THE TSC OF THE 80 THIS MESSAGE PROVIDES THE RESULTS OF THE RP - INPLANT SUPERylSOR 14:15 06:15 RESULTS.
FRYS SAMPLE TAKEN AT T3:30. OSC TEAM 1. THE OSC TEAM INFORMS THE OSCC THAT 06:49 81 THE OSC TEAM MAS SUCCESSFULLY REPLACED 14:49 REPAIRS ARE COMPLETED. THE FAILED 8AILEY LOGIC CARD ASSOCIATED WITH 1SKNV-5018. CONTROL ROOM CREW 1. CONTROL ROOM CREW RECOGNIZES THAT THE 14:49 06:49 C1D DARK BOARD MESSAGE FOR CLOSURE OF ISKMv-5018 IS CLOSED. ISKMv-5018.
- 1. CHEM TECM DISCUSSES RESULTS WITH THE 15:00 07:00 82 THIS MESSAGE PROVIDES THE RESULTS OF THE CHEMISTRY TECM CONTROL POINT CHEMISTRY SUPERVISOR.
PASS SAMPLE TAKEN AT 12:45.
- 1. AFTER THE SWSS, EDO AND ERM AGREE SNSS 07:30 83 DRILL TERMINATION PAGE ANNOUNCEMENT.
15:30 THE PLANT IS STABLE AND THE PRIMARY LEAK IS ISOLATED (OR THE REACTOR IS DEPRESSURIZED), PEAD REFEREE WILL
" T'ERMINATE DRILL.
5.2.25 .
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i 1 H94-06 Rsv. 1 SECTION 5.3 . /N ARTIFICIAL ISLAND l (~) ANNUAL EXERCISE 1994 l I MAJOR OBSERVABLE ONSITE EVENTS NOTE:_ All references to CR response are actions observable in the Hope Creek Simulator at the Nuclear Training Center. 07:45 thru 08:30 o Shift personnel pre-drill briefing and review of initial conditions, both on-site and in the HC Simulator. o Review of player instructions (drillsmanship and safety concerns, extent of play are covered) o Referees post initial data displays in the Simulator and other ERFs where appropriate. o Referees are stationed at key locations to control player activities and response to early scenario events. CR Staff and shift personnel onsite are in position, on o watch. 08:30 thru 09:25 o Exercise begins. o CR response to loss of 480 VAC Unit Substation due to an electrical fault and subsequent fire. o CR response to a loss of Feedwater Heater string caused (r'N) by Sitedeenergization of a control Protection (Fire panel. response to combat the Brigade) o USS fire event. o Unusual Event declaration and notifications from the HC Simulator. o CR response to indications of a Recirculation Jet Pump Riser failure and loose parts alarm in the Reactor. 09:25 thru 10:30 o CR response to a Feedwater Heater NEO high level condition will be directed with failure to isolate remotely. to take local action to isolate. CR response to Main Turbine Vibrations as water from the o flooded feeawater heater impinges on the turbine blading, o CR response to Main Turbine Trip with rotating turbine blading failure and casing penetration causing loss of Rx Scram is condenser vacuum and MSIV closure. automatic and successful. o CR response to a complete loss of feedwater and condensate from a piping rupture at the Primary Condensate Pump suction. o NEO dispatched to the Turbine Building for damage assessment. o CR response and Fire Brigade dispatch to combat firas and control damage in the Turbine Bldg. o CR response to loss of 13.8 KV Bus Sections 2 & 8 with "B" 4160 VAC Vital Bus. ('N) \ , failure of fast transfer of 5.3.0
H94-06 R v. 1 ,,e"g 09:25 thru 10:30 (cont'd)
\- o CR response to failure of "B" EDG to start and continued loss of "B" Vital 4160 Bus.
o Alert declaration and notifications from the HC Simulator. o Emergency Response Organization (ERO) callout and activation of onsite emergency facilities (TSC, OSC, and control Point). Assembly of predesignated drill players only, o EOF and ENC begin staffing and facility setup in preparation for activation if needed, o ERF access control is established by security. 19: 30 thru 12:00 o CR response to indications of a small Reactor Coolant leak outside Primary Containment in the South Pipe Chase from checka valve crackedwillinstrumentation line. The close to automatically excess flow isolate the leak. o Emergency Coordinator (EC) turnover from SNSS to EDO, TSC activation. "B" Recirc Pump o CR response to a large break LOCA as Suction piping fails completely due to the impact of a loose part of the failed Jet Pump. o site Area Emergency declaration and notifications from the TSC. o Limited Accountability is performed (Hope Creek drill O o players only). OSC response team to investigate the failure of "D" LPCI Injection Valve (motor short circuit). o CR response to a failure of the Drywell Atmospheric Gaseous Radioactivity Monitoring Inboard Isolation Valves to close (electrically deenergized) RHR Pump which has o OSC response team to restore "A" tripped on overcurrent. o OSC response team to attempt manual closure of the failed open Drywell isolation valve. o CR and TSC technical support response to indications of ECCS Suction Strainer plugging in the Suppression Pool. o NRC Region I Incident Response Team arrives onsite and at the EOF to demonstrate co-location objectives. 12:00 thru 13:15 1 turnover from EDO to the ERM, o Emergency Coordinator (EC)ivation. EOF activation and ENC act o CR response to losses of both available ECCS pumps and i OSC response teams dispatched to troubleshoot,and restore operability o Fuel Damage indications are observed as RPV Water Level decreases below TAF. o Possible General Emergency declaration and PAR development based on EC judgment from the EOF. I 5.3.1
l H94-06 ! Rsv. 1 13:15 thru 14:00 (- ( ,) o Primary Containment is breached by the sudden failure of the Drywell Atmospheric Gaseous Radioactivity Monitoring Sample Line downstream of the failed open Drywell inboard isolation Radiological valve. Release to the environment begins through o the Rx Bldg. FRVS Vent path, o General Emergency declaration, if not done previously, PAR selection or upgrade, and notifications from the : EOF. o Onsite and offsite field monitoring teams begin tracking and sampling the plume. 14:00 thru 15:30 o CR response to the restoration EDGofare power to "B" 4160 VAC completed. , Bus when OSC repairs to "B" ' o OSC team repairs the failed power supply to the stuck open Drpell Atmospheric Gaseous Radioactivity Monitoring Inboard Isolation Valve which is closed, restoring Primary Containment. o Radiological release rates decrease at the FRVS Vent. o Head Referee will terminate the exercise with the concurrence of the NRC and FEMA Evaluation Team Leaders when the exercise objectives have been demonstrated. 15:30 thru 16:30 (~'g o ERFs are restored to pre-exercise conditions. o Facility critiques for players, referees and observers, (_j o Offsite Field Monitoring Teams return for debriefing and critiques. 1 i
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l 1 I l c:\pw\ scenario \5-3.94
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5.3.2
H94-06 Rev. O SECTION 5.4 ARTIFICIAL ISLAND ANNUAL EXERCISE 1994 ONSITE ACTUAL VS. SIMULATED EVENTS Actual.(Pagers
- 1. Callout of Emergency Response Plant PA and Personnel Manual Callout Actual
- 2. Activation of ERFs
- Actual ,
- 3. PASS Sampling and Analysis Actual
- 4. Emergency Notification '
- Actual (Offsite
- 5. Radiation Protection Measures Monitors will
& Dose Assessment not wear PCs)
Actual
- 6. Personnel Monitoring Onsite, Offsite Monitoring Actual ,
- 7. Inplant,
- 8. Non-essential Personnel Assembly & Simulated Site Evacuation Simulated ;
- 9. Owner Controlled Area Siren Activation Accountability Actual (Limited
- 10. to drill players only) i Access Control (TSC, EOF, & ENC) -Actual 11.
Simulated ;
- 12. Main Guard House Access Control Core Damage Estimation Actual l
- 13. .
i Demonstrating proficiency in donning SCBAs need only be
- NOTE: After initial demonstration, the players will "
performed once.not wear facepieces while in the field. O 5.4.0 c:\pw\ scenario \S-4.94 t 5
O ( ,/ SECTION 5.5 HOPE CREEK GRADED EXERCISE (H94-06) RADIOLOGICAL ASSUMPTIONS / CALCU j Public Service Electric and Gas designed a radiological transport program for HCGS to be used in developing scenarios for emergency drills. The l calculations and tables of specific information used by this program can be l found in the PSE&G HCGS Emergency The Preparedness Software - Module A Technical radiological assumptions used by this program ! Basis Manual (HCGSEPTBM). cre as follows: 5.5.1.1 Reactor Core and Clad Failure Inventory i The design basis core inventory assumes a 1000 day run time at 3485 associated corrosion and activation product inventories have been adjusted where applicable using the data and The information core from used inventory the HCin Core this program Damageare Assessment Procedure (HCCDAP). The clad failure inventory was displayed in Table 2-1 of the HCGSEPTBM. calculated using the HCCDAP and are also displayed in Table 2-1 of the HCGSEPTBM. 5.5.1.2 Reactor Coolant System (RCS) The Power Correction Factor uses the power operation history toA correction determine the effective full power days on the reactor core. factor for each isotope which is used in calculating the See actual Section core inventory 3.1.1 of available for release is produced by this calculation. the HCGSEPTBM for the calculations. The RCS Inventory is calculated based on the power operating history, the fuel damage postulated, the reactor coreSee inventory, section and then 3.1.2 of are the (_, decayed corrected for the time since reactor trip. HCGSEPTBM for the calculations. The RCS Concentration is converted to uCi/cc, volume corrected for and then combined to yield RCS concentration for the temperature and pressure, fuel damage postulated. See Section 3.1.3 of the HCGSEPTBM for the calculations. 5.5.1.3 Main Steam (MS) The MS isotopic activities are calculating using partition factors that are derived from the design basis accident analysis tables in Hope Creek FSAR Chapter 15. See Section 3.2 of the HCGSEPTBM for the MS calculations and Table 2-2 for the MS partition factors also in the HCGSEPTBM. 5.5.1.4 Torus Water Concentrations Torus water is maintained at a baseline concentration until a reactor trip or accident occurs. Steam may be discharged into the Torus during a reactor trip. The calculations used for this are found in Section 3.3.1 of the HCGSEPTBM. The Torus is used to depressurize the Drywell and RCS during accident situations. The calculations used for this are in Section 3.3.2 of the HCGSEPTBM. 5.5.1.5 Reactor Feedwater (RF) RF calculations are derived from the source term shielding tables located in Chapter 12 of the Hope Creek FSAR, which are based on partitions of the MS concentrations. The calculations used for this as well as the i f-partition factors are in Section 3.4 and Table 2-3 of the HCGSEPTBM. 5.5.0 i
l 5.5.1.6 Drywall Atmosphere - Normal (D/WA-N) j RCS leakage is partitioned to the atmosphere using tha informationThe D/WA-N is corrected ! and data in Chapters 6 and 15 of the Hope Creek FSAR.The source term used in this calculation l i for temperature and pressure.The calculation and partition factors are in Section l OtheRCSleakrate.3.5.1 and Tables 2-4 and 2-5 of the HCGSEPTBM. 1
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5.5.1.7 Reactor Building Atmosphere - Normal (RBA-N) i The D/W leakage into the Reactor Building is a pressure dependentThe R calculation. The data and parameters used in these calculations filters are in service. come from the Hope Creek FSAR Chapters 6 and 15. See Section 3.6.1 and Table 2-7 of the HCGSEPTBM for the calculations and FRVS Recirc Filter Factors. (S/ RWA-N) 5.5.1.8 Service /Radwaste Building Atmosphere - Normal The data and parameters used in the calculation come from the HopeThis calculation Creek FSAR Chapters 6,12,and 15. See Section 3.8.1 component leakage in the S/RW building as the source term. of the HCGSEPTBM for the calculations. 5.5.1.9 Radiation Monitoring System (RMS) The ARM's use both atmosphere concentrations and component radiation Monitor shine as the source terms for the monitor response calculations. response factors and shield factors , source are calculated geometry, andvalues monitor using isotopic response to mix, source location, source size The data and parameters used in the calculations come from combined sources. the Hope Creek RMS Manual, and the most the Hope Creek FSAR Chapter 15, See Sections current floor plan and equipment layout drawings of Hope Creek. The Duct Monitors use atmosphere concentrations, pre-filter or post filter, whichever is applicable, component radiation shine, and atmosphere radiation shine for the monitor response calculation values which use isotopic O mix, source location, source size, source geometry, and monitor. response to i combined sources. The data and parameters used in the cticulations come from~ Hope Creek RMS Manual, and the most current , Chapter 15 of the Hope Creek FSAR, See Sections 3.9.2.1 floor plan and equipment layout drawings of Hope Creek. through 3.9.2.18 of the HCGSEPTBM for the calculations. The Effluent Monitors use effluent stream concentrations, component radiation shine, and atmosphere radiation shine for the monitor response calculations. Monitor response factors and shield factors are calculated values which use isotopic mix, source location, source size, source geometry, The data effluent stream activity, and monitor response to combined sources. and FSAR, parameters used in the calculations are from chapter 15 HCGSEPTBM for the calculations. The shine, Process Monitors use system concentrations, component rad Monitor response factors and shield factors are calculated values which use isotopic mix, source location, source size, source geometry, The data system stream and parameters activity, and monitor response to combined sources. used in the calculations come from Chapter 15 of the Hope Creek FSAR, The Hope Creek RMS Manual, and the most current floor plan and equipment layout . the calculations. 5.5.1.10 Sample and Dose Rate Calculations The Sample and Dose rate calculations use the system effluent streamThe sample geometry, and/or atmosphere concentrations as the source term.and isotopic mix are the parameters u distance, counting instrument, HCGSEPTBM for the calculations. 5.5.1
~' -- _ _
5.5.1.11 Plums Data Module B Plumn
.The Emergency Preparedness Scenario Ganerator-(EPSG)
Program, is designed to generate offsite dose assessment scenario data for ! HCGS. The software utilizes an A+ atmospheric dispersion model in all X/Q calculations. Dose assessment calculations are performed Version utilizing the The g 3.1 (11/89). i f information and data from the HCGS EPSG - Module A, l guidance and equations utilized in the software come from the following l l references: (2/83) " Atmospheric U.S. Nuclear Regulatory Commission, Reg. Guide 1.145 Dispersi l Power Plants". D. Bruce Turner, " Workbook for Atmospheric Dispersion Estim Park, N.C. Rev. 1970. I I NUREG/CR-3365 " Report to the NRC on Guidance for Pre contains , Section 3.0 of the Technical Basis Manual, HCGS EPSG - Module B, ' the actual equations utilized in the software. ! Additional guidance for the data generated for this exercise came from: I EPA 400-R-92-001, Manual Of Protective Action Guides And Protective Actions . For Nuclear Incidents ' PLG's Meteorological Incident Dose Assessment System (MIDAS) dose assessment computer program. O .
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i f i I i O ; 5.5.2 r i
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I l 5.5.2.0 Specific Radiological Assumptions for the Hopo Crotk Graded Excroico are as follows: 5.5.2.1 Reactor Building Atmosphere - Large Break Loss Of Coolant Accident , l (RX. BLDG-LBLOCA) O The Rx. Bldg. Atmosphere Concentration is determined by two sepa I calculations.The first equation uses the break flow rate for the first pipe break. The second equation uses the make up flow rate for the four minutes. ! remaining time. RCS activity is partitioned to the atmosphere using theBldg. ' The Rx. information and data in the Hope Creek FSAR Chapters 6 and 15.The calculations atmosphere data is corrected for temperature and pressure. Tables 2-4 and 2-7 used as well as the partition factors are in Section 3.6.2, of the HCGSEPTBM. 5.5.2.2 Accident Type and
Description:
The Main Turbine will be tripped and the One 09:47 (Real Time) 01:47 (Drill Time) Reactor will be Scrammed a high vibration condition on the Main Turbine.This leads to minute after this blades will penetrate the Main Turbine casing. Pump suction header.
"B" Reactor Recire Pump. Suction Piping 11:35 (Real Time) 03:35 (Drill Time) TheThis will also lead to the uncovering of will experience an unisolable failure.
active fuel causing 80% clad damage and 50% fuel melt. 13:15 (Real Time) 05:15 (Drill Time) A radiological release to the atmosphere via the FRVS will occur. The release will be monitored and filtered. The radiological release will be isolated 15:00 (Real Time) 07:00 (Drill Time) O and FRVS will show a trending downward from this point until the term the exercise. O I 5.5.3 J 1
j Section 5.6
/ ~
LOMPARISON OF SCENARIO EVENTS VERBUS INDUSTRY EVENT Industry Event Scenario Event Grand Gulf 1 Jet Pump Failure Jet Pump Riser. Failure on 9-13-93, (OE-6285). Calvert Cliffs Rx Trip due to Feedwater Heater High Level High level on 6-11-93. Hope Creek Pothead Failure on Ring Bus Damage, 13.8 KV 5-13-93, (LER# 93-003-00). Susquehanna 1 Loss of 2 Buckets Main Turbine High Vibrations on 7-12-93, (OE-6205).
& Failure.
Fermi 2 Turbine Failure with casing penetration on 12-25-93, ["h (,.,/ (SEN107). Salem 2 Overspeed Turbine Failure with casing penetration on 11-9-91, (AIT 50-311/91-81). Vital Bus 4160 Breaker St. Lucie Breaker Failure on "B" 4-18-90, (OE-4020). Failure Shearon Harris Loss of Vital l Bus on 5-23-93, (OE-5986). l l l ECCS Pump Suction Strainer Perry Inspection Findings on l i 5-22-93, (OE-6023). j Fouling. Barsbeck 2 (Sweie n '- findings on ' 7-28-92. . l
<~ l l \
V 5.6.0
l l H94-06 ; I R0v. O SECTION 6.0 ('~) 1 (m,/ ARTIFICIAL ISLAND ANNUAL EXERCISE 1994 l MESSAGE FORMS NOTES: 1. The messages contained in this section are for Referee / Evaluator information only. The messages that are handed out to the players during the exercise will be on YTLLOW paper and will not include REFEREE NOTES or EXPECTED ACTIONS.
- 2. The page numbers in this section correspond to thein chronological message order asnumber which they will beare cenerally(Occasionally messages are issued.
issued simultaneously at different locations) Section 5.2, Scenario Timeline, may be used as an index 3. for all message forms contained in this section. Some message numbers are not used (skipped) due to revisions of the scenario. effective pages forRefer thistosection. Section 5.2 as a list of )
- 4. Special codes / message designators.
C - Contingency Message. Issued as needed to maintain (/)
,/ the overall scenario timeline or to ensure a specific planned activity is performed for the purpose of demonstrating an objective.
NOTE: Some Contingency Messages are planned primarily to coordinate the dispatch of site personnel by the Control Room Staff from theSimulator in a limited number of OSC Referees. (Scenario control) Event Classification Contingency Messages should not be handed out without the Head Referee's permission. If a Contincency Message is issued,_ the facility Lead Referee Evaluator will note is aware thepurpose of its reason and ensure as soon asthe NRC practical after it is issued. D - Dark Board Message. May not be issued unless needed to support Simulator indications and annunciators. Should be issued if Simulation is FRO 3EN or Information unavailable at time of exercise. contained in MESSAGE section conveys in abbreviated form what the player would have seen or heard if the Simulator were fully operational. l (~% \ Q 6.0.0
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 08:00
. MESSAGE #: 01 DRILL TIME : 00:00 TO : HOPE CREEK SHIFT PERSONNEL ;
FROM : HEAD REFEREE / SIMULATOR REFEREE LOCATION : HOPE CREEK TSC / HC SIMULATOR MESSAGE : THE ATTACHED INFORMATION ARE THE INITIAL CONDITIONS FOR THE D THEY ARE FOR YOUR REFERENCE NOW AND AS NEEDED DURING THE DRI WE WILL REVIEW THEM AT THIS TIME AND IF THERE ARE ANY QUESTIONS, PLEASE ASK FOR CLARIFICATIONS. 4
- THIS IS DRILL !!!********************************
*********************************A I!! * '
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS FN REFEREE NOTES :
V 1. 2. PROVIDE A REVIEW OF THE INITIAL CONDITIONS. ENSURE THAT ALL PARTICIPANTS ARE IDENTIFIED. SCOPE, AND OBJECTIVES OF
- 3. REVIEW SIGNIFICANT PLAYER INSTRUCTIONS, TODAY'S DRILL AS NEEDED.
EXPECTED ACTIONS :
- 1. LEAD REFEREE WILL HOLD AN INITIAL CONDITIONS BRIEFING FOR ALL DRILL PLAYERS.
- 2. ENSURE KEY PLAYERS AND REFEREES ARE AVAILABLE TO START THE DRILL. >
6.01
(h O t ARTIFICIAL ISLAND ANNUAL GRADED EXERCISE , OCTOBER 25, 1994 INITIAL _ONDITIONS:. C Salem 1 is currently at 100% power. Salam 2 is currently at 85% Power, with power ascension in progress following repairs to the #21 Main Feed Pump. Core, with a Hope Creek is at 95% Power, End of Life (EOL)ine for the past coastdown in progress. The unit has been on l 9 months. All Major Equipment is operable with the following exceptions: is Cleared and Tagged to replace "B" CRD Pump (1B-P-2 07) the pump motor, which failed during the night shift. Repairs are expected to be completed on the day shift tomorrow.
] "A" Core spray Loop is cleared and Tagged for a scheduled preventative maintenance outage. Tech spec LCO 3.5.1 was entered at 0607 yesterday morning, October 24. Work is in progress and should be completed by the end of swing shift tomorrow.
is Cleared and Tagged to replace "C" SACS Pump (1C-P-210) its Motor Breaker. Tech Spec LCO 3.7.1.1 was entered at 0543 this morning. Work is expected to be completed by swing shift today. Reactor Coolant System (RCS) chemical sample analysis indicates several fuel pins are leaking, causing a minor increase in Reactor Coolant Activity. The leakage started one month ago and the Nuclear FuelsThe Group estimates leaking approximately fuel pins are 0.01% clad defects currently. suspected to be manufacturing imperfections and will be replaced during the upcoming Refuel Outage. RCS activity is still well below Tech Spec Limits. O 6.01a
i f ARTIFICIAL ISLAND j EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 08:20 5 MESSAGE #: 02 DRILL TIME : 00:20 L TO : SNSS (HOPE CREEK) FROM : CONTROL ROOM DRILL CONTROLLER LOCATION : CONTROL ROOM (HOPE CREEK) MESSAGE : Please make the following page announcement: ;
" ATTENTION ALL PERSONNEL. ATTENTION ALL PERSONNEL", ;
"AN EMERGENCY PLAN DRILL WILL BE HELD TODAY AT HOPE CREEK i '
COMMENCING AT 08:30."
"ONLY DESIGNATED DRILL PARTICIPANTS ARE REQUIRED TO RESPON TO DRILL MESSAGES AND ANNOUNCEMENTS. ALL OTHER PERSONNEL CONTINUE WITH THEIR NORMAL WORK FUNCTIONS."
"THIS IS A DRILL. THIS IS A DRILL."
Please repeat message one time.
*******************************IS
- THIS A DRILL !!! !!!
- l
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS !
********************************************************************** i REFEREE NOTES :
O
- 1. PROVIDE THIS MESSAGE TO THE SNSS.
- 2. CONTACT THE LEAD REFEREE AT THE HOPE CREEK TSC TO ESTABLISHl CONTROLLER PHONE NUMBERS TO BE USED THROUGHOUT THE DRILL CONFIRM NO OPERATIONAL PROBLEMS THAT :
& SYNCHRONIZE WATCHES.
WOULD POSTPONE THE START OF THE DRILL.
- 3. INFORM THE SNSS THAT A PASS SAMPLE WILL BE TAKEN DURING FROM THE RHR SYSTEM.
EXPECTED ACTIONS :
- 1. HOPE CREEK CONTROL ROOM IS AWARE l OF THE DRILL. I
- 2. DRILL CONTROLLERS ARE READY TO START THE DRILL.
6.02 I I I l
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 08:33 MESSAGE #: 03D DRILL TIME : 00:33 , TO : CONTROL ROOM STAFF FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : YOU HAVE JUST RECEIVED THE FOLLOWING ALARMS: (OVERHEAD E3-F3) USS FEEDER BRKR TRBL (OVERHEAD E3-F2) 4.16 KV FDR TO USS XFMR BRKR MALF (OVERHEAD'A2-A5) FIRE PROT PANEL 10C671 (OVERHEAD A7-E2) FEEDWATER HEATER TRIP (OVERHEAD A7-F2) ' FEEDWATER HEATER PNL 1A/B/C C102 (OVERHEAD Cl-D4) REACTOR RECIRC A TROUBLE (OVERHEAD C8-F4) TURBINE SEALING STM TROUBLE (OVERHEAD ES-F1)- CHILLED WTR SYSTEM TROUBLE (OVERHEAD E3-A1) STA SERVICE TRANSFORMER 1AX502 TRBL (OVERHEAD E3-A4) STA SERVICE TRANSFORMER 1BX502 TRBL (OVERHEAD E3-B1) STA SERVICE TRANSFORMER 1AX501 TRBL (OVERHEAD E3-B4) STA SERVICE TRANSFORMER 1BX501 TRBL (OVERHEAD E5-F5) TURB BLDG HVAC PANEL TROUBLE
******************************IS
- THIS A DRILL !!) !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS REFEREE NOTES : !
- 1. MESSAGE FOR DARK BOARD CONTROL ONLY.
- 2. ENSURE NCO RESPONDS TO ALARMS APPROPRIATELY. .
- 3. THIS IS TIME CRITICAL TO THE SCENARIO TIMELINE. l
- 4. LOSS OF THE 10-B-130 UNIT SUBSTATION IS A PREREQUISITE CONDIT !
FOR THE MAIN TURBINE FAILURE THAT OCCURS AT 09:47. t I EXPECTED ACTIONS :
- 1. CREW RECOGNIZES THAT 10-B-130 HAS BEEN LOST AND STABILIZES PLANT.
- 2. CREW RECOGNIZES THE PRESENCE OF A t FIRE, REFERS TO FIRE RESPONSE MANUAL AND DISPATCHES THE FIRE BRIGADE.
"B"
- 3. NSS RECOGNIZES LOSS OF THE FEEDWATER HEATER STRING AND REFERS TO OP-AB.ZZ-0118, LOSS OF FEEDWATER HEATERS AND OP-AB.ZZ-0204, POSITIVE REACTIVITY ADDITION.
6.03D F O
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 08:33 MESSAGE #: 04 DRILL TIME : 00:33 , TO : CONTROL ROOM STAFF FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : : YOU HAVE JUST RECEIVED THE FOLLOWING FIRE ALARM AT 08:33 '
'"1B26, FIRE TURBINE BLDG, ELEV 120', ELECTRICAL EQUIPMENT MEZZ AREA, ROOM 1401".
i
*************************THIS IS A DRILL !!! !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL **********
PLANT OPERATIO REFEREE NOTES : O (REFER
- 1. TO SUPPLEMENTAL SCENARIO #7.01) ISSUE T OVERHEAD ALARM A2-A5, " FIRE PROT PANEL 10C671 TROUBLE"
- 2. THIS IS TIME CRITICAL TO THE SCENARIO TIMELINE.
EXPECTED ACTIONS :
- 1. CREW RECOGNIZES THAT A FIRE HAS STARTED IN THE TURBINE BUILDING, t l
ELEVATION 120'.
- 2. SNES CONTACTS FIRE PROTECTION TO RESPOND.
- 3. NSS REFERS TO PREFIRE PLAN FRH-II-452 (TURBINE BUILDING, r ELEVATION 120')
- 4. SNSS NOTIFIES RAD PRO AND SECURITY TO SUPPORT SITE PROTECTION. ,
B 6.04 i O i
l 1 ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 08:33 04D (O/ MESSAGE #: TO : CONTROL ROOM STAFF DRILL TIME : 00:33 FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : YOU HAVE JUST RECEIVED-THE FOLLOWING ALARMS AND INDICATIONS: ALARMS: (CRIDS POINT D5608) CHW PUMP A MALFUNCTION (CRIDS POINT D257S) FW HTR TRAIN B RCP BC102 TROUBLE (CRIDS POINT D2988) FEEDWATER HEATER B2E104 LEVEL (CRIDS POINT D2991) FEEDWATER HEATER B1E103 LEVEL FEEDWATER HEATER BE106 LEVEL (CRIDS POINT D2997) FEEDWATER HEATER B3E103 LEVEL (CRIDS POINT D2994) TB M-G SET HVAC RCP OC184 (CRIDS POINT D3610) INDICATIONS:
"B" FEEDWATER HEATER STRING HAS TRIPPED.
THE GREEN " TRIP" LIGHT FOR THE 10-B-130 IS FLASHING. AUDIBLE ALARM FROM FIRE PROTECTION PANEL 10C671. > LOSS OF POWER TO SEVERAL FWH ISOLATION VLVS (SEE LOAD LIST
*********************************A
- THIS IS DRILL !!! !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS REFEREE NOTES :
- 1. MESSAGE FOR DARK BOARD CONTROL ONLY.
- 2. ENSURE NCO RESPONDS TO ALARMS APPROPRIATELY. ,
- 3. THIS IS TIME CRITICAL TO THE SCENARIO TIMELINE.
- 4. LOSS OF THE 10-B-130 UNIT SUBSTATION IS A PREREQUISITE CONDITION FOR THE MAIN TURBINE FAILURE THAT OCCURS AT 09:47.
EXPECTED ACTIONS :
- 1. CREW RECOGNIZES THAT 10-B-130 HAS BEEN LOST AND STABILIZES PLANT. j
- 2. CREW RECOGNIZES THE PRESENCE OF A '
FIRE, REFERS TO FIRE RESPONSE MANUAL ! AND DISPATCHES THE FIRE BRIGADE.
- 3. NSS RECOGNIZES LOSS OF THE "B"
FEEDWATER HEATER STRING AND REFERS TO OP-AB.ZZ-0118, LOSS OF FEEDWATER HEATERS AND OP-AB.ZZ-0204, POSITIVE REACTIVITY ADDITION. 6.04D
.-__e
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 08:36 MESSAGE #: 05 DRILL TIME : 00:36 TO : EQUIPMENT OPERATOR FROM : IN PLANT REFEREE LOCATION : TURBINE BUILDING, ELEVATION 120' MESSAGE : IN THE TURBINE BUILDING, YOU OBSERVE THAT VARIOUS LIGHTS ARE OUT. TURBINE BUILDING, ELEVATION 120', ELECTRICAL SWITCHGEAR AREA IS FILLED k(TH SMOKE. UNIT SUBSTAi' ION 10-B-130 IS ON FIRE AN ORANGE GLOW IS VISIBLE AT FLOOR LEVEL OF THE UNIT S THE FIRE IS CONFINED TO THE UNIT SUBSTATION AND IS NOT S TO OTHER PLANT EQUIPMENT.
*************************THIS IS A DRILL !!! !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIO O REFEREE NOTES :
C (REFER TO SUPPLEMENTAL SCENARIO #7.01) ISSUE TH 1.
- 2. ENSURE THE OPERATOR UNDERSTANDS THAT SOME LIGHTING H
- 3. ENSURE THAT THE EQUIPMENT OPERATOR UNDERSTANDS THA LIMITED ONLY TO THE 10-B-130 UNIT SUBSTATION. (SIMULATOR)
- 4. ENSURE THE EQUIPMENT OPERATOR NOTIFIES THE CONTROL ROOM OF THE STATUS OF 10-B-130.
- 5. USE DID PHONE EXTENSION 3339 OR RADIO TO CONTACT THE EXPECTED ACTIONS :
- 1. THE EQUIPMENT OPERATOR ACKNOWLEDGES THE PRESENCE OF A FIRE ON THE 10-B-130 UNIT SUBSTATION.
- 2. EQUIPMENT OPERATOR VERIFIES THAT THE UNIT SUBSTATION IS DEENERGIZED PRIOR TO ATTEMPTING ANY FIRE FIGHTING ACTIVITES.
- 3. EQUIPMENT OPERATOR MAY OBTAIN PORTABLE CO2 FIRE EXTINGUISHERS TO COMBAT THE FIRE.
- 4. EQUIPMENT OPERATOR AWAITS ARRIVAL OF THE FIRE BRIGADE.
6.05 O
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM I REAL TIME : 08:36 ! k.,/ MESSAGE #: 05C DRILL TIME : 00:36
- CONTROL ROOM STAFF l TO FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK)
MESSAGE : THIS IS A CONTINGENCY MESSAGE: YOU SHOULD DISPATCH AN EQUIPMENT OPERATOR AND/OR THE BRIGADE TO RESPOND TO THE FIRE ALARM.
*************************THIS IS A DRILL !!! !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS
('^) REFEREE NOTES : V (REFER TO SUPPLEMENTAL SCENARIO #7.01) 1. DELIVER THIS MESSAGE ONLY IF IT APPEAR BRIGADE REGARDING THE FIRE ON THE 10-B-130 UNIT SUBSTATION
- 2. THIS IS CRITICAL TO THE DRILL TIMELINE.
EXPECTED ACTIONS :
- 1. THE SNSS/NSS REFERS TO THE FIRE PROTECTION ALARM RESPONSE PROCEDURE AND DISPATCHES AN EQUIPMENT OPERATOR AND THE FIRE BRIGADE TO RESPOND.
6.05C s_- 1 l l l 1
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 08:38
) MESSAGE #: 06 DRILL TIME : 00:38 ~
TO : FIRE BRIGADE TEAM LEADER FROM : IN PLANT REFEREE LOCATION : TURBINE BUILDING, ELEVATION 120' MESSAGE : IN THE TURBINE BUILDING, YOU OBSERVE THAT VARIOUS LIGHTS ARE OUT. TURBINE BUILDING, ELEVATION 120', ELECTRICAL SWITCHGEAR AREA IS FILLED WITH SMOKE. UNIT SUBSTATION 10-B-130 IS ON FIRE AN ORANGE GLOW IS VISIBLE AT FLOOR LEVEL OF THE UNIT SUBSTAT THE FIRE IS CONFINED TO THE UNIT SUBSTATION AND IS NOT SPREAD TO OTHER PLANT EQUIPMENT.
*********************************A
- THIS IS DRILL !!! !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS (3 REFEREE NOTES :
Q (REFER TO SUPPLEMENTAL SCENARIO #7.01) ISSUE THIS 1.
- 2. ENSURE PLAYERS UNDERSTAND THAT SOME LIGHTING HAS BEEN LOST.
- 3. ENSURE THAT THE FIRE BRIGADE UNDERSTANDS THAT THE FIRE IS LIM ONLY TO THE 10-B-130 UNIT SUBSTATION.
- 4. ENSURE THE FIRE BRIGADE DEMONSTRATES APPROPRIATE FIRE FIGHT TECHNIQUES AND RADIOLOGICAL CONCERNS.
- 5. USE DID PHONE EXTENSION 3339 OR RADIO TO CONTACT THE CONTRO EXPECTED ACTIONS :
- 1. THE FIRE BRIGADE ACKNOWLEDGES THE PRESENCE OF A FIRE ON THE 10-B-130 UNIT SUBSTATION ONLY.
- 2. FIRE BRIGADE LEADER VERIFIES THAT THE UNIT SUBSTATION IS DEENERGIZED PRIOR TO COMMENCING FIRE FIGHTING ACTIVITES.
- 3. FIRE BRIGADE MEMBERS OBTAIN PORTABLE CO2 FIRE EXTINGUISHERS TO COMBAT THE FIRE.
6.06 O
l l 1 ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM I b y MESSAGE #: 06C REAL TIME : DRILL TIME : 08:39 00:39 TO : CONTROL ROOM STAFF FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : THIS IS A CONTINGENCY MESSAGE:
"B" FEEDWATER YOU SHOULD DISPATCH AN EQUIPMENT OPERATOR TO THE HEATER CONTROL PANEL, 1B-C-102, TO INVESTIGATE THE LOSS OF THE "B" FEEDWATER HEATER STRING.
I 1 l l
- THIS IS A DRILL
- l l
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS !!!
********************************************************************** l REFEREE NOTES : !
( (REFER TO SUPPLEMENTAL SCENARIO #7.01)
- 1. DELIVER THIS MESSAGE ONLY IF IT APPEARS LIKELY THAT THE"B" SNSS/NSS l
IS NOT GOING TO DISPATCH AN-EQUIPMENT OPERATOR TO THE FEEDWATER HEATER CONTROL PANEL. l I i EXPECTED ACTIONS :. l
- 1. THE CREW DISPATCHES AN EQUIPMENT j OPERATOR TO THE "B" FEEDWATER HEATER CONTROL PANEL.
i i 6.06C l O V l
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 08:40 MESSAGE #: 07
TO : EQUIPMENT OPERATOR DRILL TIME : 00:40 FROM : IN PLANT REFEREE LOCATION : TURBINE BUILDING, ELEVATION 81' MESSAGE :
IN THE TURBINE BUILDING, YOU OBSERVE THAT VARIOUS LIGHTS ARE OUT. AT THE "B" FEEDWATER HEATER CONTROL PANEL (1B-C-102), YOU OBSERVE THE FOLLOWING ALARMS AND INDICATIONS: ALARMS: INSTRUMENT MODULE LOSS OF POWER (ALARM 1-2) POWER SUPPLY FAILURE (ALARM 1-3) 24 VAC LOSS OF POWER TO REPEAT RELAYS (ALARM 2-3) INDICATIONS:
"B" FEEDWATER HEATER LEVELS DO NOT APPEAR TO BE CHANGING.
ALL PANEL INDICATIONS APPEAR TO BE DEENERGIZED.
- THIS IS A DRILL *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS If!
( REFEREE NOTES : e \ (REFER TO SUPPLEMENTAL SCENARIO #7.01)
- 1. ISSUE THIS MESSAGE TO THE EQUIPMENT OPERATOR AFTER ARRIVING AT THE CONTROL PANEL AND SURVEYING THE INDICATIONS.
- 2. USE DID PHONE EXTENSION 3339 OR RADIO TO CONTACT THE CONTROL ROOM (SIMULATOR).
- 3. ALL VERBAL COMMUNICATIONS MUST START WITH "THIS IS A DRILL".
- 4. ENSURE THE OPERATOR UNDERSTANDS THAT SOME LIGHTING HAS BEEN LOST.
EXPECTED ACTIONS :
- 1. THE EQUIPMENT OPERATOR ACKNOWLEDGES THE INDICATIONS AT THE "B" FEEDWATER HEATER CONTROL PANEL AND NOTIFIES THE CONTROL ROOM CREW.
6.07 m v
ARTIFICIAL ISLAND . EMERGENCY PREPAREDNESS MESSAGE FORM $ REAL TIME : '08:41.
-MESSAGE #: 07C.. DRILL TIME : 00:41 :
TO- : SNSS/NSS . I FROM : SIMULATOR REFEREE LOCATION :. SIMULATOR (HOPE CREEK) MESSAGE : THIS IS A CONTINGENCY MESSAGE. . FOR SCENARIO CONTROL, DO NOT SCRAM THE REACTOR AT THIS TIME. . P h 6
******************************IS
- THIS A DRILL !!1 !!! -*
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS
********************************************************************** l REFEREE NOTES :
.l
- 1. DELIVER THIS MESSAGE ONLY IF IT APPEARS LIKELY THAT THE SNSS/'
IS ABOUT TO ORDER A MANUAL SCRAM OF THE UNIT.
- 2. THE INITIAL POSITIVE REACTIVITY TRANSIENT FROM THE LOSS OF THE '
"B" FEEDWATER HEATER STRING CAUSES LPRM UPSCALE ALARMS TO ILLUMINATE ON THE FULL CORE DISPLAY.
- 3. THIS IS CRITICAL TO THE DRILL TIMELINE. -
- 4. THE STUFF SHEET IS USED TO INSERT CONTROL RODS.
EXPECTED ACTIONS :
- 1. THE SNSS/NSS DOES NOT SCRAM THE REACTOR.
- 2. THE NSS ORDERS CONTROL RODS BE :
INSERTED PER THE STUFF SHEET TO CLEAR THE LPRM UPSCALE ALARMS. I 6.07C O
l ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM (h 08 REAL TIME : 08:42 (_) MESSAGE #: TO : EQUIPMENT OPERATOR DRILL TIME : 00:42 FROM : IN PLANT REFEREE LOCATION : TURBINE BUILDING, ELEVATION 171' MESSAGE : IN THE TURBINE BUILDING, YOU OBSERVE THAT VARIOUS LIGHTS ARE OUT. l AT THE "A" TURBINE BUILDING CHILLED WATER CIRC WATER PUMP REMOTE i PANEL (10-C-152), YOU OBSERVE THE FOLLOWING ALARM: l CHILLED WATER CIRC PUMP AP161 DISCH HI/LO FLOW FAHL-9487A2 l FAHL-9487A2 (ALARM C-1) AT THE "A" TURBINE BUILDING CHILLED WATER CIRC WATER PUMP (1A-P-161), ; YOU OBSERVE THE FOLLOWING: i THE "A" CIRC WATER PUMP IS NOT RUNNING. AT THE "B" TURBINE BUILDING CHILLER (1B-K-111), YOU dBSERVE THAT THE CHILLER IS NOT RUNNING.
- THIS IS A DRILL !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS REFEREE NOTES :
(~S (-) (REFER TO SUPPLEMENTAL SCENARIO #7.01)
- 1. ISSUE THIS MESSAGE WHEN THE OPERATOR ARRIVES AT THE 10-C-152 PANEL, LOCATED ON ELEVATION 171' OF THE TURBINE BUILDING.
"A" TURBINE BUILDING
- 2. ENSURE THAT THE OPERATOR UNDERSTANDS THAT THE CHILLED WATER CIRC WATER PUMP HAS TRIPPED.
- 3. USE DID PHONE EXTENSION 3339 TO CONTACT CONTROL ROOM (SIMULATOR).
- 4. ALL VERBAL COMMUNICATIONS MUST START WITH "THIS IS A DRILL".
- 5. ENSURE OPERATOR UNDERSTANDS THAT SOME LIGHTING IS EXTINGUISHED.
EXPECTED ACTIONS : '
- 1. THE OPERATOR DISPATCHED TO THE CHECK OUT THE STATUS OF THE TURBINE BUILDING CHILLED WATER SYSTEM ACKNOWLEDGES THAT THE "A" CHILLED l
WATER CIRC WATER PUMP HAS TRIPPED. ' l
- 2. THE OPERATOR PROVIDES THE INFORMATION l TO THE CONTROL ROOM (SIMULATOR) '
USING DID PHONE EXTENSION 3339. 6.08
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 08:42 MESSAGE #: OSC DRILL TIME : 00:42 TO : FIRE BRIGADE TEAM LEADER ^ FROM : IN PLANT REFEREE LOCATION : TURBINE BUILDING, ELEVATION 120' MESSAGE : THIS IS A CONTINGENCY MESSAGE YOU SHOULD REQUEST THE CONTROL ROOM TO WITH ALL. CONTROL ENSURE POWER THAT THE 10-B REMOVED. UNIT SUBSTATION IS DEENERGIZED,
- THIS A DRILL !!!********************************
******************************IS !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT *****************
OPERATIONS ("N REFEREE NOTES : i > (REFER TO SUPPLEMENTAL SCENARIO #7.01) ISSUE THIS 1. EQUIPMENT OPERATOR DO NOT REALIZE THAT THE 125 VDC CONTROL IS STILL AVAILABLE TO THE 10-B-130.
- 2. FIRE FIGHTING EFFORTS SHOULD NOT COMMENCE UNTIL CONTROL POWE BEEN REMOVED FROM THE UNIT SUBSTATION.
1 i EXPECTED ACTIONS :
- 1. THE FIRE BRIGADE TEAM LEADER REQUEST THE CONTROL ROOM TO DISPATCH .
AN OPERATOR TO REMOVE 125 VDC CONTROL POWER FROM THE 10-B-130 UNIT SUBSTATION. ! 6.08C O
ARTIFICIAL ISLAND l EMERGENCY PREPAREDNESS MESSAGE FORM f') REAL TIME : 08:45 MESSAGE #: 09 ( '/
~
- EQUIPMENT OPERATOR DRILL TIME : 00:45 TO FROM : IN PLANT REFEREE LOCATION : TURBINE BUILDING, ELEVATION 123' MESSAGE :
AT NON 1E 125 VDC DISTRIBUTION PANEL 1C-D-318, YOU HAVE SUCCESSFULLY OPENED BREAKER #4, NORMAL 125 VDC CONTROL POWER TO 10-B-130 UNIT SUBSTATION. AT NON 1E 125 VDC DISTRIBUTION PANEL 1D-D-318, YOU HAVE SUCCESSFULLY OPENED BREAKER #6, ALTERNATE 125 VDC CONTROL POWER TO 10-B-130 UNIT SUBSTATION.
*************************************ILL
- THIS IS A DR !!!
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS g'N REFEREE NOTES :
Q (REFER TO SUPPLEMENTAL SCENARIO #7.01)
- 1. ISSUE THIS MESSAGE WHEN THE EQUIPMENT OPERATOR HAS CORRECTLY SIMULATED OPENING BREAKER #4 IN 1C-D-318 AND BREAKER #6 IN 1D-D-318
- 2. DO NOT OPEN EITHER DISTRIBUTION PANEL (SIMULATE).
- 3. ENSURE THE EQUIPMENT OPERATOR PROMPTLY PROVIDES THE INFORMATION TO THE CONTROL ROOM USING DID PHONE EXTENSION 3339.
- 4. ALL VERBAL COMMUNICATIONS MUST START WITH "THIS IS A DRILL".
EXPECTED ACTIONS :
- 1. THE EQUIPMENT OPERATOR CORRECTLY SIMULATES OPENING THE 125VDC CONTROL POWER BREAKERS TO THE 10-B-13C UNIT SUBSTATION AND NOTIFIES THE MAIN CONTROL ROOM.
6.09 O v
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 08:45 MESSAGE #: 09C
- CONTROL ROOM STAFF DRILL TIME : 00:45 TO FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK)
MESSAGS : THIS IS A CONTINGENCY MESSAGE: YOU SHOULD NOTIFY THE SHIFT CHEMISTRY TECHNICIAN TO OBTAIN A REACTOR COOLANT SAMPLE AS REQUIRED BY TECH SPEC 3.4.5.C FOLLOWING A REACTOR POWER CHANGE OF GREATER THAN 15 % IN ONE HOUR.
- THIS IS A DRILL !!! !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS REFEREE NOTES :
- 1. DELIVER THIS MESSAGE ONLY IF IT APPEARS LIKELY THAT THE SNSS/NSS IS NOT GOING TO CONTACT THE SHIFT CHEMISTRY TECHNICIAN TO REQUEST A REACTOR COOLANT SAMPLE BE TAKEN.
- 2. THIS MESSAGE IS NOT TIME CRITICAL TO THE DRILL TIMELINE.
EXPECTED ACTIONS :
- 1. THE CREW CONTACTS THE SHIFT CHEMISTRY '
TECHNICIAN TO OBTAIN THE REQUIRED REACTOR COOLA1,T SAMPLE IN ACCORDANCE WITH TECH SPEC REQUIREMENTS. , f 6.09C O .
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM
- c. REAL TIME : 08:45 MESSAGE #: 09D
(' ') TO : CONTROL ROOM STAFF DRILL TIME : 00:45 FROM : SIMULATOR REFEREE LOCATION : SIMUALTOR (HOPE CREEK) MESSAGE : YOU HAVE JUST RECEIVED THE FOLT.OWING INDICATIONS: THE FLASHING " GREEN" TRIP LIGHT ON THE BEZEL FOR THE 10-B-130 UNIT SUBSTATION EXTINGUISHES. THE AMBER INOP LIGHT ON THE BEZEL FOR THE 10-B-130 UNIT SUBSTATION TLLUMINATES.
- THIS IS A DRILL !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS REFEREE NOTES :
(; , 'R TO SUPPLEMENTAL SCENARIO #7.01) b 1. SSAGE FOR DARK BOARD CONTROL ONLY.
- 2. ENSURE NCO RESPONDS TO ALARMS APPROPRIATELY.
EXPECTED ACTIONS :
- 1. THE CREW RECOGNIZES THAT THE EQUIPMENT OPERATOR HAS SUCCESSFULLY REMOVED 125 VDC CONTROL POWER FROM THE 10-B-130 UNIT SUBSTATION.
- 2. THE SNSS/NSS NOTIFIES THE FIRE BRIGADE TEAM LEADER THAT 125 VDC CONTROL POWER HAS BEEN REMOVED FROM THE UNIT SUBSTATION.
6.09D 1 ~> 1 4
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 08:50 b(y MESSAGE #: 10 DRILL TIME : 00:50 TO : EQUIPMENT OPERATOR FROM : IN PLANT REFEREE LOCATION : TURBINE BUILDING, ELEVATION 171', PANEL 10-C-184 MESSAGE : IN THE TURBINE BUILDING, YOU OBSERVE THAT VARIOUS LIGHTS ARE OUT. AT PANEL 10-C-184, REACTOR RECIRC PUMP MG SET HVAC CONTROL PANEL, YOU OBSERVE THE FOLLOWING ALARMS AND INDICATIONS: ALARMS: (ALARM 1-1) TURB. BLDG. MGV FAN 1AV107 LOW FLOW INDICATIONS:
"A" REACTOR RECIRC PUMP MG SET VENT FAN (1A-V-107) IS TRIPPED.
"B" REACTOR RECIRC PUMP MG SET VENT FAN (1B-V-107) IS RUNNING.
- THIS IS DRILL !!!********************************
*********************************A !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS REFEREE NOTES :
(y'~} (REFER
- 1. TO SUPPLEMENTAL SCENARIO #7.01) ISSUE THIS PANEL, LOCATED ON ELEVATION 171' OF THE TURBINE BUILDING.
"B" REACTOR RECIRC
- 2. ENSURE THAT THE OPERATOR UNDERSTANDS THAT THE MG SET VENT FAN HAS STARTED AND IS RUNNING SATISFACTORILY.
- 3. USE DID PHONE EXTENSION 3339 TO CONTACT CONTROL ROOM (SIMU
- 4. ALL VERBAL COMMUNICATIONS MUST START WITH "THIS IS A DRILL".
- 5. ENSURE OPERATOR UNDERSTANDS THAT SOME LIGHTING IS EXTINGUIS EXPECTED ACTIONS :
- 1. THE OPERATOR DISPATCHED TO THE 10-C-184 PANEL ACKNOWLEDGES THAT THE "A" REACTOR RECIRC PUMP MG SET VENT FAN IS TRIPPED AND THAT THE "B" VENT HAS STARTED.
- 2. THE OPERATOR PROVIDES THE INFORMATION TO THE CONTROL ROOM (SIMULATOR)
USING DID PHONE EXTENSION 3339. 6.10 0
l ARTIFICIAL ISLAND l EMERGENCY PREPAREDNESS MESSAGE FORM l REAL TIME : 08:54 O MESSAGE #: 10C TO : CONTROL ROOM STAFF DRILL TIME : 00:54 l FROM : SIMULATOR REFEREE i LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : THIS IS A CONTINGENCY MESSAGE: YOU SHOULD DISPATCH AN EQUIPMENT OPERATOR TO MONITOR REACTOR RECIRC PUMP MG SET LUBE OIL TEMPERATURE FOLLOWING THE POWER DECREASE.
- THIS IS A DRILL !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS !!!
REFEREE NOTES : I (REFER TO SUPPLEMENTAL SCENARIO #7.01) k/ 1. ISSUE THIS MESSAGE AS NEEDED. '
- 2. DUE TO OTHER EVENT CURRENTLY IN PROGRESS, THE TIMING OF ISSUANCE OF THIS CONTINGENCY MESSAGE IS NOT CRITICAL TO THE SCENARIO TIMELINE, AND WILL BE ISSUED ACCORDINGLY.
EXPECTED ACTIONS :
- 1. CREW DISPATCHES AN AVAILABLE EQUIPMENT OPERATOR TO MONITOR REACTOR RECIRC PUMP MG SET LUBE OIL .
TEMPERATURES. 6.10C , O 1
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 08:55 ('~ MESSAGE #: 11 00:55
- FIRE BRIGADE TEAM LEADER DRILL TIME :
TO FROM : IN PLANT REFEREE LOCATION : TURBINE BUILDING, ELEVATION 120' MESSAGE :
"THIS IS A DRILL, THIS IS A DRILL" THE FIRE ON 10-B-130, UNIT SUBSTATION IS SUCCESSFULLY EXTINGUISHED.
SMOKE REMAINS IN THE AREA. PAINT ON THE OUTSIDE OF THE UNIT SUBSTATION IS BEGINNING TO BLISTER AND PEEL.
- THIS IS A DRILL *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS !!!
,o REFEREE NOTES : V) ( (REFER TO SUPPLEMENTAL SCENARIO #7.01)
- 1. ISSUE THIS MESSAGE TO THE FIRE BRIGADE LEADER AT 08:55
- 2. ENSURE THE FIRE BRIGADE NOTIFIES THE CONTROL ROOM THAT THE FIRE IS EXTINGUISHED.
- 3. ENSURE THAT THE FIRE BRIGADE COMMENCES ACTIONS TO REMOVE SMOKE FROM THE AREA.
- 4. USE DID PHONE EXTENSION 3339 OR RADIO TO CONTACT THE CONTROL ROOM (SIMULATOR).
EXPECTED ACTIONS :
- 1. THE FIRE BRIGADE ACKNOWLEDGES THAT THE FIRE IS EXTINGUISHED.
- 2. FIRE BRIGADE COMMENCES ACTIONS TO BEGIN CLEARING SMOKE FROM THE AREA.
6.11 1 l
/*~s k/
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM , O MESSAGE #: TO FROM 11C SNSS LEAD SIMULATOR REFEREE REAL TIME : DRILL TIME : 08:59 00:59 LOCATION : SIMULATOR (HOPE CREEK) , MESSAGE : THIS IS A CONTINGENCY MESSAGE: i YOU SHOULD DECLARE AN UNUSUAL EVENT IN ACCORDANCE WITH ECG SECTION 14.A, FIRE WITHIN A PERMANENT PLANT STRUCTURE LASTING GREATER THAN 10 MINUTES.
- THIS IS A DRILL !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS !!!
REFEREE NOTES * (REFER TO SUPPLEMENTAL SCENARIO #7.01) '
- r 1. ISSUE THIS MESSAGE AS NEEDED TO MAINTAIN THE SCENARIO TIMELINE.
- 2. BE PREPARED TO PROVIDE MARKED UP COPIES OF ATTACHMENTS AND EPIPS FOR DRILL USE. .
- 3. THIS MESSAGE MAY BE USED BETWEEN 0855 AND 0905 HOURS. ;
- 4. CONFER WITH THE HEAD REFEREE PRIOR TO ISSUING THIS MESSAGE. ;
- 5. ENSURE MET DATA DISPLAY IS UPDATED, BE PREPARED TO ROLE PLAY l I
SRPT WITH SSCL. l EXDECTED ACTIONS . i
- 1. SNSS SHOULD REFER TO ECG SECTION 14.A i AND DECLARE AN UNUSUAL EVENT.
- 2. SNSS IMPLEMENTS APPROPRIATE ECG ATTACHMENTS AND EPIPS.
l l l l 6.11C O
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE #: 12 REAL TIME : 09:00 U TO : EQUIPMENT OPERATOR DRILL TIME : 01:00 FROM : IN PLANT REFEREE LOCATION : TURBINE BUILDING, ELEVATION 137', SSE PANEL MESSAGE : IN THE TURBINE BUILDING, YOU OBSERVE THAT VARIOUS LIGHTS ARE OUT. AT THE STEAM SEAL EVAPORATOR, ALL INDICAT9NS APPEAR NORMAL.
- THIS IS A DRILL !!! *-
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS !!!
REFEREE NOTES : I (REFER TO SUPPLEMENTAL SCENARIO #7.01) \ 1. ISSUE THIS MESSAGE WHEN THE OPERATOR ARRIVES AT THE STEAM SEAL EVAPORATOR PANEL, LOCATED ON ELEVATION 137' OF THE TURBINE BUILDING
- 2. ENSURE THAT THE OPERATOR UNDERSTANDS THAT SOME LIGHTING IS EXTINGUISHED.
- 3. USE DID PHONE EXTENSION 3339 TO CONTACT CONTROL ROOM (SIMULATOR).
- 4. ALL VERBAL COMMUNICATIONS MUST START WITH "THIS IS A DRILL".
EXPECTED ACTIONS :
- 1. THE OPERATOR DISPATCHED TO THE STEAM SEAL EVAPORATOR PANEL ACKNOWLEDGES THAT LOCAL INDICATIONS ARE NORMAL AND THE STEAM SEAL EVAPORATOR IS FUNCTIONING PROPERLY.
- 2. THE OPERATOR PROVIDES THE INFORMATION TO THE CONTROL ROOM (SIMULATOR)
USING DID PHONE EXTENSION 3339. 6.12 O
I ARTIFICIAL ISLAND ' l EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 09.00 12C ( MESSAGE #: TO : NSS DRILL TIME : 01:00 FROM : SIMULATOR REFEREE l LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : THIS IS A CONTINGENCY MESSAGE: YOU SHOULD CONTACT THE REACTOR ENGINEER TO OBTAIN FURTHER GUIDANCE FOR REACTIVITY MANIPULATION AND CHECK THERMAL LIMITS FOLLOWING THE MAJOR LOSS OF FEEDWATER HEATING.
- THIS IS A DRILL
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS !!!
n N' REFEREE NOTES (REFER TO SUPPLEMENTAL SCENARIO #7.01)
- 1. ISSUE THIS MESSAGE AS NEEDED TO MAINTAIN THE SCENARIO TIMELINE.
- 2. THIS IS NOT CRITICAL TO THE DRILL TIMELINE.
- 3. HAVE REFEREE STATIONED WITH RX ENGINEER FOR THIS EVENT.
f EXPECTED ACTIONS :
- 1. NSS CONTACTS THE REACTOR ENGINEER TO REVIEW THERMAL LIMITS AND PROVIDE GUIDANCE ON FURTHER REACTIVITY MANIPULATIONS.
b 6 6.12C O
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM
,-~,
REAL TIME : 09:00 (') MESSAGE #: TO : 13 EQUIPMENT OPERATOR IN PLANT REFEREE DRILL TIME : 01:00 FROM LOCATION : TURBINE BUILDING, ELEVATION 120, SA CMPR MESSAGE : AT THE 10-K-107, UNIT 1 SERVICE AIR COMPRESSOR, YOU OBSERVE THAT THE COMPRESSOR HAS TRIPPED. AT THE 00-K-107, COMMON SERVICE AIR COMPRESSOR, YOU OBSERVE THAT THE COMPRESSOR IS RUNNING. AT THE 1A-F-104, EMERGENCY INSTRUMENT AIR DRYER, YOU OBSERVE THAT THE DRYER PACKAGE IDS STARTED.
- THIS IS A DRILL !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS
,- REFEREE NOTES : ( 1. THE LOSS OF THE 10-B-130 UNIT SUBSTATION RESULTS IN A LOSS OF THE 10-K-107 SERVICE AIR COMPRESSOR.
- 2. ISSUE THIS MESSAGE AFTER THE EQUIPMENT OPERATOR HAS ARRIVED AT THE SERVICE AIR COMPRESSORS IN THE TURBINE BUILDING, ELEVATION 120'
- 3. THE STATUS MAY CHANGE DUE TO ACTIONS TAKEN BY CONTROL ROOM OPERATORS. INFORMATION WILL BE PROVIDED TO THE INPLANT REFEREE FROM THE LEAD OSC REFEREE.
- 4. THIS IS NOT CRITICAL TO THE DRILL TIMELINE.
EXPECTED ACTIONS :
- 1. THE EQUIPMENT OPERATOR ACKNOWLEDGES THE STATUS OF THE SERVICE AIR COMPRESSORS AND NOTIFIES THE CONTROL ROOM.
6.13 O
- - ~ _ _ _ _
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM O MESSAGE #: 13C REAL TIME : 09:01 Q TO : SNSS DRILL TIME : 01:01 FROM : LEAD SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE- : THIS IS A CONTINGENCY MESSAGE: FOR SCENARIO CONTROL, DO NOT IMPLEMENT ASSEMBLY / ACCOUNTABILITY AT THIS TIME.
**********************************************w************************
- THIS IS A DRILL !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS !!!
REFEREE NOTES : O- (REFER TO SUPPLEMENTAL SCENARIO #7.01)
- 1. ISSUE THIS MESSAGE AS NEEDED TO MAINTAIN THE SCENARIO TIMELINE.
- 2. THIS IS CRITICAL TO THE DRILL TIMELINE.
- 3. THE SNSS MAY DECIDE TO ACTIVATE THE OSC PRIOR TO THE ALERT BASED ON HIS JUDGEMENT.
EXPECTED ACTIONS :
- 1. SNSS DOES NOT IMPLEMENT ASSEMBLY /
ACCOUNTABILITY AT THIS TIME. l 1 l 6.13C O i
~
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM es n REAL TIME : 09:01 t MESSAGE #: 13D TO : CONTROL ROOM STAFF DRILL TIME : 01:01 FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : YOU HAVE JUST RECEIVED THE FOLLOWING ALARMS AND INDICATIONS: ALARMS: RPV LEVEL 7 (OVERHEAD A7-BS) RPV LOOSE PARTS MON PNL 10-C-675 (OVERHEAD C6-A5) RPV LPM IMPACT VIB LVL (CRIDS POINT D5457) INDICATIONS:
#5 JET PUMP FLOW DECREASES.
"B" RECIRC LOOP TOTAL JET PUMP FLOW DECREASES.
REACTOR POWER DECREASES. REACTOR WATER LEVEL INCREASES. ,-
- THIS IS A DRILL !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS !!!
*********************************************************************w REFEREE NOTES :
O (REFER TO SUPPLEMENTAL SCENARIO #7.03)
- 1. MESSAGE FOR DARK BOARD CONTROL ONLY.
- 2. ENSURE NCO RESPONDS TO ALARMS APPROPRIATELY.
EXPECTED ACTIONS :
- 1. CREW RECOGNIZES THAT INDICATED FLOW THROUGH THE #5 JET PUMP HAS DECREASED
- 2. CREW RECOGNIZES THE POSSIBLE PRESENCE OF A LOOSE PART IN THE REACTOR VESSEL DUE TO RECEIPT OF THE LOOSE PARTS MONITOR OVERHEAD ALARM. '
- 3. CREW DISPATCHES AN EQUIPMENT OPERATOR TO VALIDATE THE LOOSE PARTS ,
MONITOR ALARM.
- 4. NSS DIRECTS THE DAILY JET PUMP SURV (OP-ST.BB-001) BE PERFORMED TO ASSESS THE OPERABILITY OF THE #5 JET PUMP.
6.13D 1 I O ; I I
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 09:02 O MESSAGE #: TO FROM 14 EQUIPMENT OPERATOR IN PLANT REFEREE DRILL TIME : 01:02 LOCATION : TURBINE BUILDING, ELEVATION 137' MESSAGE : IN THE "A" REACTOR RECIRC PUMP MG SET ROOM, "A" REACTOR RECIRC PUMP MG SET LUBE OIL TEMPERATURE IS INDICATING 118 DEGREES F ON 1BBTI-8290A. IN THE "B" REACTOR RECIRC PUMP MG SET ROOM, "B" REACTOR RECIRC PUMP MG SET LUBE OIL TEMPERATURE IS INDICATING 116 DEGREES F ON 1BBTI-8290B. ,
- THIS IS A DRILL !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS !!!
REFEREE NOTES : (REFER TO SUPPLEMENTAL SCENARIO #7.01)
- 1. ISSUE THIS MESSAGE AS THE OPERATOR CHECKS LUBE OIL TEMPERATURES.
- 2. REACTOR RECIRC SYSTEM OPERATING PROCEDURE, OP-SO.BB-0002, REQUIRES LUBE OIL TEMPERATURE TO BE MAINTAINED BETWEEN 110 & 130 DEGREES F.
- 3. USE DID PHONE EXTENSION 3339 OR RADIO TO CONTACT THE CONTROL ROOM (SIMULATOR).
- 4. ALL VERBAL COMMUNICATIONS MUST START WITH "THIS IS A DRILL". l EXPECTED ACTIONS :
- 1. EQUIPMENT OPERATOR MONITORS REACTOR RECIRC PUMP MG SET LUBE OIL TEMPERATURES.
- 2. EQUIPMENT OPERATOR NOTIFIES THE CONTROL ROOM.
1 I 6.14 l O
l ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM 1 (~) (j MESSAGE #: 14C REAL TIME DRILL TIME :
- 09:06 01:06 i
TO : CONTROL ROOM STAFF J FROM : SIMULATOR REFEREE l LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : l THIS IS A CONTINGENCY MESSAGE YOU SHOULD DISPATCH AN EQUIPMENT OPERATOR TO THE LOOSE PARTS l MONITOR PANEL (10-C-675), LOCATED IN THE UPPER RELAY ROOM TO : VALIDATE THE LOOSE PARTS ALARM IN ACCORDANCE WITH THE LOOSE PARTS MONITORING SYSTEM OPERATING PROCEDURE, - OP-SO . SC -00 01.
********************************w*********!!!
- THIS IS A DRILL !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS REFEREE NOTES :
O (REFER TO SUPPLEMENTAL SCENARIO #7.03) DELIVER THIS 1. GOING TO DISPATCH AN EQUIPMENT OPERATOR TO VALIDATE THE LOOSE PARTS MONITOR ALARM. EXPECTED ACTIONS :
- 1. CREW REFERS TO OP-SO.SC-0001, LOOSE PARTS MONITORING SYSTEM OPERATION AND DISPATCHES AN EQUIPMENT OPERATOR TO VALIDATE THE ALARM IN ACCORDANCE WITH THE PROCEDURE.
6.14C O
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 09:08 MESSAGE #: 15C
\- TO : CONTROL ROOM STAFF DRILL TIME : 01:08 FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK)
MESSAGE : THIS IS A CONTINGENCY MESSAGE YOU SHOULD PERFORM THE DAILY JET PUMP SURVEILLANCE, OP-ST.BB-0001 TO DETERMINE THE OPERABILITY OF THE #5 JET PUMP. i
- THIS IS A DRILL *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS !!!
REFEREE NOTES : O (REFER TO SUPPLEMENTAL SCENARIO #7.03)
- 1. DELIVER THIS MESSAGE ONLY IF IT APPEARS LIKELY THAT THE CREW IS NOT GOING TO PERFORM THE DAILY JET PUMP SURVEILLANCE TO DETERMINE THE OPERABILITY OF THE #5 JET PUMP.
EXPECTED ACTIONS :
- 1. CREW PERFORMS OP-ST.BB-0001, DAILY JET PUMP SURVEILLANCE, IN ORDER TO DETERMINE THE OPERABILITY ;
OF THE #5 JET PUMP.
- 2. CREW DETERMINES THAT THE #5 JET PUMP IS INOPERABLE. ,
I NSS REFERS TO TECH SPEC 3.4.1.2
- 3. l AND COMMENCES A REACTOR SHUTDOWN.
6.15C O
i f l ARTIFICIAL ISLAND l EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 09:09 MESSAGE f: 15D TO : CONTROL ROOM STAFF DRILL TIME : 01:09 FROM : SIMULATOR REFEREE ' LOCATION : SIMULA'IOR (HOPE CREEK) MESSAGE : YOU HAVE RECEIVED THE FOLLOWING INDICATIONS: THE "C" TURBINE BUILDING CHILLER (1C-K-111) HAS STARTED AND APPEARS TO BE OPERATING SATISFACTORILY.
**************************************************+********************
- THIS IS A DRILL !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS !!!
REFEREE NOTES : , O 1. MESSAGE FOR DARK BOARD CONTROL ONLY.
- 2. ENSURE NCO RESPONDS TO ALARMS APPROPRIATELY.
EXPECTED ACTIONS :
- 1. THE CONTROL ROOM STAFF ACKNOWLEDGES THAT THE "C" TURBINE BUILDING CHILLER HAS STARTED AND IS OPERATING SATISFACTORILY.
6.15D . O
ARTIFICIAL ISLAND l EMERGENCY PREPAREDNESS MESSAGE FORM l (~) ('j MESSAGE #: 16 REAL TIME : 09:10 TO : EQUIPMENT OPERATOR DRILL TIME : 01:10 l l FROM : IN PLANT REFEREE LOCATION : AUXILIARY BUILDING, UPPER RELAY ROOM, 10-C-675 l MESSAGE : AT THE LOOSE PARTS MONITOR PANEL (10-C-675), LOCATED IN THE UPPER RELAY ROOM, YOU OBSERVE THE FOLLOWING INDICATIONS: CHANNEL 5, INLET RECIRC LINE VIBRATION AND LOOSE PART LEDS ARE ILLUMINATED. CHANNEL 6, INLET RECIRC LINE VIBRATION AND LOOSE PART LEDS ARE ILLUMINATED. CHANNEL 12, RECIRC PUMP 1BP210 VIBRATION LED IS ILLUMINATED.
- THIS IS A DRILL
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS !!!
REFEREE NOTES : (#r%) (REFER TO SUPPLEMENTAL SCENARIO #7.03)
- 1. ISSUE THIS MESSAGE AS THF EQUIPMENT OPERATOR IMPLEMENTS SECTION 5.2 OF OP-SO.SC-0001, VALIDATING LOOSE PARTS MONITORING SYSTEM ALARMS.
- 2. ENSURE THE EQUIPMENT OPERATOR PROVIDES THE INFORMATION TO THE CONTROL ROOM (SIMULATOR).
- 3. USE DID PHONE EXTENSION 3339 TO CONTACT THE SIMULATOR (CONTROL ROOM)
EXPECTED ACTIONS :
- 1. EQUIPMENT OPERATOR PROPERLY IMPLEMENTS THE VALIDATION PROCEDURE FOR THE LOOSE PARTS ALARM AND NOTIFIES THE CONTROL ROOM (SIMULATOR)
OF HIS FINDINGS. 6.16
-s l u.)
l l ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 09:15 MESSAGE #: 16C
- CONTROL ROOM STAFF DRILL TIME : 01:15 l
TO . FROM ': SIMULATOR REFEREE l LOCATION : SIMULATOR.(HOPE CREEK) l l MESSAGE : . l THIS IS A CONTINGENCY MESSAGE YOU SHOULD CONTACT THE SYSTEM ENGINEER, JOHN HAWRYLAK, TO ASSURE APPROPRIATE ALARM VALIDATION, AS REQUIRED BY THE THE LOOSE PARTS MONITOR OVERHEAD ALARM RESPONSE PROCEDURE. i
**************************************LL
- THIS IS A DRI !!!
1!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS REFEREE NOTES : .
( (REFER TO SUPPLEMENTAL SCENARIO #7.03) DELIVER THIS
- 1. -
GOING TO CONTACT THE SYSTEM ENGINEER IN ACCORDANCE WITH THE ALARM RESPONSE PROCEDURE..
- 2. THE ACTUAL SYSTEM ENGINEER WHO HAS RESPONSIBILITY FOR THETHE I&C LOOSE PARTS MONITOR SYSTEM IS NOT PARTICIPATING TN THE DRILL.
ENGINEER IN THE TSC WILL ASSUME THIS RESPO65IBILITY FOR THE ; DURATION OF THE DRILL. EXPECTED ACTIONS :
- 1. CREW CONTACTS THE SYSTEM ENGINEER 3 FOR THE LOOSE PARTS MONITORING SYSTEM TO ENSURE CORRECT VALIDATION OF THE ALARM.
n 5 A 6.16C
}
i
,r - - , s
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 09:16 MESSAGE #: 17
- EQUIPMENT OPERATOR DRILL TIME : 01:16 TO FROM : IN PLANT REFEREE LOCATION : CONTROL BUILDING, LOWER RELAY ROOM MESSAGE :
IN THE LOWER RELAY ROOM, AT THE JET PUMP DIFFERENTIAL PRESSURE j INDICATORS, YOU OBSERVE THE FOLLOWING: JET PUMP # DP JET PUMP # DP 27 24 11 1 23 26 12 2 24 25 13 3 28 23 14 4 25 i 6 15 5 16 24 6 27 27 7 25 17 18 25 8 28 26 9 25 19 20 24 10 24
*****************************e4****************************************
- THIS IS A-DRILL !!! !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS
******************************************s*************************** % REFEREE NOTES :
i (REFER TO SUPPLEMENTAL SCENARIO #7.03) ISSUE THIS ME
- 1. l JET PUMP DIFFERENTIAL PRESSURE PANEL IN THE LOWER RELAY ROOM AND HAS SIMULATED RECORDING THE DATA.
ENSURE THE OPERATOR HAS A COPY OF OP-ST.BB-0001, JET PUMP 2. OPERABILITY SURVEILAANCE.
- 3. USE DID PHONE EXTENSION 3339 TO CONTACT CONTROL ROOM (SIMULATOR)
- 4. ALL VERBAL COMMUNICATIONS MUST START WITH "THIS IS A DRILL". ,
EXPECTED ACTIONS :
- 1. THE EQUIPMENT OPERATOR RECORDS' THE JET PUMP DIFFERENTIAL PRESSURE DATA PROVIDED BY THE REFEREE IN THE PROCEDURE.
- 2. THE OPERATOR CONTACTS THE CONTROL ROOM AND PROVIDES THE INFORMATION TO THE CREW.
6.17 ; b O
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 09:17 /) (
^'
MESSAGE #: TO : 17C SNSS/NSS DRILL TIME : 01:17 FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : THIS IS A CONTINGENCY MESSAGE FOR SCENARIO CONTROL, DO NOT SCRAM THE REACTOR AT THIS TIME.
***************************************L
- THIS IS A DRIL !!!
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS
************c*********************************************************
(q REFEREE NOTES : (REFER TO SUPPLEMENTAL SCENARIO #7.03)
- 1. BE PREPARED TO ISSUE MESSAGE AS NECESSARY.
- 2. DELIVER THIS MESSAGE ONLY IF IT APPEARS LIKELY TIULT THE SNSS IS ABOUT TO ORDER A MANUAL SCRAM OF THE UNIT.
- 3. ONCE THE #5 JET PUMP HAS BEEN DETERMINED TO BE INOPERABLE, THE SNSS/NSS ENTERS TECH SPEC 3.4.1.2 (JET PUMP OPERABILITY) AND PROCEED TO PLACE THE REACTOR IN HOT SHUTDOWN WITHIN THE NEXT 12 HOURS. POWER DECREASE WILL BE LIMITED TO < 15%/ HOUR.
EXPECTED ACTIONS :
- 1. THE SNSS DOES NOT SCRAM THE REACTOR AND COMMENCES A CONTROLLED REACTOR SHUTDOWN WITH REACTOR POWER REDUCTION NOT EXCEEDING 15%/ HOUR.
i 6.17C l l
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 09:17 (_, MESSAGE #: 18 DRILL TIME : 01:17 TO : FIRE BRIGADE TEAM LEADER FROM : IN PLANT REFEREE TURBINE BUILDING, ELEVATION 120' LOCATION : MESSAGE :
"THIS IS A DRILL, THIS IS A DRILL" THE MAJORITY OF THE SMOKE FROM THE 10-B-130 UNIT SUBST BEEN CLEARED SO THAT OTHER PERSONNEL MAY SAFELY ENT
*******************************IS
- THIS A DRILL !!! !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIO
/^} (> REFEREE NOTES : 1.
- 2. ISSUE THIS MESSAGE TO THE FIRE BRIGADE L SMOKE HAS BEEN CLEARED.
- 3. USE DID PHONE EXTENSION 3339 OR RADIO TO CONTACT THE C (SIMULATOR).
i EXPECTED ACTIONS :
- 1. THE FIRE BRIGADE ACKNOWLEDGE THAT MOST OF THE SMOKE IS CLEARED.
6.18 rN b
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 09:22 MESSAGE #: 18C DRILL TIME : 01:22 TO : SNSS FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : THIS IS A CONTINGENCY MESSAGE YOU SHOULD DIRECT THE SHIFT ELECTRICIAN TO ASSESS THE DAMAGE TO 10-B-130 UNIT SUBSTATION.
- THIS IS DRILL !!!********************************
*********************************A !!1 *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS p REFEREE NOTES :
g (REFER TO SUPPLEMENTAL SCENARIO #7.02) ISSUE THIS M 1. ELECTRICIAN TO 10-B-130 TO PERFORM DAMAGE ASSESSMENT. EXPECTED ACTIONS :
- 1. THE SNSS DISPATCHES THE SHIFT ELECTRICIAN TO PERFORM DAMAGE ASSESSMENT ON 10-B-130 UNIT SUBSTATION.
6.18C O
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM !D REAL TIME : 09:23 !s,/ MESSAGE #: 19 DRILL TIME : 01:23 TO : REACTOR ENGINEER FROM : TSC REFEREE LOCATION : HOPE CREEK CONTROL ROOM MESSAGE : (SIMULATOR) AND OBTAINING AFTER A P1 EDITCONTACTING OF CURRENTTHE CONTROL THERMAL ROOM CREWYOU OBSERVE THE FOLLOWIN LIMITS, CMFCP = 0.823 CMFLPD = 0.867 CMAPR = 0.805
*********************************A
- THIS IS DRILL 111 !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS REFEREE NOTES :
(O / (REFER TO SUPPLEMENTAL SCENARIO #7.01) ISSUE THIS 1.
- 2. OBTAINING CMFCP = A Pl. CORE MAXIMUM FRACTION OF LIMITING CRITICAL POWER CMFLPD = CORE MAXIMUM FRACTION OF LIMITING POWER DENSITY CMAPR = CORE MAXIMUM AVERAGE PLANAR RATIO
- 3. USE DID PHONE EXTENSION 3339 TO CONTACT CONTROL ROOM (SIM
- 4. ALL VERBAL COMMUNICATIONS MUST START WITH "THIS IS A DRILL".
EXPECTED ACTIONS :
- 1. REACTOR ENGINEER SUCCESSFULLY OBTAINS A P1 AND REVIEW THERMAL LIMITS AND THEN CONTACTS THE CONTROL ROOM (SIMULATOR) WITH THE RESULTS.
- 2. THE REACTOR ENGINEER PROVIDES REACTIVITY CONTROL GUIDANCE TO THE CREW.
6.19 0
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM
- 09:30 REAL TIME U MESSAGE #:
19C SNSS/NSS DRILL TIME : 01:30 TO
-FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK)
MESSAGE : YOU SHOULD COMMENCE A REACTOR SHUTDOWN IN ACCORDANCE W TECHNICIAL SPECIFICATION 3.4.1.2, JET PUMP OPERABILITY I
**************************HIS
- T IS A DRILL !!1 !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATION REFEREE NOTES :
O (REFER TO SUPPLEMENTAL SCENARIO #7.03) ISSUE TH 1. IS NOT GOING TO COMMENCE A REACTOR SHUTDOWN IN ACCORD TECH SPEC 3.4.1.2, JET PUMP OPERABILITY.
- 2. THIS IS NOT CRITICAL TO THE DRILL TIMELINE.
EXPECTED ACTIONS :
- 1. THE SNSS/NSS REFERS TO TECH SPEC 3.4.1.2 AND DIRECTS THE REACTOR .
SHUTDOWN.
- 2. THE SNSS/NSS NOTIFIES THE OPS MANAGER AND LOAD DISPATCHER OF THE IMPENDING SHUTDOWN. (THESE INTERFACES-WILL BE ,
ROLE PLAYED BY A SIMULATOR REFEREE) 6.19C O , t P
i f ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 09:30 MESSAGE #: 19D DRILL TIME : 01:30 TO : CONTROL ROOM STAFF FROM : SIMULATOR REFEREE i LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : f YOU HAVE JUST RECEIVED THE FOLLOWING ALARMS AND INDICATIONS ALARMS: (OVERHEAD A7-E2) FEEDWATER HEATER TRIP (OVERHEAD A7-F2) FEEDWATER HEATER PNL 1A/B/C C102 (CRIDS POINT D2790) FWH 6C BLEEDER TRIP VALVE NCLOSED INDICATIONS: REACTOR POWER BEGINS TO INCREASE. INDICATED LEVEL IN THE #6C FEEDWATER HEATER ON 10-C-650 INCREASING.
#6C FWH BLEEDER TRIP VALVE INDICATES TRIPPED.
THE #6C FEEDWATER HEATER EXTRACTION STEAM ISOLATION V HAS NO INDICATION.
**************************HIS
- T IS A DRILL !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT dPERATI O REFEREE 1.
NOTES (REFER TO SUPPLEMENTAL SCENARIO #7.04) MESSAGE FOR DARK BOARD CONTROL ONLY. LEAK STARTS AT 09:28, AND THE HIGH LEVEL ALARM COMES IN AT 09:30. < 2. 3. DUE TO A LOSS OF 10-B-130, THERE IS CURRENTLY NO POWER AVAILABLE TO THE #6C FEEDWATER HEATER EXTRACTION STEAM ISOLATION V SUCH, THE VALVE DOES NOT CLOSE FOLLOWING THE HIGH LEVEL IN THE HEATER AND CONDENSATE BEGINS TO FILL THE EXTRACTION STEAM EXPECTED ACTIONS :
- 1. CREW RECOGNIZES THE HIGH LEVEL CONDITION IN THE #6C FEEDWATER HEATER AND ATTEMPTS TO ISOLATE THE FEEDWATER HEATER TO PREVENT WATER INDUCTION INTO THE MAIN TURBINE.
- 2. NSS REFERS TO OP-AB.ZZ-0118, LOSS OF FEEDWATER HEATERS. I e
6.19D O i l
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 09:30 MESSAGE #: 20 DRILL TIME : 01:30 TO : I&C SYSTEM ENGINEER
- TSC REFEREE FROM LOCATION : AUXILIARY BUILDING, UPPER RELAY ROOM, 10-C-675 MESSAGE : LOCATED IN THE UPPER AT THE LOOSE PARTS MONITOR PANEL (10-C-675),
RELAY ROOM, YOU OBSERVE THE FOLLOWING INDICATIONS: CHANNEL 5, INLET RECIRC LINE VIBRATION AND LOOSE PART LEDS ARE ILLUMINATED. CHANNEL 6, INLET RECIRC LINE VIBRATION AND LOOSE PART LEDS ARE ILLUMINATED. CHANNEL 12, RECIRC PUMP 1BP210 VIBRATION LED IS ILLUMINATED
*************************THIS IS A DRILL !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERA REFEREE NOTES :
O\ (REFER TO SUPPLEMENTAL SCENARIO #7.03) ISSUE TH 1. PARTS MONITORING SYSTEM ALARM.
- 2. USE DID PHONE EXTENSION 3339 TO CONTACT THE SIMULAT
- 3. ALL VERBAL COMMUNICATIONS MUST START WITH "THIS IS A DRIL EXPECTED ACTIONS :
- 1. SYSTEM ENGINEER PROPERLY VALIDATES LOOSE PARTS MONITOR ALARM AND NOTIFIES THE SNSS.
6.20 0 .
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM r% REAL TIME : 09:32 d MESSAGE #: TO : 20D CONTROL ROOM CREW DRILL TIME : 01:32 FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : YOU CLOSEDHAVE JUSTFORRECEIVED PUSHBUTTON THE FOLLOWING INDICATION AF THE 1AEHV-1768C, INLET VALVE: BOTH THE OPEN AND CLOSED LIGHTS REMAIN ILLUMINATED FOR APPROXIMATELY THREE SECONDS, WHEN BOTH LIGHTS EXTINGUISH. LEVEL IN THE #6C FEEDWATER HEATER CONTINUES TO INCREASE.
*******************************S
- THIS I A DRILL !!! !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS Og REFEREE NOTES :
Q (REFER TO SUPPLEMENTAL SCENARIO #7.01)
- 1. MESSAGE FOR DARK BOARD CONTROL ONLY.
- 2. ENSURE NCO RESPONDS TO ALARMS APPROPRIATELY.
- 3. FAILURE OF THE #6C FEEDWATER HEATER CONDENSATE INLET VALVE TO CLOSE RESULTS IN AN UNISOLABLE TUBE LEAK IN THE #6C FEEDWATER HEATER THAT WILL RESULTS IN WATER INTRUSION IN THE MAIN TURB AND SUBSEQUENT TURBINE BLADE IMPINGEMENT.
EXPECTED ACTIONS :
- 1. THE CREW ACKNOWLEDGES THAT THE -
#6C FEEDWATER HEATER CONDENSATE INLET VALVE MOTOR HAS TRIPPED ON THERMAL OVERLOAD AND DISPATCHES AN OPERATOR TO INVESTIGATE AND ATTEMPT TO CLOSE THE VALVE MANUALLY.
6.20D O
ARTIFICIAL ISLAND ' EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 09:33 V MESSAGE #: 21 DRILL TIME : 01:33 TO : EQUIPMENT OPERATOR FROM : IN PLANT REFEREE LOCATION : TURBINE BUILDING, ELEVATION 155' MESSAGE : UPON ENTERING THE TURBINE BUILDING, A LARGE PORTION OF THE LIGHTING IS NOT ILLUMINATED. AT THE #6B FEEDWATER HEATER CONDENSATE OUTLET VALVE, YOU OBSERVE THE FOLLOWING: WHEN DEPRESSED, THE MOTOR OPERATED VALVE DECLUTCH LEVER SUCCESSFULLY DISENGAGES THE MOTOR AND ENGAGES THE HANDWH WHEN AN ATTEMPT IS MADE TO MANUALLY CLOSE THE VALVE, THE HANDWHEEL AND STEM BOTH TURN VERY SLOWLY IN THE CLOSED DIRECTION.
***********************q****************** *****************************S
- THI IS A DRILL 111 111 *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS C\ REFEREE NOTES :
V (REFER TO SUPPLEMENTAL SCENARIO #7.01) ISSUE THIS 1. MANUALLY CLOSE THE #6B FEEDWATER HEATER CONDENSATE OUTLE DUE TO A LOSS OF MOTIVE POWER TO THE MOTOR OPERATOR.
- 2. THIS ACTIONS IS NOT SUCCESSFUL.
"B" FEEDWATER 3.
IT IS NOT HEATER STRING. CRITICAL TO THE SCENARIO TIMEL EXPECTED ACTIONS :
- 1. EQUIPMENT OPERATOR ATTEMPTS TO MANUALLY CLOSE THE #6B FEEDWATER HEATER CONDENSATE OUTLET VALVE.
6.21
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM
,_s e s REAL TIME : 09:33
\.j MESSAGE #: 21C DRILL TIME : 01:33 TO : SNSS/NSS FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : THIS IS A CONTINGENCY MESSAGE FOR SCENARIO CONTROL, DO NOT SCRAM THE REACTOR AT THIS TIME.
******************************IS
- THIS A DRILL !!! !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PL7 lit OPERATIONS
[] REFEREE NOTES : (/ (REFER TO SUPPLEMENTAL SCENARIO #7.04)
- 1. BE PREPARED TO ISSUE MESSAGE AS NECESSARY.
- 2. DELIVER THIS MESSAGE ONLY IF IT APPEARS LIKELY THAT THE SNSS ABOUT TO ORDER A MANUAL SCRAM OF THE UNIT.
- 3. CREW SHOULD CONTINUE WITH THE CONTROLLED PLANT SHUTDOWN.
EXPECTED ACTIONS :
- 1. THE SNSS DOES NOT SCRAM THE REACTOR AND COMMENCES A CONTROLLED REACTOR SHUTDOWN WITH REACTOR POWER REDUCTION NOT EXCEEDING 15%/ HOUR.
6.21C l'D C/
ARTIFICIAL ISLAND l EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 09:37 MESSAGE #: 22 DRILL TIME : 01:37 TO- : SHIFT ELECTRICIAN i FROM : IN PLANT REFEREE TURBINE BUILDING,-ELEVATION 120' LOCATION : > MESSAGE : AT 10-B-130 UNIT SUBSTATION, YOU OBSERVE THE FOLLOWING: PAINT ON THE OUTSIDE OF THE UNIT SUBSTATION IS BLIST PEELING. ! WIRING DAMAGE IS CLEARLY VISIBLE. . INSULATION IS CRACKED AND CHARRED. t "THIS IS A DRILL, THIS IS A DRILL"
********************************************** 7 *************************THIS IS A DRILL !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPE ;
t REFEREE NOTES : O (REFER TO SUPPLEMENTAL SCENARIO #7.02) ISSUE T 1. PERFORMANCE OF A THOROUGH DAMAGE ASSESSMENT OF 10-B-130 2.BUILDING.
- 3. USE DID PHONE EXTENSION 3339 TO CON !
EXPECTED ACTIONS :
- 1. SHIFT ELECTRICIAN SHOULD REPORT THE DAMAGE TO THE SNSS (EC) WITH AN !
ESTIMATE OF TIME TO REPAIR AND REQUEST DIRECTION ON WHETHER OR NOT TO PROCEED WITH REPAIRS. (AT THIS TIME, NORMAL WORK PROCEDURES ARE TO BE FOLLOWED. 6.22 l I O
i 1 ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM () MESSAGE.#: TO : 22C CONTROL ROOM STAFF SIMULATOR REFEREE REAL TIME : DRILL TIME : 09:37 01:37 FROM LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : r THIS IS A CONTINGENCY MESSAGE:
"C" FEEDWATER YOU SHOULD DISPATCH AN EQUIPMENT OPERATOR TO THE HEATER CONTROL PANEL, 1C-C-102, TO INVESTIGATE THE HIGH LEVEL IN THE #6C FEEDWATER HEATER.
- THIS IS A DRILL !!! I!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS l O (REFER TO SUPPLEMENTAL SCENARIO #7.04)
REFEREE NOTES 1.-DELIVER THIS MESSAGE IS NOT GOING TO DISPATCH AN EQUIPMENT OPERATOR TO THE "C" O FEEDWATER HEATER CONTROL PANEL. . EXPECTED ACTIONS :
- 1. THE CREW DISPATCHES AN EQUIPMENT OPERATOR TO THE "C" FEEDWATER HEATER CONTROL PANEL.
6.22C
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM A REAL TIME : 09:40 h MESSAGE #: TO : 23 MAINTENANCE TEAM DRILL TIME : 01:40 ' FROM : INPLANT REFEREE LOCATION : TURBINE BUILDING, ELEVATION 120' , MESSAGE : YOU HAVE SUCCESSFULLY HOOKED UP THE TEMPORARY AIR COMPRESSOR
- THIS A DRILL !!!*********************************
******************************IS !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS O REFEREE
- 1. NOTESISSUE THIS MESSGE ONLY IF A MAINTENANCE SNSS/NSS TO HOOKUP THE TEMPORARY AIR COMPRESSOR, AS A RESULT OF TEAM I COMPRESSOR PROBLEMS ENCOUNTERED WHEN THE 10-B-130 UNIT SUBSTATION WAS LOST.
- 2. THIS IS NOT CRITICAL TO THE SCENARIO TIMELINE.
EXPECTED ACTIONS :
- 1. MAINTENANCE TEAM ACKNOWLEDGES THAT THE TEMPORARY AIR COMPRESSOR HAS BEEN HOOKED UP AND INFORMS THE CONTROL ROOM (SIMULATOR).
l 6.23
\
l O
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM A REAL TIME : 09:40 !'~ ') MESSAGE #: 23C DRILL TIME : 01:40 TO : CONTROL ROOM STAFF FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : THIS IS A CONTINGENCY MESSAGE YOU SHOULD ATTEMPT TO ISOLATE CONDENSATE TO THE #6C FEEDWAT HEATER BY CLOSING THE CONDENSATE INLET VALVE 1AEHV-1768C.
- TFIS IS DRILL !!!*******************************
*********************************A !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS p REFEREE NOTES :
('y (REFER TO SUPPLEMENTAL SCENARIO #7.04) ISSUE THIS 1.
- 2. ATTEMPTS TO REMOTELY CLOSE THE CONDENSATE INLET VALVE WIL UNSUCCESSFUL, AS THE VALVE MOTOR BREAKER TRIPS ON A THERMAL OVERLOAD CONDITION.
- 3. MANUAL CLOSURE OF THE VALVE IS REQUIRED. ELEVATION 155', ABOVE
- 4. VALVE IS LOCATED IN THE TURBINE BUILDING, THE #6C FEEDWATER HEATER ROOM. .
EXPECTED ACTIONS :
- 1. CREW ATTEMPTS TO REMOTELY ISOLATE CONDENSATE TO THE #6C FEEDWATER HEATER. THE MOV WILL TRIP ON THERMAL OVERLOAD WHILE STROKING CLOSED.
MANUAL OPERATION IS REQUIRED. 6.23C O
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 09:41 23D V MESSAGE #: TO : CONTROL ROOM STAFF DRILL TIME : 01:41 FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : YOU HAVE JUST RECEIVED THE FOLLOWING INDICATIONS: VIBRATION LEVELS ON MAIN TURBINE BEARINGS #3 AND #4 HAVE BEGUN TO INCREASE AT A RATE OF APPROXIMATELY 0.5 MILS / MIN. VIBRATION LEVELS ON THE OTHER MAIN TURBINE BEARINGS IS ALSO INCREASING, BOT AT A SLOWER RATE.
- THIS IS DRILL !!!********************************
*********************************A !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS REFEREE NOTES :
(] U 1. MESSAGE FOR DARK BOARD CONTROL ONLY.
- 2. ENSURE NCO RESPOND TO ALARMS APPROPRIATELY.
- 3. MAIN TURBINE VIBRATIONS ARE INCREASING AT THIS TIME DUE TO WAT INDUCTION INTO THE MAIN TURBINE CAUSED BY THE HIGH WATER LEV DUE TO INABILITY TO ISOLATE THE HEATER THE #6C FEEDWATER HEATER.
AND SUBSEQUENT FAILURE OF THE ASSOCIATED BLEEDER TRIP VALVE, WATER IS BACKING UP INTO THE TURBINE AND IS IMPINGING ON THE B EXPECTED ACTIONS :
- 1. CREW RECOGNIZES THAT MAIN TURBINE VIBRATIONS ARE INCREASING.
- 2. CREW REFERS TO MAIN TURBINE OPERATING PROCEDURE, OP-SO.AC-001 FOR GUIDANCE REGARDING THE INCREASED VIBRATION CONDITION.
6.23D [t
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM (D REAL TIME : 09:42 MESSAGE #: 24 DRILL TIME : 01:42 () TO : EQUIPMENT OPERATOR FROM : IN PLANT REFEREE - LOCATION : TURBINE BUILDING, ELEVATION 155' MESSAGE : UPON ENTERING THE TURBINE BUILDING, A LARGE PORTION OF THE LIGHTING IS NOT ILLUMINATED. AT THE #6C FEEDWATER HEATER CONDENSATE INLET VALVE, YOU OBSERVE THE FOLLOWING: WHEN DEPRESSED, THE MOTOR OPERATED VALVE DECLUTCH LEVER SUCCESSFULLY DISENGAGES THE MOTOR AND ENGAGES THE HANDWHE THE WHEN AN ATTEMPT IS MADE TO MANUALLY CLOSE THE VALVE, HANDWHEEL AND STEM BOTH TURN VERY SLOWLY IN THE CLOSED DIRECTION. A SIGNIFICANT AMOUNT OF RESISTANCE IS ENCOUNTERED.
*************************THIS IS A DRILL !!! !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS O REFEREE NOTES :
(REFER TO SUPPLEMENTAL SCENARIO #7.04) ISSUE THIS 1. MANUALLY CLOSE THE #6C FEEDWATER HEATER CONDENSATE INLE AS THE OPERATOR SIMULATES THE PROCESS OF CLOSING THE VALV MANUALLY.
- 2. IT IS CRITICAL TO THE DRILL TIMELINE THAT MANUAL CLOSURE IS SUCCESSFUL PRIOR TO THE MAIN TURBINE BLADING FAILURE.
EXPECTED ACTIONS :
- 1. EQUIPMENT OPERATOR ATTEMPTS TO MANUALLY CLOSE THE #6C FEEDWATER HEATER CONDENSATE INLET VALVE. j j
- 2. THE EQUIPMENT OPERATOR ACKNOWLEDGES THAT A SIGNIFICANT AMOUNT OF 1 RESISTANCE IS ENCOUNTERED WHEN l ATTEMPTING TO CLOSE THE VALVE. i 6.24 I
b
l ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 09:43
) MESSAGE #: 24C DRILL TIME : 01:43 TO : SNSS/NSS FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK)
MESSAGE : THIS IS A CONTINGENCY MESSAGE FOR SCENARIO CONTROL, DO NOT SCRAM THE REACTOR AT THIS TIME. E THIS IS A DRILL !!!******************************
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS
/"'s REFEREE NOTES : C/ (REFER TO SUPPLEMENTAL SCENARIO #7.04)
- 1. BE PREPARED TO ISSUE MESSAGE AS NECESSARY.
- 2. DELIVER THIS MESSAGE ONLY IF IT APPEARS LIKELY THAT THE SNSS 16 ABOUT TO ORDER A MANUAL SCRAM OF THE UNIT. ,
- 3. CREW SHOULD CONTINUE WITH THE CONTROLLED PLANT SHUTDOWN.
EXPECTED ACTIONS :
- 1. THE SNSS DOES NOT SCRAM THE REACTOR AND CONTINUES THE CONTROLLED REACTOR SHUTDOWh WITH REACTOR POWER REDUCTION NOT EXCEEDING 15%/ HOUR.
6.24C
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 09:44 MESSAGE #: 25 DRILL TIME : 01:44 TO : SHIFT ELECTRICIAN FROM : IN PLANT REFEREE LOCATION : TURBINF. BUILDING, ELEVATION 171' MESSAGE : UPON ENTERING THE TURBINE BUILDING, SOME LIGHTS ARE EXTINGUISHED. AT BREAKER 52-143074, YOU OBSERVE THE FOLLOWING: THE BREAKER IS TRIPPED ON THERMAL OVERLOAD. THE CLOSED CONTACTOR IS EXTREMELY HOT.
- THIS IS A DRILL !!! !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS REFEREE NOTES :
O (REFER TO SUPPLEMENTAL SCENARIO #7.04) ISSUE THIS ME 1. THE 10-B-143 MOTOR CONTROL CENTER AND IDENTIFIES THE CORRECT BREAKER. i
- 2. IT IS CRITICAL TO THE DRILL TIMELINE THAT CLOSURE OF THE VALVE IS NOT SUCCESSFUL PRIOR TO THE MAIN TURBINE BLADING FAILURE.
EXPECTED ACTIONS :
- 1. SHIFT ELECTRICIAN INSPECTS THE MOTOR BREAKER FOR THE #6C FEEDWATER HEATER CONDENSATE INLET VALVE.
6.25 O
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM (D 26 REAL TIME : 09:45 (j MESSAGE #: TO : EQUIPMENT OPERATOR DRILL TIME : 01:45 FROM : IN PLANT REFEREE LOCATION
- TURBINE BUILDING, ELEVATION 102' CONDENSER BAY MESSAGE :
UPON ENTERING THE CONDENSER BAY, SOME LIGHTING IS EXTINGUISHED. AT THE (6C FEEDWATER HEATER EXTRACTION STEAM ISOLATION VALVE, YOU OBSERVE THE FOLLOWING: ATTEMPTS TO REACH PROVES TO BE DIFFICULT AS THE RAILING UNDER THE VALVE IS EXTREMELY SLIPPERY, SUCH THAT THE VALVE CAN NOT BE REACHED BY STANDING Oi! THE RAILING.
***************************************L
- THIS IS A DRIL !!! !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS A REFEREE NOTES :
Q1 (REFER TO SUPPLEMENTAL SCENARIO #7.04)
- 1. ISSUE THIS MESSAGE TO THE EQUIPMENT OPERATOR DISPATCHED TO MANUALLY CLOSE THE #6C FEEDWATER HEATER EXTRACTION STEAM ISOLATIO VALVE, AS THE OPERATOR SIMULATES ATTEMPTS TO REACH THE VALVE BY STANDING ON RAILING BELOW THE VALVE.
- 2. IT IS CRITICAL TO THE DRILL TIMELINE THAT MANUAL CLOSURE IS NOT SUCCESSFUL PRIOR TO THE MAIN TURBINE BLADING FAILURE.
EXPECTED ACTIONS :
- 1. FQtIIPMENT OPERATOR ATTEMPTS TO MANUALLY CLOSE THE #6C FEEDWATER HEATER EXTRACTION STEAM ISOLATION VALVE. ]
l 6.26 O
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM () MESSAGE #: TO : 27D CONTROL ROOM STAFF SIMULATOR REFEREE REAL TIME DRILL TIME :
- 09:47 01:47 FROM LOCATION : SIMULATOR (HOPE CREEK)
MESSAGE : YOU HAVE JUST RECEIVED THE FOLLOWING ALARMS AND INDICATIONS: ALARMS: (OVERHEAD C3-A4) REACTOR SCRAM TRIP LOGIC B1 REACTOR SCRAM TRIP LOGIC B2 (OVERHEAD C3-A5) REACTOR SCRAM TRIP LOGIC A1 (OVERHEAD C3-A2) REACTOR SCRAM TRIP LOGIC A2 (OVERHEAD C3-A3) APRM DOWNSCALE (OVERHEAD C3-D4) LPRM DOWNSCALE (OVERHEAD C3-E5) RPV WATER LEVEL LO (OVERHEAD C5-A4) TCV FAST CLOSE & MSV TRIP BYP (OVERHEAD C5-C2) CRD SCRAM DISCH VOL LVL HI (OVERHEAD C5-B4) MAIN STOP VALVE CLOSURE (OVERHEAD C5-B2)
- THIS IS A DRILL !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS REFEREE NOTES :
- 1. THIS MESSAGE FOR DARK BOARD DRILL CONTROL ONLY.
- 2. ALARMS AND INDICATIONS ARE NECESSARILY LIMITED TO KEY ITEMS.
- 3. THE INCREASED MAIN TURBINE VIBRATION CONDITION HAS RESULTED IN A FAILURE OF THE MAIN TURBINE BEARING OIL HEADER, CAUSING A LOW BEARING HEADER OIL PRESSURE TRIP.
- 4. THE INCREASED VIBRATION CONDITION IS DUE TO WATER INDUCTION INTO THE MAIN TURBINE FROM THE #6C FEEDWATER HEATER.
EXPECTED ACTIONS :
- 1. NSS ENTERS EOP-101, RPV CONTROL AND ALSO MONITORS KEY CTMT. PARAMETERS.
- 2. NCO's PERFORM POST SCRAM ACTIONS, USE RFP FOR LEVEL CONTROL AND TURBINE BYPASS VALVES FOR PRESSURE CONTROL.
- 3. SNSS SHOULD REFER TO ECG.
6.27D O 9
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 09:47 28D ( . MESSAGE #: TO : CONTROL ROOM STAFF DRILL TIME : 01:47 ; FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : YOU HAVE JUST RECEIVED THE FOLLOWING ALARMS AND INDICATIONS: ALARMS: (OVERHEAD C5-A5) RPV PRES 5URE HI ROD DRIFT (OVERHEAD C6-E3) CRD SCRAM DISCH VOL NOT DRAINED (OVERHEAD C6-E4) CRD SYSTEM TROUBLE (OVERHEAD C6-F2) UNIT PROT LOCKOUT RELAY TRIP (OVERHEAD El-A5) MAIN TRANSFORMER TROUBLE (OVERHEAD El-A4) ' TURBINE GENERATOR TRIP (OVERHEAD D3-AS) TURBINE GENERATOR VIBRATION (OVERHEAD D3-C5) RPV-LEVEL 4 (OVERHEAD A7-CS) RPV LEVEL 3 (OVERHEAD A7-DS) , EHC UNIT PANEL 10C363 (OVERHEAD D3-DS)
**************************************LL
- THIS IS A DRI !!!
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS i
REFEREE NOTES : !
- 1. THIS MESSAGE FOR DARK BOARD DRILL CONTROL ONLY.
- 2. ALARMS.AND INDICATIONS ARE NECESSARILY LIMITED TO KEY ITEMS.
- 3. THE INCREASED MAIN TURBINE VIBRATION CONDITION HAS RESULTED IN A FAILURE OF THE MAIN TURBINE BEARING OIL HEADER, CAUSING A LOW BEARING HEADER OIL PRESSURE TRIP. l
- 4. THE INCREASED VIBRATION CONDITION IS DUE TO WATER INDUCTION INTO THE MAIN TURBINE FROM THE #6C FEEDWATER HEATER.
EXPECTED ACTIONS : l
- 1. NSS ENTERS EOP-101, RPV CONTROL AND ALSO MONITORS KEY CTMT. PARAMETERS.
- 2. NCO's PERFORM POST SCRAM ACTIONS, USE l RFP FOR LEVEL CONTROL AND TURBINE '
BYPASS VALVES FOR PRESSURE CONTROL.
- 3. SNSS SHOULD REFER TO ECG. :
6.28D O t
I ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 09:48 MESSAGE #: 29D DRILL TIME : 01:48 TO :- CONTROL ROOM STAFF FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : YOU HAVE JUST RECEIVED THE FOLLOWING ALARMS: OVERHEAD Al-ES) SACS LOOP B TROUBLE S (OVERHEAD Al-B4) SACS /TACS LOOP PRESS LO (OVERHEAD Al-B3) SSWS INTAKE B TROUBLE SSWS PANEL A/B/C/D C516 (OVERHEAD Al-D2) RADIATION MONITORING ALARM /TRBL (OVERHEAD C6-C1) BOP SAFETY SYS OUT OF SVCE (OVERHEAD D1-A4) CONTAINMENT ISOLATION VALVE O/PF (OVERHEAD D1-B3) 4.16 KV SYS INCOMING BRKR MALF (OVERHEAD E3-E2) USS FEEDER BRKR TRBL (OVERHEAD E3-E3) 4.16 KV FDR TO USS XFMR BRKR MALF (OVERHEAD E3-F2) 13.8 KV BUS LOCKOUT RELAY TRIP (OVERHEAD E3-A2) STA SERVICE TRANSFORMER lok 502 TRBL (OVERHEAD E3-A4) STA SERVICE TRANSFORMER 1BX501 TRBL (OVERHEAD E3-B4)
- THIS IS A DRILL !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS REFEREE NOTES :
O 1. MESSAGE FOR DARK BOARD CONTROL ONLY. THE TURBINE BLADING EJECTED INTO THE HOPERESULTING CREEK SWITCHYARD 2. DAMAGED 13.8 KV RING BUS SECTION 2 AND 8, IN A FAST HAS "B" SIDE STATION SERVICE TRANSFER OF LOADS NORMALLY POWERED BY THE TRANSFORMERS TO THE "A" SIDE STATION SERVICE TRANSFORMER.
- 3. DUE TO A FAILURE OF THE "B" 4160 VAC VITAL BUS ALTERNATE FEEDER BREAKER, THE "B" VITAL BUS DEENERGIZES.
EXPECTED ACTIONS :
- 1. THE CREW RECOGNIZES THE FAST TRANSFER OF LOADS FROM THE "B" SIDE STATION SERVICE TRANSFORMERS TO THE "A" SIDE STATION SERVICE TRANSFORMER.
- 2. THE CREW RECOGNIZES THE LOSS OF THE "B" 4160 VAC VITAL BUS.
- 3. THE CREW ATTEMPTS TO MANUALLY START THE "B" EDG FROM THE CONTROL ROOM.
6.29D O i
ARTIFICIAL ISLAND l EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 09:48 MESSAGE #: 30D <
- CONTROL ROOM STAFF DRILL TIME : 01:48 TO FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) !
MESSAGE : YOU HAVE JUST RECEIVED THE FOLLOWING ALARMS (OVERHEAD AND INDICATIONS: E3-C4) ALARMS: STA SERVICE TRANSFORMER 1BX503 TRBL STA SERVICE TRANSFORMER 1DX501 TRBL (OVERHEAD E3-D1) 250 VDC SYSTEM TROUBLE (OVERHEAD D3-E2) 125 VDC SYSTEM TROUBLE (OVERHEAD D3-F2) 120 VAC UPS TROUBLE (OVERHEAD D3-E3) 24 VDC SYSTEM TROUBLE (OVERHEAD D3-F3) INDICATIONS:
"B" SERVICE WATER PUMP TRIPS "B" SACS PUMP TRIPS "B" RHR IS UNAVAILABLE DUE TO BUS LOCKOUT "B" CORE SPRAY PUMP IS UNAVAILABLE DUE TO BUS LOCKOUT "B" SLC PUMP IS UNAVAILABLE "B" RACS PUMP IS UNAVAILABLE "B" & "F" FRVS RECIRC FANS ARE UNAVAILABLE **************************************LL
- THIS IS A DRI !!!
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS REFEREE NOTES :
- 1. MESSAGE FOR DARK BOARD CONTROL ONLY.
- 2. THE TURBINE BLADING EJECTED INTO THE HOPE CREEK SWITCHYARD HAS DAMAGED 13.8 KV RING BUS SECTION 2 AND 8, RESULTING IN A FAST "B" SIDE STATION SERVICE TRANSFER OF LOADS NORMALLY POWERED BY THE TRANSFORMERS TO THE "A" SIDE STATION SERVICE TRANSFORMER.
- 3. DUE TO A FAILURE OF THE "B" 4160 VAC VITAL BUS ALTERNATE FEEDER BREAKER, THE "B" VITAL BUS DEENERGIZES.
EXPECTED ACTIONS :
- 1. THE CREW RECOGNIZES THE FAST TRANSFER OF LOADS FROM THE "B" SIDE STATION SERVICE TRANSFORMERS TO THE "A" SIDE STATION SERVICE TRANSFORMER. )
- 2. THE CREW RECOGNIZES THE LOSS OF THE "B" 4160 VAC VITAL BUS.
- 3. THE CREW ATTEMPTS TO MANUALLY START THE "B" EDG FROM THE CONTROL ROOM.
6.30D O .
t ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM
/" REAL TIME : 09:48
- h)
MESSAGE #: TO : 31 EQUIPMENT OPERATOR DRILL TIME : 01:48 : FROM : IN PLANT REFEREE LOCATION : TURBINE BUILDING, ELEVATION 155' $ MESSAGE : YOU HAVE JUST OBSERVED THE FOLLOWING:
- 1) A LOUD BANG COMING FROM THE MAIN TURBINE ENCLOSURE.
- 2) AS YOU LOOK EAST, YOU SEE TWO OBJECTS PENETRATING THE EAST WALL OF THE TUREINE BUILDING, '
- 3) OVERALL MAIN TURBINE NOISE HAS INCREASED SIGNIFICANTLY.
t b
**************************************LL
- THIS IS A DRI !!!-
!!1 *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS O REFEREE NOTES (REFER TO SUPPLEMENTAL SCENARIO #7.06)
- 1. ISSUE THIS MESSAGE TO THE EQUIPMENT OPERATOR DISPATCHED TO MANUALLY CLOSE THE #6C FEEDWATER HEATER CONDENSATE INLET VALVE.
- 2. IT IS CRITICAL TO THE DRILL TIMELINE THAT THE OPERATOR RECEIVE THIS INFORMATION AND THAT THE INFORMATION IS PROVIDED TO THE SNSS AT THE SIMULATOR.
r EXPECTED ACTIONS :
- 1. EQUIPMENT OPERATOR PROVIDES INFORMATION TO THE SNSS.
6.31 O
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM , O 31D REAL TIME : 09:49 Q MESSAGE #: TO : CONTROL ROOM STAFF DRILL TIME : 01:49 FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : YOU HAVE JUST RECEIVED THE FOLLOWING ALARMS AND INDICATIONS: ALARMS: (OVERHEAD A6-E1) MAIN CONDENSER A VACUUM LO MAIN CONDENSER B VACUUM LO (OVERHEAD A6-E2) MAIN CONDENSER C VACUUM LO (OVERHEAD A6-E3) CONDENSATE TRAIN A TROUBLE (OVERHEAD A6-F1) CONDENSATE TRAIN B TROUBLE (OVERHEAD A6-F2) CONDENSATE TRAIN C TROUBLE (OVERHEAD A6-F3) CNDS RECIRC CAPACITY EXCEEDED (OVERHEAD A6-F4) RFP TURBINE TRIP (OVERHEAD B3-E1) RPV LEVEL 4 (OVERHEAD A7-CS) RPV LEVEL 3 (OVERHEAD C5-DS)
*************************************ILL
- THIS IS A DR !!!
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS REFEREE NOTES :
- 1. THIS MESSAGE FOR DARK BOARD DRILL CONTROL ONLY.
- 2. ALARMS AND INDICATIONS ARE NECESSARILY LIMITED TO KEY ITEMS.
- 3. THE INCREASED MAIN TURBINE VIBRATION CONDITION HAS RESULTED IN A FAILURE OF THE MAIN CONDENSER ALONG WITH THE PRIMARY CONDENSATE PUMP SUCTION HEADER.
- 4. ENSURE NCO RESPONDS TO ALARMS APPROPRIATELY.
?
EXPECTED ACTIONS :
- 1. NSS ENTERS EOP-101, RPV CONTROL AND ALSO MONITORS KEY CTMT. PARAMETERS.
2, NCO's CONTROL REACTOR WATER LEVEL USING HPCI AND OR RCIC. SRVS ARE USED FOR PRESSURE CONTROL. 6.31D , O I _ . _ _ _ _ _ _ _ _ _ _
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE #: 32D REAL TIME : 09:49 CONTROL ROOM STAFF DRILL TIME : 01:49 TO : FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : YOU HAVE JUST RECEIVED THE FOLLOWING ALARMS AND INDICATIONS: ALARMS: SRV LO LO SET ARMED (OVERHEAD Cl-E5) ADS / SAFETY RELIEF VALVE NOT CLOSED (OVERHEAD Cl-A3) INDICATIONS : REACTOR PRESSURE IS INCREASING. MAIN CONDENSER VACUUM IS RAPIDLY DEGRADING. MAIN CONDENSER DRIP TRAY CONDUCTIVITY IS INCREASING RAPIDLY. CDI IS INCREASING RAPIDLY. MAIN GENERATOR HYDROGEN PRESSURE IS DECREASING RAPIDLY.
- THIS IS A DRILL !!! *
*- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS 1!!
REFEREE NOTES : f 1. THIS MESSAGE FOR DARK BOARD DRILL CONTROL ONLY. l 2. ALARMS AND INDICATIONS ARE NECESSARILY LIMITED TO KEY ITEMS.
- 3. THE INCREASED MAIN TURBINE VIBRATION CONDITION HAS RESULTED IN A FAILURE OF THE MAIN CONDENSER ALONG WITH THE PRIMARY CONDENSATE PUMP SUCTION HEADER.
- 4. ENSURE NCO RESPONDS TO ALARMS APPROPRIATELY.
EXPECTED ACTIONS :
- 1. NSS ENTERS EOP-101, RPV CONTROL AND ALSO MONITORS KEY CTMT. PARAMETERS.
- 2. NCO's CONTROL REACTOR WATER LEVEL USING HPCI AND OR RCIC. SRVS ARE USED FOR PRESSURE CONTROL.
6.32D
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM p REAL TIME : 09:50 Q MESSAGE #: TO : 33 MGH SECURITY SUPERVISOR DRILL TIME : 01:50 FROM : SECURITY PATROL LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : YOU ARE CURRENTLY ON SECURITY PATROL ON THE EAST SIDE OF THE HOPE CREEK TURBINE BUILDING WHEN YOU OBSERVE THE FOLLOWING: YOU HEAR A LOUD BANG AND LOOK UP TOWARDS THE TURBINE BLDG AND SEE TWO RUST COLORED OBJECTS THAT HAVELAND JUST PENETRATED IN THE THE EAST HOPE CREEK WALL OF THE HOPE CREEK TURBINE BUILDING, SWITCHYARD. IT LOOKS LIKE SOME LINES WERE HIT.
**************************************LL
- THIS IS A DRI 111
- DO NOT INITIATE ACTIONS AFFECTING NLPMAL PLANT OPERATIONS O REFEREE NOTES :
(~) (REFER TO SUPPLEMENTAL SCENARIO #7.05)
- 1. HAVE SECURITY CALL THE CONTROL ROOM (SIMULATOR) ON DID PHONE EXTENSION 3339.
- 2. THE RUST COLORED OBJECTS ARE 2 PIECES OF MAIN TURBINE BLADING THAT HAVE PENETRATED THE TURBINE CASING AND THEN THE EAST WALL OF THE TURBINE BUILDING AND HAVE IMPACTED IN THE HOPE CREEK SWITCHYARD.
- 3. THERE IS NO EXPLOSION FROM THE IMPACT.
EXPECTED ACTIONS :
- 1. SNSS DIRECTS NCO TO MAKE PAGE - l ANNOUNCEMENT REGARDING OBJECTS. !
- 2. SNSS DISPAfCHES EO TO DETERMINE l EXTENT OF DAMAGE. I
- 3. DECLARE AN ALERT PER ECG SECTION 13.E, TURBINE ROTATING COMPONENT FAILURE WITH CASING PENETRATION.
6.33 s J
1 4 ARTIFICIAL ISLAND ' EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 09:51 MESSAGE #: 33D
- CO'iTROL ROOM STAFF DRILL TIME : 1 0..:51 TO FROM : S1MULi. TOR REFEREE LOCATION : SIMULATOR (HOPE CREEK)
MESSAGE : YOU HAVE JUST RECEIVED THE FOLLOWING INDICATIONS:
"B" EDG IS RUNNING. "B" VITAL BUS.
"B" EDG OUTPUT BREAKER IS CLOSED ONTO THE "B" SERVICE WATER PUMP IS RUNNING.
"B" RACS PUMP IS RUNNING.
"B" SACS PUMP IS RUNNING.
IN ADDITION, "B" RHR IS AVAILABLE.
"B" CORE SPRAY PUMP IS AVAILABLE.
"B" SLC PUMP IS AVAILABLE.
"B" & "F" FRVS RECIRC FANS ARE AVAILABLE.
**************************************LL
- THIS IS A DRI !!!
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS REFEREE NOTES :
O 1. 2. MESSAGE FOR DARK BOARD CONTROL ONLY. FOLLOWING THE LOSS OF THE "B" SIDE STATION SERVICE TRANSFORMERS 4160 VAC ALTERNATE FEEDER BREAKER, THE r AND FAILURE OF THE "B" "B" 4160 VAC VITAL BUS DEENERGIZED.
- 3. STARTING OF THE "B" EDG AND CLOSURE OF THE ASSOCIATED OUTPUT BREAKER RESULTS IN RESTORATION OF THE BUS AND ITS ASSOCIATED LOA .
EXPECTED ACTIONS :
- 1. THE CREW RECOGNIZES THAT THE "B" EDG SUCCESSFULLY STARTS AND LOADS ONTO THE "B" 4160 VAC VITAL BUS.
- 2. THE CREW VERIFIES SUCCESSFUL STARTING OF "B" VITAL BUS LOADS VIA THE LOP SEQUENCER.
6.33D , O l l
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM o REAL TIME : 09:55 MESSAGE #: 34 DRILL TIME : 01:55 TO : CONTROL ROOM STAFF FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : YOU HAVE JUST RECEIVED THE FOLLOWING COMPUTER POINTS ON 1B02 " FIRE TURBINE BLDG EL. 137'" MAIN GEN EXCITER CO2 SYS 1B03 "ACTN TURBINE BLDG EL. 137'" MAIN GEN EXCITER CO2 SYS 1G10 ELECTRIC FIRE PUMP RUNNING. 1G13 DIESEL FIRE PUMP RUNNING. 1A56 " FIRE TURBINE BLDG EL. 137'" 1D8 TURBINE BLDG SOUTH WATER SPRAY SYS. 1A57 "ACTN TURBINE BLDG EL. 137'" 1D8 TURBINE BLDG SOUTH WATER SPRAY SYS.
+******************************************* **************************HIS
- T IS A DRILL !!! !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS O REFEREE NOTES :
b 1. ISSUE THIS MESSAGE AFTER THE CONTROL ROOM STAFF RECEIVES OVERHEAD ALARM A2-A5, FIRE PROT PANEL 10C671 TROUBLE"
- 2. THIS IS TIME CRITICAL TO THE SCENARIO TIMELINE.
EXPECTED ACTIONS :
- 1. CONTROL ROOM CREW RECOGNIZES THE RECEIPT OF SEVERAL FIRE ALARM COMPUTER POINTS THROUGHOUT THE TURBINE BUILDING.
- 2. SNSS CONTACTS FIRE PROTECTION TO RESPOND.
- 3. NSTA REFERS TO PREFIRE PLAN.
6.34 L) 1 l 1
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM 35 REAL TIME : 09:56 MESSAGE #: TO : CONTROL ROOM STAFF DRILL TIME : 01:56 FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : YOU HAVE JUST RECEIVED THE FOLLOWING COMPUTER POINTS ON 10C671: 1A50 " FIRE TURBINE BLDG EL. 102'" H2 SEAL OIL UNIT WATER SPRAY SYS. 1D7 1A51 "ACTN TURBINE BLDG EL. 302'" H2 SEAL OIL UNIT WATER SPRAY SYS. 1D7
- THIS IS A DRILL !!!
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS !!!
i p REFEREE NOTES :
- 1. ISSUE THIS MESSAGE AFTER THE CONTROL ROOM STAFF RECEIVES OVERHEAD ALARM A2-AS, FIRE PROT PANEL 10C671 TROUBLE"
- 2. THIS IS TIME CRITICAL TO THE SCENARIO TIMELINE.
EXPECTED ACTIONS : *
- 1. CONTROL ROOM CREW RECOGNIZES THE RECEIPT OF SEVERAL FIRE ALARM COMPUTER POINTS THROUGHOUT THE TURBINE BUILDING.
- 2. SNSS CONTACTS FIRE PROTECTION TO RESPOND.
- 3. NSTA REFERS TO PREFIRE PLAN.
6.35 , O
I l l ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM () MESSAGE #: TO : 35C CONTROL ROOM CREW SIMULATOR REFEREE REAL TIME DRILL TIME :
- 09:58 01:58 l
( 1 FROM f LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : THIS IS A CONTINGENCY MESSAGE YOU SHOULD DISPATCH AN EQUIPMENT OPERATOR TO SURVEY THE TURBINE BUILDING.
**************************************LL
- THIS IS A DRI !!!
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS REFEREE NOTES :
O-(REFER
- 1. TO SUPPLEMENTAL SCENARIO #7.06) ISSUE THIS ME{
i
- 2. IN ORDER TO MAINTAIN SCENARIO CONTROL, IT IS IMPORTANT THAT DAMAGE 1 ASSESSMENT INFORMATION BE PROVIDED TO THE SNSS.
l i j l I EXPECTED ACTIONS :
- 1. THE CREW DISPACHES AN EQUIPMENT OPERATOR TO PERFORM DAMAGE ASSESSMENT IN THE TURBINE BUILDING.
I 6.35C l l O 1
ARTIFICIAL ISLAND , EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 09:59
) MESSAGE #: 36C 01:59
- CONTROL ROOM CREW DRILL TIME : l TO l FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) .
MESSAGE : THIS IS A CONTINGENCY MESSAGE YOU SHOULD DISPATCH AN EQUIPMENT OPERATOR TO SURVEY THE HOPE CREEK SWITCHYARD. ,
**********w************************
- THIS IS A DRILL !!! 1!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS REFEREE NOTES :
O (REFER 1. 2. TO SUPPLEMENTAL SCENARIO #7.05) ISSUE THIS ME IN ORDER TO MAINTAIN SCENARIO CONTROL, IT IS IMPORTANT THAT DAMAGE ASSESSMENT INFORMATION BE PROVIDED TO THE SNSS. EXPECTED ACTIONS :
- 1. THE CREW DISPACHES AN EQUIPMENT OPERATOR TO PERFORM DAMAGE ASSESSMENT IN THE HOPE CREX SWITCHYARD.
6.36C
j ARTIFICIAL ISLAND I EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 09:59 MESSAGE #: 37C TO : CONTROL ROOM CREW DRILL TIME : 01:59 FROM : SIMULATOR REFEREE , LOCATION : SIMULATOR (HOPE CREEK) 1 i MESSAGE : ! THIS IS A CONTINGENCY MESSAGE YOU SHOULD DISPATCH AN EQUIPMENT OPERATOR TO DETERMINE WHY. THE "B" VITAL BUS DID NOT SUCCESSFULLY FAST TRANSFER WHEN THE "B" SIDE STATION SERVICE TRASNSFORMER WERE LOST. , 1
- THIS IS A DRILL *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS !!!
REFEREE NOTES : O (REFER
- 1. TO SUPPLEMENTAL SCENARIO #7.07) ISSUE THIS MESS IN ORDER TO MAINTAIN SCENARIO CONTROL, IT IS IMPORTANT THAT THE 2.
CAUSE FOR FAILURE OF THE "B" VITAL BUS BE IDENTIFIED. 3 EXPECTED ACTIONS :
- 1. THE CREW DISPACHES AN EQUIPMENT OPERATOR TO THE "B" VITAL BUS SWITCHGEAR TO INVESTIGATE THE REASON FOR THE FAST TRANSFER FAILURE.
6.37C O :
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM (O REAL TIME : 10:04 () MESSAGE #: TO : 38 EQUIPMENT OPERATOR DRILL TIME : 02:04 FROM : IN PLANT REFEREE LOCATION : HOPE CREEK SWITCHYARD MESSAGE : YOU HAVE JUST OBSERVED THE FOLLOWING:
- 1. ONE 13.8 KV POTHEAD, LOCATED ON THE 1BX501 TRANSFORMER FEEDER IS DAMAGED. A RUST COLORED PIECE OF METAL IS PERTRUDING FROM THE POTHEAD. A SECOND PIECE OF METAL HAS APPARENTLY DAMAGED 13.8 KV BUS SECTION 8 AND IS LAYING ON THE GROUND.
- 3. THERE ARE NO FIRES PRESENT,
- 4. THERE APPEARS TO BE 2 HOLES IN THE EAST WALL OF THE HOPE CREEK TURBINE BUILDING.
- 5. THE FOLLOWING 13.8 KV RING BUS BREKKERS HAVE TRIPPED OPEN:
BS 1-2 AND BS 9-0.
- 6. THERE DOES NOT APPEAR TO BE ANY OTHER VISIBLE DAMAGE TO PLANT STRUCTURE FROM THE HOPE CREEK SWITCHYARD.
- THIS IS A DRILL !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS A REFEREE NOTES :
I V (REFER TO SUPPLEMENTAL SCENARIOS #7.05)
- 1. ENSURE EO REPORTS THE CONDITIONS TO THE CONTROL ROOM (SIMULATOR).
- 2. ENSURE EO REPORTS THAT THERE APPEAR TO BE TWO HOLES IN THE EAST WALL OF THE TURBINE BUILDING.
- 3. BE PREPARED TO PROVIDE ADDITIONAL INFORMATION AS NECESSARY FROM THE SUPPLEMENTAL SCENARIO.
EXPECTED ACTIONS :
- 1. SNSS REFERS TO ECG FOR EVENT DECLARATION AFTER RECEIVING A COMPLETE DESCRIPTION OF THE DAMAGE THAT HAS OCCURRED IN THE SWITCHYARD.
- 2. SNSS OBTAINS ADDITIONAL INFORMATION FROM EQUIPMENT OPERATORS DISPATCHED TO DETERMINE THE EXTENT OF DAMAGE TO THE PLANT.
6.38 i v l
l ARTIFICIAL ISLAND i l EMERGENCY PREPAREDNESS MESSAGE FORM A REAL TIME : 10:04 : (j MESSAGE #: 39 !
' TO : EQUIPMENT / FIRE PROT. OPERATOR DRILL TIME : 02:04 I FROM : OSC TEAM REFEREE l LOCATION : VARIOUS LOCATION IN TURBINE BUILDING MESSAGE :
YOU HAVE JUST OBSERVED THE FOLLOWING: ON ELEVATION 137' (AT FRONT STANDARD)
- 1. THERE IS LIMITED LIGHTING IN THE AREA.
- 2. MAIN TURBINE BEARING OIL PRESSURE INDICATES 0 PSIG.
- 3. NOISE LEVEL FROM MAIN TURBINE ENCLOSURE IS HIGHER THAN NORMAL.
- 4. THERE ARE NO FIRES PRESENT OR SMOKE IN THIS AREA.
ON ELEVATION 137'(AT THE GENERATOR END)
- 1. YOU OBSERVE A 2 FOOT SECTION OF TWISTED UP TURBINE BLADING ON THE FLOOR IN FRONT OF "B" FEED PUMP TURBINE ROOM.
- 2. THERE IS LIMITED LIGHTING IN THE AREA.
- 3. THERE DOES NOT APPEAR TO BE ANY SIGNIFICANT DAMAGE TO THE MAIN GENERATOR.
- 4. THERE ARE SEVERAL SMALL FIRES BURNING AROUND THE GENERATOR.
***************************************L
- THIS IS A DRIL !!! !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS p REFEREE NOTES : '
Q (REFER TO SUPPLEMENTAL SCENARIOS #7.06)
- 1. ISSUE THE APPROPRIATE INFORMATION TO THE EQUIPMENT OPERATOR AS HE MOVES THROUGH THE AREA DESCRIBED. '
- 2. ENSURE THE EQUIPMENT OPERATOR PROVIDES INFO TO THE SNSS.
- 3. BE PREPARED TO PROVIDE ADDITIONAL INFORMATION AS NECESSARY FROM THE SUPPLEMENTAL SCENARIO.
EXPECTED ACTIONS :
- 1. SNSS REFERS TO ECG FOR EVENT DECLARATION AFTER RECEIVING A COMPLETE DESCRIPTION OF THE DAMAGE THAT HAS OCCURRED IN THE TURBINE BLDG
- 2. SNSS OBTAINS ADDITIONAL INFORMATION FROM EQUIPMENT OPERATORS DISPATCHED TO THE SWITCHYARD TO DETERMINE THE EXTENT OF DAMAGE TO THE PLANT.
l l 6.39 l V ! i l 1
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 10:04 MESSAGE #: 39C DRILL TIME : 02:04 TO : CONTROL ROOM CREW FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : THIS IS A CONTINGENCY MESSAGE YOU SHOULD DISPATCH THE FIRE BRIGADE TO RESPOND TO FIRES , IN THE TURBINE BUILDING.
- THIS I A DRILL !!!*******************************
*******************************S !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS j
O REFEREE
- 1. NOTES :(REFER TO SUPPLEMENTAL S IN ORDER TO MAINTAIN SCENARIO CONTROL, IT IS IMPORTANT THAT THE 2.
FIRE BRIGADE RESPONDS AND EXTINGUISHES ALL FIRES BY 10:30. EXPECTED ACTIONS :
- 1. THE CREW DISPACHES THE FIRE BRIGADE TO RESPOND TO THE FIRES IN THE TURBINE BUILDING.
6.39C O
I ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 10:05 MESSAGE #: 40 DRILL TIME : 02:05 TO : EQUIPMENT / FIRE PROT. OPERATORS FROM : IN PLANT REFEREE LOCATION : VARIOUS LOCATION IN TURBINE BUILDING MESSAGE : YOU HAVE JUST OBSERVED THE FOLLOWING: ON ELEVATION 137' (ALONG THE EAST WALL)
- 1. THERE IS LIMITED LIGHTING IN THE AREA.
- 2. THERE APPEARS TO BE A COUPLE OF HOLES ABOUT 25 FEET UP THE WAL
- 3. NOISE LEVEL FORM MAIN TURBINE ENCLOSURE IS HIGHER THAN NnRMAL.
- 4. THERE ARE NO FIRES PRESENT OR SMOKE IN THIS AREA.
ON ELEVATION 102' (GENERATOR AUXILIARIES AREA)
- 1. THERE IS LIMITED LIGHTING IN THE AREA.
- 2. THE FLOOR IS SLIPPERY. THERE APPEARS TO BE OIL ON THE FLOOR.
- 3. THERE ARE SEVERAL FIRES BURNING IN THE OVERHEAD AREA.
- 4. FIRES ARE BURNING IN THE VICINTY OF THE H2 SEAL OIL SKID.
- 5. THE EMERGENCY H2 SEAL OIL PUMP IS RUNNING.
- 6. SOME DEBRIS HAS FALLEN INTO AREA.
- THIS IS A D RILL !!! !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS REFEREE NOTES :
O (REFER TO SUPPLEMENTAL SCENARIOS #7.06) ISSUE THE AP 1. HE MOVES THROUGH THE AREA DESCRIBED.
- 2. ENSURE THE EQUIPMENT OPERATOR PROVIDES INFO TO THE SNSS.
- 3. BE PREPARED TO PROVIDE ADDITIONAL INFORMATION AS NECESSARY FROM THE SUPPLEMENTAL SCENARIO.
EXPECTED ACTIONS :
- 1. SNSS REFERS TO ECG FOR EVENT DECLARATION AFTER RECEIVING A COMPLETE DESCRIPTION OF THE DAMAGE THAT HAS OCCURRED IN THE TURBINE BLDG
- 2. SNSS OBTAINS ADDITIONAL INFORMATION -
FROM EQUIPMENT OPERATORS DISPATCHED TO THE SWITCHYARD TO DETERMINE THE EXTENT OF DAMAGE TO THE PLANT. 6.40 0
_ _ . . . _ _ _ ~. ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 10:05
>O ' MESSAGE #: 41 DRILL TIME : 02:05 TO : EQUIPMENT / FIRE PROT. OPERATORS '
FROM : IN PLANT REFEREE LOCATION : VARIOUS LOCATION IN TURBINE BUILDING MESSAGE : YOU HAVE JUST OBSERVED THE FOLLOWING: ON ELEVATION 102' (COMMON AREA)
- 1. THERE IS LIMITED LIGHTING IN THE AREA.
- 2. YOU HEAR NOISE COMING FROM THE CONDERSER BAY AREA.
- 3. EMERGENCY BEARING OIL PUMP IS RUNNING.
- 4. THERE ARE NO FIRES PRESENT OR SMOKE IN THIS AREA.
ON ELEVATION 77' (NORTH END)
- 1. THERE IS LIMITED LIGHTING IN THE AREA.
- 2. THERE ARE NO FIRES IN THE AREA
- 3. SIGNIFICANT NOISE APPEARS TO BE COMING FROM THE C' ; DENSER BAY.
*****************************S
- THI IS A DRILL !!! !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL*****************
PLANT OPERATIONS
/ REFEREE NOTES :
(REFER TO SUPPLEMENTAL SCENARIOS #7.06) ISSUE T 1. HE MOVES THROUGH THE AREA DESCRIBED. 2.
- 3. ENSURE THE EQUIPMENT OPERATOR PROVIDES THE SUPPLEMENTAL SCENARIO.
EXPECTED ACTIONS :
- 1. SNSS REFERS TO ECG FOR EVENT DECLARATION AFTER RECEIVING A COMPLETE DESCRIPTION OF THE DAMAGE THAT HAS OCCURRED IN THE TURBINE 3LDG
- 2. SNSS OBTAINS ADDITIONAL INFORMATION FROM EQUIPMENT OPERATORS DISPATCHED TO THE SWITCHYARD TO DETERMINE THE EXTENT OF DAMAGE TO THE PLANT.
6.41 ,, O w - =
i ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS M':,SSAGE FORM REAL TIME : 10:05 42 DRILL TIME : 02:05 MESSAGE #: TO : EQUIPMENT / FIRE PROT. OPERATORS FROM LOCATION : IN PLANT REFEREEVARIOUS LOCATION IN TURBINE B MESSAGE : YOU HAVE JUST OBSERVED THE FOLLOWING: (SOUTH END) ON ELEVATION 77'1. THERE IS LIMITED LIGHTING IN THE ARE R LEADING 2.
- 3. THERE ARE NO FIRES IN THE AREA.THERE ER BAY. IS t
- 4. TO THE PRIMARY CONDENSATE PUMP U
- 5. THE PRIMARY CONDENSATE PUMP AREA IS FLOODED. ,
E APPEARS '
- 6. THE PRIMARY CONDENSATE PUMPS ARE UNDER WA TO BE A FILM OF OIL ON TOP OF THE WATER.
*************************THIS IS A DRILL !!! * * * * * * * * * * * * * * *
- IONS 1!!* **
REFEREE NOTES : RATOR AS (REFER
- 1. TO SUPPLEMENTAL SCENARIOS HE MOVES THROUGH THE AREA DESCRIBED.
S. #7.06 SSARY FROM
- 2. ENSURE THE EQUIPMENT OPERATOR PROVIDES INF ;
- 3. BE PREPARED TO PROVIDE ADDITIONAL INFORMAT .
THE SUPPLEMENTAL SCENARIO. I EXPECTED ACTIONS :
- 1. SNSS REFERS TO ECG FOR EVENT DECLARATION AFTER RECEIVING A COMPLETE DESCRIPTION OF THE DAMAGE THAT HAS OCCURRED IN THE TURBINE BLDG
' 2. SNSS OBTAINS ADDITIONAL INFORMATION FROM EQUIPMENT OPERATORS DISPATCHED TO THE SWITCHYARD TO DETERMINE THE EXTENT OF DAMAGE TO THE PLANT. 6.42 l O
I ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 10:07 43 DRILL TIME : 02:07 MESSAGE #: TO : SHIFT ELECTRICIAN I
- IN PLANT REFEREE FROM AUXILIARY BUILDING, ELEVATION 130' LOCATION :
l MESSAGE : j VITAL BUS SWITCHGEAR ROOM, YOU OBSERVE THE FOLLOWING I IN THE "B" i "B" 4160 VAC VITAL THE NORMAL AND ALTERNATE FEEDERS FOR THE BUS ARE CHANNEL LOP SEQUENCER TRIPPED.THE "B" HAS INITIATED. 1 i
*************************THIS IS A DRILL !!!
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PL O REFEREE NOTES :
(REFER
- 1. TO SUPPLEMENTAL "B" SCENARIO #7.07) ISSU CURRENT STATUS OF THE
- 2. VITAL BUS. ENSURE THAT INDICATIONS ARE RE EXPECTED ACTIONS :
- 1. SHIFT ELECTRICIAN ACKNOWLEDGES THAT THE NORMAL AND ALTERNATE FEEDER VITAL BUS ARE BREAKER FOR THE "B" .
TRIPPED. I 6.43 O
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME ': 10:10 MESSAGE #: 43C DRILL TIME : 02:10 TO : CONTROL ROOM STAFF FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : THIS IS A CONTINGENCY MESSAGE YOU SHOULD DISPATCH AN EQUIPMENT OPERATOR TO SECURE THE FOLLOWING 250 VDC OIL PUMPS: (ESOP) TURBINE GENERATOR EMERGENCY SEAL OIL PUMP (EBOP) TURBINE GENERATOR EMERGENCY BEARING OIL PUMP "A" RFPT EMERGENCY DC OIL PUMP "B" RFPT EMERGENCY DC OIL PUMP "C" RFPT EMERGENCY DC OIL PUMP
*******************************S
- THIS I A DRILL !!! 1!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS REFEREE NOTES :
O (REFER TO SUPPLEMENTAL SCENARIO #7.06) ISSUE THIS 1. STAFF IS GOING TO DISPATCH AN OPERATOR TO SECURE THE DC OIL
- 2. THIS IS NOT CRITICAL TO THE SCENARIO TIMELINE.
EXPECTED ACTIONS : <
- 1. CONTROL ROOM CREW DISPATCHES l AN EQUIPMENT OPERATOR TO OPEN THE J BREAKERS FOR THE DC OIL PUMPS l LOCATED IN THE TURBINE BUILDING. l I
l 6.43C
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM 10:14 / REAL TIME : 44 DRILL TIME : 02:14 MESSAGE #: TO : EQUIPMENT OPERATOR
- OSC REFEREE FROM TURBINE BUILDING, ELEVATIO:4 102' LOCATION :
MESSAGE : YOU HAVE SUCCESSFULLY AT THE 250 VDC NON 1E SWITCHGEAR 10D170, . OPENED THE FOLLOWING DC MOTOR BREAKERS: (ESOP) (EBOP) 72-17013 72-17014 TURBINE GENERATOR EMERGENCY SE "A" RFPT EMERGENCY OIL PUMP 72-17021 72-17022 "B" RFPT EMERGENCY OIL PUMP 72-17023 "C" RFPT EMERGENCY OIL PUMP 1
*************************THIS IS A DRILL !!! NS !!! * * *************** i REFEREE NOTES :
(REFER TO SUPPLEMENTAL SCENARIO #7.06) HE 250 VDC N 102', AT
- 1. ISSUE SWITCHGEAR THIS10D170, MESSAGE LOCATED WHEN THE EQUIPMENT ON TURBINE BUILDING OPERA ELEVATIO BREAKER.
ILL" 2. 3. THE NORTH END OF THE BUILDING A THIS ACTIVITY IS NOT TIME CRITICAL. , EXPECTED ACTIONS
- 1. EQUIPMENT OPERATOR NOTIFIES THE OSC THAT THE DC OIL PUMP MOTOR BREAKERS ,
HAVE BEEN OPENED. i 1 6.44 ; l
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM (] REAL TIME : 10:15 02:15 MESSAGE #: 44C DRILL TIME : TO : SNSS FROM : LEAD SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : THIS IS A CONTINGENCY MESSAGE: YOU SHOULD DECLARE AN ALERT IN ACCORDANCE WITH ECG SECTIO TURBINE ROTATING COMPONENT FAILURE WITH CASING PE
*************************THIS IS A DRILL !!! !!!
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OP REFEREE NOTES :
)
- 1. ISSUE THIS MESSAGE AS NEEDED TO MAINTAIN SCENARIO
- 2. BE PREPARED TO PROVIDE MARKED UP COPIES OF ATT FOR DRILL USE.
- 3. CONFER WITH THE HEAD REFEREE PRIOR TO ISSUING THIS
- 4. THE SNSS MAY TAKE AN EXTREMELY CONSERVATIVE APP DECLARATION AND ATTEMPT TO DECLARE A SITE AREA ECG SECTION 13.G.
EXPECTED ACTIONS :
- 1. SNSS SHOULD REFER TO ECG SECTION 13.E AND DECLARE AN ALERT. ,
- 2. TSC AND OSC ACTIVATION PROCESS BEGINS.
6.44C O
+
s ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM : 10:20 REAL TIMb 02:20 MESSAGE #: 4SC DRILL TIME : TO : SNSS
- FROM : LEAD SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK)
MESSAGE : THIS IS A CONTINGENCY MESSAGE: FOR SCENARIO CONTROL, DO NOT IMPLEMENT ACCOUNTABILITY AT T
*************************THIS IS A DRILL !!! IONS !!1
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PL
- i REFEREE NOTES : INE.
- 1. ISSUE THIS MESSAGE AS NEEDED TO MAINTAIN SC
- 2. THIS IS CRITICAL TO THE DRILL TIMELINE.
EXPECTED ACTIONS
- 1. SNSS DOES NOT IMPLEMENT ACCOUNTABILITY AT THIS TIME.
I i l 6.45C O V l
> - _ ' wMT -
i I ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM ) REAL TIME : 10:22 C\ ( ,/ MESSAGE #: 45D DRILL TIME : 02:22 TO : CONTROL ROOM STAFF FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : ' YOU HAVE JUST RECEIVED THE FOLLOWING ALARMS AND INDICATIONS ALARMS: (OVERHEAD E4-A3) DIESEL ENG PNL A/B/C/D C422 (OVERHEAD A7-A1) RHR LOGIC B OUT OF SERVICE (OVERHEAD A7-B1) RHR LOOP B TROUBLE (OVERHEAD D3-E3) 120VAC UPS TROUBLE (OVERHEAD D3-F2) 125VDC SYSTEM TROUBLE (OVERHEAD E4-A1) DIESEL GENERATOR BRKR MALF (OVERHEAD E4-A2) DIESEL ENG PNL A/B/C/D C423 (OVERHEAD E5-C1) CHILLER A/BK403 PNL A/BC 487 (OVERHEAD Cl-C1) SLC SQUIB VLV LOSS OF CONTINUITY INDICATIONS: EDG "B" BKR OPEN LIGHT FLASHING EDG "B" STOP LIGHT FLASHING
******************************IS
- THIS A DRILL !!! !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS REFEREE NOTES :
I (REFER
- 1. TO SUPPLEMENTAL SCENARIO # 7.08)THIS MESSA CANNOT BE RESTARTED FROM THE CONTROL ROOM.
- 2. EDG "B" "B" SSWS PUMP,
- 3. ALSO LOST AT THIS SACS THE "B" RM RECIRC FANS,"B" RACS PUMP,"B" T TIME ISPUMP,DG DRYWELL CLR FANS, AND THE "B" TSC CIRC WATER PUMP.
EXPECTED ACTIONS :
- 1. SNSS SHOULD DIRECT THE OSC TO RESPOND TO THE "B" EDG.
- 2. CR STAFF CONTINUE TO FOLLOW EOPs AND MONITOR CONTROL BOARDS.
- 3. NCO's RESPOND TO ALARMS AND EVALUATE l ALL LOADS THAT HAVE BEEN LOST.
6.45D
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM O REAL TIME : 10:25 46 .Q MESSAGE #: TO : OSC TEAM LEADER DRILL TIME : 02:25 FROM : OSC REFEREE LOCATION : AUXILIARY BUILDING, ELEVATION 130' MESSAGE : YOU HAVE RECEIVED THE FOLLOWING ALARMS AND INDICATIONS: REMOTE GENERATOR CONTROL PANEL BC423 ALARMS: LUBE OIL PRESSURE LOW SHUTDOWN LUBE OIL PRESSURE LOW PRE-TRIP LUBE OIL MAKEUP TANK LEVEL LOW REMOTE GENERATOR CONTROL PANEL BC422 ALARMS: LOCKOUT RELAYS ACTIVATED INDICATIONS: REGULAR LOCKOUT RELAY TRIPPED BACKUP LOCKOUT RELAY TRIPPED
*********************************A
- THIS IS DRILL !!! !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS ,
REFEREE NOTES : O (REFER TO SUPPLEMENTAL SCENARIO #7.08)
- 1. ENSURE THAT INDICATIONS ARE DUE TO THE LOSS OF THE "B" REPORTED EDG, TO THECONDITION AND DEGRADED OSC/SNSS. OF THE 2.
OFFSITE POWER SUPPLY, EDG REPAIRS SHOULD BE GIVEN A HIGH PRIORITY. EDG TO BE RESTARTED, THE GENERATOR LOCKOUT
- 3. IN ORDER FOR THE "B" RELAYS AND THE SHUTDOWN RELAY MUST BE RESET.
EXPECTED ACTIONS :
- 1. OSC TEAM LEADER REPORTS THE PROBABLE .
CAUSE OF THE EDG TRIP TO THE OSC.
- 2. OSC INFORMS SNSS OF REASON FOR TRIP.
- 3. SNSS DIRECTS OSC TO INITIATE REPAIR AND CLEANUP EFFORTS.
I 6.46 O
_ . . m ARTIFICIAL ISLAND - EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 10:28 47 DRILL TIME : 02:28 MESSAGE #: TO : OSC TEAM LEADER FROM : OSC REFEREE ELEVATION 102', "B" EDG AUXILIARY BUILDING, LOCATION : MESSAGE : YOU OBSERVE THE EMERGENCY DIESEL GENERATOR ROOM, IN THE "B" FOLLOWING: LUBE OIL IS OBSERVED ON THE FLO LUBE OIL SUMP. LUBE OIL IS CONTINUING TO FLOW OUT TH EDG REMOTE PANEL 1BC423, YOU OBSERVE THE FOLLOWING ALARMS: AT THE "B" (ANNUNCIATOR F3) LUBE OIL PRESSURE LOW SHUTDOWN (ANNUNCIATOR E3) LUBE OIL PRESSURE LOW PRE-TRIP
*************************THIS IS A DRILL !!! !!!
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLL T REFEREE NOTES :
(REFER
- 1. TO SUPPLEMENTAL CURRENT STATUS OF THE "B" SCENARIO #7.08) ISS
- 2. EMERGENCY DIESEL GENERATOR. ENSUR EXPECTED ACTIONS
- 1. EQUIPMENT OPERATOR ACKNOWLEDGES THAT THE "B" EDG IS TRIPPED AND THAT THE LUBE OIL SUPPLY LINE IS CRACKED.
- 2. EQUIPMENT OPERATOR REPORTS THE CAUSE OF THE TRIP TO THE OSCC/SNSS.
6.47 . U
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 10:30 48 DRILL TIME : 02:30
) MESSAGE #:
TO : FIRE BRIGADE TEAM LEADER FROM : OSC REFEREE LOCATION : TURBINE BUILDING, ELEVATION 137' MESSAGE : YOU HAVE SUCCESSFULLY EXTINGUISHED ALL FIRES BURNING IN T TURBINE BUILDING. i
*********************************A
- THIS IS DRILL !!! !!!
- 3
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS REFEREE NOTES :
O' ' (REFER TO SUPPLEMENTAL SCENARIO #7.06) DELIVER T 1.
- 2. THIS MESSAGE CONCLUDES FIRE FIGHTING ACTIVITIES IN THE TUR l BUILDING.
EXPECTED ACTIONS :
- 1. FIRE BRIGADE TEAM LEADER ACKNOWLEDGES THAT ALL FIRES IN THE TURBINE BUILDING HAVE BEEN EXTINGUISHED.
- 2. NOTIFY THE OSCC OF THE CONDITION.
- 3. ESTABLISH A REFLASH WATCH (SIMULATED) .
6.48 O
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE :FORM 10:51 [] (/ 48D REAL TIME DRILL TIME : 02:51 MESSAGE f: CONTROL ROOM CREW TO : FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK)
- DICATIONS:
MESSAGE YOU HAVE JUST RECEIVED THE FOLLOWING ALARMS ALARMS: (OVERHEAD A7-B2) RHR LOOP D TROUBLE (CRIDS POINT D4424) i RHR/LPCI INJ HV-F017D OPF INDICATIONS: THE OVERLOAD / POWER FAILURE AMBER LIGHT F "D" LPCI INJECTION VALVE IS ILLUMINATED.
*************************THIS IS A DRILL !!! ATIONS !!!
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLAN REFEREE NOTES :
- 1. MESSAGE FOR DARK BOARD CONTROL ONLY. D AT 10:02.
- 2. ENSURE NCO RESPONbS APPROPRIATELY TO ALARMS. CREATES
- 3. THE INSTRUMENT LPCI INJECTION VALVE LINE MOTOR ATIT HAS CREATEDPIPE LEAK IN THE SOUTH 10:51.
A HARS CH "D" A SHORT TO GROUND ON THE EXPECTED ACTIONS :
- 1. CREW RECOGNIZES "D" THATLPCIMOTIVE POWER HAS BEEN LOST TO THE INJECTION VALVE.
- 2. SNSS CONTACTS THE "D" OSCC LPCI TO DISPATCH A TEAM TO CHECK THE INJECTION VALVE MOTOR BREAKER.
6.48D O O
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 10:56 MESSAGE #: 49C DRILL TIME : 02:56 TO : CONTROL ROOM CREW FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : THIS IS A CONTINGENCY MESSAGE YOULPCI SHOULD CONTACT THE OSCC TO DISPATCH A INJECTION VALVE MOTOR BREAKER.
"D"
*************************THIS IS A DRILL !!! !!!
DO NOT INITIATE ACTIONS AFFECTING NORMAL PLA O) (', REFEREE NOTES : (REFER TO SUPPLEMENTAL SCENARIO #7.09) SNSS E
- 1. DELIVER THIS MESSAGE ONLY IF IT APPEARS UNLIKE PPED.
IS NOT GOING "D"TO LPCICONTACT THEMOTOR INJECTION VALVE OSCCBREAKER TO DISPA TRI THE REASON WHY THE EXPECTED ACTIONS
- 1. SNSS CONTACTS THE LPClOSCC TO DISPATCH INJECTION A TEAM TO THE "D" VALVE MOTOR BREAKER.
G.49C
Al<TIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 11:00 50 DRILL TIME : 03:00 MESSAGE #: TO : OSC TEAM FROM : OSC REFEREE TURBINE BUILDING, ELEVATION 120' LOCATION : 4 MESSAGE : YOU HAVE SUCCESSFULLY COMPLETED REPAIRS TO THE
*************************THIS IS A DRILL !!!
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT O O REFEREE NOTES :
(REFER TO SUPPLEMENTAL SCENARIO #7.02)
- 1. DELIVER THIS MESSAGE AT 11:00 ONLY IF AN OSC TEAM
- REPAIR ACTIVITIES ASSOCIATED WITH THE 10-B-130 UNIT AND DEMONSTRATED APPROPRIATE REPAIR ACTIVITIES.
EXPECTED ACTIONS :
- 1. THE OSC TEAM ACKNOWLEDGES THAT THE 10-B-130 HAS BEEN SUCCESSFULLY REPAIRED AND IS READY TO BE PLACED IN SERVICE.
- 2. THE OSC TEAM LEADER CONTACTS THE OSCC AND PROVIDES THE INFORMATION.
6.50 O
)
ARTIFICIAL ISLAND
/q EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 11:02 MESSAGE #: 50D DRILL TIME : 03:02 TO : CONTROL ROOM STAFF FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK)
MESSAGE : YOU HAVE JUST RECEIVED THE FOLLOWING ALARMS AND IND ALARMS: (OVERHEAD D1-C3) EXCESS FLOW CHECK VALVE CLOSED (CRIDS POINT D5825) RCP BC204 EX FL CHK V CH B/W/X INDICATIONS:
"B" CHANNEL FUEL ZONE LEVEL INSTRUMENTATION FAILED
#5 JET PUMP FLOW INDICATION FAILED LOW.
*************************THIS IS A DRILL !!! !!!
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPE 1.EFEREE NOTES :
MESSAGE FOR DARK BOARD CONTROL ONLY. THE LEAK ON THE "B" CHANNEL FUEL ZONE VARIABLE LEG CAUSES FLOW 1. 2. EXCEED 5 GPM, AND THE ASSOCIATED CHECK VALVE GOES CLOSED, CAUSING THE INSTRUMENT TO FAIL DOWNSCALE.
- 3. ENSURE NCO RESPONDS TO ALARMS APPROPRIATELY.
EXPECTED ACTIONS :
- 1. CONTROL ROOM STAFF RECOGNIZES ALARM FOR CLOSURE OF AN EXCESS FLOW CHECK VALVE.
- 2. SNSS CONTACTS THE OSCC TO DISPATCH A TEAM TO THE 1BC204 PANEL TO DETERMINE WHICH EXCESS FLOW CHECK VALVE HAS CLOSED.
- 3. NSTA AND NCO COORDINATED EFFORTS TO DETERMINE INSTRUMENTATION EFFECTED BY CLOSURE OF THE EXCESS FLOW CHECK VALVE.
6.50D f [v} l
l ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 11:04 51 DRILL TIME : 03:04 MESSAGE #: TO : OSC TEAM
- OSC REFEREE FROM LogATION : REACTOR BUILDING, ELEVATION 77' MESSAGE :
YOU OBSERVE THE FOLLOWING: AT MOTOR CONTROL CENTER 10-B-242, (52-242052) IS FOUND "D" LPCI INJECTION VALVE MOTOR BREAKER TRIPPED. ATTEMPTS TO RESET THE BREAKER ARE UNSUCCESSFUL.
*************************THIS IS A DRILL !!!
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLA REFEREE NOTES :
(REFER TO SUPPLEMENTAL SCENARIO #7.09) ISSU 1. MOTOR CONTROL CENTER.
- 2. USE DID PHONE EXTENSION 3339 OR RADIO TO CON
- 3. ALL VERBAL COMMUNICATIONS MUST START WITH "TH EXPECTED ACTIONS :
- 1. OSC TEAM ACKNOWLEDGES THAT THE "D" LPCI INJECTION VALVE MOTOR BREAKER IS TRIPPED AND WILL NOT RESET.
- 2. OSC TEAM REPORTS THE FINDINGS TO THE OSC COORDINATOR. .
6.51 i l l l l
- *e w- y- %
' __ ---__ .- =-- - - --- _ -- .-__
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM (~ REAL TIME : 11:08 ; (_- MESSAGE #: 52C DRILL TIME : 03:08 i TO : SNSS FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : THIS IS A CONTINGENCY MESSAGE DIRECT THE OSCC TO DISPATCH AN OPERATOR TO EX CHECK VALVE PANEL 1BC204 TO INVESTIGATE.
** * * * * * * * * * * * * * * * * * * * * * <: *
- THI S I S A DRILL ! ! ! !!!
DO NOT INITIATE ACTIONS AFFECTING NORMAL PLA
) REFEREE NOTES :
(REFER ISSUE TOTHISSUPPLEMENTAL MESSAGE SCENARIO AS #7.10)TO MAINTAIN E 1.
- 2. THE LEAK ON THE "B" CHANNEL FUEL ZONE LEVEL INSTRUMENTSCEN NEEDED HAS RESULTED IN CLOSURE OF EXCESS VARI LEG IN THE SOUTH PIPE CHASE, AS LEAKAGE EXCEEDS 5 GPM.
FLOW CHECK VALVE 1BBXV-3734B, EXPECTED ACTIONS :
- 1. SNSS DIRECTS OSCC TO DISPATCH AN OSC TEAM TO EXCESS FLOW CHECK VALVE 4 PANEL 1BC204, '
- 2. NSTA REVIEWS P& IDS TO DETERMINE ,
INSTRUMENTATION EFFECTED BY THE CLOSURE OF EXCESS FLOW CHECK VALVE 1BBXV-3734B. 6.52C - l l (" V
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 11:15 MESSAGE #: 53 DRILL TIME : 03:15 TO : OSC TEAM FROM : OSC REFEREE ; LOCATION : REACTOR BUILDING, ELEVATION 102' MESSAGE :
"THIS IS A DRILL, THIS IS A DRILL" AT PANEL 1BC204, YOU OBSERVE THAT EXCESS FLOW CHECK VALVE 1BBXV-3734B IS CLOSED. .
*************************THIS IS A DRILL !!! !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIO
*****************************************w*************************
REFEREE NOTES : ( O (REFER TO SUPPLEMENTAL SCENARIO #7.10)
- 1. ISSUE THIS MESSAGE AS THE OPERATOR REACHES THE 1BC204 PA I
- 2. THE LEAK ON THE "B" CHANNEL FUEL ZONE LEVEL INSTRUMENT VARIABLE CHANNEL FUEL ZONE LEG HAS RESULTED IN THE"B"CLOSURE 1BBXV-3734B. OF EXCES LEVEL INDICATION TO FAIL DOWNSCALE.
- 3. ALL VERBAL COMMUNICATIONS MUST START WITH "THIS IS A DRI EXPECTED ACTIONS :
- 1. THE OPERATOR ACKNOWLEDGES THAT EXCESS FLOW CHECK VALVE 1BBXV-3734B IS CLOSED AND INFORMS THE OSCC.
6.53 O 8
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE: FORM 11:20 REAL TIME 03:20 54 DRILL TIME : MESSAGE #: OSC TEAM TO :
- OSC REFEREE FROM REACTOR BUILDING, ELEVATION 102' LOCATION :
MESSAGE : YOU OBSERVE THE AT THE ENTRANCE TO THE SOUTH PIPE CHASE, FOLLOWING: THE DOOR IS HOT TO THE TOUCH.A LARGE RUSH OF STEAM LE UPON OPENING THE DOOR, EXTREMELY PIPE CHASE, CONTAMINATION LEVELS INSIDE THE PIPE CHASE HIGH. (SEE SURVEY MAP) R IT DOOR IS IMMEDIATELY AND SUCCESSFULLY RE WAS CRACKED OPEN. .
*************************THIS *****************************************!
IS A DRILL !!! ERATIONS !! {U REFEREE NOTES (REFER THE CORRELATION
- 1. ISSUETO THISSUPPLEMENTAL MESSAGE ONLY SCENARIO "D" LPCIIF DRILL INJECTIO #7.10)
N VALVE AND PLAYERS REC AND BETWEEN THE CLOSURE THE LOSS OF POWERFLOW OF EXCESS TO THE CHECK VALVE SE TO 1BBXV-3734B, SUBSEQUENTLY DISPATCH A TEAM TO THE SOUTH DRILL". INVESTIGATE.
- 2. ALL VERBAL COMMUNICATIONS MUST START WIT EXPECTED
- 1. ACTIONSTHE OSC TEAM ACKNOWLEDGES THE CONDITIONS IN THE SOUTH PIPE CHASE AND INFORMS THE OSCC.
- 2. THE TEAM DOES NOT ATTEMPT TO ENTER -
- 3. THE SOUTH PIPE CHASE AT THIS TIME.THE FROM THE TSC ENGINEERING STAFF IN ATTEMPTING TO IDENTIFY POTENTIAL '
CORRELATIONS BETWEEN THE STEAM LEAK IN THE SOUTH PIPE CHASE AND THE OVLD/PWR FAILURE CONDITION ON THE "D" LPCI INJECTION VALVE. 6.54 O
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM () MESSAGE #: TO FROM 55D CONTROL ROOM STAFF SIMULATOR REFEREE REAL TIME DRILL TIME :
- 11:33 03:33 LOCATION : SIMULATOR (HOPE CREEK)
MESSAGE : YOU HAVE JUST RECEIVED A REFLASH OF THE FOLLOWING ALARMS: ALARMS: RPV LOOSE PARTS MON PNL 10-C-675 (OVERHEAD C6-AS) RPV LPM IMPACT VIB LVL (CRIDS POINT D5457)
******************************IS
- THIS A DRILL 111 !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS REFEREE NOTES :
O (REFER TO SUPPLEMENTAL SCENARIO #7.03) 1. 2. MESSAGE FOR DARK BOARD CONTROL ONLY. OPERATORS RESPONDED TO THE LOOSE PARTS MONITOR ALARM PANEL AN INFORM THE SNSS TO CONTACT THE OSCC TO DISPATCH A TEAM TO INVESTIGATE. EXPECTED ACTIONS :
- 1. SNSS RECOGNIZES THE POSSIBLE PRESENCE OF A LOOSE PART IN THE REACTOR VESSEL DUE TO A REFLASH OF THE LOOSE PARTS MONITOR OVERHEAD ALARM AND CONTACTS THE OSC TO DISPATCH A TEAM.
6.55D O
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM f 'g REAL TIME : 11:35 56D DRILL TIME : 03:35 MESSAGE #: TO : CONTROL ROOM STAFF FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : YOU HAVE JUST RECEIVED THE FOLLOWING ALARMS: (OVERHEAD C3-A2) REACTOR SCRAM TRIP LOGIC A1 (OVERHEAD C3-A3) REACTOR SCRAM TRIP LOGIC A2 (OVERHEAD C3-A4) REACTOR SCRAM TRIP LOGIC B1 (OVERHEAD C3-A5) REACTOR SCRAM TRIP LOGIC B2 (OVERHEAD A7-C5) RPV LEVEL 4 (OVERHEAD A7-DS) RPV LEVEL 3 (OVERHEAD A7-ES) RPV LEVEL 2 (OVERHEAD A7-F5) RPV LEVEL 1 (OVERHEAD Cl-B4) ADS CH B INITIATION PENDING (OVERHEAD Cl-BS) ADS CH D INITIATION PENDING (OVERHEAD A7-D4) DRYWELL PRESSURE HI/HI (OVERHEAD A7-E4) DRYWELL PRESSURE HI/LO
*************v********************************
*************************THIS IS A DRILL !!! !!!
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OP REFEREE NOTES :
1. 2. 3. THIS MESSAGE FOR DARK BOARD DRILL CO ENSURE NCO RESPONDS TO ALARMS APPROPRIATELY. EXPECTED ACTIONS :
- 1. NSS ENTERS EOP 101 AND 102 FOR RPV CONTROL AND CONTAINMENT CONTROL.
- 2. SNSS NOTIFIES THE EDO AND RECOMMENDS APPROPRIATE ESCALATION OF THE EMERGENCY CLASSIFICATION.
- 3. NCOS VERIFY PROPER RESPONSE OF ECCS AND NOTIFY THE NSS OF ANY MALFUNCTIONS.
- 4. NSS ASSESSES AVAILABLE INJECTION SOURCES.
6.56D O
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 11:35 MESSAGE #: 57D DRILL TIME : 03:35 TO : CONTROL ROOM STAFF FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : YOU HAVE JUST RECEIVED THE FOLLOWING ALARMS AND INDICATIONS: ALARMS: (OVERHEAD D3-C3) DRYWELL SUMP LEVEL HI/LO CORE SPRAY PUMP D AUTO START (OVERHEAD B3-A4) RHR PUMP A AUTO START (OVERHEAD A6-B3) RHR PUMP C AUTO START (OVERHEAD A6-B4) RHR PUMP D AUTO START (OVERHEAD A7-B4) RPV WATER LEVEL LO (OVERHEAD C5-A4) DRYWELL PRESSURE HI (OVERHEAD C5-BS) RADIATION MONITORING ALARM /TRBL (OVERHEAD C6-A2) . DLD SYSTEM ALARM /TRBL (OVERHEAD C6-B1) , RADIATION MONITORING ALARM /TRBL (OVERHEAD C6-C1) INDICATIONS: ALL PRIMARY CONTAINMENT ISOLATION VALVES HAVE CLOSED, WITH THE EXCEPTION OF 1SKHV-5018, WHICH INDICATES DUAL POSITION. ,i
*********************************A
- THIS IS DRIL1 '!
- DO NOT INITIATE ACTIONS AFFECTING NUk!AL PLANT OPERATIONS
() 1. 2. THIS MESSAGE FOR DARK BOARD DEILL CONTROL ONLY. ALARMS AND INDICATIONS.ARE LIMITED TO KEY INDICATIONS. ,
- 3. ENSURE NCO RESPONDS TO ALARMS APPROPRIATELY.
EXPECTED ACTIONS :
- 1. NSS ENTERS-EOP 101 AND 102 FOR RPV CONTROL AND CONTAINMENT CONTROL.
- 2. SNSS NOTIFIES THE EDO AND RECOMMENDS APPROPRIATE ESCALATION OF THE '
EMERGENCY CLASSIFICATION.
- 3. NCOS VERIFY PROPER RESPONSE OF ECCS AND NOTIFY THE NSS OF ANY MALFUNCTIONS.
- 4. NSS ASSESSES AVAILABLE INJECTION SOURCES.
6.57D l0
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 11:35 58D DRILL TIME : 03:35 MESSAGE #: TO : CONTROL ROOM STAFF FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : YOU HAVE JUST RECEIVED THE FOLLOWING ALARMS AND ALARMS: (OVERHEAD A6-A1) RHR LOGIC A OUT OF SERVICE (CRIDS POINT D4505) RHR PUMP AP202 OUT OF SERVICE INDICATIONS: THE RED " PUMP A RUNNING" LIGHT IS EXTINGUISHED. THE GREEN " STOPPED" LIGHT IS ILLUMINATED.
*************************THIS IS A DRILL !!! !!!
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT O O
Q REFEREE NOTES : (REFER TO SUPPLEMENTAL SCENARIO #7.11)THIS 1.
- 2. ENSURE NCO RESPONDS TO ALARMS APPROPRIATELY.
- 3. THE "A" RHR PUMP WILL MOST LIKELY BE IN TORUS COOLING LARGE THE PUMP CASING.
BREAK LOCA OCCURS. THE PU EXPECTED ACTIONS :
- 1. THE CONTROL ROOM RECOGNIZES THAT THE "A" RHR HAS TRIPPED AND IS NOT AVAILABLE TO INJECT TO THE VESSEL IN THE LPCI MODE.
- 2. THE SNSS DIRECTS THE OSCC TO DISPATCH A TEAM TO INVESTIGATE.
6.58D O
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 11:42 (~)x TO i MESSAGE #: 59C SNSS DRILL TIME : 03:42 FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MES'0 AGE : THIS IS A CONTINGENCY MESSAGE YOU SHOULD DIRECT THE OSCC TO DISPATCH A TEAM TO INVESTIGATE THE CAUSE OF THE TRIP OF THE "A" RHR PUMP.
- THIS IS A DRILL ! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS !!!
ps I REFEREE NOTES : ( (REFER TO SUPPLEMENTAL SCENARIO #7.11)
\- 1. ISSUE THIS MESSAGE ONLY IF IT APPEARS UNLIKELY THAT THE SNSS IS GOING TO DIRECT THE OSCC TO DISPATCH A TEAM TO THE INVESTIGATE THE CAUSE OF THE TRIP OF THE "A" RHR PUMP.
- 2. THIS IS CRITICAL TO THE SCENARIO TIMELINE.
EXPECTED ACTIONS :
- 1. THE SNSS DIRECTS THE OSCC TO DISPATCH A TEAM TO INVESTIGATE THE "A" RHR PUMP TRIP.
6.59C f% U
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM
,3 ,
REAL TIME : 11:45
?
' MESSAGE #: 59D DRILL TIME : 03:45 TO : CONTROL ROOM CREW FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK)
MESSAGE : YOU HAVE RECEIVED THE FOLLOWING INDICATIONS:
"C" RHR PUMP FLOW, WHICH STARTED AT 10000'GPM IN THE LPCI MODE, HAS BEGUN TO SLOWLY DECREASE.
"C" LPCI INJECTION VALVE (F017C) INDICATES FULL OPEN.
TORUS TEST RETURN VALVE (F010A) INDICATES FULL CLOSED.
*********************************A
- THIS IS DRILL !!!*********************************
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS n REFEREE NOTES :
i (REFER TO SUPPLEMENTAL SCENARIO #7.13) i
- 1. MESSAGE FOR DARK BOARD CONTROL ONLY.
ENSURE NCO RESPONDS APPROPRIATELY TO ALARMS. AS A RESULT OF THE LOCA INSIDE THE DRYWELL, DEBRIS IS BEING 2. 3. GENERATED BY THE RPV DEPRESSURATION AND IS BEING CARRIED INTO TORUS, WHERE IT HAS BEGUN TO PLUG THE ECCS SUCTION STRAINERS FOR THE OPERATINC. PUMPS. EXPECTED ACTIONS :
- 1. CONTROL CREW RECOGNIZES THAT THE "C" RHR PUMP SUCTION STRAINER IS BEGINNING TO PLUG.
- 2. THE SNSS DIRECTS THE OSCC TO DISPATCH A TEAM TO IMPLEMENT OF-AB.7.2-0155, DEGRADED ECCS PERFORMANCE.
6.59D O v
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM 60 REAL TIMb : 11:47 MESSAGE #: DRILL TIME : 03:47 TO : OSC TEAM FROM : OSC REFEREE AUXILIARY BUILDING, "A" VITAL BUS SWITCHGEAR LOCATION : MESSAGE : AT THE "A" RHR PUMP MOTOR BREAKER (52-40106), YOU OBSERVE THE FOLLOWING: THE BREAKER OVERCURRENT RELAY DEVICE (51) HAS ACTUATED. ATTEMPTS TO RESET THE DEVICE ARE UNSUCCESSFUL.
- THIS IS A DRILL
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS !!!
REFEREE NOTES : O (REFER TO SUPPLEMENTAL SCENARIO #7.11)
- 1. DELIVER THIS MESSAGE WHEN THE TEAM ARRIVES AT THE MOTOR BREAKER FOR THE "A" RHR PUMP.
- 2. ATTEMPTS TO RESET THE OVERCURRENT DEVICE ARE UNSUCCESSFUL.
EXPECTED ACTIONS :
- 1. OSC TEAM ACKNOWLEDGES THE STATUS OF THE "A" RHR PUMP MOTOR BREAKER AND INFORMS THE OSC.
t 4 i 6.60 l O
i ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM l REAL TIME : 11:49 MESSAGE #: 60C DRILL TIME : 03:49 TO : SNSS FROM : LEAD SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : THIS IS A CONTINGENCY MESSAGE YOU SHOULD IMPLEMENT OP-AB.ZZ-0155, DEGRADED ECCS PERFORMANCE AS NEEDED FOR DEGRADED ECCS PUMP FLOW.
- THIS IS A DRILL !!! !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS REFEREE NOTES :
p/ (REFER TO SUPPLEMENTAL SCENARIO #7.13)
- 1. DELIVER THIS MESSAGE AS NEEDED.
- 2. CURRENT AVAILABILTY OF RHR PUMP COUPLED WITH THE RESTORATION OF THE "A" RHR PUMP WILL DETERMINE WHEN THE CREW IS ABLE TO SECURE AN RHR PUMP FOR BACKWASHING PURPOSES, WHILE MAINTAINING ADEQUATE CORE COOLING BY CORE SUBMERGENCE.
EXPECTED ACTIONS :
- 1. AS PRACTICAL, RHR PUMPS CAN BE REMOVED FROM SERVICE FOR BACKWASHING OF THE ASSOCIATED SUCTION STRAINER.
6.60C i
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM 11:50 ("') REAL TIME : 03:50
~
MESSAGE #: 61D DRILL TIME : TO : CONTROL ROOM CREW FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) ; MESSAGE : IC SAMPLE WHEN THE CLOSED PUSHBUTTON FOR DRYWELL GASE VALVE, ISKHV-5018 IS DEPRESSED,
)
l l
************se*******************************
*************************THIS IS A DRILL !!! S !!!
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PL REFEREE NOTES :
- 1. MESSAGE FOR DARK BOARD CONTROL ONLY. LOSE 2.
- 3. ENSURE NCO RESPONDS TO ALARMS ISKHV-5018 FROM THE CONTROL ROOM.
LVE HAS APPR
- 4. THE BAILEY CARD ASSOCIATED WITH THE CONTRO FAILED AND REQUIRES REPLACEMENT.
EXPECTED
- 1. ACTIONS : CONTROL ROOM CREW ACKNOWLEDGES T ISKHV-5018 FAILS TO CLOSE FROM THE CONTROL ROOM.
- 2. SNSS NOTIFIES THE TSC OF THE CONDITION AND REQUEST ENGINEERS DEVELOP A TROUBLESHOOTING PLAN.
l 6.61D O , 1 l 1
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 11:50 MESSAGE #: 62 (' ') TO : OSC TEAM DRILL TIME : 03:50 FROM : OSC REFEREE LOCATION : REACTOR BUILDING, ELEVATION 162' MESSAGE WHEN YOU ARRIVE AT THE DRYWELL GASEOUS ATMOSPHERIC SAMPLE SKID, YOU OBSERVE THE FOLLOWING: 1-SK-V004, DW SAMPLE SKID SUPPLY MANUAL ISOLATION VALVE IS OPEN. 1-SK-V007, DW SAMPLE SKID RETURN MANUAL ISOLATION VALVE IS OPEN. 1SKHV-5018, DW SAMPLE SKID SUPPLY MOV IS PARTIALLY OPEN 1SKHV-4953, DW SAMPLE SKID SUPPLY MOV IS CLOSED. 1SKHV-4957, DW SAMPLE SKID RETURN MOV IS CLOSED. ISKHV-4981, DW SAMPLE SKID RETURN MOV IS CLOSED. IN ADDITION, THE SAMPLE PUMP (10-P-270) IS NOT OPERATING.
- THIS IS A DRILL !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS 3 REFEREE NOTES :
1 (REFER TO SUPPLEMENTAL SCENARIO #7.12)
- 1. DELIVER THIS MESSAGE ONLY IF THE OSCC DISPATCHES A TEAM TO DETERMINE THE STATUS OF THE SYSTEM.
- 2. UPON RECEIPT OF THE LOCA LEVEL 1 SIGNAL, THREE OF THE FOUR DRYWELL GASEOUS ATMOSPHERIC SAMPLE VALVES HAVE CLOSED.
THE INBOARD SUPPLY VALVE, ISKHV-5018 IS IN A DUAL POSITION.
- 3. THE SNSS/OSCC SHOULD MAKE ISOLATION OF THIS PENETRATION A HIGH PRIORITY.
EXPECTED ACTIONS :
- 1. IF THE SNSS RECOGNIZES THE FAILURE OF THE PRIMARY CONTAINMENT ISOLATION VALVE TO CLOSE (1SKHV-5018), THEN HE SHOULD DIRECT THE OSC TO DISPATCH A TEAM TO RESPOND.
6.62
l ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS. MESSAGE FORM REAL TIME : 11:55 MESSAGE #: 63C DRILL TIME : 03:55 ' TO : EDO / . SNSS FROM : LEAD REFEREE LOCATION : TSC / CONTROL ROOM MESSAGE : THIS IS A CONTINGENCY MESSAGE: YOU SHOULD DECLARE A SITE AREA EMERGENCY PER ECG SECTION 1.D LOSS OF COOLANT ACCIDENT GREATER THAN MAKEUP. .
*************************THIS IS A DRILL !!! !!! * .
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERA i REFEREE NOTES :
- 1. ISSUE THIS MESSAGE ONLY IF THE EDO / SNSS ARE NOT IN .
OF CLASSIFYING THE EVENT.
- 2. CONFER WITH HEAD REFEREE PRIOR TO ISSUING.
EXPECTED ACTIONS :
- 1. DECLARE A SITE AREA EMERGENCY.
- 2. IMPLEMENT ECG ATTACHMENT 3.
- 3. IMPLEMENT EPIP 103H.
- 4. IMPLEMENT ACCOUNTABILITY (LIMITED) 6.63C
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM
/N 64D REAL TIME : 11:55 l MESSAGE #:
N/ l TO : CONTROL ROOM CREW DRILL TIME : 03:55 FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : YOU HAVE RECEIVED THE FOLLOWING INDICATIONS:
"C" RHR PUMP FLOW IS CURRENTLY 4000 GPM AND DECREASING.
"C" LPCI INJECTION VALVE (F017C) INDICATES' FULL OPEN.
TORUS TEST RETURN VALVE (F010A) INDICATES FULL CLOSED.
**********************k************************************************
- THIS IS A DRILL !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLAl'f OPERATIONS !!!
f_s REFEREE NOTES : ( ) (REFER TO SUPPLEMENTAL SCENARIO #7.13) V 1. MESSAGE FOR DARK BOARD CONTROL ONLY.
- 2. ENSURE NCO RESPONDS APPROPRIATELY TO ALARMS.
- 3. AS A RESULT OF THE LOCA INSIDE THE DRYWELL, DEBRIS IS BEING GENERATED BY THE RPV DEPRESSURATION AND IS BEING CARRIED INTO THE TORUS, WHERE IT HAS BEGUN TO PLUG THE ECCS SUCTION STRAINERS FOR THE OPERATING PUMPS.
EXPECTED ACTIONS : -
- 1. CONTROL CREW RECOGNIZES THAT THE "C" RHR PUMP SUCTION STRAINER IS PLUGGING.
- 2. THE SNSS DIRECTS THE OSCC TO DISPATCH A TEAM TO IMPLEMENT OP-AB.ZZ-0155, DEGRADED ECCS PERFORMANCE 6.64D l
[T , \_) 1 l e
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM : 11:56 REAL TIME 03:56 MESSAGE #: 65 DRILL TIME : TO : OSC TEAM MEMBERS FROM : OSC REFEREE REACTOR BUILDING,. ELEVATION S4' LOCATION : > MESSAGE : AT THE "C" RHR PUMP SUCTION LINE PRESSURE INDICATO 1BCPI-R002C, 3.2 PSI.
*************************THIS IS A DRILL !!! NS 1!! *
*******************w*****************************
REFEREE NOTES : ESSURE (REFER ISSUE TOTHIS SUPPLEMENTAL MESSAGESCENARIO ONLY IF #7.13) A TEAM IS. IS DISPATCH
- 1. "C" SSURE INDICATOR TO DETERMINE WHAT
- 2. RHR INDICATOR.
PUMP SUCTION PRESSUREDELIV , EXPECTED ACTIONS :
- 1. OSC TEAM DETERMINE"C" RHR THE PUMP.
SUCTION PRESSURE FOR THE 6.65 O
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM12:00 REAL TIME : 04:00 MESSAGE #: 66 DRILL TIME : TO : OSC TEAM
- OSC REFEREE FROM REACTOR BUILDING, ELEVATION 162' LOCATION :
MESSAGE : SSFUL, DUE TO ATTEMPTS TO MANUALLY CLOSE THE 1-SK-V004 ARE U A BENT STEM. UL. ATTEMPTS TO MANUALLY CLOSE THESSFUL, 1-SK-V007 AS THE ARE ATTEMPTS TO MANUALLY CLOSE THE ISKHV-5018 ARE DECLUTCH FAILS TO DECLUTCH THE MOTOR OPERATOR.
*************************THIS IS A DRILL !!! NS !!!
- REFEREE NOTES : NOT i
(REFER TO SUPPLEMENTAL SCENARIO #7.12) D
- 1. ON THE l
PROVIDE THE INFORMATION IF NO ATTEMPT IS MADE. 2 FAILURE OF THE INBOARD SUPPLY LOCA LEVEL 1 SIGNAL, NETRATIONISOLAT AT
- 3. THE SNSS AND OSCC SHOULD PURSUE ISOLATION O
- 4. THIS TIME.THIS IS CRITICAL TO THE SCENARIO TIMELINE.
EXPECTED
- 1. ACTIONSIF THE CREW RECOGNIZES THE FAILURE OF THE PRIMARY CONTAINMENT ISOLATION VALVE TO CLOSE, THEN AN OSC TEAM SHOULD BE DISPATCHED TO INVESTIGATE.
6.66 l l
l
\
l ARTIFICIAL ISLAND i EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 12:10
) MESSAGE #:
TO : 67C CONTROL ROOM CREW DRILL TIME : 04:10 l FROM : SIMULATOR REFEREE J LOCATION : SIMULATOR (HOPE CREEK) l MESSAGE : THIS IS A CONTINGENCY MESSAGE YOU SHOULD DIRECT THE OSCC TO DISPATCH A TEAM TO TROUBLESHOOT l THE EAILURE OF 1SKHV-5018 TO CLOSE. . t i r
***************************************L
- THIS IS A DRIL !!!. !!!
- i
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS
********************************************************************** i REFEREE NOTES :
O (REFER TO SUPPLEMENTAL SCENARIO #7.12) ISSUE THIS MES 1. TIMELINE. EXPECTED ACTIONS : j
- 1. SNSS CONTACTS THE OSCC TO DISPATCH A TEAM.
i n 6.67C , _ _ _ _ _ _ . _ _ _ _ ___________.._i
i l ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM q 68D REAL TIME : 12:15 I MESSAGE #:
/ TO : CONTROL ROOM STAFF DRILL TIME : 04:15 FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK)
MESSAGE : YOU HAVE JUST RECEIVED THE FOLLOWING ALARMS AND INDICATIONS: ALARMS: (OVERHEAD A6-A2) RHR LOGIC C OUT OF SERVICE RHR PUMP CP202 OUT OF SERVICE (CRIDS POINT D4507) INDICATIONS: THE RED " PUMP A RUNNING" LIGHT IS EXTINGUISHED. THE GREEN " STOPPED" LIGHT IS ILLUMINATED.
**************************************LL
- THIS IS A DRI !!!
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS REFEREE NOTES :
- 1. THIS MESSAGE FOR DARK BOARD CONTROL ONLY.
- 2. ENSURE NCO RESPONDS TO ALARMS APPROPRIATELY.
- 3. THE "C" RHR PUMP HAS TRIPPED AS A RESULT OF CONTINUED OPERATION WITH A PLUGGED ECCS SUCTION STRAINER.
- 4. THE TIMING OF THIS MALFUNCTION WILL BE AT THE DIRECTION OF THE LEAD SIMULATOR REFEREE, BASED ON REACTOR WATER LEVEL.
EXPECTED ACTIONS :
- 1. THE CONTROL ROOM RECOGNIZES THAT THE "C" RHR HAS TRIPPED AND IS NOT AVAILABLE TO INJECT TO THE VESSEL IN THE LPCI MODE.
- 2. THE SNSS DIRECTS THE OSCC TO DISPATCH A TEAM TO INVESTIGATE. .
6.68D /~'N
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE :FORM 12:20 REAL TIME 04:20 MESSAGE #: 69C DRILL TIME : TO : SNSS SIMULATOR REFEREE FROM : LOCATION : SIMULATOR (HOPE CREEK) . MESSAGE : THIS IS A CONTINGENCY MESSAGE ATE YOU SHOULD DIRECT THE CAUSE OF THE TRIP OF THE THE "C" RHR PUMP.OSCC TO DISPATCH
*************************THIS IS A DRILL !!! NS !!!
- REFEREE NOTES E SNSS (REFER TO SUPPLEMENTAL SCENARIO #7.14) VESTIGATE ISSUE THIS MESSAGE ONLY IF IT APP 1.
"C" RHR PUMP. ,
THE CAUSE OF THE TRIP OF THE
- 2. THIS IS CRITICAL TO THE SCENARIO TIMELINE. i EXPECTED ACTIONS
- 1. THE SNSS DIRECTS THE OSCC TO DISPATCH A TEAM TO INVESTIGATE THE "C" RHR PUMP TRIP.
6.69C 4 0
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 12:23 MESSAGE #: 70 DRILL TIME : 04:23 TO : OSC TEAM l FROM : OSC REFEREE AUXILIARY BUILDING, "C" VITAL BUS SWITCHCEAL LOCATION.: 1 MESSAGE : AT THE "C" RHR PUMP MOTOR BREAKER (52-40306), YOU OBSERVE THE FOLLOWING. t THE BREAKER OVERCURRENT RELAY DEVICE (51) HAS ACTUATED.- ATTEMPTS TO RESET THE DEVICE ARE UNSUCCESSFUL. i
**************************************LL
- THIS IS A DRI !!!
11! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS R :
O (EFEREE 1. NOTES REFER TO SUPPLEMENTAL FOR THE "C" RHR PUMP. SCENARIO #7.14) DELIVER THIS MESSAGE WHEN THE TEAM ARRIVES AT THE MOTOR BREAKER
- 2. ATTEMPTS TO RESET THE OVERCURRENT DEVICE ARE SUCCESSFUL. .
- l EXPECTED ACTIONS :
- 1. OSC TEAM ACKNOWLEDGES THE STATUS OF THE "C" RHR PUMP MOTOR BREAKER AND INFORMS THE OSC.
s 6.70 O
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 12:45 bi MESSAGE #: 71 DRILL TIME : 04:45 (_f TO : DRILL REFEREES FROM : LEAD REFEREES LOCATION : SIMULATOR / TSC / EOF MESSAGE : THIS MESSAGE IS FOR REFEREE INFORMATION CLY. SEE EXPLANATION BELOW.
**************************HIS
- T IS A DRILL !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERA REFEREE NOTES :
O THIS REFEREE MESSAGE IS BEING PROVIDED GENERAL EMERGENCY BASED ON HIS JUDGEMENT THAT THE THIRD , PRODUCT BOUNDARY HAS FAILED. i EXPECTED ACTIONS : AT APPROXIMATELY 12:45, THE DAPA MONITORS WILL EXCEED 200 R/HR, WHICH IS INDICATION OF A LOSS OF THE FUEL CLAD BARRIER. BASED ON EMERGENCY COORDINATOR JUDGEMENT, A GENERAL EMERGENCY COULD BE DECLARED AT THIS TIME. IF A GENERAL EMERGENCY IS DECLARED, THE EXPECTED PAR IS AS FOLLOWS: EVACUATE ALL SECTORS 0 - 5 MILES l 6.71
)
j
" ~ . _
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM ,g REAL TIME : 12:45 72C DRILL TIME : 04:45 k- MESSAGE #: CHEMISTRY SUPERVISOR - TSC TO FROM : TSC RAD PRO REFEREE 1 LOCATION : HOPE CREEK TSC MESSAGE : THIS IS A CONTINGENCY MESSAGE YOU SHOULD REQUEST THE CHEMISTRY SUPERVISOR TO HAVE A PASS SAMPLE TAKEN AT THIS TIME.
**********************************w+********** *************************THIS IS A DRILL !!! !!!
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT O REFEREE NOTES :
1. THE TSC DIRECT THE CHEMISTRY SUP TO HAVE A PASS SAMPLE TAKEN.
- 2. THE PASS SAMPLE WILL BE TAKEN FROM RHR.
EXPECTED ACTIONS :
- 1. THE CHEMISTRY SUPERVISOR IN THE TSC REQUESTS A PASS SAMPLE BE TAKEN.
6.72C O
)
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM : 12:50 REAL TIME 04:50 MESSAGE #: 73 DRILL TIME : TO : OSC TEAM
- OSC REFEREE FROM REACTOR BUILDING, ELEVATION 162' LOCATION :
MESSAGE : ESSFUL DUE TO ATTEMPTS TO CLOSE THE 1-SK-V004 ARE INITIALLY U THE VALVE STEM BEING BENT. O SOME DEGREE, THE OSC TEAM HASHOWEVER, BEEN ABLE TO STRAIGHTEN THE S ALLOWING THE STEM TO MOVE. RESISTANCE IS STI
*************************THIS IS A DRILL !!! IONS !!!
- REFEREE NOTES : NED THE (REFER TO SUPPLEMENTAL SCENARIO #7.12)
- 1. DELIVER THIS MESSAGE AFTER THE OSC T WILL TEAM TAKE HAS VALVE STEM AND IS NOW TRYING TO CLOSE THE VE WILL VALVE.
AGAIN 2.JAMTHE TEAM WILL SLOWLY BE ILEABLE WHEN IT IS ONLY HALF CLOSED. ATTEMP- TO 3. THIS IS A CRITICAL ACTIVITY. STRES EXPECTED
- 1. ACTIONSTHE OSC TEAM WORKS AT CLOSING THE MANUAL ISOLATION VALVE, 1-SK-V004.
6.73 O
ARTIFICIAL ISLAND EMERGFNCY PREPAREDNESS MESSAGE FORM [' MESSAGE #: 74 REAL TIME : 13:00 TO : OSC TEAM DRILL TIME : 05:00 FROM : OSC REFEREE LOCATION : CONTROL BUILDING MESSAGE : TROUBLESHOOTING THE FAILURE OF THE 1SKHV-5018 'IO STROKE FULL CLOSED, YOU FIND AN ASSOCIATED BAILEY CARD WITH NO OUTPUT SIGNAL.
***,************ww .....***********************************************
- THIS IS A DRILL !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS !!!
REFEREE NOTES : Q V (REFER TO SUPPLEMENTAL SCENARIO #7.12)
- 1. ISSUE THIS MESSAGE AFTER THE TEAM HAS CORRECTLY TROUBLESHOT THE PROBLEM, USING THE APPROPRIATE LOGIC PRINTS.
- 2. AFTER THE OSC TEAM HAS LOCATED A REPLACEMENT BAILEY CARD AND TAKEN ACTION TO REPLACE THE CARD, THEY WILL BE SUCCESSFUL AT 14:49 AND THE VALVE WILL STROKE CLOSED. THIS IS A TIME CRITICAL EVOLUTION SINCE THIS ACTION TERMINATES THE RELEASE OF FISSION PRODUCTS INTO THE REACTOR BUILDING.
EXPECTED ACTIONS :
- 1. OSC TEAM NOTIFIES THE OSCC AND ATTEMPTS TO FIND A REPLACEMENT CARD.
6.74 l O l
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM
- 13:15
(]) ( MESSAGE #: 74D REAL TIME DRILL TIME : 05:15 TO : CONTROL ROOM STAFF FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : YOU HAVE RECEIVED THE FOLLOWING ALARMS AND INDIC (OVERHEAD C6-A2) ALARMS: RADIATION MONITORING ALARM /TRBL (OVERHEAD C6-C1) RADIATION MONITORING ALARM /TRBL (OVERHEAD E6-A4) NEW FUEL CRITICALITY RAD HI (OVERHEAD E6-A3) REFUEL FLOOR EXH RAD ALARM /TRBL (OVERHEAD E6-AS) RB EXH RADIATION ALARM /TRBL 6 INDICATIONS: AUDIBLE RM-11 COMPUTER ALARM
***************+*********THIS IS A DRILL !!! !!!
- REFEREE NOTES : OM
- 1. ENSURE RM11 DISPLAY DATA IS UPDATED AT THIS AS A REPAIR TEAM ATTEMPTING STAFF REFERENCE.
DW ATMOSPHERIC SAMPLE LINE HAS FAILED, DAMAGES THE LINE.
- 2. BLDG.
3. TO CLOSE THE MANUAL ISOLATION VALVE 1-SK-V004,
- 4. AND FRVS VENT EFFLUENT ALARMING. RADIOLO EXPECTED ACTIONS
- 1. CONTINUE EFFORTS TO DETERMINE AND LOCATE THE SOURCE OF THE LINE BREAK.
- 2. SNSS INFORM EDO OF INCREASED RAD LEVEL AND INDICATION OF FRVS RELEASE
- 3. INFORM OSC OF RAD CONCERNS IN REACTOR BLDG,
- 4. NSS ENTERS EOP-103 (REACTOR BUILDING CONTROL) AND EOP-104 (RADIOACTIVE RELEASE CONTROL)
- 5. NCO GASEOUSENTERS ABNORMAL RELEASES OF(OP-AB.ZZ-126)
RADIOACTIVITY 6.74D l 1
ARTIFICIAL ISLAND
- EMERGENCY PREPAREDNESS MESSAGE FORM i REAL TIME : 13:15 j MESSAGE #: 75 s
' : OSC TEAM DRILL TIME : 05:15 1 TO i FROM : OSC REFEREE LOCATION : REACTOR BUILDING, ELEVATION 162' MESSAGE :
AS YOU CONTINUE TO ATTEMPT TO CLOSE 1-SK-V004, YOU OBSERVE THAT THE SAMPLE LINE SHEARS ON A WELDED JOINT BETWEEN THE TWO MOTOR OPERATED VALVES IN THE LINE YOU WERE WORKING ON. i YOUR ALNOR IMMEDIATELY BEGINS TO ALARM. YOU OBSERVE THE SYMPTOMS OF A LOW PRESSURE STEAM RELEASE FROM THE FAILED LINE.
- THIS IS A DRILL- !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS REFEREE NOTES :
O (REFER TO SUPPLEMENTAL SCENARIO #7.12)
- 1. DELIVER THIS MESSAGE AT EXACTLY 13:15. THIS TIME IS CRITICAL TO THE DRILL.
- 2. THIS ACTIVITY IS CRITICAL TO THE RADIOLOGICAL RELEASE THAT OCCURS AT 13:15, IN THAT IT CAUSES THE FAILURE OF THE SAMPLE LINE.
- 3. THE FAILURE OF THE SAMPLE LINE IS DUE TO EXCESSIVE FORCE USED BY THE OSC TEAM IN COMBINATION WITH A SAMPLE LINE THAT WAS PREVIOUSLY WEAKENED BY THE DRYWELL PRESSURE SPIKE WHEN THE LOCA OCCURRED.
EXPECTED ACTIONS :
- 1. THE OSC TEAM NOTIFIES THE OSCC OF THE EVENTS AND IMMEDIATELY EVACUATES THE AREA AND THE REACTOR BUILDING.
I 6.75 O
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM () MESSAGE #: TO FROM 76 CHEMISTRY SUPERVISOR - TSC TSC RAD PRO REFEREE REAL TIME DRILL TIME :
- 13:30 05:30 LOCATION : HOPE CREEK TSC MESSAGE :
THE FOLLOWING ARE THE RESULTS OF THE PASS SAMPLE OBTAINED AT 12:45. NOBLE GASES IODINES I-131 =1.52E+4 UCI/ML KR-85 =6.67E+0 UCI/ML XE-131M =1.58E+1 UCI/ML I-132 =8.83E+3 UCI/ML KR-87 =2.46E+2 UCI/ML XE-133 =3.38E+3 UCI/ML I-133 =3.09E+4 UCI/ML KR-88 =8.86E+2 UCI/ML XE-133M =8.16E+1 UCI/ML XE-135 =2.59E+3 UCI/ML I-134 =3.12E+3 UCI/ML TOTAL NOBLE GASES = 7.21E+3 UCI/ML I-135 =2.25E+4 UCI/ML TOTAL IODINE = 8.06 E+4 UCI/ML PARTICULATES MO-99 =2.92E+4 UCI/ML TE-129 =8.74E+2 UCI/ML BA-140 =2.82E+4 UCI/ML RB-88 =9.83E+0 UCI/ML TE-132 =2.07E+4 UCI/ML LA-140 =2.85E+4 UCI/ML SR-89 =1.47E+4 UCI/ML CS-134 =1.72E+3 UCI/ML LA-142 =1.03E+4 UCI/ML SR-90 =3.48E+3 UCI/ML CS-137 =4.94E+3 UCI/ML CE-144 =1.01E+4 UCI/ML TOTAL PARTICULATES = 1.49 E+5 UCI/ML
- THIS IS A DRILL *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS !!!
REFEREE NOTES : O 1. THIS INFORMATION IS BEING PROVIDED TO THE CHEMISTRY SUPERVISOR IN THE TSC FOR DRILL PURPOSES BEFORE ACTUAL SAMPLE RESULT ARE COMPLETED. THE TEAM ANALYZING THE PASS SAMPLE SHOULD CONTINUE WITH THAT ACTIVITY UNTIL COMPLETED. EXPECTED ACTIONS :
- 1. PROVIDE THE RAC AND FUELS ENGINEER WITH THE PASS RESULTS.
I 4 6.76 4 O
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM () MESSAGE #: TO FROM 77C-RAC (RAD ASSESSMENT COORD.) TSC RAD PRO REFEREE REAL TIME : DRILL TIME : 13:30 05:30 LOCATION : HOPE CREEK TSC MESSAGE : THIS IS A CONTINGENCY MESSAGE: DIRECT THE RAD PRO IN-PLANT SUPERVISOR TO TAKE AN FRVS EFFLUENT SA
********************************* e **************************************LL
- THIS IS A DRI !!!
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS REFEREE NOTES :
O 1. ISSUE AS NECESSARY TO ALLOW ENOUGH TIME FOR THE RAD PRO TECHNICIAN TO PULL A REAL FRVS SAMPLE AND PERFORM AN ANALYSIS OF THE SAMPLE.
- 2. THIS IS CRITICAL TO THE DRILL TIMELINE.
EXPECTED ACTIONS :
- 1. RAC DIRECTS IN-PLANT RAD PRO SUPV. TO TAKE FRVS EFFLUENT SAMPLE.
- 2. RAD PRO TECH. SAMPLES AND ANALYZES FRVS EFFLUENT.
6.77C 1 1 1
._ = - ,
l ARTIFICIAL ISLAND l EMERGENCY PREPAREDNESS MESSAGE FORM l REAL TIME : 13:35 i 78C ( / MESSAGE #: TO : ERM DRILL TIME : 05:35 , l FROM : EOF LEAD REFEREE i LOCATION : EOF ! MESSAGE : THIS IS A CONTINGENCY MESSAGE: YOU SHOULD DECLARE A GENERAL EMERGENCY IN ACCORDANCE WITH ECG SECTION 6A + 6B + 6C, LOSS OF FUEL CLAD INTEGRITY AND LOSS OF RPV INTEGRITY AND LOSS OF PRIMARY CONTAINMENT, OR ECG SECTION 1E, LOSS OF COOLANT ACCIDENT WITH FAILURE OF ECCS SYSTEMS TO PERFORM.
- THIS IS A DRILL !
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS !!!
REFEREE NOTES : O 1. 2. DO NOT ISSUE THIS MESSAGE WITHOUT HEAD REFEREE PERMISSION. ISSUE THIS MESSAGE ONLY IF THE SNSS, EDO AND ERM ARE NOT IN THE PROCESS OF CLASSIFYING THE EVENT.
- 3. EOF REFEREE MUST CONFER WITH THE HEAD REF BEFORE ISSUING THIS MESSAGE.
EXPECTED ACTIONS :
- 1. DECLARE A GENERAL EMERGENCY. I
- 2. IMPLEMENT ATTACHMENT 4.
- 3. IMPLEMENT EPIP 104H.(EPIP 401, APP.B)
- 4. DEVELOPMENT OF A PAR.
AS A MINIMUM; SECTORS DISTANCE EVACUATE ALL 0-5 MILES EVACUATE W-WNW-NW 5-10 MILES SHELTER ALL REMAINING 5-10 MILES SECTORS 6.78C
- O l
1 ARTIFICIAL ISLAND i EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 14:11
) MESSAGE #:
TO : 79 OSC "B" EDG REPAIR TEAM DRILL TIME : 06:11 FROM : OSC REFEREE LOCATION : AUXILIARY BUILDING, ELEVATION 102' MESSAGE : YOU HAVE THE REPAIRS ON "B" EDG LUBE OIL SUCTION HEADER ARE COMPLETE. YOU ARE STANDING BY FOR A ALSO FILLED THE LUBE OIL TANK AND SUMP. EDG START TO ENSURE THERE ARE NO PROBLEMS.
- THIS IS A DRILL !!! !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS >
*****************w****************************************************
REFEREE NOTES : O (REFER TO SUPPLEMENTAL SCENARIO #7.08) i
- 1. THIS RESTORATION CAN NOT BE SUCCESSFUL UNTIL 14:18.
- 2. INFORM LEAD SIMULATOR REFEREE WHEN OSCC IS GOING TO CONTACT S CONCERNING THIS REPAIR ACTIVITY.
EXPECTED ACTIONS :
- 1. OSC TEAM TO NOTIFY THE OSCC OF JOB COMPLETION.
- 2. OSCC TO INFORM SNSS THAT "B" EDG IS REPAIRED AND READY FOR START.
- 3. CR CREW TO START "B" EDG.
k 6.79
\
ARTIFICIAL ISLAND EMERGENCYLPREPAREDNESS MESSAGE FORM REAL TIME : 14:15 i MESSAGE #: 80
- RP - INPLANT SUPERVISOR DRILL TIME : 06:15 TO-FROM : CP REFEREE LOCATION : CONTROL POINT t
MESSAGE : THE FOLLOWING ARE THE RESULTS OF THE FRVS SAMPLE OBTAINED AT 13:30. FRVS ISOTOPIC VALUES NOBLE GASES IODINES XE-131M =9.90E-2 UCI/CC I-131 =8.20E-3 UCI/CC KR-85 =5.71E-2 UCI/CC KR-87 =4.40E-1 UCI/CC XE-133 =2.67E+1 UCI/CC I-132 =3.34E-3 UCI/CC KR-88 =5.91E+0 UCI/CC XE-133M =6.50E-1 UCI/CC
-I-133 =2.43E-2 UCI/CC XE-135 =1.30E+1 UCI/CC I-134 =8.17E-4 UCI/CC TOTAL NOBLE GASES = 4.52 E+01 UCI/CC I-135 =9.89E-3 UCI/CC TOTAL IODINE = 4.65 E-02 UCI/CC PARTICULATES MO-99 =2.01E-3 UCI/CC TE-129 =3.11E-5 UCI/CC BA-140 LA-140
=2.07E-3 UCI/CC
=2.07E-3 UCI/CC ,
RB-88 =7.41E-8 UCI/CC TE-132 =8.81E-4 UCI/CC LA-142 =3.78E-4 UCI/CC SR-89 =6.60E-4 UCI/CC CS-134 =7.54E-5 UCI/CC CE-144 =5.19E-4 UCI/CC SR-90 =2.32E-4 UCI/CC CS-137 =2.88E-5 UCI/CC TOTAL PARTICULATES = 8.96 E-3 UCI/CC
- THIS IS A DRILL !!! !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS REFEREE NOTES :
EXPECTED ACTIONS :
- 1. NOTIFY THE RAC IN THE TSC OF THE RESULTS.
t 6.80 0 I i 1
. _ . - .- ~ .. - - . .- _- . . -
l l l ARTIFICIAL ISLAND ! EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 14:49 I 06:49 ^% / MESSAGE #: 81 DRILL TIME : TO : OSC TEAM FROM : OSC REFEREE LOCATION : CONTROL BUILDING MESSAGE- : YOU HAVE SUCCESSFULLY REPLACED THE FAILED BAILEY LO ; ASSOCIATED WITH THE DRYWELL GASEOUS ATMOSPHERIC SAMPLE INBOARD SUPPLY ISOLATION VALVE, ISKHV-5018. e
***+******:++************THIS IS A DRILL !!!
DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERA REFEREE NOTES : O(ms/ 1. (REFER TO SUPPLEMENTAL SCENARIO #7.12)IT IS CR i
- 2. AT EXACTLY 14:49. ENSURE THAT THE OSC TEAM INFORMS THE ..
COMPLETE. h i EXPECTED ACTIONS :
- 1. THE OSC TEAM INFORMS THE OSCC THAT REPAIRS ARE COMPLETED.
6.81 l l j l l
i l ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 14:49 MESSAGE #: 81D DRILL TIME : 06:49 TO- : CONTROL ROOM CREW FROM : SIMULATOR REFEREE LOCATION : SIMULATOR (HOPE CREEK) MESSAGE : YOU HAVE OBSERVED THE FOLLOWING INDICATIONS: 1SKHV-5018, DRYWELL GASEOUS ATMOSPHERIC SAMPLE VALVE INDICATES I CLOSED. i
******************************IS
- THIS A DRILL !!! !!! *
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS
- O REFEREE NOTES (REFER TO SUPPLEMENTAL SCENARIO #7.12)
MESSAGE FOR-DARK BOARD CONTROL ONLY. 1.
- 2. ENSURE NCO RESPONDS TO ALARMS APPROPRIATELY.
EXPECTED ACTIONS :
- 1. CONTROL ROOM CREW RECOGNIZES THAT THE 1SKHV-5018 IS CLOSED.
6.81D O
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(
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM g-) REAL TIME : 15:00 82 DRILL TIME : 07:00 MESSAGE #: TO : CHEMISTRY TECH FROM : CP REFEREE LOCATION : HOPE CREEK CHEMISTRY LAB l MESSAGE : THE FOLLOWING ARE THE RESULTS NOBLE GASES OF THE PASS SAM IODINES XE-131M =1.58E+1 UCI/ML KR-85 =6.67E+0 UCI/ML XE-133 =3.38E+3 UCI/ML I-131 =1.52E+4 UCI/ML KR-87 =2.46E+2 UCI/ML XE-133M =8.16E+1 UCI/ML I-132 =8.83E+3 UCI/ML KR-88 =8.86E+2 UCI/ML XE-135 =2.59E+3 UCI/ML I-133 =3.09E+4 UCI/ML I-134 =3.12E+3 UCI/ML TOTAL NOBLE GASES = 7.21E+3 UCI/ML I-135 =2.25E+4 UCI/ML TOTAL IODINE = 8.06 E+4 UCI/MLPARTICULATES BA-140 =2.82E+4 UCI/ML MO-99 =2.92E+4 UCI/ML TE-129 =8.74E+2 UCI/ML LA-140 =2.85E+4 UCI/ML RB-88 =9.83E+0 UCI/ML CS-134 =2.07E+4 TE-132 UCI/ML
=1.72E+3 UCI/ML LA-142 =1.03E+4 UCI/ML SR-89 =1.47E+4 UCI/ML CS-137 =4.94E+3 UCI/ML CE-144 =1.01E+4 UCI/ML SR-90 =3.48E+3 UCI/MLTOTAL PARTICULATES = 1.49 E+5 UCI/ML
*************************THIS IS A DRILL !!! !!!
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT O
[' REFEREE NOTES :
- 1. DO NOT PROVIDE THIS INFORMATION TO THE CHEMIS UNTIL ANALYSIS OF THE PASS SAMPLE TAKEN RILL AT 12:45
- 2. IT IS IMPORTANT TO UNDERSTAND THAT THESE SAMPL PROVIDED TO THE CHEMISTRY SUPERVISOR IN THE T PURPOSES.
!%PECTED ACTIONS
- 1. CHEM TECH DISCUSSES RESULTS WITH THE CONTROL POINT CHEMISTRY SUPERVISOR.
6.82 O
ARTIFICIAL ISLAND EMERGENCY PREPAREDNESS MESSAGE FORM REAL TIME : 15:30
\. MESSAGE #: 83
_s-[ / TO : SNSS DRILL TIME : 07:30 FROM : CONTROL ROOM DRILL CONTROLLER LOCATION : HOPE CREEK CONTROL ROOM MESSAGE : Please make the following page announcement:
" ATTENTION ALL PERSONNEL. ATTENTION ALL PERSONNEL."
" TODAYS EMERGENCY PLAN DRILL HAS BEEN TERMINATED."
Please repeat message one time.
******************************************111
- THIS IS A DRILL
- DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS !!!
REFEREE NOTES :
- 1. PROVIDE THIS MESSAGE TO THE DUTY SNSS ONLY WHEN AUTHORIZED BY THE O- HEAD REFEREE. (TIME ABOVE IS APPROXIMATE)
- 2. ENSURE THAT THE CONTROL ROOM NETS PHONE LINES AND THE STATION FADIO ARE RETURNED TO NORMAL AFTER THE DRILL IS TERMINATED.
- 3. PROVIDE ANY COMMMTS CONCERNING THE DRILL TO THE HEAD REFEREE IN THE TSC AFTER ENSURING CR COMMUNICATION SYSTEMS ARE RESTORED.
( EXPECTED ACTIONS :
- 1. AFTER THE SNSS, EDO AND ERM AGREE THE PLANT IS STABLE AND THE PRIMARY LEAK IS ISOLATED (OR THE REACTOR IS DEPRESSURIZED), HEAD REFEREE WILL TERMINATE DRILL.
- 2. DRILL CONTROLLER WILL ENSURE NETS AND RADIO COMMUNICATIONS ARE RESTORED TO READY CONDITIONS. ;
- 3. NCO AT H.C. MAKES PAGE ANNOUNCEMENT. I 6.83 O
v
l H94-06 REV. 2 O ' s' SECTION 7.0 l HOPE CREEK GRADED EXERCISE (H94-06) SUPPLEMENTAL SCENARIOS TIME SUCCESS RESP SCENARIO # BEGIN/END ? DEPT
- 7.01 10-B-130 USS FIRE 08:33/09:30 YES NSP i
- 7.02 10-B-130 USS REPAIRS 08:55/11:00 YES ' ELECT ,
- 7.03 LOOSE PARTS MONITOR ALARM 09:01/09:20 YES OPS
- 7.04 MANUAL ISOLATION OF THE 09:28/10:00 NO OPS /
#6C FEEDWATER HEATER MAINT
- 7.05 13.8 KV SWITCHYARD DAMAGE 09:48/15:30 NO OPS /
ASSESSMENT AND REPAIR RELAY
- 7.06 TURBINE BUILDING FIRE 09:49/10:30 YES NSP/
FIGHTING AND DAMAGE OPS ASSESSMENT
- 7.07 "B" 4160 VAC VITAL BUS 09:49/14:18 YES ELECT '
ALT FEEDER BREAKER REPAIR [ 7.08 "B" EDG LUBE OIL 10:22/14:11 YES MAINT SUCTION LINE REPAIR 7.09 "D" LPCI INJECTION 10:51/15:30 NO ELECT VALVE MOTOR MALFUNCTION 7.10 FUEL ZONE VARIABLE LEG 11:02/11:35 NO I&C LEAK WITH EFCV CLOSURE 7.11 "A" RHR PUMP REPAIRS 11:35/15:30 YES MAINT 7.12 ISOLATION OF THE DRYWELL 11:35/14:49 YES OPS / ATMOSPHERIC SAMPLE LINE ELECT 7.13 RHR PUMP SUCTION 11:45/15:30 YES OPS / STRAINER BACKWASH MAINT 7.14 "C" RHR PUMP TRIP 12:15/13:46 NO ELECT 7.15 LINEUP OF ALTERNATE 12:20/15:30 YES OPS RPV INJECTION SOURCES
- SCENARIO STARTS PRIOR TO OSC ACTIVATION 7.0.0 0
1994 Graded - Exercise (H94-06) pplemental Scenario Timolino _= - =%__a = z l 7', g iroBr30 _1 (USS Fire ~Q ,- b0833 -0939 l y_n 90Br30 USS Repaire =l 0855 1100
"*lE % D
- .04 !
0928 1000 - 7.05 F3.8KF Swifehyaed Damage Aesesement & Repairs g 0,48 L 7.06 nen ) 0949 \1030 7.07
- g ed a Repa 1
- 1418 0949 g
7.0B B' EDC lssbe Oil Suction Line Repair =
> 1022 1411
=
t Moto e netton
I O tirm 110 2 1135 W 7.11 "A* RER Pump Repaire =
[--4 1135 7.12 frotation of the hell Atmospheric Sample Line _l 1135 1449 7.13 HR Pump Suction Strainer Backwash , 1145 7.14 (" RHR Pump Trip - 1215 1346 [ 7.15 Lineup of Altentafe RPF fnfection Sources : 1220 08 0045 0950 1135 1315 EE=a= @@' > &[6803V' > @A@> > @Ma EE.s > 1 1 I I I I I I I I I I 0900 1000 '1100 1200 1300 1400 1500 TIME: (0100) (0200) (0300) (0400) (0500) (0000) (0700)
i I ARTIFICIAL ISLAND i ./- ANNUAL EXERCISE 1994 OSC REFEREE SUPPLEMENTAL GUIDELINES t PRIOR TO OSC ACTIVATION: Prior to the ALERT, a number of individuals and teams will be dispatched by the Control Room Staff from the Simulator. Until the OSC is activated, your function is to serve as Inplant Referees for the purpose of controlling the player responses and providing messages and indications in the plant. These activities are not to be evaluated as OSC activities UNTIL the OSCC assumes responsibility for them, since they fall outside the scope of drill objectives for OSC participation. (These activities are to be evaluated as part of Control Room Command and Control) Some of these activities will be picked up by the OSC at the time of activation (10:30 A.M. or earlier) and the following will be demonstrated;
- 1. OSCC receives a turnover of authority and responsibility to control the teams in the field from the SNSS, establishes contact, begins tracking their locations and providing support, as needed.
NOTE: Teams and individuals in plant responding to the directions of the Control Room are expected to heed the Radiation Alert Alarm and announcement concerning Assembly by immediately contacting the Control Room for an update and directions to either continue or return for Assembly. ,
- 2. In this scenario, individuals and teams in progress when the OSC activates should remain in the field at Assembly or Accountability and the OSC should update them on changing conditions or revised objectives if necessary.
- 3. OSC Referee evaluation of team activities begins with the turnover and activation of the OSC.
- 4. Turnover objectives:
a) Teams establish contact with the OSC Point of t Contact (POC) and receive a briefing on plant conditions and either return to work or are recalled to the OSC, as necessary. b) ALL DISPATCHED TEAMS AND INDIVIDUALS are being tracked by the OSC. c) Teams complete their activities and return to the OSC for de-briefing and subsequent dispatch on new O- tasks from the OSC. 7.0.1 c:\pw\ scenario \7-0.94
STANDARD OSC TEAM OBJECTIVES: I For each team that is dispatched, the OSC Staff should l ('/ demonstrate the following: f
- 1. Thorouch briefina. (Refer to Appendix 5, EPIP 202H) ;
Radioloaical support provided is adequate to protect j 2. as needed. l team members That is, from Rad Tech anticipated and hazards,ing survey meter tak the lead, l checking with the referee periodically for dose rates.
- 3. Team arrives at the right destination in a timely manner and is properly equipped to perform tasks assigned.
(keys, procedures, diagrams, tools, proper dosimetry, etc.) responds well to
- 4. Team changingleader keeps the conditions OSC informed,ision including a rev to the mission (if needed) based on new information or escalating emergency conditions.
- 5. OSC Staff supports teams by tracking their location and status. They provide additional resources as needed.
(obtain parts, diagrams, engineering expertise, etc.)
- 6. Thorouch de-briefina of mission results and other observations while in the field, radiological dose received, etc. ,
O O 7.0.2 c:\pw\ scenario \7-0.94
DOSECHRT ALNOR READINGS / DOSE CHART im I i DOSE RATE ----> DOSE DOSE RATE ----> DOSE V' per min. 5 min. per min. 5 min. mR/hr mrem mrem R/hr mRnm mPem 50 1 5 100 2 10 > 1 20 100 150 3 15 1.5 30 150 200 3 17 2 33 170 250 4 20 2.5 40 200 300 5 25 3 50 250 400 7 35 4 70 350 500 8 40 5 80 400 600 10 50 6 100 500 700 12 60 7 120 600 800 13 65 8 130 650 900 15 75 9 150 750 10 170 850 Continued in next column 15 300 1,500 20 330 1,700 25 400 2,000 30 500 2,500 35 600 3,000 40 700 3,500 50 800 4,000 60 1,000 5,000 100 1,700 8,500 7s
- 200 3,30r 17,000
\ 300 5,000 25,000 400 7,006 35,000 500 8,000 40,000 540 9,000 45,000 R/hr mR/ min /5 min REFEREES' NOTES:
The table above is for making " quick" approximations of OSC or field team doses received and indicated on their ALNORS, when the player checks its reading. All readings are intentionally rounded and are within acceptable deviation of calculated values given normal variations in area dose rates, geometry factors, accuracy of dosimetry and approximate times of exposure.
- 1. You should know the Alarm setting on the player's ALNOR that you are controlling. Give the player an " audible" cue when the ALNOR would have reached alarm status.
- 2. You should also give audible cues for Friskers, Portal Monitors, and Air Monitoring Systems (AMS) that are encountered in the field. Refer to your Maps.
s_ / 7.0.3
SUPPLEMENTAL SCENARIO # 7.01 TITLE : 10-B-130 UNIT SUBSTATION FIRE RESPONSE START TIME : 08:33(00:33) END TIME : 09:30(01:30) LOCATION : TURBINE BUILDING, ELEVATION 120' t A. INITIATING CONDITIONS: THE CONTROL ROOM STAFF RECEIVES INDICATION THAT 10-B-130 480 VAC UNIT SUBSTATION (USS) HAS BEEN LOST. A FIRE ALARM IS RECEIVED ON THE FIRE PROTECTION PANEL 10C671. LOADS ASSOCIATED WITH 10-B-130 ARE LOST, INCLUDING POWER TO THE "B" FEEDWATER HEATER STRING. THE SNSS DIRECTS THE FIRE BRIGADE TO RESPOND. B. RELATED MESSAGE FORMS: 4,5,6,7,8,8C,9,10,11,12,13,14,18,21,23 C. POSTULATED EVENT:
- 1) FAILURE MODE (OR CAUSE):
' O THE FIRE IS CAUSED BY AN ELECTRICAL MALFUNCTION OF THE UNIT SUBSTATION (USS). THE FLAMES HAVE SLOWLY SPREAD THROUGHOUT THE UNIT SUBSTATION. BOTH LOAD AND SUPPLY SIDE WIRING HAVE BEEN DAMAGED LEADING TO AN ELECTRICAL GROUND FAULT THAT HAS , DEENERGIZED THE UNIT SUBSTATION.
- 2) SYMPTOMS (OR INDICATIONS):
TURBINE BUILDING, ELEVATION 120' MEZZANINE AREA IS FILLED ' WITH SMOKE. AN ORANGE GLOW IS VISIBLE AT THE FLOOR LEVEL OF THE UNIT SUBSTATION. PAINT ON THE OUTSIDE OF THE UNIT SUBSTATION IS BEGINNING TO BLISTER AND PEELING MAY BE SEEN WHEN THE FIRE IS OUT AND SMOKE HAS CLEARED. IN ADDITION, LOSS OF 10-B-130 RESULTS IN A LOSS OF LIGHTING IN VARIOUS AREA OF THE TURBINE BUILDING. , t 7.01.1 O
SUPPLEMENTAL SCENARIO # 7.01 - (CONTINUED)
-C. POSTULATED EVENT:
- 3) RESTORATION GUIDELINES: '
FIRE FIGHTING GUIDELINES: USE OF PORTABLE CO2 FIRE EXTINGUISHERS IS SIMULATED. THE FIRE IS EXTINGUISHED AT 08:55. (TIME CRITICAL). VENTILATION OF THE AREA IS REQUIRED AFTER THE FIRE IS OUT. VENTILATION OF THE AREA IS COMPLETED AT 09:17.
- 4) SCENARIO CONTROLS:
A) THE FIRE IS EXTINGUISHED, BUT NOT BEFORE 08:55 (CRITICAL) B) THERE ARE NO POSTULATED INJURIES. C) THIS FIRE DOES NOT SPREAD TO ANY OTHER EQUIPMENT. D) ENSURE THAT THE FIRE BRIGADE LEADER DETERMINES THAT THE UNIT SUBSTATION IS DEENERGIZED. E) VENTILATION OF THE AREA IS COMPLETED 09:17. D. RADIOLOGICAL CONCERNS: SINCE THE FIRE IS LOCATED WITHIN THE RCA, ENSURE THAT TEAM MEMBERS DEMONSTRATE APPROPRIATE RADIOLOGICAL PRECAUTIONS. O E. ATTACHMENTS: ,
- 1) 10-B-130 UNIT SUBSTATION LOAD LIST
- 2) 10-L-102 TURBINE BUILDING LIGHTING PANEL LOAD LIST
- 3) POWER SUPPLY TO 10-B-130 UNIT SUBSTATION
- 4) 10-Y-104 120 VAC DISTRIBUTION PANEL LOAD LIST
- 5) 10-Y-106 120 VAC DISTRIBUTION PANEL LOAD LIST
- 6) 10-B-130 125 VDC CONTROL POWER SOURCES
- 7) TURBINE BUILDING, ELEVATION 120' LAYOUT MAP F. CONTROLLERS SPECIAL NOTES / REFERENCES / OBJECTIVES:
- 1) IT IS CRITICAL TO THE DRILL TIMELINE THAT THE FIRE IS NOT EXTINGUISHED BEFORE 08:55. (FIRE > 10 MINUTES)
- 2) THE FIRE DOES NOT DAMAGE ANY SAFETY RELATED EQUIPMENT AND IS LIMITED TO ONLY THE 10-B-130 UNIT SUBSTATION.
- 3) OSC IS NOT ACTIVATED AT THIS TIME, FIRE BRIGADE MAY RETURN TO THE FIRE HOUSE.
7.01.2 0
- .~ . - - . - .
10 - B - 13 o LoAos 3 : g, goos TOA8ME , 52-1!511 *NL 13L132 # P Id 8'08 N 32-13012 DMPr: HILL VTR CI;C 1 7161 ( 52-13013 $NL 103132 DNL 133132 52-13014 FANiTG5 EXd 13V135 52-13021 'MPr1G-SET L/3 1?10123 si Rx g. p ,P 6- Cr 5d 52-13322 FAN,MG-SIT VNT 1AV137 .A , 32-13023 " N L l 'J 3131 , 4 4 4 'frip5,c^d5'^j
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- 52-13024 .
RE 52-13331 2MPiMS-SIT L/0 1A1313G g g d ein-tLL 32-13032 CENTRI:U3ErMTL3.10512? 32-13033 sNL 1351:3 O bbo DNL 133133 52-131311 Sor : L :. 3;N SUNP 1E?163 32-131012 ?MP,r39 icuI? 3:N SU9: 133165 3 2- 131 J13 213rEME; SJM3 13D167 52-131321 93V A<-HV2691E COS 39 SUCT 52-131322 "3V A< nV2671E CNDS 3M SUC7 52-131323 DMPrREGEN 4: CNDCT SJMS 13P169 52-131324 o v. or5Ett WTD CIRC 13:132 52-131031 M3V A<-4/27019 CN')S 3 '1 BY3 32-131032 '13 V A<-HV2701E CNDS 3 'i 3YP 5 2-131 J 3 3 MOV AD-HV2723 CN35 39 FLUSH 32-131034 PMP,C3ND 39 CAUSTIC 15P147 , 52-131341 v3V t<-aV27023 CON 3 3 *' 35CH 52-131342 13v A<-uv2732E C3ND :' DSC4 ; 52-131343 SoARE 52-131344 ?MPe:3ND DM ACIO.1SP110 52-131051 4ECE?TrT33 1 N T 31331
#ECESTrT35 1NTi1331 52-131332 3Mo,T39 03ND RTN 1=o137 ,
52-131353 XFMRe v-3 SIT ALT 3UP 1EX432 32-1310o1 HTarTG3 WTR TK 3]E133 - l 52-132321 v3V 2C-HV1363C C3E105 M/ S tRN 32-132322 v3V A C -d V13:1 C CIE135 M/ S 32N 52-132023 13V AF-hV1362C S an CIE133 ISLN ~ - r2-132024 "3V #A-HV1373 3SI ' Il ~< IIU i
!2-132331 '3V 5 F-H V13c 3 C F-H 012106 IS LN --> ExTAAcTaov Nm 52-132332 '3V AF-HV1511 :N 03E105 *>US 150LprioW VAuvE TO 52-132033 *3V 2F-HV1533C F4 C1E103 32N 52-132334 !?ARE q g ggg pg ;
52-132341 w3V A3-Hv160')C C3/ a/C5 GH 37 LNES M*Tevc PowEA-
- 52-132342 '3V A3-Hv1613C FWH C3/C4/C5 IN "
32-132]43 (Fvo 1AX531 ALT 'W: SUD
- xFv? 1 X531 tLT 'd SU" C&o '
52-132344 tFvR 1AX502 "LT a* SUS MM x:MR 1AX5J2 SLT 2 44 3U y, ,,,v [ F4 M 'D4E : 32-132351 13V C3-HV1 6:A1 1F STS SUC~ ' 52-132352 ~' 3 V C3 nV126fi2 157 3T3 ?UCT M 6C. FEED w ATEA_ l 52-132333 93V C3 "V1772C VAC 3</VAC ISU HEATgj( L g g 5 " #I'# 6 L i 52-132354 JT:f 3F2T L/3 C3N30LE 1CE13-5 E* M [
> 32-132361 10V C3-HV1873C is/VA0 # II 32-132362 "3V AD-HV1623 FDWTR iT9 3YP 52-132063 23V C3-HV1066A3 15T ST3 SUCT i
- 7. 01 A :
10 - B - 130 LOADS (.O'HT t 52-132364 LTiCOND C3M*T .55T 1rVH113 52-132371- *0V A0-HV1654 SEC COND ?Mo :Y? 52-132372 10V A3 nV1663 S*E 13E110 INL 52-132373 MOV A0-HV1661 5?F 13E110 3TL 52-132374 ' M
- e L / a7 fFR 13P137 52-132351 33V C 3 -H V 2 317 ;UX 27'4 FIET .
52-132332 40V E3-HV2662 T V 2. 5 AJ 5/3 ML 13 Y10D;
@-1323c3 s 2NL 1'Y104 # gg ggg y 52-1323E4 (FM4 13X531 2L- Da; 3US
!. F M 3 11X 5 31 LLT :-s : su= .Soffu G Poe 52-132355 (F** 13X532 ALT N3 3U3 , yo ' g 4 (ggougTE/L X F v. R 19X532 LLT 3; SUS 52-132]?1 2NLi:3ND DEMIN -T TRACE 1 ': C 13 5 \ M@ W '
I 52-132372 3?ARE I PA H E.t-. . 52-132393 13V AD-HV1745C FJh SC 3Yo , 52-132394 3 V A0-HV1746C F*n 2C ?Yo 52-132131 2Mo rEMER SUMP 20?167 32-132131 ??ARE 52-133312 *0V AE-NV17535 :44 3E196 OTL 32-133313 A3V AF-HV15033 F4H E E136 0 3'l 52-133314 EXTR/3EMISTr4F'T 13<136 52-133321 '3V AC-HV17513 0F37 7 L? 3 T.M 52-133322 v]v *W-HV17523 ?:3T s HI P2E5 t 32-133323 '3V AF-HV15332 F Jr :E136 3 UMP 52-133324 ADV CA-HV2331 STY EEAL 1Y? s 32-133331 13V F '4 - H V 17 6 3 5 HI ==ES ELW ;T 5?-133332 20V FJ-HV1761E H: =RES A2V ST 52-133333 MOV F 4-H V176 53 R .: 2T 3 M3TWE VV 52-133334 v0V CA-HV2313 EVA: WT9.EEEC 52-133341 43V cW-HV17$63 :FoT 3 EXH. 52-133342 SOV FJ-HV17673 MST 5 4VV ?LW 52-133343 <Tii3E=V SUP FLN OAVH131 52-133344 "0V Ca-9/2337 AUX 5T4 TO IEAL ~ 32-133351 MOV AE-HV17675 :FPT E 3 5 C 'd 52-133352 */S Rv 1512 ;A) SHLD 330R v/S 2v 1512 4AD SHL) 0001 52-133353 4ECE=TrT35 1NT31453 : R E C E STi T 3 5 1 N T314 5 3 52-133354 FANrL/0 ST3R RM EXH 13V114 52-133361 MOV 84-HV1772B L3 3REE E L'd ST 52-133362 MOV AE-HV17323 RF=T 3 2. E C I S C V ' 32-133363 40ISTi M-3 5ET 33H135 - i 40ISTi"-3 SET OsH195 52-133364 :ANiSECV AiEA SU: JAVH131 52-133371 40V A3-4V1'313 RcDT 3 SUCT 52-133372 CHLRi4T: 1EX111 ALT 52-133373 WOISTi:FP 1A4107 WOISTr:FD 1 A 4107 32-133374 3LOWERi3 TEAM P A C.< EX4 13X133 52-133351 SNL 13 Y13 6 l 2NL 13Y136 l O 4 1 . 018
10 - B - 130 LOADS (uNT (~8 4-HV37113 RFoT : 3Tv 3R1 ( ,) 32-133032 MOV MOV :4-HV3719 HP ITM HD2 OSN 52-1330E3 32-133034 *0V AE-HV17633 FWH 3E106 INL 52-133391 SOV AC-HV1365 CNT AREA CN?S ST 52-133092 90V 43-HV1305 COND HTWL 3DAPS: 52-133093 90V 45-HV17773 RECIRC LN ISLN 53-133J94 HTRiSE:V SUP FAN OAVW131 32-133131 4T4e ocoT /0 DURIF 1]E1?? 52-133102 v0V ai-HV17446 F4H ?Yoa53 32-133103 40!ST iTG3 AUX CRANE 3 H102 H0!STrT32 AUX C.ANE JOH120 52-133104 CM?Sar.A) a ::) 3REATHING A I O. C.PS3rAA) 1 230 3R ATHING AI? 52-133111 HTRrSERV 5 'J P FAN 3AV4131 52-133112 HTo r3ERV Sd> cAN GAV4131 52-133113 HTRr5EDV S 'J o FAN OAVH131 52-133114 HTRrSE3V $JP FAN OAVH131 N (O ( (. , 1 I i
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TU FtSWE Bo i LDirJ Cr l o - L - I o 2- (17-() *C L ICr Wr4 rJ Cr loa 05 m ( i \_) 10L102-31 ~~~ L TGiT? EL 137 (4IGJ *AY) 10L132-02 LT3,T3 EL 137 ( M. : 3.4 3AY) 13L102-03 LT3,T9 EL 137 (4!34 SAY) 13L102-04 LTGrT3 EL 137 (HIGH 3AY) iSL102-03 LT3rT3 EL 137 C *G4 2AY) 10L102-0$ LT3eT9 E '_ 137 (,134 3AY) 10L102-07 LTG,T3 EL 137 */S i. 20AT* d T P. 10L102-03 LTGrT3 EL 137 10L102-07 LTGrTE EL 137 v./S '. F0WT5 272 10L102-10 LTGrTS EL 137 10L102-11 L T,3 r T 3 EL 137 M/S E FDWTR HT2 10L102-12 LT3rT3 EL 137 10L102-13 LT3eT5 EL 123 1 123 SW3R 10L132-14 LTGiT3 EL 171 43V 303M
.10L102-15 LTGrT3 E L 12 3 3 12 3 SWGR 10L1J2-16 LTG,T3 EL 171 MtV 400M 10L102-17 LTGrT3 EL 12 3 3 123 SW3R 10L132-13 LTG,T3 EL 171 ELEC MAINT :"
10L102-19 LT3rT5 EL 123 s DIDE CHASE 10L102-20 _ T3rT3 EL 77 10L102-21 LTGiT3 EL 123 i "IDE CHASE 10L102-22 LTS,T3 EL 77 10L102-23 LTG,T2 EL 123 i PI?E CHASE 10L102-24 LTGrT5 EL 77
10L102-25 LTGr3T;WELL 11-03 (s,)N 10L102-26 LT3rTS EL 5'+
10L102-27 LT3,379WELL 11-33 10L102-23 LT3eT5 EL 54 10L102-29 LT3r3TRWELL 11-03 10L102-30 LT3rT5 EL 51 10L102-31 SPARE 10L102-32 LT3i 3 EL 54 & 137 . 10L102-33 E?A;E 10L132-34 LT3rTA EL 54 1 137 10L102-33 SPARE 10L102-36 LTGrii EL 54 3 137 10L102-37 PNL 13L122 10L132-35 LTGrTB EL 53 6 137 10L102-39 'NL 10L122 10L102-40 LT3,TS El 54 s 137 10L102-61 2NL 13L122 10L102-42 L T 3 r T_3 EL is s 137 C t x 7.010
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E:Uc"c O ww o . -- mm 1BX501 M% 1AX501 ( W'8=2' NEL'....,.'.'.G'" - O I I l __ 10 IEEDER BRKRS FOR 1E SW GEAR: 10 A401.402. I) I NO W l) NO l 403.404 ' l 4.16KV BUS 10A101 i O l 4.16KV BUS 10A102 __ -m __ __ -_-_-- D 480VAC USS 108490 10B120 108250 108130 10B110 108260 108140 At 08:33, the Control Room Crew will receive indication that Non-Essential 480 VAC Unit substation (USS) 10-B-130 has beGn lost. The Unit Substation has overheated and is on fire. The loss of this Unit Substation among other things will cause a Loss of AC Power to various Cond:nsate and Extraction Steam System Valves, that will become significant later in the scenario.
10 - Y -- lotl LoAOS (i2.o NA c ' O 10Y104-01 HTRi SD AC E MC C 135111 HT9,3?2CE MCC 1321?3 i i 10Y104-02 10Y104-03 4TRi5 PACE 3'J5 101103 7 MTRr1 AVE 130 3 15VE103 10Y104-04 10Y104-05 HTRe10VE135 5 10VE106 10Y104-06 AT*i3SACE EU3 10 A119 ' 10Y104-07 2NL,73WTR TRN E I.1ST 1SC102 10Y104-03 3 PARE 10Y104-09 WTo rSPACE BATT.CdGR 100143 10Y104 10 SNLeT3 CLRS 10C137
' 10 Y 104 -11 4 Tar 3 PACE 3W30.10D173 10Y1]4-12 ALAR 9sCO2 1T3R TX REFRIG 10Y104-13 ATR,1 AVE 104 3 1 a V E104 10Y134-14 'iT4.i1 LV E100 5 1 MVE100 +
10Y104-13 HTRe1JVE133 7 1 <V E10 3 13f134-16 iTo r1 EVE 102 '. 10VE143 10(104-17 4To r5 PACE STA SERV XFM 1AX531 10 Y 10 4-13 iTF 10VE130 s 15V E131. , 10Y134-19 4TS 14VE13; s 10V E143 ' 13Y104-20 NTRe? ACE STA SE:V XFM= 13X501 10Y104-21 4TPe3: ACE STs qEoV x Ma 1 Ax5:2 10Y104-22 iTRr3 PACE STA SERV XFMR 13X532 10Y134-23 4T4eS ACE EHC HYO oM? 128116 " 10Y104-24 TERM 30X,MN T3 LO RSV 1NT21209 10Y134-25 SPARE 10Y104-26 4To i5 PACE 3U3 13A111 10Y104-27 4TRiSPACE 3US 13A109 ; 13Y104-23 '4 7 R i S S A C'E SUS 104129 i i I i t f "7 . o t F
10 - Y - LOG LOAD.S (17o VAc I n < \-) 10Y106-31 1AF134 INST AIR 3 3 Y E S. DUTLET 10Y106-02 DNLeAIR oVRIFIE2 CONT 13C143 10Y106-03 S?ARE 10Y106-04 $NLeRFDT L3 CONSOLE 1CC133 10Y106-05 PNLeRF'T L3 CONS 3LE 13C133 10Y106-05 30ARE 10Y106-07 'NLiINST AIR STATUS 33C133 10Y106-36 2NLiINST AIR CMP 3R 13C193 10Y13o-07 4TFeSPACE SU2 105143 10Y136-13 4~4,13VE132 ? 1CVE102 10Y106-11 HTRi3? ACE SU? 103140 13Y1?6-12 H T S. r 1 A V E 13 3 10Y196-13 HTRr1 AVE 132 '. 10 V E 10 2 10Y106-14 DEMINSrTACS CONTROL IT AT:3'l 10Y106-15 SPARE 10Y136-16 HTRrSPACE MCC 103113 10Y100-17 PNLeRFPT Lo CONSOLE 1AC133 10Y106-13 dTRi1 EVE 103 10Y136-19 oNLeCNDS3 0 INST 1CC134 10Y136-23 HTRiSPACE SW31 10A106 10Y106-21 HTRes? ACE SW3R 10A103 13Y106-22 MTReSPACE SWGR 13A104 10Y196-23 HTRrSPACE S43R 13 A103 g 10Y106-24 H T C.i S P A C E SWGR 10 A104 10Y136-25 dic eS3 ACE SW3R 13 A10 3 13Y106-25 4T1,soACE SW3R 13 A102 10Y106-27 SSASE 10Y106-23 979esoACE SW3R 13 A10 2 10Y106-29 SPARE 10Y106-33 HTReSPACE SW3R 13A102 10Y106-31 SDARE - 10Y106-32 SPAR - 10Y137-01 33A45 l l l W U 7,oiGr
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g SUPPLEMENTAL SCENARIO # 7.02 d TITLE : 10-B-130 USS REPAIRS START TIME : 08:55(00:55) END TIME : 11:00(03:00) LOCATION : TURBINE BUILDING, ELEVATION 120' A. INITIATING CONDITIONS: UNIT SUBSATION 10-B-130 HAS BEEN DAMAGED BY A FIRE. THE FIRE IS EXTINGUISHED BY SITE PROTECTION PERSONNEL AT 08:55. SMOKE IS CURRENTLY BEING CLEARED FROM THE AREA. B. RELATED MESSAGE FORMS: 18C,22,50 C. POSTULATED EVENT:
- 1) FAILURE MODE (OR CAUSE):
AS THE RESULT OF THE FIRE IN THE 10-B-130 UNIT SUBSTATION (USS), BOTH LOAD SIDE AND SUPPLY SIDE WIRING HAVE BEEN DAMAGED, LEADING TO AN ELECTRICAL GROUND FAULT THAT HAS DEENERGIZED THE UNIT SUBSTATION.
- 2) SYMPTOMS (OR INDICATIONS): !
WHEN THE FIRE IS EXTINGUISHED AND SMOKE CLEARED FROM THE AREA, THE REPAIR TEAM WILL OBSERVE THE FOLLOWING:
- PAINT ON THE OUTSIDE OF THE UNIT SUBSTATION IS BEGINNING TO BLISTER AND SOME PEELING MAY BE SEEN.
- WIRING DAMAGE IS CLEARLY VISIBLE.
- INSULATION IS CRACKED AND CHARRED. REPLACEMENT IS REQUIRED.
l 7.02.1 O
SUPPLEMENTAL SCENARIO # 7.02 (CONTINUED) i C. POSTULATED EVENT:
- 3) RESTORATION GUIDELINES:
UNIT SUBSTATION RESTORATCON: ALL GROUNDS AND SHORT CIRCUITS MUST BE LOCATED AND CLEARED BY REPLACING THE DAMACED WIRING OR MAKING TEMPORARY REPAIRS BY WRAPPING THE BARE SPOTS AND RECONNECTING LEADS.
- 4) SCENARIO CONTROLS:
A) REPAIRS TO THE UNIT SUBSTATION CAN BE SUCCESSFUL AFTER 11:00, PROVIDED OSCC PURSUES REPAIR EFFORTS AND THE TEAM SATISFACTORILY DEMONSTRATES REQUIRED REPAIRS. B) LOSS OF THIS UNIT SUBSTATION WILL RESULT IN THE LOSS OF POWER TO THE "B" FEEDWATER HEATER STRING, AS WELL AS SOME CONDENSATE AND EXTRACTION STEAM VALVES. C) REPAIRS EFFORT SHALL NOT COMMENCE UNTIL THE FIRE IS EXTINGUISHED (08:55) AND SMOKE HAS BEEN CLEARED (09:17). D. RADIOLOGICAL CONCERNS: TEAM MEMBERS SHALL DEMONSTRATE APPROPRIATE RADIOLOGICAL PRECAUTIONS WHEN WORKING INSIDE THE RCA. O E. ATTACHMENTS:
- 1) 10-B-130 UNIT SUBSTATION LOAD LIST
- 2) 10-L-102 TURBINE BUILDING LIGHTING PANEL LOAD LIST
- 3) POWER SUPPLY TO 10-B-130 UNIT SUBSTATION
- 4) 10-Y-104 120 VAC DISTRIBUTION PANEL LOAD LIST
- 5) 10-Y-106 120 VAC DISTRIBUTION PANEL LOAD LIST
- 6) 10-B-130 125 VDC CONTROL POWER SOURCES
- 7) TURBINE BUILDING, ELEVATION 120' LAYOUT MAP F. CONTROLLERS SPECIAL NOTES / REFERENCES / OBJECTIVES:
- 1) IT IS CRITICAL TO THE DRILL TIMELINE THAT REPAIR OF THE UNIT SUBSTATION NOT BE SUCCESSFUL UNTIL AFTER 11:00, FOLLOWING THE MAIN TURBINE TRIP AND SUBSEQUENT TURBINE DAMAGE.
- 2) VENTILATION OF THE AREA IS SUCCESSFUL AT 09:17.
7.02.2 0
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.At 08:33, tiie control Ii55m Crew will recElv'e indication that Non-Essential 480 VAc Unit substation (USS) 10-B-130 has been.
lost. The Unit substation has overheated and is on fire. The loss of this Unit substation among other things will cause a Loss of AC Power to various Condensate and Extraction Steam System Valves, that will become significant later in the scenario.
10 - Y - 104 LoAos (r2 o VAcl P V 10Y104-01 HTRr 5? AC E ' 4CC 105111 10Y104-02 HTo.e3P2CE MCC 1031?3 10Y104-03 MTRr5 PACE 3'JS 10:103 10Y104-04 HTRe1 AVE 100 3 13VE103 10Y104-05 HTRi10VE135 5 10VE105 10Y104-06 4Tois= ACE sus 10 A119 10Y104-07 SNLe70WTR TRN E IN S T 1 S C10.2 10Y104-03 3 PARE 10Y104-09 4TRes? ACE 3ATT CdGR 100143
- 10Y 10 4-10 SNLeT3 CLR5 10C137 10Y104-11 4 Tar 5 Pace SW3D 10D173 10Y104-12 ALAR 9eCO2 STOR TX 2EFRIG 10Y104-13 ATR e1 AVE 104 1 19V E104 1 10Y104-14 4 T R e 1 LV E100 1 1 MVE100 10Y104-15 HTRi1JVE133 R 1 <VE103 10Y104-16 iTs e1 EVE 102 ? 10VE140:
10Y104-17 HTRe s? ACE ST A SERV x. MR 1AX501 10 Y 10 4-13 iT ?i1 CVE100 8, 15V E131 10Y104-19 4To.r1 AVE 13 9 3 10V E14 3 10Y104-20 HTo eSDACI STA. SERV XFva 13X501 ' 10 Y104-21 4TRr3 ACE STA SERV XFMR 1AX502 10Y104-22 4TRi3 PACE STA SERV XFMR 13X502 10Y104-23 4T9/58 ACE EHC HYD OMP 122116 10Y104-24 TERM 30XiMN T3 L3 RSV 1NT31200 10Y104-25 $ PARE
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10Y104-26 HTRiSPACE 3US 104111 10Y104-27 iTRrSPACE 3US 10 A109.
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SUPPLEMENTAL SCENARIO # 7.03 TITLE : LOOSE PARTS MONITOR ALARM START TIME : 09:01(01:01) END TIME : 09:20(01:20) LOCATION : AUXILIARY BUILDING, ELEVATION 163' A. INITIATING CONDITIONS: THE CONTROL ROOM WILL RECEIVE OVERHEAD ANNUNCIATOR C6-AS, l RPV LOOSE PARTS MONITOR PNL 10C675, ALONG WITH INDICATION OF A RAPID DECREASE IN FLOW IN THE #5 JET PUMP, AS WELL AS A DECREASE IN TOTAL JET PUMP FLOW IN THE "B" REACTOR RECIRC LOOP. B. RELATED MESSAGE FORMS: 13D,16,17,20,55D C. POSTULATED EVENT:
- 1) FAILURE MODE (OR CAUSE):
O THE #5 JET PUMP RISER SECTION HAS FAILED. THE ELBOW / MIXER SECTION (RAM'S HEAD ASSEMBLY) SUDDENLY SEPERATES FROM THE TOP OF THE JET PUMP RISER. THE BROKEN PIECE OF THE #5 JET PUMP SUBSEQUENTLY BECOMES WEDGED BETWEEN THE TOPS OF JET PUMPS #4 AND #5.
- 2) SYMPTOMS (OR INDICATIONS):
IN THE MAIN CONTROL ROOM: A) #5 JET PUMP FLOW AND REACTOR POWER DECREASE. B) TOTAL JET PUMP FLOW IN THE "B" RECIRC LOOP DECREASES. AT PANEL 10C675 IN THE UPPER RELAY ROOM:
" LOOSE PART" LIGHT IS ON FOR THE FOLLOWING CHANNELS:
CHANNELS 5 & 6 (INLET RECIRC LINE)
" VIBRATION" LIGHT IS ON FOR THE FOLLOWING CHANNELS: 1 CHANNELS 5& 6, AS WELL AS, CHANNEL 12 (RECIRC PUMP 1BP210).
7.03.1 l i l
i SUPPLEMENTAL SCENARIO # 7.03 ; (CONTINUED) ? C. POSTULATED EVENT: Q,
- 3) RESTORATION GUIDELINES:
A) AN OPERATOR NEEDS TO BE DISPATCHED TO THE LOOSE PARTS MONITOR PANEL (10C675) TO VALIDATE THE ALARM. B) CONFIRMATION OF THE FAILURE OF THE #5 JET PUMP WILL REQUIRE A REACTOR SHUTDOWN BE COMMENCED. C) THE #5 JET PUMP IS NOT RECOVERABLE. D) ATTEMPTS TO RESET THE ALARMS WILL NOT BE SUCCESSFUL.
- 4) SCENARIO CONTROLS:
A) WHEN AN OPERATOR IS DISPATCHED TO THE LOOSE PARTS MONITOR PANEL, ENSURE HE VALIDATES THE ALARM IN ACCORDANCE WITH THE SYSTEM OPERATING PROCEDURE. D. RADIOLOGICAL CONCERNS: NONE E. ATTACHMENTS:
- 1) 10-C-675 LOOSE PARTS MONITOR PANEL
- 2) JET PUMP ASSEMBLY SCHEMATICATIC
- 3) JET PUMP INSTRUMENTATION SCHEMATIC
- 4) LOOSE PARTS MONITORING SENSOR LOCATIONS
- 5) AUXILIARY BUILDING, ELEVATION 163' LAYOUT MAP F. CONTROLLERS SPECIAL NOTES / REFERENCES / OBJECTIVES:
- 1) ENSURE THAT AFTER THE INFORMATION HAS BEEN OBTAINED FROM THE LOOSE PARTS MONITOR PANEL, THAT IT IS PROVIDED TO THE CONTROL ROOM CREW AT THE SIMULATOR (X3339).
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- 1. BB-VE-7933A (7933B) Reactor Vessel - Steam Dryer Level
- 2. BB-VE-7933C (7933D) Reactor Vessel - Steam Dryer Level
- 3. BB-VE-7934A (7934B) Reactor Vessel - Steam Separator Level
- 4. BB-VE-7934C (7934D) Reactor Vessel - Steam Separator Level
- 5. BB-VE-7935A (7935B) Reactor Vessel - Fuel Assembly Level
- 6. BB-VE-7935C (7935D) Reactor Vessel - Fuel Assembly Level
- 7. BB-VE-7937A (79378) Reactor Vessel - Bottom Head
(~ 8. BB-VE-7937C (7937D) Reactor Vessel - Bottom Head '~'
- 9. BB-VE-7937E (7937F) Reactor Vessel - Bottom Head
- 10. BB-VE-7937G (7937H) Reactor Vessel - Bottom Head
- 11. BB-VE-792SA (79388) Recirc Pumps - No. 1 Seal Cavity
- 12. BB-VE-7938C (7938D) Recirc Pumps - No. 1 Seal Cavity NOTE: See M-42-1 Sheet 1 for Sensor AZIMUTH O
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(~wg SUPPLEMENTAL SCENARIO # 7.04 U TITLE : MANUAL ISOLATION OF THE #6C FEEDWATER HEATER START TIME : 09:28(01:28) END TIME : 10:00(02:00) LOCATION : TURBINE BUILDING, ELEVATION 155' A. INITIATING CONDITIONS: A LARGE TUBE LEAK DEVELOPS IN THE #6C FEEDWATER HEATER. LEVEL IN THE HEATER INCREASES. DUE TO A PREVIOUS LOSS OF 10-B-130, POWER IS LOST TO THE EXTRACTION STEAM ISOLATION VALVE. RECOGNIZING THAT THE HEATER HAS NOT ISOLATED, THE CREW WILL ATTEMPT TO CLOSE THE CONDENSATE INLET VALVE TO THE #6C FWH. THE VALVE FAILS TO REMOTELY CLOSE FROM THE CONTROL ROOM. B. RELATED MESSAGE FORMS: 19D,24,25,26 C. POSTULATED EVENT:
- 1) FAILURE MODE (OR CAUSE):
O THE #6C FEEDWATER HEATER CONDENSATE INLET VALVE, 1AEHV-1768C DOES NOT CLOSE REMOTELY FROM THE MAIN CONTROL ROOM DUE TO THE MOTOR BREAKER TRIPPING ON THERMAL OVERLOAD.
- 2) SYMPTOMS (OR INDICATIONS):
AT THE VALVE: A) THE MOTOR OPERATOR DECLUTCH LEVER DISENGAGES FROM THE MOTOR WHEN ATTEMPTED. B) THE VALVE HANDWHEEL IS EXTREMELY DIFFICULT TO TURN. AT THE BREAKER: A) THE BREAKER IS FOUND IN THE TRIPPED CONDITION. B) THE CLOSED CONTACTOR IS EXTREMELY HOT. 7.04.1 l l
i i i SUPPLEMENTAL SCENARIO # 7.04 ) (CONTINUED) l
) C. POSTULATED EVENT:
- 3) RESTORATION GUIDELINES: ;
MANUAL OPERATION OF THE VALVE IS REQUIRED TO CLOSE IT. THE VALVE CAN BE CLOGED, BUT ONLY IF THE EQUIPMENT OPERATOR CONTINUES ATTEMPTING TO CLOSE THE VALVE FOR 30 MINT /TES.
- 4) SCENARIO CONTROLS:
A) IT IS CRITICAL TO THE SCENARIO TIMELINE THAT THIS VALVE NOT BE CLOSED BEFORE 10:00. B) THE EQUIPMENT OPERATOR IS TO BE IN THE TURB7NE BUILDING AT 09:48. IT IS CRITICAL TO PROVIDE THE INDIVIDUAL WITH ; THE MESSAGE REGARDING THE TURBINE FAILURE AND BLADING PENETRATION THAT OCCURS AT THIS TIME. D. RADIOLOGICAL CONCERNS:
- 1) APPROPRIATE RADIOLOGICAL PRECAUTION SHOULD BE DEMONSTRATED BY THE EQUIPMENT OPERATOR WHEN MANUALLY CLOSING THE #6C FEEDWATER HEATER CONDENSATE INLET. VALVE.
[\ E. ATTACHMENTS:
- 1) FWH EXTRACTION STEAM SYSTEM SCHEMATIC ,
- 2) #6C FEEDWATER HEATER CONDENSATE FLOW SCHEMATIC-F. CONTROLLERS SPECIAL NOTES / REFERENCES / OBJECTIVES: ,
THIS SUPPLEMENTAL SCENARIO IS DESIGNED TO SUPPORT THE FAILURE OF THE MAIN TURBINE WITH SUBSEQUENT BLADING PENETRATION OF THE TURBINE CASING, BY ALLOWING WATER FROM THE #6C FEEDWATER HEATER TO BE DRAWN UP THE EXTRACTION STEAM LINE AND SUBSEQUENTLY IMPINGE ON THE MAIN TURBINE BLADING. 7.04.2 O V
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- m TO HEATERS 1360 1363 ?< > TO CONDENSER
- 58. C V FROM MOISTURE SEPARATOR DRAIN TANKS A&B HV LV 1361 1364 (362 367
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- 58. C d LP HV d TURBINE PT 1355 1 '
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4 G c. Feeumg. HerriE& CONDEP5KiE Ft.ow Su4ermTt c rm level in the #6C Feedwater Heater (FWH) will begin At 09:28, (' ') to increase as the result of a large tube leak. As level in the Heater continues to increase, a Heater Trip signal will be initiated. However, due to the previous loss of power to the extraction and condensate system valves, remote isolation of the #6C FWH is not possible from the -Control Room. The NSS will again refer to OP-AB.ZZ-0118, Loss of Feedwater Heaters and dispatch an operator to attempt to locally
- isolate the #6C FWH.
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, s SUPPLEMENTAL SCENARIO # 7.05 \, ~
TITLE : 13.8 KV SWITCHYARD DAMAGE ASSESSMENT AND REPAIRS START TIME : 09:48(01:48) END TIME : 15:30(07:30) LOCATION : HOPE CREEK SWITCHYARD 1 A. INITIATING CONDITIONS: THE MAIN TURBINE WILL EXPERIENCE A ROTATING COMPONENT FAILURE. 2 MAIN TURBINE BLADES ARE THROWN INTO THE SWITCHYARD, AFTER PENETRATING THE EAST WALL OF THE TURBINE BUILDING AND THEN IMPACT THE 13.8 KV RING BUS. ONE BLADE WIL7 DESTROY 13.8 KV BUS SECTION 2, WHILE ANOTHER DESTROYS 13.8 KV BUS SECTION 8. B. RELATED MESSAGE FORMS: 33,38 C. POSTULATED EVENT:
- 1) FAILURE MODE (OR CAUSE):
[ \ DUE TO THE LARGE TUBE LEAK IN THE #6C FEEDWATER HEATER AND
\> A SUBSEQUENT INABILITY TO ISOLATE THE FEEDWATER HEATER, WATER INDUCTION IS BEGINNING TO OCCUR (BLEEDER TRIP VALVE -
IS FAILED OPEN). AS THE WATER ENTERS THE HIGH PRESSURE TURBINE, WATER IMPINGEMENT ON THE MAIN TURBINE BLADING OCCURS, RESULTING IN A HIGH VIBRATION CONDITION AND TURBINE BLADING FAILURE.
- 2) SYMPTOMS (OR INDICATIONS):
- 1) A SECURITY PATROL WILL OBSERVE THE TURBINE BLADING PENETRATING THE EAST WALL OF THE TURBINE BUILDING AND LANDING IN THE SWITCHYARD.
- 2) THE "B" SIDE STATION SERVICE TRANSFORMERS DEENERGIZE AS 13.8 KV BREAKERS BS 1-2 AND BS 9-0 OPEN.
- 3) 13.8 KV BUS SECTIONS 2 AND 8 ARE DAMAGED.
- 4) ONE 13.8KP POTHEAD ON THE 1BX501 XFMER FEEDER IS DAMAGED AND HAS A PIECE OF METAL PERTRUDING FROM IT.
7.05.1 O v
\
l l SUPPLEMENTAL SCENARIO # 7.05 (CONTINUED) C. POSTULATED EVENT:
- 3) RESTORATION GUIDELINES:
THE DAMAGED BUS SECTIONS OF THE 13.8 KV YARD ARE NOT RECOVERABLE FOR THE DURATION OF THE EXERCISE.
- 4) SCENARIO CONTROLS:
- 1) THERE ARE NO INJURIES DUE TO THE TURBINE BLADES.
- 2) THERE IS NO FIRE IN THE SWITCHYARD DUE TO THIS EVENT.
- 3) THE ACTUAL LINE DEPARTMENT WORK WILL BE SIMULATED, BUT THEIR ACTIVITIES SHOULD BE CONTROLLED AND COORDINATED BY THE OSC AND TSC.
D. RADIOLOGICAL CONCERNS:
- 1) TURBINE BLADING IN THE SWITCHYARD WILL HAVE A MAXIMUM READING OF 90 CCPM WHEN/IF SURVEYED.
- 2) SINCE THE PREVAILING WIND DIRECTION IS FROM THE EAST, O THE LINE CREWS WORKING IN THE SWITCHYARD SHOULD BE ABLE TO CONTINUE WORKING, AFTER THE RAD PRECAUTIONS HAVE BEEN DEMONSTRATED AFTER THE RAD RELEASE STARTS AT 13:15.
E. ATTACHMENTS:
- 1) HOPE CREEK 13.8 KV RING BUS - SINGLE LINE DIAGRAM
- 2) ONSITE PLUME PATHWAY MAPS (SEE SECTION 9.0)
F. CONTROLLERS SPECIAL NOTES / REFERENCES / OBJECTIVES:
- 1) THIS SCENARIO WILL NOT CAUSE A LOSS OF OFFSITE POWER, AS STATION LOADS, NORMALLY SUPPLIED BY THE "B" SIDE TRANSFORMERS, FAST-TRANSFER TO THE "A" SIDE TRANSFORMERS.
- 2) OSC SHOULD ENSURE PROPER SAFETY PRECAUTIONS REGARDING ,
ELECTRICAL HAZARDS ARE TAKEN PRIOR TO MAINTENANCE ACTIVITIES IN THE SWITCHYARD. 7.05.2 O
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1 THE MAIN TURBINE WILL EXPERIENCE A ROTATING COMPONENT FAILURE. 2 MAIN TURBINE BLADES ARE THROWN INTO THE SWITCHYARD, AFTER PENETRATING THE EAST WALL OF THE TURBINE BUILDING AND THEN IMPACT THE 13.8 KV RING BUS. ONE BLADE WILL DESTROY 13.8 KV BUS SECTION 2, WHILE ANOTHER DESTROYS 13.8 KV BUS SECTION 8.
SUPPLEMENTAL SCENARIO / 7.06 U TITLE : TURBINE BUILDING FIRE FIGHTING & DAMAGE ASSESSMENT i START TIME : 09:49(01:49) END TIME : 10:30(02:30) LOCATION : TURBINE BUILDING, ELEVATIONS 137', 102' AND 54' A. INITIATING CONDITIONS: THE MAIN TURBINE EXPERIENCES ROTATING COMPONENT FAILURE. TWO MAIN TURBINE BLADES ARE THROWN INTO THE SWITCHYARD. THE MAIN CONDENSER SHELL EXPERIENCES FAILURE DUE TO THE INDUCED VIBRATION FROM THE MAIN TURBINE. A MAJORITY OF MAIN CONDENSER TUBES ARE DESTROYED. AS A RESULT OF THE FAILURE, SEVERAL SMALL FIRES IGNITE ON ELEVATION 137 AND ELEV 102', CAUSING ACTUATION OF THE FIRE PROTECTION DELUGE SYSTEM. B. RELATED MESSAGE FORMS: 31,34,35,39,39C,40,41,42,44,48 C. POSTULATED EVENT:
- 1) FAILURE MODE (OR CAUSE):
O DUE TO THE LARGE TUBE LEAK IN THE #6C FEEDWATER HEATER AND SUBSEQUENT INABILITY TO ISOLATE THE FEEDWATER HEATER, WATER INDUCTION IS BEGINNING TO OCCUR (BLEEDER TRIP VALVE FAILS TO CLOSE). AS WATER ENTERS THE HP TURBINE, IT IMPINGES ON THE MAIN TURBINE BLADING, RESULTING IN A HIGH VIBRATION CONDITION. THIS CAUSES A RUPTURE OF THE TURBINE BEARING OIL SUPPLY LINE, RESULTING IN A TURBINE TRIP AND DAMAGE TO THE "A" LP TURBIPE, AS TWO BLADES PENETRATES THE TURBINE CASING.
- 2) SYMPTOMS (OR INDICATIONS):
A) LARGE QUANTITIES OF WATER AND OIL ARE RAPIDLY FILLING THE LOWER ELEVATIONS OF THE TURBINE BUILDING. AN OIL FILM IS OBSERVED ON TOP OF THE WATER. B) A LARGE HOLE IN THE "A" LOW PRESSURE TURBINE CASING IS OBSERVED IF/WHEN THE TURBINE ENCLOSURE IS ENTERED. C) SMOKE IS PRESENT ON ELEVATIONS 137' AND 102'. D) SMALL FIRES ARE BURNING ON ELEVATIONS 137' AND 102'. E) SOME LIGHTING HAS BEEN LOST ON ELEVATION 102'. 7.06.1 (_/ 1 l l
SUPPLEMENTAL SCENARIO # 7.06 (CONTINUED) n I I C. POSTULATED EVENT:
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- 3) RESTORATION GUIDELINES:
THE TEAM WILL BE SUCCESSFUL IN EVENTUALLY STABILIZING CONDITIONS IN THE TURBINE BUILDING AS FOLLOWS: A) FIRES ARE EXTINGUISHED BY 10:30. B) OPS PERSONNEL SUCCESSFULLY SECURE ALL TURBINE RELATED OIL PUMPS AND ISOLATE CIRC WATER FROM THE CONDENSER. C) SLIPPERY FLOORS DUE TO LUBE OIL REQUIRE CLEANING.
- 4) SCENARIO CONTROLS:
A) NO INJURIES OCCUR DUE TO TURBINE BLADES OR OTHER DEBRIS. B) THE MAIN GENERATOR REMAINS INTACT. NO HYDROGEN LEAKS. C) ACCESS TO ELEVATIONS BELOW 102' IS NOT POSSIBLE (FLOODED) D) THE FIRES LOCATED ON ELEVATIONS 137' AND 102' WILL BE SUCCESSFULLY EXTINGUISHED BY 10:30. E) NO OFFSITE FIRE FIGHTING ASSINTANCE IS NEEDED. D. RADIOLOGICAL CONCERNS: ALL RAD CONDITIONS ARE NORMAL. N - E. ATTACHMENTS:
- 1) TURBINE BUILDING, ELEVATION 137' LAYOUT MAP
- 2) TURBINE BUILDING, ELEVATION 102' LAYOUT MAP F. CONTROLLERS SPECIAL NOTES / REFERENCES / OBJECTIVES:
- 1) THE MAIN TURBINE BLADING FAILURE WILL RESULT IN THE DECLARATION OF AN ALERT.
- 2) THIS SCENARIO IS DESIGNED FOR DAMAGE CONTROL AND ASSESMENT. DUE TO THE MAGNITUDE OF THE FAILURE, THE ERO WILL NOT HAVE SUFFICIENT TIME TO DEMONSTRATE LONG TERM REPAIRS, HOWEVER ACTIVITIES SHOULD STILL BE DISCUSSED.
7.06.2
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- SUPPLEMENTAL SCENARIO # 7.07 TITLE : "B" 4160 VAC VITAL BUS ALT FEEDER BREAKER REPAIR START TIME : 09:49(01:49) END TIME : 14:18(06:18) LOCATION : DIESEL BUILDING, ELEVATION 130' "B" VITAL SWITCHGEAR ROOM A. INITIATING CONDITIONS: LOSS OF THE "B" SIDE STATION SERVICE TRANSFORMERS DUE TO TURBINE BLADING IMPACTING 13.8 KV BUS SECTIONS 2 AND 8 RESULTS IN A FAST TRANSFER OF ASSOCIATED LOADS TO THE "A" SIDE STATION SERVICE TRANSFORMERS. THE FAST TRANSFER IS SUCCESSFUL WITH THE EXCEPTION OF THE "B" 4160 VAC VITAL BUS, WHICH DOES NOT REMAIN ENERGIZED DUE TO A FAILURE OF THE ALTERNATE FEEDER BREAKER TO CLOSE. B. RELATED MESSAGE FORMS: 29D,37C,43 C. POSTULATED EVENT: ,
~g 1) FAILURE MODE (OR CAUSE):
1E 4160 VAC ALTERNATE FEEDER BREAKER 10-A-402-08 FAILS TO CLOSE ON A FAST TRANSFER SIGNAL DUE TO BREAKER FAILURE. THE FAILURE TO CLOSE IS CAUSED BY EXCESSIVE WEAR OF THE BREAKER LATCHING MECHANISM, WHICH HAS CAUSED THE LATCHING MECHANISM TO BREAK, PREVENTING THE BREAKER FROM LATCHING IN THE CLOSED POSITION.
- 2) SYMPTOMS (OR INDICATIONS):
- 1) THE ALTERNATE FEEDER BREAKER IS TRIPPED LOCALLY.
- 2) "B" 4160 VAC VITAL BUS INDICATES 0 AMPS AND 0 VOLTS UNTIL THE "B" EDG IS STARTED AND LOADS, REENERGIZING THE "B" 4160 VAC VITAL BUS UNTIL 10:22, WHEN IT TRIPS ON LOW LUBE OIL PRESSURE (REFER TO SUPPLEMENTAL SCENARIO #7.08).
7.07.1 O
SUPPLEMENTAL SCENARIO # 7.07 (CONTINUED) C. POSTULATED EVENT:
- 3) RESTORATION GUIDELINES:
- 1) ATTEMPTS TO RACK THE BREAKER TO THE TEST AND/OR DISCONNECT POSITION ARE UNSUCCESSFUL, AS THE BREAKER RACKING MECHANISM FAILS.
- 2) ATTEMPTS TO REWORK THE BREAKER MAY BE ATTEMPTED, BUT WILL BE UNSUCCESSFUL.
- 3) BREAKER REPLACEMENT IS REQUIRED. THIS ACTIVITIES IS NOT SUCCESSFUL UNTIL 14:18, PROVIDED IT IS PURSUED TO i COMPLETION BY AN OSC TEAM.
- 4) SCENARIO CONTROLS:
A) IT IS CRITICAL TO THE DRILL TIMELINE THAT THE ALTERNATE FEEDER FOR THE "B" VITAL BUS NOT BE REPAIRED BEFORE 14:18 B) THERE ARE NO INJURIES DURING THE REPAIR EFFORT. C) THERE ARE NO FIRLS DURING THE REPAIR EFFORT. D) ATTEMPTS TO CRO';S TIE THE "B" 4160 VAC VITAL BUS TO ANOTHER VITAL BUS WILL NOT BE SUCCESSFUL UNTIL 14:18. D. RADIOLOGICAL CONCERNS: NONE O E. ATTACHMENTS:
- 1) 1E AC POWER DISTRIBUTION SCHEMATIC
- 2) 4160 VAC VITAL BUS FEEDER BREAKER POSITIONS
- 3) AUXILIARY BUILDING, ELEVATION 130' LAYOUT MAP F. CONTROLLERS SPECIAL NOTES / REFERENCES / OBJECTIVES:
- 1) IN ORDER TO SUBSTANTIATE POSTULATED FUEL DAMAGE, IT IS IMPERATIVE THAT THE "B" 4160 VAC VITAL BUS REMAIN DEENERGIZED UNTIL AT LEAST 14:18, TO PREVENT ADDITIONAL INJECTION TO THE REACTOR.
7.07.2 i
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G DG ww { 480V UNIT 108410 108450 ES * % O TS480 SUBSTATION :. A^ BUS Due to the loss of 13.8 KV Bus Section 2 g Station Service Transformers 1BX501, 1BX502 and 1BX503 will deenergize,
# , resulting in a fast transfer of the associated loads to the 6 41Go VAc- "A" side Station Service Transformesrs. All loads successfully fast transfer, with the exception of the "B" 4160 VAC Vital v g-T A L. 605 Bus (10-A-402). The alternate Feeder Breaker for the "B"
! Vital Bus fails to close due to a breaker malfunction.
As a result, the "B" Emergency Diesel Generator (EDG) will be j started and load onto the "B" Vital Bus.,. m_ ____ _ __ _ ___
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c - i i g- SUPPLEMENTAL SCENARIO # 7.08 l N~/l TITLE : "B" EDG LUBE OIL SUCTION LINE REPAIR ! START TIME : 10:22(02:22) END TIME : 14:11(06:11) LOCATION : DIESEL BUILDING, ELEVATION 102' "B" DIESEL BAY A. INITIATING CONDITIONS: FOLLOWING A START OF THE "B" EMERGENCY DIESEL GENERATOR, AS THE RESULT OF AN UNDERVOLTAGE CONDITION ON THE "B" 4160 VAC VITAL BUS, THE "B" EDG WILL RUN FOR , APPROXIMATELY 33 MINUTES AND THEN TRIPS ON LOW LUBE OIL ! PRESSURE, DUE TO A BREAK IN THE LUBE OIL SUCTION LINE, ! l BETWEEN THE RESEVOIR AND THE ENGINE DRIVEN LUBE OIL PUMP. THE "B" VITAL BUS WILL REMAIN DEENERGIZED, WITH A LOSS OF POWER TO ALL ASSOCIATED LOADS. B. RELATED MESSAGE FORMS: 45D,46,47,79 C. POSTULATED EVENT:
- 1) FAILURE MODE (OR CAUSE) :
O LOCALIZED CORROSION HAS RESULTED IN A WELD FAILURE ON THE "B" EMERGENCY DIESEL GENERATOR SUCTION LINE, WHERE THE SUCTION LINE CONNECTS TO THE LUBE OIL SUMP. THIS FAILURE j RESULT IN A PARTIAL DRAINING OF THE LUBE OIL HEADER, AS WELL AS DRAINING OF THE LUBE OIL SUMP.
- 2) SYMPTOMS (OR INDICATIONS):
- 1) UPON ENTERING THE "B" EDG ROOM, AN OILY SMELL IS PRESENT. '
l
- 2) LUBE OIL CAN BE OBSERVED UNDER THE GRATING PLATFORM ON BOTH SIDE OF THE DIESEL.
- 3) LUBE OIL MAKEUP TANK LEVEL IS DECREASING.
- 4) LUBE OIL PRESSURE LOW SHUTDOWN ANNUNCIATOR IS LIT AT THE ENGINE CONTROL PANEL ON ELEVATION 130'.
- 5) AT "B" EDG REMOTE PANEL BOTH THE REGULAR AND BACKUP LOCKOUT RELAYS ARE TRIPPED.
7.08.1 O
SUPPLEMENTAL SCENARIO # 7.08 (CONTINUED) C. POSTULATED EVENT:
- 3) RESTORATION GUIDELINES:
A) MAINTENANCE WILL BE SUCCESSFUL IN REPAIRING THE FAILED ' LINE, BUT NOT BEFORE 14:11. ' B) ANY REPAIR OF A TEMPORARY NATURE WILL NOT BE SUCCESSFUL (I.E. BAND-IT TYPE MATERIAL), AS THE REPAIR WILL FAIL WHEN THE EDG IS STARTED. C) RESTORATION EFFORTS MUST INCLUDE OBTAINING AND REFILLING THE LUBE OIL TANK AND SUMP. D) TEAM SHOULD SIMULATE GRATING REMOVAL AND OIL CLEANUP. s
- 4) SCENAR.IO CONTROLS:
A) IT IS CRITICAL TO THE DRILL TIMELINE THAT THE "B" EDG IS NOT AVAILABLE PRIOR TO 14:11. B) THERE ARE NO INJURIES DURING THE REPAIR EFFORT. C) THERE ARE NO FIRES DURING THE REPAIR EFFORT. D) ATTEMPTS TO CROSS TIE THE "B" 4160 VAC VITAL BUS TO ANOTHER VITAL BUS WILL NOT BE SUCCESSFUL UNTIL 14:11. D. RADIOLOGICAL CONCERNS: NONE O V E. ATTACHMENTS:
- 1) AUXILIARY BUILDING, ELEVATION 130' LAYOUT MAP
- 2) AUXILIARY BUILDING, ELEVATION 102' LAYOUT MAP
- 3) "B" EDG LUBE OIL SIMPLIFIED DRAWING.
F. CONTROLIERS SPECIAL NOTES / REFERENCES / OBJECTIVES:
- 1) IN CRDER TO SUBSTANTIATE POSTULATED FUEL DAMAGE, IT IS IMPERATIVE THAT THE "B" EDG REMAIN OUT OF SERVICE UNTIL AT LEAST 14:11, TO PREVENT ADDITIONAL INJECTION TO THE REACTOR.
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i TO AND FROM SACS EMERGENCY DIESEL-GENERATOR At 10:22, the "B" Emergency Diesel Generator (EDG) Lube Oil ! Suction line will develop a large, unisolable leak between l the Lube 011 Reservoir and the Engine Driven Lube Oil Pump, l resulting in a trip of the "B" EDG. g
p SUPPLEMENTAL SCENARIO # 7.09 V TITLE : "D" LPCI INJECTION VALVE MOTOR MALFUNCTION START TIME : 10:51(02:51) END TIME : 15:30(07:30) LOCATION : RX BUILDING, ELEV. 102' SOUTH PIPE CHASE RX BUILDING, ELEV. 77' MCC 10-B-242 A. INITIATING CONDITIONS: FAILURE OF THE #5 JET PUMP HAS GENERATED SEVERAL LOOSE PARTS INSIDE THE REACTOR VESSEL. ONE SMALL PIECE IS IMPACTING THE INSTRUMENT LINE ASSOCIATED WITH THE #5 JET PUMP FLOW AND "B" CHANNEL FUEL ZONE LEVEL INDICATION (VARIABLE LEG) RESULTING IN INDUCED VIBRATIONS AND SUBSEQUENT DEVELOPMENT OF A SMALL LEAK AT 10:02 IN THE INSTRUMENT LINE INSIDE THE SOUTH PIPE CHASE, JUST DOWNSTREAM OF THE EXCESS FLOW CHECK VALVE. THE INITIAL LEAK IS LESS THAN 3 GPM. B. RELATED MESSAGE FORMS: 48D,49C,51 C. POSTULATED EVENT:
- 1) FAILURE MODE (OR CAUSE):
THE SMALL LEAK IN THE SOUTH PIPE CHASE, WHICH BEGAN AT ('fw) 10:02 AND HAS REMAINED UNOBSERVED BY THE CONTROL ROOM CREW i (NO ALARM CONDITIONS HAVE YET OCCURRED), HAS CREATED A HARSH STEAM ENVIRONMENT IN THE SOUTH PIPE CHASE, CAUSING THE MOTOR ASSOCIATED WITH THE "D" LPCI INJECTION VALVE TO DEVELOP AN ELECTRICAL SHORT.
- 2) SYMPTOMS (OR INDICATIONS):
- 1) THE BREAKER ASSOCIATED WITH THE MOTOR OPERATOR FOR THE "D" LPCI INJECTION VALVE (1BCHV-F017D) IS TRIPPED.
ATTEMPTS TO RESET THE BREAKER ARE NOT SUCCESSFUL, AS THE BREAKER TRIPS FREE REPEATEDLY. (BREAKER 52-242052)
- 2) WHEN THE TEAM REACHES THE SOUTH PIPE CHASE, THE DOOR IS IS FOUND TO BE EXTREMELY HOT.
- 3) AN AUDIBLE HISSING CAN BE HEARD WHEN STANDING AT THE DOOR, PRIOR TO 11:02 (LEAK ISOLATION).
7.09.1 j l i
SUPPLEMENTAL SCENARIO # 7.09 (CONTINUED) I C. POSTULATED EVENT:
- 3) RESTORATION GUIDELINES:
- 1) THE "D" LPCI-INJECTION VALVE IS NOT RECOVERABLE FOR THE DURATION OF THE EXERCISE, AS THE SOUTH PIPE CHASE HAS BEEN HIGHLY CONTAMINATED BY THE STEAM LEAK.
- 2) MANUAL OPERATION OF OTHER VALVES IN THE SOUTH PIPE CHASE, SPECIFICALLY THE "B" CORE SPRAY INJECTION VALVES AND THE "B" LPCI INJECTION VALVE ARE NOT SUCCESSFUL FOR THE SAME REASON.
- 4) SCENARIO CONTROLS:
- 1) AT NO TIME WILL THE FAILED VALVE BE RECOVERABLE.
- 2) THE LEAK HAS ALSO EFFECTED OTHER VALVES IN THE SOUTH PIPE CHASE, INCLUDING THE "B" LPCI INJECTION VALVE AND THE "B" CORE SPRAY INJECTION VALVE.
D. RADIOLOGICAL CONCERNS:
- 1) THE SOUTH PIPE CHASE IS HIGHLY CONTAMINATED DUE TO THE PRESENCE OF THE LEAK ON THE INSTRUMENT LINE.
E. ATTACHMENTS:
- 1) REACTOR BUILDING, ELEV. 77', RAD SURVEY MAP (2 PAGES)
- 2) REACTOR BUILDING, ELEV. 102', RAD SURVEY MAP (2 PAGES)
F. CONTROLLERS SPECIAL NOTES / REFERENCES / OBJECTIVES:
- 1) IT IS CRITICAL TO THE DRILL TIMELINE THAT THE "D" LPCI INJECITON VALVE IS NOT OPENED. THE SAME HOLDS TRUE FOR THE "B' LPCI INJECTION VALVE AND "B" CORE SPRAY IN;TECTION VALVE.
7.09.2 (_)
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l l SUPPLEMENTAL SCENARIO # 7.10 L TITLE : FUEL ZONE VARIABLE LEG LEAK WITH EFCV CLOSURE START TIME : 11:02(03:02) END TIME : 11:35(03:35) LOCATION : REACTOR BUILDING, ELEVATION 102' A. INITIATING CONDITIONS: A SMALL LEAK HAS DEVELOPED ON THE INSTRUMENT LINE ASSOCIATED WITH THE #5 JET PUMP FLOW INDICATION AND THE "B" FUEL ZONE LEVEL INSTRUMENT VARIABLE LEG. THE LEAK STARTED AT 10:02 AND IS DISCHARGING INTO THE SOUTH PIPE CHASE AREA. BY 11:02, THE LEAK khTE HAS EXCEEDED THE 5 GPM SETPOINT FOR THE ASSOCIATED EXCESS FLOW CHECK VALVE (1BBXV-3734B) AND THE EFCV CLOSES, SUCCESSFULLY ISOLATING THE LEAK. j B. RELATED MESSAGE FORMS: 50D,52C,53,54 C. POSTULATED EVENT:
- 1) FAILURE MODE (OR CAUSE):
O THE LEAK HAS STARTED AS THE RESULT OF OSCILLATORY VIBRATION CAUSED BY A SMALL PIECE OF THE FAILED #5 JET PUMP RAM'S HEAD IMPACTING THE HIGH PRESSURE INSTRUMENT TAP FOR THAT JET PUMP BETWEEN THE CORE SHROUD AND THE REACTOR VESSEL WALL. THE VIBRATIONS HAVE PROPAGATED THROUGH THE INSTRUMENT l LINE AND HAS RESULTED IN THE DEVELOPMENT OF A LEAK IN THE ) SOUTH PIPE CHASE, D0WNSTREAM OF THE EXCESS FLOW CHECK VALVE.
- 2) SYMPTOMS (OR INDICATIONS):
- 1) IN THE REACTOR BUILDING, AT EXCESS FLOW CHECK VALVE PANEL 1B-C-204:
EFCV 1BBXV-3734B GREEN CLOSED LIGHT IS ILLUMINATED. EFCV 1BBXV-3734B RED OPEN LIGHT IS EXTINGUISHED.
- 2) IN THE REACTOR BUIDING, AT THE DOOR TO THE SOUTH PIPE CHASE: l THE DOOR IS HOT TO THE TOUCH. l BEFORE 11:02, A HISSING SOUND IS HEARD COMING FROM INSIDE l i
7.10.1 0
SUPPLEMENTAL SCENARIO # 7.10 (CONTINUED) O Q C. POSTULATED EVENT:
- 3) RESTORATION GUIDELINES:
CONDITIONS IN THE SOUTH PIPE CHASE MAKE ENTRY EXTREMELY DIFFICULT. DUE TO DISCHARGE OF HIGHLY RADIOACTIVE REACTOR COOLANT INTO THE SOUTH PIPE CHASE, CONTAMINATION LEVELS ARE EXTREMELY HIGH. TEMPERATURE IN THE PIPE CHASE ARE APPROXIMATELY 160 DEGREES AND SLOWLY DECREASING. THE INSTRUMENT LINE WILL NOT BE RECOVERABLE FOR THE DURATION OF THE EXERCISE.
- 4) SCENARIO CONTROLS:
- 1) IT IS CRITICAL TO THE SCENARIO, THAT THE OSC TEAM DISPATCHED REPORT BACK THAT THE EXCESS FLOW CHECK VALVE IS CLOSED, AS INDICATED AT PANEL 1B-C-204.
- 2) SINCE THE LEAK IS LOCATED IN THE SOUTH PIPE CHASE, NO WATER OR OTHER EVIDENCE OF A LEAK IS FOUND AT THE INSTRUMENT RACK.
D. RADIOLOGICAL CONCERNS: THIS SUPPLEMENTAL SCENARIO WILL CREATE A MAJOR RADIOLOGICAL CONCERN FOR PLANT PERSONNEL. CONTAMINATION LEVELS, WHICH WERE ALREADY PRESENT PRIOR TO THE LEAK HAVE NOW INCREASED SIGNIFICANTLY. ATTEMPTS BY OSC TEAMS TO ENTER THE PIPE
~ ^t CHASE WILL REQUIRE DEMONSTRATION OF ALL APPROPRIATE RADIOLOGICAL AND SAFETY PRECAUTIONS.
E. ATTACHMENTS:
- 1) REACTOR BUILDING SOUTH PIPE CHASE LAYOUT DRAWING. *
- 2) #5 JET PUMP FLOW INSTRUMENT LINE SCHEMATIC.
F. CONTROLLERS SPECIAL NOTES / REFERENCES / OBJECTIVES: . t
- 1) THIS SUPPLEMENTAL SCENARIO IS DESIGNED TO CREATE CONDITIONS IN THE SOUTH PIPE CHASE TO SUBSTANTIATE FAILURE OF THE "D" LPCI INJECTION VALVE MOTOR OPERATOR AND PREVENT MANUAL OPERATION OF THE "B" AND "D" LPCI INJECTION VALVES AND THE "B' CORE SPRAY INJECTION VALVE.
7.10.2 j l l l l
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eS JET POMP FLo u I9 frf oM eJT LWE Sci h A n c_ At 10:02, a small leak (less than 3 GPM) will develop just downstream of Instrument Root Valve 1BB-V-600 and associated Excess Flow Check Valve 1BBXV-3734B, which is associated with the #5 Jet Pump Flow Instrumentation, as well as the "B" Channel Fuel Zone Instrument. The Control Room will not receive indication of the leak at this time. The leak has been caused by a small piece of the #5 Jet Pump beam, which is impacting against the instrument line and is causing oscillatory vibration of the instrument line. The leak is located Elevation 102'. in the South Pipe Chase, Reactor Building, j to vr.7m -
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e~ SUPPLEMENTAL SCENARIO # 7.11 {}g TITLE : "A" RHR PUMP REPAIRS START TIME : 11:35(03:35) END TIME : 15:30(07:30) LOCATION : AUXILIARY BUILDING, ELEVATION 130' REACTOR BUILDING, ELEVATION 54' A. INITIATING CONDITIONS: THE LOSS OF COOLANT ACCIDENT (LOCA) THAT OCCURS AT 11:35 RESULTS IN INITIATION OF A LOCA LEVEL 1 SIGNAL. THE "A" RHR PUMP WHICH WAS PLACED IN TORUS COOLING TO SUPPORT CONTAINMENT HEAT REMOVAL REQUIREMENTS FOLLOWING CLOSURE OF THE MSIVS, WILL TRIP APPROXIMATELY 1 MINUTE AFTER THE LOCA SIGNAL IS RECEIVED, RESULTING IN A LOSS OF "A" LPCI INJECTION CAPABILITIES. B. RELATED MESSAGE FORMS: 58D,59C,60 C. POSTULATED EVENT:
- 1) FAILURE MODE (OR CAUSE) :
O THE "A" RHR PUMP TRIPS ON OVERCURRENT AS A PIECE OF THE PUMP IMPELLER BREAKS OFF AND BECOMES LODGED BETWEEN THE IMPELLER AND THE PUMP CASING, RESULTING IN MECHANICAL f BINDING. i
- 2) SYMPTOMS (OR INDICATIONS):
- 1) AT THE "A" RHR PUMP MOTOR BREAKER (52-40106),
THE "A" RHR PUMP MOTOR BREAKER OVERCURRENT RELAY DEVICE HAS ACTUATED.
- 2) IN THE "A" RHR PUMP ROOM, THE "A" RHR PUMP SHAFT IS EXTREMELY HOT AND CAN NOT BE TURNED. THE PUMP MOTOR IS EXTREMELY HOT. THE ROOM HAS SMELL OF BURNT INSULATION.
7.11.1
l SUPPLEMENTAL SCENARIO / 7.11 (CONTINUED) /~ . C. POSTULATED EVENT:
- 3) RESTORATION GUIDELINES:
- 1) IF AN ATTEMPT IS MADE TO RECLOSE THE MOTOR BREAKER, THE BREAKER IMMEDIATELY TRIPS FREE.
- 2) THE PUMP AND MOTOR MUST BE DISCONNECTED, TO ALLOW FOR EITHER PUMP REPLACEMENT OR REPAIR.
l l 1
- 4) SCENARIO CONTROLS:
A) THE PUMP WILL NOT BE RESTORED SUCESSFULLY IN THE DRILL DUE TO THE LENGTH OF TIME REQUIRED FOR REPAIR, COMBINED WITH THE DEGRADED RADIOLOGICAL CONDITIONS THAT OCCUR IN THE REACTOR BUILDING AT 13:15. B) PLANS AND PREPARATION TO REPAIR THE PUMP SHOULD BE DEVELOPED. D. RADIOLOGICAL CONCERNS:
- 1) REFER TO ATTACHED RAD SURVEY MAPS.
- 2) BE PREPARED TO PROVIDE DOSE RATES AND ALNOR READIliGS.
- 3) DOSE RATE IN THE REACTOR BUILDING INCREASE SUBSTANTIALLY AT 13:15. IF A TEAM IS IN THE REACTOR BUILDING AT THAT TIME, THEY SHOULD PROMPTLY EXIT THE REACTOR BUILDING.
O> E. ATTACHMENTS:
- 1) REACTOR BUILDING, ELEV. 54', RAD SURVEY MAP (2 PAGES)
- 2) AUXILIARY BUILDING, ELEVATION 130' LAYOUT MAP F. CONTROLLERS SPECIAL NOTES / REFERENCES / OBJECTIVES:
- 1) THIS SCENARIO IS TIME CRITICAL TO THE DRILL. THE "A" RHR PUMP WILL NOT BE AVAILABLE FOR THE REMAINDER OF THE EXERCISE. LOSS OF THE "A" RHR PUMP RESULTS IN A SIGNIFICANT CHALLENGE TO ADEQUATE CORE COOLING. t 7.11.2 O
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SUPPLEMENTAL SCENARIO # 7.12 O-TITLE : ISOLATION OF THE DRYWELL ATMOSPHERIC SAMPLE LINE START TIME : 11:35(03:35) END TIME : 14:49(06:49) LOCATION : REACTOR BUILDING, ELEVATION 162' A. INITIATING CONDITIONS: UPON RECEIPT INITIATION OF THE LOCA LEVEL 1 SIGNAL, ALL PRIMARY CONTAINMENT ISOLATION VALVES WILL PROPERLY CLOSE WITH THE EXCEPTION OF THE DRYWELL ATMOSPHERIC GASEOUS RADIOACTIVITY MONITORING INBOARD SUPPLY ISOLATION VALVE, ISKHV-5018, WHICH INDICATES MID POSITION IN THE MAIN CONTROL ROOM. B. RELATED MESSAGE FORMS: 57D,61D,62,66,67C,73,74,75,81 C. POSTULATED EVENT:
- 1) FAILURE MODE (OR CAUSE) :
O THE FAILURE OF A BAILEY CARD ASSOCIATED WITH ISKHV-5018, RESULT IN THE VALVE FAILING TO FULLY CLOSE ON THE LOCA LEVEL 1 SIGNAL THAT IS GENERATED AT APPROXIMATELY 11:35. ATTEMPTS TO MANUALLY CLOSE THE VALVE FROM THE CONTROL ROOM ARE UNSUCCESSFUL. ATTEMPTS TO ISOLATE THE LINE LOCALLY ARE ALSO UNSUCCESSFUL AT THIS TIME, AND IN FACT HAVE AN ADVERSE EFFECT ON THE INTEGRITY OF THE LINE.
- 2) SYMPTOMS (OR INDICATIONS):
IN THE REACTOR BUILDING, ELEVATION 162' 1-SK-V004, DW SAMPLE SKID SUPPLY MANUAL ISOL VLV IS OPEN. UPON INSPECTION, THE VALVE STEM IS OBSERVED TO BE BENT. 1-SK-V007, DW SAMPLE SK1D RETUPN MANUAL ISOL VLV IS OPEN. ISKHV-5018, DW SAMPLE SKID SUPPLY MOV IS IN MID POSITION. 1SKHV-4953, DW SAMPLE SKID SUPPLY MOV IS CLOSED. 1SKHV-4957, DW SAMPLE SKID RETURN MOV IS CLOSED. 1SKHV-4981, DW SAMPLE SKID RETURN MOV IS CLOSED. l 4 7.12.1 C) !
l SUPPLEMENTAL SCENARIO # 7.12 (CONTINUED) C. POSTULATED EVENT:
- 3) RESTORATION GUIDELINES:
WHEN THE OSC TEAM ATTEMPTS TO CLOSE THE 1-SK-V004, THE BENT i STEM WILL LIMITED THE ABILITY TO CLOSE THE VALVE. TEAM MEMBERS SHOULD CONSIDER STRAIGHTENING THE VALVE STEM. ATTEMPTS TO MANUALLY CLOSE THE ISKHV-5018 ARE UNSUCCESSFUL AS THE DECLUTCH LEVER FAILS TO DECLUTCH THE MOTOR. I 1-SK-V007 CAN BE SUCCESSFULLY CLOSED MANUALLY. BAILEY CARD REPLACEMENT WILL BE SUCCESSFUL AT 14:49, RESULTING IN VALVE CLOSURE.
- 4) SCENARIO CONTROLS:
A) IT IS CRITICAL TO THE DRILL TIMELINE, THAT THE 1-SK-V004 MANUAL ISOLATION VALVE NOT BE CLOSED FOR THE DURATION OF THE DRILL. THE TEAM SHOULD CONTINUE EFFORTS TO REPAIR THE BENT STEM SO THE VALVE CAN BE CLOSED. IT IS IMPORTANT TO SIMULATE THAT THE TEAM NEEDS TO USE EXCESSIVE FORCE TO CLOSE THE VALVE. B) IT IS ALSO CRITICAL THAT THE 1SKHV-5018 NOT BE MANUALLY OPERATED AT ANY TIME. (DECLUTCH LEVER IS FAILED) D. RADIOLOGICAL CONCERNS: THE TEAM WILL BE WORKING IN THE AREA WHERE THE RADIOLOGICAL RELEASE OCCURS AT 13:15. IT IS CRITICAL THAT THE OSC REFEREE WITH THE TEAM AT THE TIME OF THE RELEASE SIMULATES RAPIDLY DEGRADING RADIOLOGICAL CONDITIONS. DOSE RATES WILL APPROACH g APPROXIMATELY 10R/HR WITHIN THE NEXT 5 MINUTES. AREA RAD j z j MONITORS WILL GO INTO ALARM. THE TEAM SHOULD QUICKLY EXIT U THE AREA AND WILL BE CONTAMINATED. E. ATTACHMENTS:
- 1) REACTOR BUILDING, ELEV 162' RAD SURVEY MAP. (2 PAGES)
- 2) DRYWELL GASEOUS ATMOSPHERIC SAMPLE SYSTEM SCHEMATIC.
l F. CONTROLLERS SPECIAL NOTES / REFERENCES / OBJECTIVES: IT .IS CRITICAL THAT THE TEAM IS NOT SUCCESSFUL ISOLATING THE DW GASEOUS ATMOSPHERIC SAMPLE SUPPLY LINE. (THIS IS THE RELEASE PATH). THE BREACH OF THE SAMPLE LINE IS DOWNSTREAM OF THE 1SKHV-5018. THE BREACH WAS THE RESULT OF THE DW PRESSURE SPIKE, DUE TO THE LOCA, COMBINED WITH EXCESSIVE FORCE USED ATTEMPTING TO CLOSE THE MANUAL ISOLATION VALVE. 7.12.2 I O
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l l (^. SUPPLEMENTAL SCENARIO # 7.13 4 l TITLE : RHR PUMP SUCTION STRAINER BACKWASH START TIME : 11:45(03:45) END TIME : 15:30(07:30) LOCATION : REACTOR BUILDING, VARIOUS LOCATIONS A. INITIATING CONDITIONS: THE CONTROL ROOM CREW RECEIVES INDICATION THAT "C" RHR PUMP FLOW IS DECREASING FROM 10000 GPM TO 3000 GPM. THE NSS WILL REFER TO OP-AB.ZZ-0155, DEGRADED ECCS PERFORMANCE, TO IMPLEMENT CORRECTIVE MEASURES. NOTE: THIS SUPPLEMENTAL SCENARIO MUST BE CLOSELY COORDINATED WITH #7.14. B. RELATED MESSAGE FORMS: 59D,60C,65,68D C. POS1ULATED EVENT:
- 1) FAILURE MODE (OR CAUSE):
O THE LOSS OF COOLANT ACCIDENT (LOCA) THAT HAS OCCURRED INSIDE THE DRYWELL, HAS RESULTED IN THE GENERATION OF LARGE AMOUNTS OF DEBRIS (PRIMARILY PIPING INSULATION). THIS DEBRIS IS BEING DISCHARGED FROM THE DRYWELL INTO THE TORUS. THE DEBRIS SUBSEQUENTLY BEGINS TO ACCUMULATE ON THE SUCTION STRAINERS OF THE RUNNING ECCS PUMPS, RESULTING IN DECREASED PUMP FLOK, AND DECREASED FUMP SUCTION PRESSURE.
- 2) SYMPTOMS (OR INDICATIONS):
A) IN THE REACTOR BUILDING, ELEVATION 54', THE "C" RHR PUMP , SUCTION PRESSURE INDICATOR READS 3.2 PSI AND DECREASING. B) THE "C" RHR PUMP IS LOUDER THAN NORMAL. C) AT 12:15, THE "C" RHR PUMP WILL TRIP (SEE MESSAGE #68D). NOTE: THESE INDICATIONS WILL BE SIMILAR FOR ANY ECCS PUMP THAT IS EXPERIENCING THE SUCTION STRAINER PLUGGING PHENOMENA. 7.13.1 . C)
SUPPLEMENTAL SCENARIO # 7.13 (CONTINUED) C. POSTULATED EVENT:
- 3) RESTORATION GUIDELINES:
A) THE SNSS WILL DIRECT THE OSCC TO IMPLEMENT OP-AB.ZZ-0155, DEGRADED ECCS PERFORMANCE. B) PRIOR TO THE RADIOLOGICAL RELEASE OCCURRING AT 13:15, AN OSC TEAM WILL BE ABLE TO ENTER THE REACTOR BUILDING TO PERFORM ATTACHMENT 4 OF THE PROCEDURE, BACK FLUSHING ECCS SUCTION STRAINERS.
- 4) SCENARIO CONTROLS:
- 1. THE TIMING OF REMOVAL AND RESTORATION OF RHR PUMPS FOR THE PURPOSE OF BACK WASHING THE SUCTION STRAINER MUST BE CAREFULLY CONTROLLED BY THE LEAD OSC AND SIMULATOR REFEREES.
D. RADIOLOGICAL CONCERNS: A) WHEN ENTERING THE REACTOR BUILDING PRIOR TO 13:15, THE TEAM SHOULD DEMONSTRATE APPROPRIATE RADIOLOGICAL PRECAUTIONS. B) AFTER THE RELEASE HAS STARTED, ENTRY INTO THE REACTOR g- BUILDING FOR THE PURPOSE OF BACK WASHING THE SUCTION STRAINERS, WILL NOT BE POSSIBLE DUE TO THE DOSE RATES. g'- C) ANY TEAMS IN THE REACTOR BUILDING AT 13:15, WHEN THE RELEASE STARTS, MUST QUICKLY EXIT THE BUILDING. E. ATTACHMENTS:
- 1) REACTOR BUILDING, ELEV 54' RAD SC4/EY MAP (2 PAGES)
- 2) REACTOR BUILDING, ELEV 102' RAD SURVEY MAP (2 PAGES)
- 3) RHR SYSTEM SCHEMATIC F. CONTROLLERS SPECIAL NOTES / REFERENCES / OBJECTIVES:
- 1) THIS SCENARIO ALLOWS THE DRILL PLAYERS TO DEMONSTRATE IMPLEMENTATION OF THE DEGRADED ECCS PERFORMANCE ABNORMAL OPERATING PROCEDURE.
- 2) IT IS IMPORTANT TO UNDERSTAND THAT IF REACTOR WATER LEVEL CAN NOT BE MAINTAINED ABOVE THE TOP OF ACTIVE FUEL, OPERABLE ECCS MUST INJECT TO THE RPV REGARDLESS OF NPSH. .
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SUPPLEMENTAL SCENARIO # 7.14 TITLE : "C" RHR PUMP TRIPS START TIME : 12:15(04:15) END TIME : 13:46(05:46) LOCATION : REACTOR BUILDING, ELEVATION 54' A. INITIATING CONDITIONS: THE "C" RHR PUMP AUTO INITIATED AS A RESULT OF THE LOCA SIGNAL. THE "C" RHR PUMP HAS BEEN INJECTING TO THE REACTOR WITH LOW FLOW DUE TO PLUGGING OF THE PUMP SUCTION STRAINER. THE CONTROL ROOM CREW RECEIVES INDICATION THAT THE "C" RHR PUMP HAS TRIPPED AT APPROXIMATELY 12:15. NOTE: THE EXACT TIME OF PUMP TRIP WILL BE CONTROLLED BY THE LEAD SIMUALTOR REFEREE, BASED ON REACTOR WATER LEVEL. B. RELATED MESSAGE FORMS: 68D,69C,70 C. POSTULATED EVENT:
- 1) FAILURE MODE (OR CAUSE) :
O DUE TO CONTINUED OPERATION UNDER LOW SUCTION PRESSURE CONDITIONS, THE RESPECTIVE PUMP MOTOR HAVE BEGUN TO HEAT UP, RESULTING IN INCREASED MOTOR WINDING TEMPERATURES. THE PUMPS TRIP ON OVERCURRENT.
- 2) SYMPTOMS (OR INDICATIONS):
A) IN THE "C" RHR PUMP ROOM, THE PUMP MOTOR IS HOT. B) IN THE "C" 4160 VAC VITAL BUS SWITCHGEAR ROOM, THE MOTOR BREAKER FOR THE "C" RHR PUMP IS TRIPPED ON OVERCURRENT. 7.14.1 O _m 1 -_
l SUPPLEMENTAL SCENARIO # 7.14 (CONTINUED) e C. POSTULATED EVENT:
- 3) RESTORATION GUIDELINES:
A) THE OVERCURRENT DEVICE FOR THE "C" RHR PUMP MOTOR , BREAKER CAN BE RESET, IF ATTEMPTED. t B) THE PUMP CAN BE RETURNED TO SERVICE AFTER WAITING FOR APPROXIMATELY 1.5 HOURS. ANY ATTEMPT TO START THE PUMP PRIOR TO THIS WILL RESULT IN A PUMP TRIP. 4
- 4) SCENARIO CONTROLS:'
IT IS IMPORTANT TO THE SCENARIO TIMELINE, THAT THE "C" RHR PUMP REMAIN UNAVAILABLE FOR 1.5 HOURS AFTER TRIPPING. THIS WILL ENSURE THAT REACTOR WATER LEVEL REMAINS LOW ENOUGH TO SUBSTANIATE THE POSTULATED FUEL FAILURE. THE LEAD SIMULATOR REFEREE WILL DETERMINE THE EXACT TIME FOR PUMP TRIP AND RETURN TO~ SERVICE, BASED ON REACTOR WATER LEVEL. ACTIVITIES MUST BE CAREFULLY COORDINATED. -! D. RADIOLOGICAL CONCERNS:
- 1) THE ARE NO RADIOLOGICAL CONCERNS IN THE SWITCHGEAR ROOMS.
- 2) IN THE REACTOR BUILDING, PRIOR TO 13:15, ALL APPROPRTATE 1 RADIOLOGICAL PRECAUTIONS SHOULD BE DEMONSTRATED BY ALL TEAMS ENTERING THE BUILDING. ,.
- 3) IN.THE REACTOR BUILDING, AT 13:15, ALL TEAMS SHOULD
- O PROMPTLY EVACUATE THE REACTOR BUILDING AS A RADIOLOGICAL RELEASE HAS BEGUN.
- 4) BE PREPARED TO PROVIDE DOSE RATES AND ALNOR READINGS.
. E. ATTACHMENTS:
- 1) AUXILIARY BUILDING, ELEVATION 130' LAYOUT MAP.
- 2) REACTOR BUILDING, ELEV 54' RAD. SURVEY MAPS (2 PAGES)
F. CONTROLLERS SPECIAL NOTES / REFERENCES / OBJECTIVES: , THIS SUPPLEMENTAL IS REQUIRED TO ENSURE THAT REACTOR WATER ' LEVEL CAN BE MAINTAINED BELOW THE. TOP OF ACTIVE FUEL FOR A SUFFICIENT TIME TO. SUBSTANTIATE THE POSTULATED FUEL DAMAGE. i 7.14.2 l O
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g'Sg SUPPLEMENTAL SCENARIO # 7.15 V TITLE : LINEUP OF ALTERNATE RPV INJECTION SOURCES START TIME : 12:20(04:20) END TIME : 15:30(07:30) LOCATION : RX BLDG, ELEV. 54, 77, & 102 CONTROL & DG BLDG., ELEV. 102 A. INITIATING CONDITIONS: DUE TO THE PLUGGING OF ECCS SUCTION STRAINERS, ALONG WITH , THE UNAVAILABILITY OF THE SEVERAL RHR AND CORE SPRAY PUMPS, THE SNSS/NSS WILL DIRECT THE OSCC TO IMPLEMENT THE LINEUP OF ALTERNATE RPV INJECTION SOURCES, INCLUDING FIRE WATER (EOP-310), SERVICE WATER (EOP-308) AND. RCIC USING EOP-321, IN AN ATTEMPT TO MAINTAIN REACTOR WATER LEVEL ABOVE THE TOP OF ACTIVE FUEL. B. RELATED MESSAGE FORMS: C. POSTULATED EVENT:
- 1) FAILURE MODE (OR CAUSE):
O DEGRADED ECCS PERFOMANCE FOLLOWING THE LOCA INSIDE THE DRYWELL, ALONG WITH THE UNAVAILABILTY OF OTHER ECCS PUMPS CREATES THE NEED FOR RPV INJECTION WITH ALTERNATE SOURCES.
- 2) SYMPTOMS (OR INDICATIONS):
A) ALL STEPS OF THE ABOVE EOPS ARE PERFORMED SUCCESSFULLY WHEN ATTEMPTED BY THE OSC TEAM MEMBERS IN THE FIELD. B) THERE ARE NO FAILED COMPONENTS OR UNUSUAL CONDITIONS, WITH THE EXCEPTION OF A HIGH RADIATION CONDITION THAT DEVELOPS IN THE RX BLDG AT 13:15 (SEE SECTION D). 7.15.1 O
-l I
I SUPPLEMENTAL SCENARIO # 7.15 j (CONTINUED) j~\ \ ( ,) C. POSTULATED EVENT.
- 3) RESTORATION GUIDELINES:
A) LINEUP AND INJECTION BY AN ALTERNATE SOURCE OF WATER IS PERFORMED IAW THE APPLICABLE EOP. B) NCO CONTROLS THE INJECTION INTO THE RPV ONCE THE LINEUP IS COMPLETE.
- 4) SCENARIO CONTROLS:
A) EOP STEPS SHALL BE WALKED THROUGH (SIMULATED) BY THE OSC TEAM BY FOLLOWING THE PROCEDURE AND DEMONSTRATING ACCEPTABLE PERFORMANCE CAPABILITY. B) ALL STEPS ARE SUCCESSFULLY PERFORMED. C) ENSURE THE SIMULATOR CONTROLLER IS NOTIFIED WHEN THE LINE UP IS COMPLETE PRIOR TO INITIATION OF INJECTION. D) ENTRY INTO THE RX BLDG AFTER 13:15 WILL REQUIRE AN EMERGENCY DOSE AUTHORIZATION. D. RADIOLOGICAL CONCERNS:
- 1) EXTREMELY HIGH RADIATION IN ALL AREAS OF THE REACTOR BLDG AFTER 13:15. (REFER TO RAD SURVEY MAPS)
O E. ATTACHMENTS:
- 1) RAD SURVEY MAPS OF REACTOR BLDG ELEVATIONS.
F. CONTROLLERS SPECIAL NOTES / REFERENCES / OBJECTIVES:
- 1) VERIFY THAT THE EOP USED IS THE LATEST REVISION AND READILY AVAILABLE TO THE OSC.
- 2) ALL ACTIONS ARE TO BE SIMULATED, BUT TOOLS, PROCEDURES, KEYS, ETC AS NEEDED SHALL BE OBTAINED BY THE TEAM.
7.15.2 O
k f-~ , \- / SECTION 8.0 ARTIFICIAL ISLAND ANNUAL EXERCISE 1994 OPERATIONAL DAT', I The operational data contained in Section 8.0 was developed using values obtained from a test run on the Hope Creek Simulator. Actual values of plant parameters seen during the exercise will vary dependent upon actions taken by the Operators in the Simulator as the scenario events occur. 1 Pump start /stop times, flow rates, reactor pressure, specific j equipment placed in and out of service and so on will deviate depending on several variables which include both operator l judgements and simulator model dynamics. The data in this section has been used to predict plant l status throughout the scenario as a basis for developing ! consistent radiological data. The radiological data in Sections 9.0 and 10.0 reflect closely the plant statua shown in Section 8.0, but are not the direct product of the Simulator. Rather, another 3 ' computer model described in Section 5.5 has been used to
'- generate the data displays and tables needed by the referees based on operational parameters in this section.
This operational data serves several purposes during the control of the exercise.
- 1. Referees in the TSC and EOF may provide interpolated data to a player after the player has demonstrated the ability to obtain the information from e.ctual plant computer systems, displays, etc. normally available in those facilities when simulator data 13 not available.
- 2. Simulator referees will continually track the performance of the Simulator against the predicted data as a check on simulation reliability and possible deviation from the scenario that may require referee intervention.
- 3. If the Simulator must be FROZEN for any reason that is unrecoverable, the data in this section will be used to replace the otherwise live parameters so that the exercise may continue with minimal interruption.
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POPE CRCE( A % AL EXERCISE (M94-06) OCTOBER 25, 994 OW OW DW DW TORUS T ORd MOUS TCRUS RX BLDG OFFSITE EDGs ECCS DW CAPr " E OFF SITE OFF SITE RSLOG EXM RF EXH FEAL ORILL PRESS TEMP LH2) [02] PGESS AIR TEMP LL..'i WTR TEMP PRESS POWER 3 or > ACTUATE ISCL OF !" . CAS IODINE RADIATION RADIAT;ON TIME TIME P51G F % % PSIG F INCHES F in M20 AVAll * ? ? ? uCi/sec UCi.'sec UCi/cc tCi/cc
====== ============ ===== ===== ===== ====== ======== ====== ======== ======== ======= ====== ======= ===== ======= ========= ========= ========= =========
08:30 00:30 0.5 102 0 0 0.5 92 76.4 85 -0.25 YES YES NO NO YES 1.90E+02 1.90E-01 1.00E-C6 1.00E-06 08:33 00:33 0.5 102 0 0 0.5 92 76.4 85 -0.25 YES YES NO NO YES 1.90E+02 1.90E-01 1.00E-06 1.00E-06 08:35 00:35 0.5 102 0 0 0.5 92 /6.4 85 -0.25 YES YES NO NO YE5 1.90E+02 1.90E-01 1.00E-06 1.00E-06 08:40 00:40 0.5 102 0 0 0.5 92 76.4 85 -0.25 YES YES NO NO YES 1.90E+02 1.90E-01 1.00E-06 1.00E-06 08:45 00:45 0.5 102 0 0 0.5 92 76.4 85 -0.25 YES YES NO NO YES 1.90E+02 1.90E-01 1.00E-06 1.00E-06 08:50 00:50 0.5 102 0 0 0.5 92 76.4 83 -0.25 YES YES NO NO YES 1.90E+02 1.90E-01 1.00E-06 1.00E-06 08:55 00:55 0.5 102 0 0 0.5 92 76.4 85 -0.25 YES YES NO NO YES 1.90E+02 1.90E-01 1.00E-06 1.00E-06 09:00 01:00 0.5 102 0 0 92 76.4 85 -0.25 YES YES NO NO YES 1.90E+02 1.90E-01 1.00E-06 1.00E-06 09:01 01:01 0.5 102 0 0 0.5 92 76.4 85 -0.25 YES YES NO No YES 1.90E+02 1.90E-01 1.00E-06 1.00E-06 09:05 01:05 0.5 102 0 0 0.5 92 76.4 85 -0.25 YES YES No NO TES 1.90E+02 1.90E-01 1.00E-06 1.00E-06 09:10 01:10 0.5 102 0 0 0.5 92 76.4 85 -0.25 YES YES NO k0 YES 1.90E+02 1.90E-01 1.00E-06 1.00E-06 09:15 01:15 0.5 102 0 0 0.5 92 76.4 85 -0.25 YES YES NO NO YES 1.90E+02 1.90E-01 1.00E-06 1.00E-06 09:20 01:20 0.5 102 0 0 0.5 92 76.4 85 -0.25 YES YES NO NO YES 1.90E+02 1.90E-01 1.00E-06 1.00E-06 09:25 01:25 0.5 102 0 0 0.5 92 76.4 85 -0.25 YES YES NO NO YES 1.90E*02 1.90E-01 1.00E-06 1.00E-06 09:30 01:30 0.5 102 0 0 0.5 92 76.4 85 -0.25 YES YES NO NO YES 1.90E+02 1.90E-01 1.00E-06 1.00E-06 09:35 01:35 0.5 102 0 0 0.5 92 76.4 85 -0.25 YES YES NO NO YES 1.90E+02 1.90E-01 1.00E-06 1.00E-06 09:40 01:40 0.5 102 0 0 0.5 92 76.4 85 -0.25 YES YES NO NO YES 1.90E+02 1.90E-01 1.00E-06 1.00E-06 09:45 01:45 0.5 102 0 0 0.5 92 76.4 85 -0.25 YES YES NO NO YES 1.90E+02 1.90E-01 1.00E-06 1.00E-06 09:47 01:47 0.5 102 0 0 0.5 92 76.4 85 -0.25 YES YES NO NO YES 1.90E+02 1.90E-01 1.00E-06 1.00E-06 09:48 01:48 0.5 102 0 0 0.5 92 76.4 85 -0.25 YES YES NO NO YES 1.90E+02 1.90E-01 1.00E-06 1.00E-06 09:49 01:49 0.5 102 0 0 0.5 92 76.4 85 -0.25 YES YES NO NO YES 1.90E+02 1.90E-01 1.00E-06 1.00E-06 09:50 01:50 0.6 103 0 0 0.5 93 76.7 86 -0.25 YES YES NO NO YES 1.90E+02 1.90E-01 1.00E-06 1.00E-06 09:51 01'51
- 0.6 105 0 0 0.5 94 77.1 87 -0.25 YES YES NO NO YES 1.90E+02 1.90E-01 1.00E-06 1.00E-06 09:52 01:52 0.6 106 0 0 0.5 95 77.3 88 -0.25 YES YES NO NO YES 1.90E+02 1.90E-01 1.00E-06 1.00E-06 09:55 01:55 0.7 108 0 0 0.5 96 77.4 89 -0.25 YES YES NO NO YES 1.90E+02 1.90E-01 1.00E-06 1.00E-06 10:00 02:00 0.7 111 0 0 0.5 97 77.6 90 -0.25 YES YES NO NO YES 1.90E+02 1.90E-01 1.00E-06 1.00E-06 10:05 02:05 0.8 114 0 0 0.5 98 77.8 91 -0.25 YES YES NO NO YES 1.90E+02 1.90E-01 1.00E-06 1.00E-06 10:10 02:10 0.8 115 0 0 0.5 99 78.0 92 -0.25 YES YES NO NO YES 1.90E+02 1.90E-01 1.00E-06 1.00E-06 10:15 02:15 0.8 116 0 0 0.5 100 78.1 93 -0.25 YES YES NO NO YES 1.90E+02 1.90E-01 1.00E-06 1.00E-06 10:20 02:20 0.9 117 0 0 0.5 101 78.2 94 -0.25 YES YES NO NO YES 1.90E+02 1.90E-01 1.00E-06 1.00E-06 10:25 02:25 0.9 118 0 0 0.5 102 78.3 95 -0.25 YES YES NO NO YES ???? ???? 1.00E-06 1.00E-06 10:30 02:30 0.9 118 0 0 0.5 103 78.4 96 -0.25 YES YES NO NO YES ???? ???? 1.00E-06 1.00E-06 10:35 02:35 0.9 118 0 0 0.5 104 78.5 96 -0.25 YES YES NO NO YES ???? ???? 1.00E-06 1.00E-06 10:40 02:40 0.9 118 0 0 0.5 105 78.5 97 -0.25 YES YES NO NO YES ???? ???? 1.00E-06 1.00E-06 10:45 02:45 0.9 118 0 0 0.5 106 78.5 98 -0.25 YES YES NO NO YEt ???? ???? 1.00E-06 1.00E-06 10:50 02:50 0.9 118 0 0 0.5 107 78.5 99 -0.25 YES iES NO NO YES ???? ???? 1.00E-06 1.00E-06 10:55 02:55 0.9 118 0 0 0.5 108 78.5 100 -0.25 YES YES NO NO YES ???? ???? 1.00E-06 1.00E-06 11:00 03:00 0.9 117 0 0 0.5 110 78.5 102 -0.25 YES YES NO NO YES ???? ???? 1.00E-06 1.00E-06 11:05 03:05 0.9 116 0 0 0.5 112 78.5 1 04 -0.25 YES YES NO NO YES ???? ???? 1.00E-06 1.00E-06 11:10 03:10 0.9 116 0 0 0.5 112 78.5 104 -0.25 YES YES NO NO YES ???? ???? 1.00E-06 1.00E-06 11:15 03:15 0.9 116 0 0 0.5 112 78.5 104 -0.25 YES YES NO NO YES ???? ???? 1.00E-06 1.00E-06 11:20 03:20 0.9 116 0 0 0.5 112 78.5 104 -0.25 YES YES NO NO YES ???? ???? 1.00E-06 1.00E-06 11:25 03:25 1.0 116 0 0 0.5 113 78.5 105 -0.25 YES YES NO NO YES ???? ???? 1.00E-06 1.00E-06 11:30 03:30 1.0 116 0 0 0.5 114 78.5 106 -0.25 YES YES NO NO YES ???? ???? 1.00E-06 1.00E-06 11:35 03:35 12.4 116 0 0 9.7 115 79.2 108 -0.25 YES YES YES YES YES ???? ???? 1.00E-06 1.00E-06 249 0 0 24.6 116 80.5 114 -0.25 YES YES YES YES YES ???? ???? 1.00E-06 1.00E-06
@ 11:36 . 11:37 03:36 03:37 28.7 34.7 269 0 0 33.7 129 81.2 121 -0.25 YES YES YES YES YES ???? ???? 1.00E-06 1.00E g 11:38 03:38 25.1 267 0 0 0 23.2 21.9 135 81.5 82.2 127 -0.25
-0.25 YES YES YES YES YES ???? ???? 1.00E-06 1.00E-06 11:39 03:39 24.3 267 0 136 128 YES YES YES YES YES ???? ???? 1.00E-06 1.00E-06 11:40 03:40 23.2 264 0 0 20.5 137 82.6 129 -0.25 YES YES YES YES YES ???? ???? 1.00E-06 1.00E-06
b \
\ V HOPE CREE ( A44UAL ENEPCISE (H94-06) OCTOBER 25, 1994 DW DW DJ DW TORUS TORUS TORUS T ORUS RX SLDG OFFSITE EDGs ECCS CW CAPABLE OFF SITE CFF S11E RBLDG EXH RF EXH REAL DRILL PRESS TEuP [N2] [02] PRESS AIR TEMP LEVEL WTR TEMP PRESS POWER 3 or > ACTUATE ISOL OF ISOL GAS 10 DINE RADIATION RADIATION TIME TIME PSIG F % % PSIG F INCHES F in H2O AVAIL 7 ? ? ? uCi/sec uti/sec uti/cc uCi/cc
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11:45 03:45 18.6 261 0 0 17.8 137 82.8 130 -0.25 YES YES YES YES VES 7??? ???? 1.00E-06 1.00E-06 11:50 03:50 16.9 244 0 0 15.9 139 83.0 132 -0.25 YES YES YES YES YES ???? ???? 1.00E-06 1.00E-06 11:55 03:55 14.7 230 0 0 13.8 139 83.1 132 -0.25 YES YES YES YES YES ???? ???? 1.00E-Oo 1.00E-06 12:00 04:00 13.3 222 0 0 12.5 139 83.2 132 -0.25 YES YES YES YES YES ???? ???? 1.00E-06 1.00E-06 12:05 04:05 11.8 206 0 0 11.0 139 83.3 132 -0.25 YES YES YES YES YES ???? ???? 1.00E-06 1.00E-06 12:10 04:10 10.7 202 0 0 9.8 139 83.4 132 -0.25 YES YES YES YES YES ???? ???? 1.00E-06 1.00E-06 12:15 04:15 10.6 200 0 0 9.7 139 83.5 132 -0.25 YES YES 'YES YES YES ???? ???? 1.00E-06 1.00E-06 12:20 D4:20 10.6 196 0 0 9.7 138 83.6 131 -0.25 YES YES YES YES YES ?777 ???? 2.46E-05 2.46E-05 12:25 04:25 10.5 195 0 0 9.7 138 83.7 131 -0.25 YES YES YES 1ES YES 777? ???? 2.54E-05 2.54E-05 12:30 04:30 10.5 104 0 0 9.7 138 83.7 131 -0.25 YES YES YES YES YFC 77?? ???? 2.63E-05 2.63E-05 12:35 04:35 10.5 195 0 0 9.7 136 83.8 130 -0.25 YES YES YES YES YES ???? ???? 7.60E-05 7.60E-05 12:40 04:40 10.5 195 0 0 9.7 136 83.8 130 -0.25 YES YES YES YES YES ???? ???? 7.89E-05 7.89E-05 12:45 04:45 10.5 194 0 0 9.7 136 83.9 130 -0.25 YES YES YES YES YES ???? ???? 9. 72E-05 9.72E-05 12:50 04:50 10.5 195 0.1 0.1 9.7 136 B4.1 130 -0.25 YES YES YES YES YES 777? ???? 1.00E- 04 1.00E-04 12:55 04:55 10.4 196 0.1 0.1 9.6 136 84.3 129 -0.25 YES YES YES YES YES ???? ???? 1.00E-04 1.00E 04 13:00 C5:00 10.4 195 0.2 0.2 9.6 135 84.5 129 -0.25 YES YES YES VES YES ???? ???? 1.00E-04 1.00E-04 13:05 05:05 10.3 195 0.3 0.3 9.6 135 84.6 129 -0.25 YES YES YES YES YES ???? ???? 1.00E-04 1.00E-04 13:10 05:10 10.2 195 0.3 0.3 9.6 135 84.8 129 -0.25 YES YES YES YES YES ???? ???? 1.00E-04 1.00E-04 13:15 05:15 10.1 194 0.4 0.4 9.6 135 85.0 129 -0.25 YES YES YES NO NO 77?? ???? 1.00E-02 1.00E-02 13:16 05:16 9.2 196 0.4 0.4 9.4 135 85.2 128 -0.25 YES YES YES NO NO ???? ???? 1.00E-02 1.OCE-02 13:17 05:17 8.6 197 0.5 0.5 8.9 134 85.4 128 -0.25 YES YES YES NO NO ???? ???? 1.00E-02 1.00E-02 13:18 05:18 8.1 194 0.6 0.6 8.3 134 85.4 128 -0.25 YES YES YES NO NO 777? ???? 1.00E-02 1.00E-02 13:19 05:19 7.7 194 0.7 0.7 7.9 134 85.4 128 -0.25 YES YES YES NO NO ???? ???? 1.00E-02 1.00E-02 13:20 05:20 7.1 193 0.8 0.8 7.4 134 85.6 128 -0.25 YES YES YES NO NO 7??? ???? 1.00E-02 1.00E-02 13:25 05:25 6.6 193 0.9 0.9 7.0 134 85.8 128 -0.25 YES YES YES NO NO ???? ???? 1.00E-02 1.00E-02 13:30 05:30 4.1 192 1.0 1.0 4.4 134 86.1 128 -0.25 YES YES YES NO NO ???? ???? 1.00E-02 1.00E-02 13:35 05:35 3.3 191 1.1 1.1 3.5 134 86.2 128 -0.25 YES YES YES NO NO ???? ???? 1.00E-02 1.00E-02 13:40 05:40 2.5 1 r0 1.2 1.2 2.7 134 B6.2 127 -0.25 YES YES YES NO NO ???7 77?? 1.00E-02 1.00E-02 13:45 05:45 1.8 190 1.3 1.3 2.0 133 86.2 127 -0.25 YES YES YES NO NO ???? ???? 1.00E-02 1.00E-02 13:50 05:50 1.5 190 1.4 1.4 1.8 133 83.4 127 -0.25 YES YES YES NO NO ???? ???? 1.00E-02 1.00E-02 13:55 05:55 1.4 190 1.5 1.5 1.6 133 81.9 127 -0.25 YES YES YES NO NO ???? ???? 1.00E-02 1.00E-02 14:00 06:00 1.3 190 1.6 1.6 1.4 133 80.5 127 -0.25 YES YES YES NO NO 7??? ???? 1.00E-02 1.00E-02 14:05 06:'05 1.2 187 1.7 1.7 1.4 132 78.5 126 -0.25 YES YES YES NO NO ???? ???? 1.00E-02 1.00E-02 14:10 06:10 1.2 184 1.8 1.8 1.3 132 77.8 126 -0.25 YES YES YES NO NO ???? ???? 1.00E-02 1.00E-02 14:15 06:15 1.1 181 1.9 1.9 1.2 132 76.6 126 -0.7 YES YES YES NO NO 1.05E+08 7??? 1.00E-02 1.00E-02 14:20 06:20 1.1 1 79 2.0 2.0 1.1 131 75.8 125 -0.25 YES YES YES NO NO 1.05E+08 ???? 1.00E-02 1.00E-02 14:25 06:25 1.1 176 2.1 2.1 1.0 131 75.4 125 -0.25 YES YES YES NO NO 1. 04E+ 08 7??? 1.00E-02 1.00E-02 14:30 D6:30 1.0 172 2.2 2.2 0.9 131 75.0 125 -0.25 YES YES YES NO NO 1.04E+08 ???? 1.00E-02 1.00E-02 14:35 06:35 0.9 168 2.2 2.2 0.8 130 74.6 124 -0.25 YES YES YES NO NO 1.03E+08 ???? 1.00E-02 1.00E-02 14:40 06:40 0.8 164 2.2 2.2 0.7 130 74.4 124 -0.25 YES YES YES NO NO 1.02E+08 7777 1.00E-02 1.00E-02 14:45 06:45 0.7 161 2.2 2.2 0.7 130 74.5 123 -0.25 YES YES YES NO NO 1.02E+08 ???? 1.00E-02 1.00E-02 14:50 06:50 0.6 159 2.2 2.2 0.6 129 74.5 123 -0.25 YES YES YES YES YES 1.02E+08 ???? 1.00E-02 1.00E-02 14:55 06:55 0.5 156 2.2 2.2 0.5 129 74.6 122 -0.25 YES YES YES YES YES 1.01E+08 77?? 1.00E-02 1.00E-02 15:00 07:00 0.5 153 2.2 2.2 0.5 128 74.7 121 -0.25 YES YES YES YES YES 1.01E+08 ???? 1.00E-02 1.00E-02
,(3 15:05 07:05 0.5 151 2.2 2.2 0.5 128 74.7 120 -0.25 YES YES YES YES YES 1.01E+08 7777 1.00E-02 1.00E-02 , 15:10 07:10 0.5 148 2.2 2.2 0.5 127 74.7 119 -0.25 YES YES YES YES YES 1.01E+08 777? 1.00E-02 1.00E-02 15:15 07:15 0.4 145 2.2 2.2 0.4 127 74.7 119 -0.25 YES YES YES YES YES 8.19E+07 7??? 1.00E-02 1.00E-02 \ \ 15:20 07:20 0.3 143 2.1 2.1 0.3 127 74.7 118 -0.25 YES YES YES YES YES 8.19E+07 77?? 1.00E-02 1.00E-02 15:25 07:25 0.3 141 2.1 2.1 0.3 126 74.8 118 -0.25 YES YES YES YES VES 8.19E+07 77?7 1.00E-02 1.00E-02 ff '
e-
O HOPE CREEK AWUAL EXERCISE (H94-06) OCTOBER 25, 1994 O O DW DW DW DW TORU4 TORUS TORUS TORUS RX BLDG OFFSITE EDGs ECCS DW CAPABLE OFF SITE OFF SITE RBLDG EXH RF EXH REAL DRILL PRESS TEMP (H2] (02] FRESS AIR TEMP LEVEL WTR TEMP PRESS POWER 3 or > ACTt' ATE ISOL OF ISOL GAS 100!NE RADIATION RADIA!!ON TIME TIME PSIG F % % PSIG F INCHES F in H2O AVAIL ? ? ? ? UCl/sec uCi/sec UCi/cc UCi/cc
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15:30 07:30 0.3 139 2.1 2.1 0.3 126 74.8 117 -0.25 YES YES YES YES YES 3. 72E + 06 7??? 1.00E-02 1.00E-02 15:35 07:35 0.2 113 2.1 2.1 0.2 126 74.9 117 -0.25 YES TES YES YES YES 3. 72E+ 06 7??? 1.00E-02 1.00E-02 15:40 07:40 - 0.2 138 1.9 1.9 0.2 125 75.0 117 -0.25 YES YES YES YES YES 3. 72E+ 06 ???? 1.00E 02 1.00E-02 15:45 07:45 0.2 137 1.8 1.8 0.2 124 75.0 116 -0.25 YES YES YES YES YES 1.24E+05 77?? 1.00E-02 1.00E-02 15:50 07:50 0.2 137 1.8 1.8 0.2 124 75.0 116 -0.25 YES YES YES YES YES 1.24E+05 ???? 1.00E-02 1.00E-02 15:55 07:55 0.2 137 1.8 1.8 0.2 124 T5. 0 115 -0.25 YES YES YES YES YES 1.24E+05 ???? 1.00E-02 1.002-02 16:00 08:00 0.2 136 1.7 1.7 0.2 123 75.0 115 -0.25 YES YES YE3 YES YES 1.06E+04 ???? 1.00E-02 1.00E-02 0)2 IP
~
.o .
r f ~ POPE CREEC ANNUAL EXERCISE (H94-06) OCTOBER 25, 1994 REAL DRILL RX BUILDING TIFE TIFr LVL TEPP RAD SIG EVENTS COMMENTS MESS #
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08:30 00:30 NMI NH! NHI DRILL BEGINS D8:33 00:33 NHI NHI NHI LOSS OF 10-B-130 USS 08:!'. 00:35 NHf NHI kHI LOSS OF "B" FWH STRING 08:40 00:40 NH! NH1 NH1 08:45 00:45 NH1 NHI NH1 08:50 00:50 NHI NHI NHI UMUSUAL EVENT DECLARED 08:55 00:55 NHI NHI NHI 09:00 01:00 NHI NHI NHI 09:01 01:01 NH1 NHI NHI #5 JET PUMP RISER FAILURE 09:05 01:05 NHI NHI NHI 09:10 01:10 NH1 NH1 NHI 09:15 01:15 NHI NHI NH1 09:20 01:20 NH1 NHI NH1 09:25 01:25 NH! NHI NH1 09:30 01:30 NH1 NH1 NHI #6C FWH TUBE LEAK 09:35 01:35 NH! NHi NHI 09:40 01:40 NHI NHI NH1 09:45 01:45 NHI NHI NHI MAIN TURBINE VIB INCREASING 09:47 01:47 NH! NH1 NHI MAIN TURBINE TRIP 09:48 01:48 NHI NHI NHI LOSS OF "B" SIDE STA SER XFMR 09:49 01:49 NHI NHI NHI LOSS OF FW/ CONDENSATE 09:50 01:50 NMI NHI NHI 09:51 ul:51 NHI NHI NHI 09:52 01:52 NHI NHI NH1 09:55 01:55 NHI NHI NHI 10:00 02:00 NH! NH1 NHi 10:05 02:05 NH] NHI NHI ALERT DECLARED 10:10 02:10 NH1 NHI NHI 10:15 02:15 NH! NHI NH! 10:20 02:20 NHI NHI NHI 10:25 02:25 NHI NHI NHI 10:30 02:30 NH! NH! NHI OSC ACTIVATED 10:35 02:35 NHI NH1 NHI 10:40 02:40 NHI NH! NHI 10:45 02:45 NHI NHI NHI 10:50 02:50 NHI NH! NHI 10:55 02:55 NHI NHI NHI "D" LPCI INJ VALVE MALF 11:00 03:00 NHI NHI NHI TSC ACTIVATED 11:05 03:05 NHI NHI NHI 11:10 03:10 NH1 NHI NHI 11:15 03:15 NHI NHI NHI 11:20 03:20 NHI NHI NHI 11:25 03:25 NHI WH1 NH! 11:30 03:30 NHI NHI NHI C)() 11:35 03:35 NHI NH1 NH! "B" RECIRC LOOP BREAK 11:36 03:36 NHI NHI NMI *A" RHR PUMP TRIP
.,_) 11:37 03:37 NHI NHI NHI 11:38 03:38 NH! NHI NHI 11:39 03:39 NHI NHI NH!
[3 11:40 03:40 NH! NH1 NHI ECCS SUCTION STRAINER PLUGGING f-r _ _ _ . _ _ _ _ _ _ _ - _- a u -_ _m - = - - - -- - -
- y. , n
f n O O U HOPE 08EEK ANNUAL EXEECISE (H94-06) CCTOBER 25, 1994 REAL DRILL RX BUILDING TIME TIME LVL TEMP RAD SIG EVENTS COMMENTS MESS #
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11:45 03:45 NHI NHI NH3 11:50 03:50 NH! WHI NHI SITE AREA EMERGENCY DECLARED 11:55 03:55 NHI NH1 NHI 12:00 04:00 NHI NHI NHI 12:05 04:05 NH; NHI NHI 12:10 04:10 NH1 NHI NHI 12:15 04:15 NHI NHI NH1 "C" RHR PUMJ TRIP 12:20 04:20 NHI NHI NHI FUEL DAMAGE STARTS 12:25 04:25 NHI NHI NHI 12:30 04:30 NHI NH] NHI 12:35 04:35 NHI NH1 NHI 12:40 04:40 NHI NHI NHI 12:45 04:45 NH3 NHI NH! GE (POSSIBLE) 12:50 04:50 NH! NHI NHI 12:55 04:55 NHI NHI NH1 13:00 05:00 NMI NH! Nbi 13:05 05:05 NHI NH1 N5' 13:10 05:10 NHI NHI m o '. 13:15 05:15 NHI NHI H. PELEASE STARTS 13:16 05:16 NMI NH1 HI : CONTAINMENT FAILURE) 13:17 05:17 NHI NHI Hi 13:18 05:18 NHI NHI Hi 13:19 05:19 NHI NHI HI 13:20 05:20 NHI NHI 41 13:25 05:25 NH! NHI H) 13:30 05:30 NHI NHI HI GENERAL EMERGENCY 13:35 05:35 NHI NHI HI 13:40 05:40 NHI NHI MI 13:45 05:45 NHI NMI Mi 13:50 05:50 NHI NH! PI 13:55 05:55 NHI NHI HI 14:00 06:00 NHI NH3 H: 14:05 06:05 NHI NHI HI 14:10 06:10 NHI NHI HI 14:15 06:15 NH1 NHf NI 14:20 06:20 NHI NHI HI "B" EDG RUNNING 14:25 06:25 NHI NHI %I 14:30 06:30 NHI NHI HI 14:35 06:35 NHI NHI HI 14:40 06:40 NHI NHI HI 14:45 06:45 NHI NHI HI 14:50 06:50 NHI NHI HI RELEASE TERMINATED 14:55 06:55 NHI NHI HI 15:00 07:00 NH1 NH1 HI CA) 15:05 07:05 NH1 NHI HI 15:10 07:10 NHI NH1 HI csC) 15:15 07:15 NH1 NHI HI 15:20 07:20 NHI NHI HI 15:25 07:25 NHI NH] HI t-
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). 2 J HCPE CREEK ANNUAL EXERCISE (M94-06) OCTOBER 25, 1994 REAL DRILL RX BUILDING TIME TIME LVL TEMP RAD SIG EVENTS CMMENTS MESS # i
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, 15:30 07:30 NH1 NHI HI 15:35 07:35 NHI NH! M1 i 15:40 07:40 NMI NHI HI 15:45 07:45 NHI NHI HI ' 4 15:50 07:50 NHI NHI HI l 15:55 07:55 NHI NHI HI [' i 16:00 08:00 NHI NHI HI DRILL TERMINATED i i I l
- l l
1 t h i l i s I i i i b . e _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ m
l CECTION 9.0 HOPE CREEK DRILL l H94-06 ONSITE RADIOLOGICAL AND CHEMISTRY DATA
<' SECTION TITLE PAGE :
1 SAMPLE ANALYSIS DATA j 9.1 RCS Concentrations (PASS) 9.1.0 l Other Chemistry Sample Data 9.1.6 Main Steam Concentrations 9.1.7 Torus Water Concentrations 9.1.12 Feed Water Concentrations 9.1.17 Reactor Suilding Air Concentrations 9.1.22 Drywell Air Concentrations 9.1.29 Service /Radwaste Air Concentrations 9.1.35 FRVS Sample Isotopic Data 9.1.42 9.2 Plant Vent Flow Rates and RMS Data Hope Creek RMS Quick Reference 9.2.0 RMS Data 9.2.4 Plant Vent Flow Rates 9.2.19 Met and Source Term Data 9.2.20 9.3 Onsite Survey Man Index 54' el. RX. BLDG. 9.3.1 77' el. RX. BLDG. 9.3.3 102' el. RX. BLDG. 9.3.3
\ 132' el. RX. BLDG. 9.3 4 145' el. RX. PTDG. 9.3.5 162' el. RX. BLDG. 9.3.6 178' el. RX. BLDG. 9.3.7 201' el. RX. BLDG. 9.3.8 54' el. S/RW BLDG. 9.3.9 65'-77' el. S/RW BLDG. N/A -
75'-87' el. S/RW BLDG. 9.3.11 102' el. S/RW BLDG. 9.3.12 124' el. S/RW BLDG. 9.3.13 137' el. S/RW BLDG. 9.3.14 153' el. S/RW BLDG. 9.3.15 54' el. TB. BLDG. 9.3.16 7?' el. TB. BLDG. 9.3.17 102' el. TB. BLDG. 9.3.18 120' el. TB. BLDG. 9.3.19 137' el. TB. BLDG. 9.3.20 153' el. TB. BLDG. 9.3.21 171' el. TB. BLDG. 9.3.22 9.4 ONSITE RADIOLOGICAL DATA Onsite Field Survey Map 9.4.0 Onsite Plume Centerline Data 9.4.1 Onsite Plume Specific Location Data 9.5.0 [ 3.0
J. L _ m_- Reactor Coolant System Concentrations l Hope Creek Nuclear Generating Station i 10/25/94 Total I-132 I-133 I-134 I-135 Iodine Clock Drill I-131 Time Time uCi/cc uCi/cc uCi/cc uCi/cc uCi/cc uCi/cc 7.96E-02 1.17E-01 1.37E-01 1.07E-01 4.93E-01 08:00 00:00 5.23E-02 4.93E-01 5.23E-02 7.96E-02 1.17E-01 1.37E-01 1.07E-01 08:15 00:15 1.07E-01 4.93E-01 5.23E-02 7.96E-02 1.17E-01 1.37E-01 08:30 00:30 1.07E-01 4.93E-01 08:45 00:45 5.23E-02 7.96E-02 1.17E-01 1.37E-01 7.96E-02 1.17E-01 1.37E-01 1.07E-01 4.93E-01 09:00 01:00 5.23E-02 7.96E-02 1.17E-01 1.37E-01 1.07E-01 4.93E-01 09:15 01:15 5.23E-02 7.96E-02 1.17E-01 1.37E-01 1.07E-01 4.93E-01 09:30 01:30 5.23E-02 7.96E-02 1.17E-01 1.37E-01 1.07E-01 4.93E-01 09:45 01:45 5.23E-02 7.84E-02 1.17E-01 1.32E-01 1.06E-01 4.86E-01 09:50 01:50 5.23E-02 7.46E-02 1.16E-01 1.15E-01 1.04E-01 4.63E-01 10:00 02:00 5.23E-02 6.91E-02 1.15E-01 9.45E-02 1.02E-01 4.33E-01 10:15 02:15 5.22E-02 6.41E-02 1.14E-01 7.75E-02 9.92E-02 4.07E-01 10:30 02:30 5.22E-02 5.94E-02 1.13E-01 6.35E-02 9.66E-02 3.85E-01 10:45 02:45 5.21E-02 5.51E-02 1.12E-01 5.21E-02 9.42E-02 3.66E-01 11:00 03:00 5.21E-02 5.10E-02 1.11E-01 4.27E-02 9.18E-02 3.49E-01 11:15 03:15 5.20E-02 4.73E-02 1.11E-01 3.50E-02 8.94E-02 3.34E-01 11:30 03:30 5.20E-02 4.61E-02 1.10E-01 3.27E-02 8.87E-02 3.30E-01 11:35 03:35 5.20E-02 4.50E-02 1.10E-01 3.06E-02 8.79E-02 3.25E-01 11:40 03:40 5.20E-02 4.39E-02 1.10E-01 2.87E-02 8.71E-02 3.21E-01 11:45 03:45 5.19E-02 5.19E-02 4.07E-02 1.09E-01 2.35E-02 8.49E-02 3.10E-01 12:00 04:00 2.99E-01 5.19E-02 3.77E-02 1.08E-01 1.93E-02 8.28E-02 2.33E+02 3.91E+01 1.78E+02 6.42E+02 ( 12:25 f*)9:1504:15
- 20 04:20 1.12E+02 7.96E+01 2.63E+02 1.82E+02 5.45E+02 8.58E+01 4.13E+02 1.49E+03 04:25 1.71E+03 12:30 04:30 3.05E+02 2.05E+02 6.29E+02 9.29E+01 4.74E+02 12:35 04:35 1.68E+03 1.10E+03 3.45E+03 4.78E+02 2.59E+03 9.29E+03 3.05E+03 1.95E+03 6.26E+03 8.14E+02 4.66E+03 1.67E+04 12:40 04:40 12:45 04:45 4.57E+03 2.86E+03 9.36E+03 1.14E+03 6.93E+03 2.49E+04 13:00 05:00 1.52E+04 8.83E+03 3.09E+04 3.12E+03 2.25E+04 8.06E+04 1.52E+04 8.18E+03 3.07E+04 2.56E+03 2.19E+04 7.86E+04 13:15 05:15 13:30 05:30 1.52E+04 7.58E+03 3.04E+04 2.10E+03 2.14E+04 7.67E+04 1.52E+04 7.03E+03 3.02E+04 1.72E+03 2.08E+04 7.49E+04 13:45 05:45 7.33E+04 14:00 06:00 1.52E+04 6.52E+03 2.99E+04 1.41E+03 2.03E+04 1.51E+04 6.04E+03 2.97E+04 1.16E+03 1.98E+04 7.18E+04 14:15 06:15 1.51E+04 5.60E+03 2.94E+04 9.48E+02 1.93E+04 7.04E+04 14:30 06:30 14:45 06:45 1.51E+04 5.19E+03 2.92E+0( 7.77E+02 1.88E+04 6.91E+04 1.51E+04 4.81E+03 2.89E+04 6.37E+02 1.83E+04 6.78E+04 15:00 07:00 15:15 07:15 1.51E+04 4.46E+03 2.87E+04 5.22E+02 1.78E+04 6.66E+04 1.51E+04 4.13E+03 2.85E+04 4.28E+02 1.74E+04 6.55E+04 15:30 07:30 15:45 07:45 1.51E+04 3.83E+03 2.82E+04 3.51E+02 1.69E+04 6. 4 4 E+04 1.50E+04 3.55E+03 2.80E+04 2.88E+02 1.65E+04 6.34E+04 16:00 08:00 D
9.1.0
Reactor Coolant System Conceritrations Hope Creek Nuclear Generating Station 10/25/94 Kr-85 Kr-87 Kr-88 Xe-131m Xe-133 Clock Drill DEI Time uCi/cc uCi/cc uCi/cc uci/cc uCi/cc uCi/cc Time 9.45E-02 1.30E-01 1.05E-03 2.00E+00 08:00 00:00 1.01E-01 4.40E-04 2.00E+00 1.01E-01 4.40E-04 9.45E-02 1.30E-01 1.05E-03 08:15 00:15 9.45E-02 1.30E-01 1.05E-03 2.00E+00 08:30 00:30 1.01E-01 4.40E-04 2.00E+00 1.01E-01 4.40E-04 9.45E-02 1.30E-01 1.05E-03 08:45 00:45 1.30E-01 1.05E-03 2.00E+00 09:00 01:00 1.01E-01 4.40E-04 9.45E-02 9.45E-02 1.30E-01 1.05E-03 2.00E+00 09:15 01:15 1.01E-01 4.40E-04 1.05E-03 2.00E+00 09:30 01:30 1.01E-01 4.40E-04 9.45E-02 1.30E-01 9.45E-02 1.30E-01 1.05E-03 2.00E+00 09:45 01:45 1.01E-01 4.40E-04 1.05E-03 2.00E+00 09:50 01:50 1.00E-01 4.40E-04 9.20E-02 1.28E-01 8.40E-02 1.23E-01 1.05E-03 1.99E+00 10:00 02:00 9.74E-02 4.40E-04 1.05E-03 1.99E+00 9.41E-02 4.40E-04 7.32E-02 1.16E-01 10:15 02:15 1.09E-01 1.05E-03 1.99E+00 10:30 02:30 9.12E-02 4.40E-04 6.39E-02 5.57E-02 1.02E-01 1.05E-03 1.99E+00 10:45 02:45 8.88E-02 4.40E-04 4.40E-04 4.86E-02 9.61E-02 1.05E-03 1.98E+00 11:00 03:00 8.66E-02 1.98E+00 11:15 03:15 8.47E-02 4.40E-04 4.24E-02 9.03E-02 1.05E-03 3.70E-02 8.49E-02 1.05E-03 1.98E+00 11:30 03:30 8.30E-02 4.40E-04 1.05E-03 1.98E+00 8.25E-02 4.40E-04 3.53E-02 8.31E-02 11:35 03:35 1.05E-03 1.98E+00 11:40 03:40 8.20E-02 4.40E-04 3.37E-02 8.14E-02 4.40E-04 3.22E-02 7.98E-02 1.05E-03 1.98E+00 11:45 03:45 8.16E-02 1.97E+00 12:00 04:00 8.03E-02 4.40E-04 2.81E-02 7.50E-02 1.04E-03 2.45E-02 7.05E-02 1.04E-03 1.97E+00 12:15 04:15 7.91E-02 4.40E-04 2.26E+00 4.27E+03 1.71E+02 9.54E-01 5.08E+01 1.50E+02 S2:20 04:20 1.14E+02 3.44E+02 5.31E+00 1.00E+04 3.98E+02 2.24E+00
)2:25 04:25 4.59E+02 1.33E+00 6.48E+01 2.01E+02 3.16E+00 6.78E+02 12:30 04:30 1.74E+01 3.73E+03 12:35 04:35 2.51E+03 7.34E+00 3.40E+02 1.08E+03 4.55E+03 1.33E+01 5.91E+02 1.93E+03 3.16E+01 6.78E+03 12:40 04:40 4.74E+01 1.02E+04 12:45 04:45 6.80E+03 2.00E+01 8.48E+02 2.83E+03 2.24E+04 6.67E+01 2.46E+03 8.86E+03 1.58E+02 3.38E+04 13:00 05:00 1.58E+02 3.38E+04 13:15 05:15 2.22E+04 6.67E+01 2.15E+03 8.33E+03 2.19E+04 6.67E+01 1.87E+03 7.83E+03 1.58E+02 3.37E+04 13:30 05:30 1.58E+02 3.37E+04 2.17E+04 6.67E+01 1.63E+03 7.35E+03 13:45 05:45 6.91E+03 1.58E+02 3.36E+04 14:00 06:00 2.16E+04 6.67E+01 1.43E+03 2.14E+04 6.67E+01 1.24E+03 6.50E+03 1.57E+02 3.36E+04 14:15 06:15 6.10E+03 1.57E+02 3.36E+04 14:30 06:30 2.12E+04 6.67E+01 1.08E+03 2.10E+04 6.67E+01 9.46E+02 5.74E+03 1.57E+02 3.35E+04 14:45 06:45 5.39E+03 1.57E+02 3.35E+04 15:00 07:00 2.09E+04 6.67E+01 8.25E+02 2.08E+04 6.67E+01 7.20E+02 5.07E+03 1.57E+02 3.34E+04 15:15 07:15 4.76E+03 1.57E+02 3.34E+04 15:30 07:30 2.06E+04 6.67E+01 6.28E+02 2.05E+04 6.67E+01 5.47E+02 4.48E+03 1.57E+02 3.33E+04 15: 45 07:45 4.21E+03 1.57E+02 3.33E+04 16:00 08:00 2.04E+04 6.67E+01 4.77E+02 9.1.1 O
I f Reactor Coolant System concentrations Hope Creek Nuclear Generating Station 10/25/94 Total Noble Gas Rb-88 Sr-89 Sr-90 Clock Drill Xe-133m Xe-135 i uCi/cc
^
Time Time uCi/cc uCi/cc uCi/cc uCi/cc uCi/cc 2.18E-01 2.45E+00 1.88E-01 < LLD < LLD 08:00 00:00 5.61E-03 2.46E+00 1.80E-01 < LLD < LLD 08:15 00:15 5.61E-03 2.18E-01
< LLD < LLD 08:30 00:30 5.61E-03 2.18E-01 2.45E+00 1.88E-01 2.18E-01 2.45E+00 1.88E-01 < LLD < LLD 08:45 00:45 5.61E-03 2.45E+00 3.88E-01 < LLD < LLD 09:00 01:00 5.61E-03 2.18E-01
< LLD < LLD 09:15 01:15 5.61E-03 2.18E-01 2.45E+00 1.88E-01 2.18E-01 2.45E+00 1.88E-01 < LLD < LLD
.09:30 01:30 5.61E-03 2.18E-01 2.45E+00 1.88E-01 < LLD < LLD 09:45 01:45 5.61E-03 09:50 01:50 5.61E-03 2. .E-01 2.44E+00 1.67E-01 < LLD < LLD 5.60E-03 2.14E-01 2.42E+00 1.13E-01 < LLD < LLD 10:00 02:00 < LLD < LLD 10:15 02:15 5.58E-03 2.10E-01 2.40E+00 6.29E-02 2.06E-01 2.38E+00 3.49E-02 < LLD < LLD 10:30 02:30 5.56E-03 2.02E-01 2.35E+00 1.94E-02 < LLD < LLD 10:45 02:45 5.54E-03 5.52E-03 1.99E-01 2.33E+00 1.08E-02 < LLD < LLD 11:00 03:00 < LLD < LLD 11:15 03:15 5.51E-03 1.95E-01 2.32E+00 6.00E-03 5.49E-03 1.91E-01 2.30E+00 3.33E-03 < LLD < LLD 11:30 03:30 < LLD < LLD 11:35 03:35 5.48E-03 1.90E-01 2.29E+00 2.74E-03 5.48E-03 1.89E-01 2.29E+00 2.25E-03 < LLD < LLD 11:40 03:40 < LLD 5.47E-03 1.88E-01 2.28E+00 1.85E-03 < LLD 11:45 03:45 < LLD 5.45E-03 1.84E-01 2.27E+00 1.03E-03 < LLD 12:00 04:00 < LLD
~
5.44E-03 1.81E-01 2.25E+00 5.73E-04 < LLD g-~3:15 04:15 3.89E+02 4.87E+03 1.02E+00 6.39E-03 1.51E-03 1.18E+01 (r2):2004:20
- 25 04:25 2.76E+01 9.07E+02 1.14E+04 1.97E+00 1.50E-02 3.54E-03 1.64E+01 5.38E+02 1.50E+03 6.37E-01 2.95E+02 6.96E+01 12:30 04:30 12:35 04:35 9.02E+01 2.94E+03 8.20E+03 2.88E+00 1.62E+03 3.83E+02 12:40 04:40 1.64E+02 5.31E+03 1.48E+04 4.30E+00 2.95E+03 6.96E+02 12:45 04:45 2.46E+02 7.91E+03 2.21E+04 5.31E+00 4.43E+03 1.04E+03 13:00 05:00 8.16E+02 2.59E+04 7.21E+04 9.83E+00 1.47E+04 3.48E+03 13:15 05:15 8.13E+02 2.54E+04 7.07E+04 5.47E+00 1.47E+04 3.48E+03 13:30 05:30 8.11E+02 2.49E+04 6.94E+04 3.04E+00 1.47E+04 3.48E+03 13:45 05:45 8.08E+02 2.45E+04 6.82E+04 1.69E+00 1.47E+04 3.48E+03 14:00 06:00 8.06E+02 2.40E+04 6.70E+04 9.39E-01 1.47E+04 3.48E+03 14:15 06:15 8.03E+02 2.35E+04 6.59E+04 5.22E-01 1.47E+04 3.48E+03 14:30 06:30 8.00E+02 2.31E+04 6.49E+04 2.90E-01 1.47E+04 3.48E+03 14:45 06:45 7.98E+02 2.27E+04 6.39E+04 1.61E-01 1.47E+04 3.48E+03 7.95E+02 2.22E+04 6.29E+04 8.96E-02 1.47E+04 3.48E+03 15:00 07:00 15:15 07:15 7.93E+02 2.18E+04 6.20E+04 4.98E-02 1.47E+04 3.48E+03 15:30 07:30 7.90E+02 2.14E+04 6.12E+04 2.77E-02 1.47E+04 3.48E+03 15:45 07:45 7.88E+02 2.10E+04 6.04E+04 1.54E-02 1.47E+04 3.48E+03 16:00 08:00 7.85E+02 2.06E+04 5.96E+04 8.55E-03 1.47E+04 3.48E+03 9.1.2
l l Reactor Coolant System Concentrations Hope Creek Nuclear Generating Station 10/25/94 O Mo-99 Te-129 Te-132 Cs-134 Cs-137 Ba-140 Clock Drill uCi/cc uC1/cc uCi/cc uCi/cc uCi/cc Time Time uC1/cc 4.26E-04 1.72E-02 4.94E-03 < LLD 08:00 00:00 3.02E-01 1.21E-04 4.94E-03 < LLD j 3.02E-01 1.21E-04 4.26E-04 1.72E-02 08:15 00:15 1.21E-04 4.26E-04 1.72E-02 4.94E-03 < LLD 08:30 00:30 3.02E-01 1.72E-02 4.94E-03 < LLD 3.02E-01 1.21E-04 4.26E-04 08:45 00:45 1.21E-04 4.26E-04 1.72E-02 4.94E-03 < LLD 09:00 01:00 3.02E-01 1.72E-02 4.94E-03 < LLD 3.02E-01 1.21E-04 4.26E-04 09:15 01:15 1.21E-04 4.26E-04 1.72E-02 4.94E-03 < LLD 09:30 01:30 3.02E-01 1.72E-02 4.94E-03 < LLD 3.C2E-01 1.21E-04 4.26E-04 09:45 01:45 4.26E-04 1.72E-02 4.94E-03 < LLD 09:50 01:50 3.02E-01 1.18E-04 < LLD 3.01E-01 1.07E-04 4.25E-04 1.72E-02 4.94E-03 10:00 02:00 4.24E-04 1.72E-02 4.94E-03 < LLD 10:15 02:15 3.00E-01 9.16E-05 < LLD 2.99E-01 7.88E-05 4.23E-04 1.72E-02 4.94E-03 10:30 02:30 4.22E-04 1.72E-02 4.94E-03 < LLD 10:45 02:45 2.99E-01 6.78E-05 4.94E-03 < LLD 2.98E-01 5.83E-05 4.21E-04 1.72E-02 11:00 03:00 4.20E-04 1.72E-02 4.94E-03 < LLD 11:15 03:15 2.97E-01 5.02E-05 < LLD 2.96E-01 4.31E-05 4.19E-04 1.72E-02 4.94E-03 11:30 03:30 4.19E-04 1.72E-02 4.94E-03 < LLD 11:35 03:35 2.96E-01 4.10E-05 < LLD 2.96E-01 3.90E-05 4.19E-04 1.72E-02 4.94E-03 11:40 03:40 4.19E-04 1.72E-02 4.94E-03 < LLD 11:45 03:45 2.96E-01 3.71E-05 4.94E-03 < LLD 2.95E-01 3.19E-05 4.18E-04 1.72E-02 12:00 04:00 4.17E-04 1.72E-02 4.94E-03 < LLD 12:15 04:15 2.94E-01 2.75E-05 1.07E+01 1.22E-02 6.37E+02 5.66E-02 9.02E-01 3.73E+01 2.12E+00 8.76E+01 2.51E+01 2.87E-02 O.2:2004:20 2:25 04:25 1.49E+03 1.26E-01 3.44E+01 9.88E+00 5.64E+02 12:30 04:30 5.87E+02 2.36E+01 4.16E+02 3.10E+03 2.29E+03 1.89E+02 5.43E+01 12:35 04:35 3.22E+03 1.24E+02 3.44E+02 9.88E+01 5.64E+03 5.86E+03 2.14E+02 4.15E+03 12:40 04:40 6.22E+03 5.17E+02 1.48E+02 8.46E+03 12:45 04:45 8.78E+03 3.05E+02 1.72E+03 4.94E+02 2.82E+04 13:00 05:00 2.92E+04 8.74E+02 2.07E+04 2.82E+04 2.07E+04 1.72E+03 4.94E+02 13:15 05:15 2.91E+04 7.51E+02 4.94E+02 2.82E+04 2.90E+04 6.46E+02 2.06E+04 1.72E+03 13:30 05:30 2.06E+04 1.72E+03 4.94E+02 2.81E+04 13:45 05:45 2.90E+04 5.56E+02 1.72E+03 4.94E+02 2.81E+04 14:00 06:00 2.89E+04 4.78E+02 2.05E+04 2.81E+C4 2.05E+04 1.72E+03 4.94E+02 14:15 06:15 2.88E+04 4.11E+02 1.72E+03 4.94E+02 2.81E+04 2.87E+04 3.54E+02 2.04E+04 14:30 06:30 2.04E+04 1.72E+03 4.94E+02 2.81E+04 14:45 06:45 2.87E+04 3.04E+02 4.94E+02 2.81E+04 2.86E+04 2.62E+02 2.03E+04 1.72E+03 15:00 07:00 2.03E+04 1.72E+03 4.94E+02 2.80E+04 15:15 07:15 2.85E+04 2.25E+02 1.72E+03 4.94E+02 2.80E+04 15:30 07:30 2.84E+04 1.94E+02 2.02E+04 2.80E+04 1.67E+02 2.02E+04 1.72E+03 4.94E+02 15:45 07:45 2.84E+04 1.72E+03 4.94E+02 2.80E+04 16:00 08:00 2.83E+04 1.43E+02 2.02E+04 9.1.3
Reactor Coolant System Concentrations Hope Creek Nuclear Generating Station () 10/25/94 Total Gross Activity La-140 La-142 Ce-144 Particulate clock Drill Time uCi/cc uCi/cc uCi/cc uCi/cc uCi/cc Time 2.21E-04 5.13E-01 3.45E+00 08:00 00:00 6.03E-06 8.73E-06 3.45E+00 6.03E-06 8.73E-06 2.21E-04 5.13E-01 08:15 00:15 2.21E-04 5.13E-01 3.45E+00 08:30 00:30 6.03E-06 8.73E-06 3.45E+00 6.03E-06 8.73E-06 2.21E-04 5.13E-01 08:45 00:45 5.13E-01 3.45E+00 09:00 01:00 6.03E-06 8.73E-06 2.21E-04 2.21E-04 5.13E-01 3.45E+00 09:15 01:15 6.03E-06 8.73E-06 3.45E+00 6.03E-06 8.73E-06 2.21E-04 5.13E-01 09:30 01:30 3.45E+00 09:45 01:45 6.03E-06 8.73E-06 2.21E-04 5.13E-01 2.21E-04 4.92E-01 3.42E+00 09:50 01:50 6.03E-06 8.54E-06 3.32E+00 10:00 02:00 6.01E-06 7.92E-06 2.21E-04 4.37E-01 2.21E-04 3.86E-01 3.22E+00 10:15 02:15 5.99E-06 7.08E-06 3.14E+00 10:30 02:30 5.96E-06 6.32E-06 2.21E-04 3.57E-01 5.65E-06 2.21E-04 3.41E-01 3.08E+00 10:45 02:45 5.93E-06 3.03E+00 11:00 03:00 5.91E-06 5.05E-06 2.21E-04 3.32E-01 4.51E-06 2.21E-04 3.26E-01 2.99E+00 11:15 03:15 5.88E-06 2.96E+00 11:30 03:30 5.86E-06 4.03E-06 2.21E-04 3.23E-01 3.88E-06 2.21E-04 3.22E-01 2.94E+00 11:35 03:35 5.85E-06 2.93E+00 11:40 03:40 5.84E-06 3.74E-06 2.21E-04 3.21E-01 5.83E-06 3.60E-06 2.21E-04 3.20E-01 2.92E+00 11:45 03:45 3.19E-01 2.90E+00 12:00 04:00 5.81E-06 3.22E-06 2.21E-04 2.88E-06 2.21E-04 3.17E-01 2.87E+00 5.78E-06 6.20E+03 4.78E-01 6.87E+02 /.2:15 (,j 04:15 2:20 04:20 1.25E-02 6.01E-03 1.61E+03 1.45E+04 12:25 04:25 2.93E-02 1.36E-02 1.12E+00 6.26E+03 5.76E+02 2.57E+02 2.21E+02 3.05E+03 12:30 04:30 1.67E+04 3.42E+04 12:35 04:35 3.16E+03 1.36E+03 1.21E+03 6.18E+04 5.74E+03 2.39E+03 2.21E+03 3.03E+04 12:40 04:40 4.53E+04 9.22E+04 12:45 04:45 8.60E+03 3.45E+03 3.31E+03 3.02E+05 2.85E+04 1.03E+04 1.10E+04 1.49E+05 13:00 05:00 1.48E+05 2.97E+05 13:15 05:15 2.84E+04 9.17E+03 1.10E+04 2.92E+05 2.83E+04 8.20E+03 1.10E+04 1.46E+05 13:30 05:30 1.45E+05 2.88E+05 13:45 05:45 2.82E+04 7.33E+03 1.10E+04 2.84E+05 2.81E+04 6.55E+03 1.10E+04 1. 4 4 E+05 14:00 06:00 1.43E+05 2.81E+05 14:15 06:15 2.79E+04 5.85E+03 1.10E+04 2.77E+05 2.78E+04 5.23E+03 1.10E+04 1.42E+05 14:30 06:30 1.41E+05 2.74E+05 14:45 06:45 2.77E+04 4.67E+03 1.10E+04 2.71E+05 2.76E+04 4.17E+03 1.10E+04 1.40E+05 15:00 07:00 1.40E+05 2.68E+05 15:15 07:15 2.75E+04 3.73E+03 1.10E+04 2.66E+05 2.73E+04 3.33E+03 1.10E+04 1.39E+05 15:30 07:30 1.38E+05 2.63E+05 15:45 07:45 2.72E+04 2.98E+03 1.10E+04 2.61E+05 2.71E+04 2.66E+03 1.10E+04 1.38E+05 16:00 08:00 9.1.4
Reactor Coolant System Pass Sample Data-Hope Creek Nuclear-Generating Station 10/25/94
)
Undiluted Diluted Diluted Undiluted Sample Sample Sample Sample
- Clock-Drill
@ 1 Foot @ Contact @ 1 Foot Tima Time @ Contact mR/hr mR/hr mR/hr mR/hr < 0.2 < 0.2 9.66E-01 < 0.2 08:00 00:00 < 0.2 < 0.2 < 0.2 l 08:15 00:15 9.66E-01 < 0.2 < 0.'2 l' 9.66E-01 < 0.2
.08:30 00:30 < 0.2 <'0.2 < 0.2 08:45 00:45 9.66E-01 < 0.2 < 0.2 9.66E-01 < 0.2 09:00 01:00 < 0.2 < 0.2 < 0.2 09:15 01:15 9.66E-01 < 0.2 < 0.2 9.66E-01 < 0.2 09:30 01:30 < 0.2 < 0.2 < 0.2 09:45 01:45 9.66E-01 < 0.2 < 0.2 9.66E-01 < 0.2 09:47 01:47 < 0.2 < 0.2 < 0.2 09:50 01:50 9.57E-01 < 0.2 < 0.2 9.30E-01 < 0.2 10:00 02:00 < 0.2 < 0.2 < 0.2 10:15 02:15 9.01E-01 < 0.2 < 0.2
< 0.2 10:30 02:30 8.79E-01
< 0.2 < 0.2 < 0.2 I
10:45 02:45 8.62E-01 < 0.2 < 0.2
< 0.2 '
11:00 03:00 8.49E-01 < 0.2 < 0.2 ' 11:15 03:15 8.37E-01 < 0 . ;2
< 0.2 < 0.2 8.27E-01 < 0.2 11:30 03:30 < 0.2 < 0.2 < 0.2 ,
11:35 03:35 8.24E-01 < 0.2 < 0.2 8.21E-01 < 0.2 11:40 03:40 < 0.2 < 0.2 < 0.2 1:45 03:45 8.19E-01 < 0.2 < 0.2 B.11E-01 < 0.2 02:0004:00 8.03E-01 < 0.2 < 0.2 <!0.2 , 12:15 04:15 3.01E+00 1.74E+01 < 0.2 12:20 04:20 1.74E+03 4.06E+01 < 0.2 12:25 04:25 4.06E+03 7.05E+00 < 0.2 3.04E+00 1.75E+01 12:30 04:30 .1.75E+03 1.66E+01- 9.58E+01 < 0.2 12:35 04:35 9.58E+03 3.01E-01 1.73E+04 3.01E+01 1.73E+02 12:40 04:40 4.48E+01 2.58E+02 4.48E-01 12:45 04:45 2.58E+04 8.55E+02 1.48E+00 12:50 04:50 8.55E+04 1.48E+02 1.48E+02 8.50E+02 1.48E+00 , 12:55 04:55 8.50E+04 8.45E+02 1.47E+00 13:00 05:00 8.45E+04 1.47E+02 1.46E+02 8.40E+02 1.46E+00 13:05 05:05 8.40E+04 1.45E+00 8.36E+04 1.45E+02 8.36E+02 13:10 05:10 1.44E+02 8.31E+02 1.44E+00 13:15 05:15 8.31E+04 1.44E+00 8.27E+04 1.44E+02 8.27E+02 13:20 05:20 1.43E+02 8.23E+02 1.43E+00 13:25 05:25 8.23E+04 1.42E+00 8.19E+04 1.42E+02 8.19E+02 13:30 05:30 1.41E+02 8.15E+02 1.41E+00 13:35 05:35 8.15E+04 8.11E+02 1.41E+00 : 13:40 05:40 8.11E+04 1.41E+02 1.40E+02 8.07E+02 1.40E+00 13:45 05:45 8.07E+04 1.38E+00 7.96E+04 1.38E+02 7.96E+02 14:00 06:00 1.36E+02 7.86E+02 1.36E+00 i 14:15 06:15 7.86E+04 1.35E+00 7.76E+04 1.35E+02 7.76E+02 , 14:30 06:30 1.33E+02 7.68E+02 1.33E+00 14:45 06:45 7.68E+04 1.32E+00 7.59E+04 1.32E+02 7.59E+02 15:00 07:00 1.30E+02 7.51E+02 1.30E+00 7.51E+04 0s15:.30 5:15 07:15 07:30 7.44E+04 1.29E+02 7.44E+02 7.37E+02 1.29E+00 1.28E+00
-15:45 07:45 7.37E+04 1.28E+02 1.27E+02 7.30E+02 1.27E+00 l 16:00 08:00 7.30E+04 9.1.5
Chemistry Data Hope Creek Nuclear Generating Station 09/08/94 Conductivity Dissolved 02 PH Silica Zinc Clock Drill Chlorides PPB S.U. PPM PPB Tita Time PPB uS/cm 6.8 0.10 0.10 0.76 0.080 <5 08:00 00:00 0.080 <5 6.8 0.10 0.10 08:15 00:15 0.76 0.10 0.10 0.080 <5 6.8 08:30 00:30 0.76 0.10 0.10 0.080 <5 6.8 08:45 00:45 0.76 0.10 0.10 0.080 <5 6.8 09:00 01:00 0.76 0.10 0.10 0.080 <5 6.8 09:15 01:15 0.76 0.10 0.10 0.080 <5 6.8 09:30 01:30 0.76 6.8 0.10 0.10 0.080 <5 09:45 01:45 0.76 0.080 <5 6.8 0.10 0.10 10:00 02:00 0.76 0.10 0.12 0.082 <5 6.8 10:15 02:15 0.78
<5 6.8 0.11 0.13 10:30 02:30 0.79 0.083
<5 6.8 0.11 0.15 10:45 02:45 0.81 0.085
<5 6.9 0.11 0.16 11:00 03:00 0.82 0.086
<5 6.9 0.12 0.18 11:15 03:15 0.84 0.088
<5 6.9 0.12 0.19 11:30 03:30 0.85 0.089
<5 6.9 0.13 0.19 11:45 03:45 4.24 0.120
<5 6.9 0.15 0.18 12:00 04:00 9.87 0.170 0.220 <5 9.9 0.18 0.17 12:15 04:15 15.50
<5 6 . 9' O.20 0.16 12:30 04:30 21.14 0.270
<5 6.9 0.22 0.15 12:45 04:45 26.77 0.320 6.9 0.24 0.14 32.40 0.370 <5 13:00 05:00 <5 6.9 0.26 0.13
/~'0 15 05:15 38.03 0.420
<5 6.9 0.28 0.11
( l:30: 05:30 43.67 0.470 0.520 <5 6.9 0.31 0.10 13:45 05:45 49.30
<5 7.0 0.33 0.09 14:00 06:00 54.93 0.570
<5 7.0 0.35 0.08 14:15 06:15 60.56 0.620
<5 7.0 0.37 0.07 14:30 06:30 66.20 0.670
<5 7.0 0.39 0.06 14:45 06:45 71.83 0.720
<5 7. 0 0.41 0.05 15:00 07:00 77.46 0.770 7.0 0.44 0.03 0.820 <5 15:15 07:15 83.09
<5 7.0 0.46 0.02 15:30 07:30 88.73 0.870
<5 7.0 0.48 0.01 15:45 07:45 94.36 0.920 7.0 0.50 0.00 99.99 0.970' <5 16:00 00:00 a.
l O . 9.1.6
Main Steam Concentrations Hope Creek Nuclear Generating Station 10/25/94
.O Total I-134 I-135 Iodine I-132 I-133
-Clock Drill I-131 uCi/cc uCi/cc uCi/cc uCi/cc Time Time uCi/cc uCi/cc 2.74E-03 2.14E-03 9.86E-03 1.05E-03 1.59E-03 2.34E-03 08:00 00:00 1.59E-03 2.34E-03 2.74E-03 2.14E-03 9.86E-03 08:15 00:15 1.05E-03 2.74E-03 2.14E-03 9.86E-03 1.05E-03 1.59E-03 2.34E-03 08:30 00:30 1.59E-03 2.34E-03 2.74E-03 2.14E-03 9.86E-03 08:45 00:45 1.05E-03 2.74E-03 2.14E-03 9.86E-03 1.05E-03 1.59E-03 2.34E-03 09:00 01:00 1.59E-03 2.34E-03 2.74E-03 2.14E-03 9.86E-03 09:15 01:15 1.05E-03 2.74E-03 2.14E-03 9.86E-03 i 1.05E-03 1.59E-03 2.34E-03 09:30 01:30 1.59E-03 2.34E-03 2.74E-03 2.14E-03 9.86E-03 l 09:45 01:45 1.05E-03 < LLD < LLD < LLD N/A l 09:50 01:50 < LLD < LLD < LLD N/A 1
< LLD < LLD < LLD 10:00 02:00 < LLD < LLD < LLD N/A
< LLD < LLD < LLD 10:15 02:15 < LLD < LLD < LLD < LLD N/A 10:30 02:30 < LLD < LLD < LLD N/A
< LLD < LLD < LLD 10:45 02:45 < LLD < LLD < LLD < LLD N/A 11:00 03:00 < LLD < LLD < LLD N/A
< LLD < LLD < LLD 11:15 03:15 < LLD < LLD < LLD < LLD N/A 11:30 03:30 < LLD < LLD < LLD N/A
< LLD < LLD < LLD l
11:35 03:35 < LLD < LLD < LLD < LLD N/A I 11:40 03:40 < LLD < LLD < LLD N/A
< LLD < LLD
! 11:45 03:45 < LLD
< LLD < LLD < LLD < LLD N/A 12:00 04:00 < LLD < LLD < LLD N/A
< LLD < LLD < LLD 1
< LLD < LLD < LLD < LLD N/A O'2:1504:15 2:20 04:20 < LLD
< LLD < LLD < LLD < LLD < LLD N/A 12:25 04:25 < LLD < LLD < LLD < LLD N/A 12:30 04:30 < LLD < LLD < LLD N/A
< LLD < LLD < LLD 12:35 04:35 < LLD < LLD < LLD < LLD N/A 12:40 04:40 < LLD < LLD N/A
< LLD < LLD < LLD 12:45 04:45 < LLD < LLD N/A
< LLD < LLD < LLD 13:00 05:00 < LLD < LLD N/A
,< LLD < LLD < LLD 13:15 05:15 < LLD < LLD < LLD N/A
< LLD < LLD < LLD 13:30 05:30 < LLD < LLD < LLD < LLD N/A 13:45 05:45 < LLD < LLD N/A i
< LLD < LLD < LLD < LLD 14:00 06:00 < LLD < LLD < LLD < LLD N/A 14:15 06:15 < LLD < LLD N/A
< LLD < LLD < LLD 14:30 06:30 < LLD < LLD N/A
< LLD < LLD < LLD < LLD 14:45 06:45 < LLD < LLD < LLD < LLD N/A 15:00 07:00 < LLD < LLD < LLD N/A
< LLD < LLD < LLD 15:15 07:15 < LLD < LLD < LLD N/A 15:30 07:30 < LLD < LLD
< LLD < LLD N/A
< LLD < LLD < LLO 15:45 07:45 < LLD < LLD < LLD < LLD N/A 16:00 08:00 < LLD O
9.1.7
I Main Steam Concentrations Hope Creek Nuclear Generating Station 10/25/94 O DEI Kr-85 Kr-87 Kr-88 Xe-131m Xe-133 Clock Drill uC1/cc uCi/cc uCi/cc uCi/cc uC1/cc Time Time uCi/cc 9.36E-02 1.29E-01 1.04E-03 1.98E+00 08:00 00:00 2.02E-03 4.36E-04 ].04E-03 1.98E+00 4.36E-04 9.36E-02 1.29E-01 , 08:15 00:15 2.02E-03 1.29E-01 1.04E-03 1.98E+00 ! 2.02E-03 4.36E-04 9.36E-02 1.98E+00 08:30 00:30 4.36E-04 9.36E-02 1.29E-01 1.04E-03 08:45 00:45 2.02E-03 1.29E-01 1.04E-03 1.98E+00 2.02E-03 4.36E-04 9.36E-02 1.98E+00 09:00 01:00 4.36E-04 9.36E-02 1.29E-01 1.04E-03 09:15 01:15 2.02E-03 1.29E-01 1.04E-03 1.98E+00 2.02E-03 4.36E-04 9.36E-02 1.98E+00 09:30 01:30 4.36E-04 9.36E-02 1.29E-01 1.04E-03 09:45 01:45 2.02E-03 < LLD < LLD < LLD < LLD N/A < LLD 09:50 01:50 < LLD < LLD < LLD < LLD < LLD 13:00 02:00 N/A < LLD < LLD < LLD < LLD N/A < LLD < LLD 10:15 02:15 < LLD < LLD < LLD < LLD 10:30 02:30 N/A < LLD < LLD < LLD < LLD 10:45 02:45 N/A < LLD < LLD < LLD
< LLD < LLD < LLD 11:00 03:00 N/A < LLD < LLD < LLD < LLD N/A < LLD 11:15 03:15 < LLD < LLD < LLD < LLD < LLD 11:30 03:30 N/A < LLD < LLD < LLD < LLD N/A < LLD 11:35 03:35 < LLD < LLD < LLD < LLD < LLD 11:40 03:40 N/A < LLD < LLD < LLD < LLD 11:45 03:45 N/A < LLD < LLD
< LLD < LLD < LLD < LLD 12:00 04:00 N/A < LLD < LLD < LLD < LLD 12:15 04:15 N/A < LLD < LLD
< LLD < LLD < LLD 2:20 04:20 N/A < LLD < LLD < LLD
< LLD < LLD < LLD 0.2:2504:25 N/A
< LLD < LLD < LLD < LLD < LLD 12:30 04:30 N/A < LLD < LLD < LLD < LLD N/A < LLD 12:35 04:35 < LLD < LLD < LLD < LLD < LLD 12:40 04:40 N/A < LLD < LLD < LLD < LLD N/A < LLD 12:45 04:45 < LLD < LLD < LLD < LLD < LLD 13:00 05:00 N/A < LLD < LLD < LLD < LLD 13:15 05:15 N/A < LLD < LLD < LLD
< LLD < LLD < LLD 13:30 05:30 N/A < LLD < LLD < LLD < LLD 13:45 05:45 N/A < LLD < LLD
< LLD < LLD < LLD < LLD 14:00 06:00 N/A < LLD < LLD < LLD < LLD 14:15 06:15 N/A < LLD < LLD < LLD
< LLD < LLD < LLD 14:30 06:30 N/A < LLD < LLD < LLD < LLD 14:45 06:45 N/A < LLD < LLD < LLD
< LLD < LLD < LLD 15:00 07:00 N/A < LLD < LLD < LLD < LLD N/A < LLD < LLD 15:15 07:15 < LLD < LLD < LLD < LLD 15:30 07:30 N/A < LLD < LLD < LLD < LLD N/A < LLD 15:45 07:45 < LLD < LLD < LLD < LLD < LLD 16:00 08:00 N/A O 9.1.8 s
Main Steam Concentrations Hope Creek Nuclear Generating Station f- g 10/25/94 Total Noble Gas Rb-88 Sr-89 Sr-90 Clock Drill Xe-133m Xe-135 uCi/cc uCi/cc uCi/cc uCi/cc uCi/cc Time Time uCi/cc 2.42E+00 1.88E-04 < LLD < LLD 08:00 00:00 5.55E-03 2.16E-01 < LLD < LLD 2.16E-01 2.42E+00 1.88E-04 08:15 00:15 5.55E-03 1.88E-04 < LLD < LLD 5.55E-03 2.16E-01 2.42E+00 08:30 00:30 2.16E-01 2.42E+00 1.88E-04 < LLD < LLD 08:45 00:45 5.55E-03 1.88E-04 < LLD < LLD 5.55E-03 2.16E-01 2.42E+00 09:00 01:00 2.16E-01 2.42E+00 1.88E-04 < LLD < LLD 09:15 01:15 5.55E-03 1.88E-04 < LLD < LLD 5.55E-03 2.16E-01 2.42E+00 09:30 01:30 2.16E-01 2.42E+00 1.88E-04 < LLD < LLD 09:45 01:45 5.55E-03 < LLD < LLD < LLD 09:50 01:50 < LLD < LLD N/A < LLD < LLD
< LLD N/A < LLD 10:00 02:00 < LLD < LLD < LLD < LLD 10:15 02:15 < LLD < LLD N/A < LLD < LLD
< LLD N/A < LLD 10:30 02:30 < LLD < LLD < LLD < LLD 10:45 02:45 < LLD < LLD N/A < LLD < LLD
< LLD N/A < LLD 11:00 03:00 < LLD < LLD < LLD < LLD 11:15 03:15 < LLD < LLD N/A < LLD < LLD
< LLD < LLD N/A < LLD 11:30 03:30 < LLD N/A < LLD < LLD < LLD 11:35 03:35 < LLD < LLD < LLD
< LLD < LLD N/A < LLD 11:40 03:40 < LLD N/A < LLD < LLD < LLD 11:45 03:45 < LLD
< LLD < LLD < LLD 12:00 04:00 < LLD < LLD N/A < LLD < LLD
< LLD N/A < LLD 1:15 04:15 < LLD < LLD < LLD < LLD
\ 2:20 04:20 < LLD < LLD N/A < LLD < LLD
< LLD N/A < LLD 12:25 04:25 < LLD < LLD < LLD < LLD 12:30 04:30 < LLD < LLD N/A < LLD < LLD
< LLD N/A < LLD 12:35 04:35 < LLD < LLD < LLD
< LLD N/A < LLD 12:40 04:40 < LLD < LLD < LLD
< LLD N/A < LLD 12:45 04:45 < LLD < LLD < LLD < LLD 13:00 05:00 < LLD < LLD N/A < LLD < LLD
< LLD N/A < LLD 13:15 05:15 < LLD < LLD < LLD
< LLD N/A < LLD 13:30 05:30 < LLD < LLD < LLD
< LLD < LLD N/A < LLD 13:45 05:45 < LLD N/A < LLD < LLD < LLD 14:00 06:00 < LLD < LLD < LLD
< LLD < LLD N/A < LLD 14:15 06: 15 < LLD < LLD < LLD 14:30 06:30 < LLD < LLD N/A < LLD < LLD
< LLD N/A < LLD 14:45 06:45 < LLD < LLD < LLD
< LLD N/A < LLD 15:00 07:00 < LLD < LLD < LLD
< LLD N/A < LLD 15:15 07:15 < LLD < LLD < LLD
< LLD < LLD N/A < LLD 15:30 07:30 < LLD < LLD < LLD 15: 45 07:45 < LLD < LLD N/A < LLD < LLD
< LLD N/A < LLD 16:00 08:00 < LLD O
9.1.9
Main Steam Concentrations Hope Creek Nuclear Generating Station 10/25/94 Ba-140 Te-129 Te-132 Cs-134 Cs-137 Clock Drill Mo-99 uCi/cc uCi/cc Time uCi/cc uCi/cc uci/cc uCi/cc Time < LLD < LLD 1.72E-05 4.94E-06 < LLD 08:00 00:00 3.02E-04 < LLD
< LLD < LLD 1.72E-05 4.94E-06 08:15 00:15 3.02E-04
< LLD < LLD 1.72E-05 4.94E-06 < LLD 08:30 00:30 3.02E-04 1.72E-05 4.94E-06 < LLD 3.02E-04 < LLD < LLD 08:45 00:45 < LLD < LLD 1.72E-05 4.94E-06 < LLD 09:00 01:00 3.02E-04 1.72E-05 4.94E-06 < LLD 3.02E-04 < LLD < LLD 09:15 01:15 < LLD < LLD 1.72E-05 4.94E-06 < LLD 09:30 01:30 3.02E-04 1.72E-05 4.94E-06 < LLD J 02E-04 < LLD < LLD 09:45 01:45 < LLD < LLD < LLD < LLD < LLD 09:50 01:50 < LLD < LLD < LLD
< LLD < LLD < LLD 10:00 02:00 < LLD < LLD < LLD
< LLD < LLD < LLD < LLD 10:15 02:15 < LLD < LLD < LLD < LLD < LLD 10:30 02:30 < LLD < LLD < LLD
< LLD < LLD < LLD 10:45 02:45 < LLD
< LLD < LLD < LLD < LLD < LLD 11:00 03:00 < LLD < LLD
< LLD < LLD < LLD < LLD 11:15 03:15 < LLD
< LLD < LLD < LLD < LLD 11:30 03:30 < LLD < LLD
< LLD < LLD < LLD < LLD < LLD 11:35 03:35 < LLD
< LLD < LLD < LLD < LLD < LLD 11:40 03:40 < LLD < LLD < LLD
< LLO < LLD < LLD 11:45 03:45 < LLD
< LLD < LLD < LLD < LLD 12:00 04:00 < LLD ( LLD < LLD
< LLD < LLD < LLD < LLD 12:15 04:15 < LLD < LLD < LLD
< LLD < LLD < LLD < LLD 2:20 04:20 < LLD < LLD < LLD < LLD
< LLD < LLD m/2:25 04:25 < LLD < LLD < LLD < LLD < LLD 12:30 04:30 < LLD
< LLD < LLD < LLD < LLD < LLD
.12:35 04:35 < LLD < LLD < LLD
< LLD < LLD < LLD < LLD 12:40 04:40 < LLD < LLD < LLD < LLD < LLD 12:45 04:45 < LLD
< LLD < LLD < LLD < LLD < LLD 13:00 05:00 < LLD < LLD < LLD
< LLD < LLD < LLD 13:15 05:15 < LLD
< LLD < LLD < LLD 13:30 05:30 < LLD < LLD < LLD
< LLD
< LLD < LLD < LLD < LLD 13:45 05:45 < LLD
< LLD < LLD < LLD < LLD . LLD 14:00 06:00 < LLD < LLD < LLD
< LLD < LLD < LLr 14:15 06:15 < LLD
< LLD < LLD < LI < LLD < LLD 14:30 06:30 < LLD < LLD < LLD
< LLD < LLD < LLD < L' 14:45 06:45 < LLD < LLD < LLD < LLD < LLD 15:00 07:00 < LLD < LLD < LLD
< LLD < LLD < LLD < LLD 15:15 07:15 < LLD < LLD < LLD < LLD < LLD 15:30 07:30 < LLD < LLD < LLD
< LLD < LLD < LLD < LLD 15:45 07:45 < LLD < LLD < LLD < LLD < LLD 16:00 08:00 < LLD 9.1.10 0
Main Steam Concentrations
-w Hope Creek Nuclear Generating Station 10/25/94 Total Gross Ce-144 Particulate Activity Clock Drill La-140 La-142 uCi/cc uCi/cc uCi/cc uCi/cc Time Time uCi/cc < LLD 5.13E-04 2.43E+00 08:00 00:00 < LLD < LLD
< LLD < LLD 5.13E-04 2.43E+00
'08:15 00:15 < LLD
< LLD < LLD < LLD 5.13E-04 2.43E+00 08:30 00:30 < LLD < LLD 5.13E-04 2.43E+00 08:45 00:45 < LLD 2.43E+00
< LLD < LLD < LLD 5.13E-04 09:00 01:00 < LLD < LLD 5.13E-04 2.43E+00 09:15 01:15 < LLD 2.43E+00
< LLD < LLD < LLD 5.13E-04 09:30 01:30 < LLD 5.13E-04 2.43E+00 09:45 01:45 < LLD < LLD
< LLD < LLD < LLD N/A N/A <
09:50 01:50 N/A
< LLD < LLD N/A 10:00 02:00 < LLD
< LLD N/A N/A 10:15 02:15 < LLD < LLD
< LLD < LLD N/A N/A 10:30 02:30 < LLD
< LLD N/A N/A 10:45 02:45 < LLD < LLD
< LLD < LLD N/A N/A 11:00 03:00 < LLD
< LLD < LLD N/A N/A 11:15 03:15 < LLD
< LLD N/A N/A 11:30 03:30 < LLD < LLD
< LLD < LLD N/A N/A 11:35 03:35 < LLD
< LLD < LLD N/A N/A 11:40 03:40 < LLD
< LLD N/A N/A 11:45 03:45 < LLD < LLD
< LLD < LLD < LLD N/A N/A 12:00 04:00 N/A o,:15 04:15 < LLD < LLD < LLD N/A
< LLD < LLD < LLD N/A N/A T .:20 04:20 N/A 12:25 04:25 < LLD < LLD < LLD N/A
< LLD < LLD < LLD N/A N/A 12:30 04:30 N/A 12:35 04:35 < LLD < LLD < LLD N/A
< LLD < LLD < LLD N/A N/A 12:40 04:40 < LLD N/A N/A 12:45 04:45 < LLD < LLD
< LLD < LLD N/A N/A 13:00 05:00 < LLD
< LLD N/A N/A 13:15 05:15 < LLD < LLD
< LLD < LLD N/A N/A 13:30 05:30 < LLD
< LLD < LLD N/A N/A 13:45 05:45 < LLD
< LLD < LLD N/A N/A 14:00 06:00 < LLD
< LLD < LLD N/A N/A 14:15 06:15 < LLD
< LLD < LLD < LLD N/A N/A 14:30 06:30 < LLD N/A 14:45 06:45 < LLD < LLD N/A
< LLD < LLD < LLD N/A N/A 15:00 07:00 < LLD < LLD N/A N/A 15:15 07:15 < LLD
< LLD < LLD < LLD N/A N/A 15:30 07:30 < LLD N/A N/A 15:45 07:45 < LLD < LLD
< LLD < LLD < LLD N/A N/A 16:00 08:00 9.1.11
Torus Water Concentrations Hope Creek Nuclear Generating Station 10/25/94 l Total l 1-134 I-135 Iodine . I-132 I-133 Clock Drill I-131 uCi/cc uCi/cc uCi/cc uCi/cc uCi/cc l Time Time uCi/cc 1.17E-04 1.37E-04 1.07E-04 4.93E-04 08:00 00:00 5.23E-05 7.96E-05 1.37E-04 1.07E-04 4.93E-04 5.23E-05 7.96E-05 1.17E-04 08:15 00:15 1.17E-04 1.37E-04 1.07E-04 4.93E-04 08:30 00:30 5.23E-05 7.96E-05 1.37E-04 1.07E-04 4.93E-04 5.23E-05 7.96E-05 1.17E-04 08:45 00:45 1.17E-04 1.37E-04 1. 07 E-04 4.93E-04 09:00 01:00 5.23E-05 7.96E-05 1.37E-04 1.07E-04 4.93E-04 5.23E-05 7.96E-05 1.17E-04 09:15 01:15 1.17E-04 1.37E-04 1.07E-04 4.93E-04 09:30 01:30 5.23E-05 7.96E-05 1.37E-04 1.07E-04 4.93E-04 5.23E-05 7.96E-05 1.17E-04 09:45 01:45 2.95E-04 3.45E-04 2.69E-04 1.24E-03 09:50 01:50 1.32E-04 2.00E-04 3.45E-04 2.69E-04 1.24E-03 1.32E-04 2.00E-04 2.95E-04 10:00 02:00 2.95E-04 3.45E-04 2.69E-04 1.24E-03 10:15 02:15 1.32E-04 2.00E-04 3.45E-04 2.69E-04 1.24E-03 2.00E-04 2.95E-04 10:30 02:30 1.32E-04 2.00E-04 2.95E-04 3.45E-04 2.69E-04 1.24E-03 10:45 02:45 1.32E-04 2.95E-04 3.45E-04 2.69E-04 1.24E-03 11:00 03:00 1.32E-04 2.00E-04 2.69E-04 1.24E-03 2.00E-04 2.95E-04 3.45E-04 11:15 03:15 1.32E-04 2.95E-04 3.45E-04 2.69E-04 1.24E-03 11:30 03:30 1.32E-04 2.00E-04 2.69E-04 1.24E-03 1.32E-04 2.00E-04 2.95E-04 3.45E-04 11:35 03:35 2.95E-04 3.45E-04 2.69E-04 1.24E-03 11:40 03:40 1.32E-04 2.00E-04 2.69E-04 1.24E-03 1.32E-04 2.00E-04 2.95E-04 3.45E-04 11:45 03:45 2.95E-04 3.?5E-04 2.69E-04 1.24E-03 12:00 04:00 1.32E-04 2.00E-04 2.69E-04 1.24E-03 1.32E-04 2.00E-04 2.95E-04 3.4CE-04 /~ 2.95E-04 3.45f-04 2.69E-04 1.24E-03 2.01E-04 (m)}2:15 04:15 1.32E-04 3:20 04:20 1.32E-04 2.01E-04 2.95E-04 3. 4 5E -04 2.69E-04 1.24E-03 12:25 04:25 2.95E-04 3.45E-04 2.69E-04 1.24E-03 12:30 04:30 1.32E-04 2.01E-04 2.70E-04 1.24E-03 1.32E-04 2.01E-04 2.96E-04 3.45E-04 12:35 04:35 2.96E-04 3.45E-(4 2.70E-04 1.25E-03 12:40 04:40 1.32E-04 2.01E-04 2.71E-04 1.25E-03 2.01E-04 2.97E-04 3.45E-C4 12:45 04:45 1.33E-04 3.03E-04 3.46E-04 2.75E-04 1.26E-03 13:00 05:00 1.36E-04 2.03E-04 1.26E-03 2.03E-04 3.03E-04 3.46E-04 2.75E-04 13:15 05:15 1.36E-04 2.75E-04 1.26E-03 1.36E-04 2.02E-04 3.03E-04 3.45E-04 13:30 05:30 3.45E-04 2.74E-04 1.26E-03 13:45 05:45 1.36E-04 2.02E-04 3.02E-04 2.74E-04 1.26E-03 14:00 06:00 1.36E-04 2.02E-04 3.02E-04 3.45E-04 3.45E-04 2.74E-04 1.26E-03 14:15 06:15 1.36E-04 2.02E-04 3.02E-04 2.74E-04 1.26E-03 1.36E-04 2.02E-04 3.02E-04 3.45E-04 14:30 06:30 3.02E-04 3.45E-04 2.74E-04 1.26E-03 14:45 06:45 1.36E-04 2.02E-04 2.74E-04 1.26E-03 15:00 07:00 1.36E-04 2.02E-04 3.02E-04 3.45E-04 3.02E-04 3.45E-04 2.74E-04 1.26E-03 15:15 07:15 1.36E-04 2.02E-04 2.74E-04 1.26E-03 1.36E-04 2.02E-04 3.02E-04 3.45E-04 15:30 07:30 3.02E-04 3.45E-04 2.73E-04 1.26E-03 15:45 07:45 1.36E-04 2.01E-04 2.73E-04 1.26E-03 16:00 08:00 1.36E-04 2.01E-04 3.02E-04 3.45E-04 O 9.1.12
x s ... eb //// aA WIO d' e 4 Tb 'l:gg' IMAGE EVALUATION d'%f
/ \/ / 'k5.0' f"f/>
a' TEST TARGET (MT-3) z[,,9 ' #$$s \\\//// g # (f f v*>+ 44<* f i.o mm
. 7 3M
- . - g~ =2n ii 1.8
==
1.25 1.4 1.6 _==- 150mm
- 4 _ _ . . _ . .
4- -
---6"
;> 3'5
$9,>b
~
m s.
?s#l,zz3 s
f{' b off's
,e ,
.a
0) efe ~ dhia e. k.' & L',Q;-
~
IMAGE EVALUATION
,6, t'6'#' / / '((%^ 4g, Ah' TEST TARGET (MT-3)
N\/// & $gs gfV
# 'k I.0 o
" , , n.~2 m 2 E: ,
i!' 2.0 l,l [I!llsiis I lil I.8 H l=1+2 1.25 1.4 1 i.6 ese le== _ _ _ _ . . _ _ _ _ - _ . - - - 150mm 4- __.___.___..._._..6 - 4 [; s% 4+ ,,4A
#eI/f 34
+;w;;;. ,%,s/ , 4tn6 , vy a> /4 N> ,;,
<g % &
- s
'-41
.b
' i ,.
p $-
+& (g
- q,
"'d & j*p IMAGE EVAL.U ATION [j#[/ j ,9 @",
%O
//o/ i *Nhf TEST TARGET (MT-3)
'f'/fh'(p gy, 9 {%,,,, ,
+
<e
,.o -
'
- E!! 2;2_
, , , u 22.0 l,l 7 ' '4 - kbs 1.8 l.25 1.4 1.6
. _ _ . . _ . - - - - - - - - - - 150mm 4
6" > 4 _ e sA CQlc3 c O 8>f! ys/ R;nl'/////;% e 9,*V gys 2
. & &+ q,
.av %v -
,t 6, s;, 9 % IMAGE EVALUATION
'E iff TEST TARGET (MT-3)
/ g/'),jf 4g'j
?
\f/7,, %h# %h3,, f
+ %
l.0 .""
' . , "gy.
=.
l 1.8
,==
1.25 1.4 1.6 150mm > 4 . _ _ _ _ .._. ____. - 6" 4 . . _ _ A_.- b'~%) ~ 4% '
%);,
ec 4%
+ [3;'
^'
<p 3 4;t% .l);3 \
5 o gy,p ((i
- i
Torus Water Concentrations
<~(
Hope Creek Nuclear Generating Station 10/25/94 Kr-88 Xe-131m Xe-133 Kr-85 Kr-87 Clock Drill DEI uCi/cc uCi/cc uCi/cc uCi/cc Tine Time uCi/cc uCi/cc 1.30E-04 < LLD 2.00E-03 1.01E-04 < LLD 9.45E-05 2.00E-03 08:00 00:00 < LLD 9.45E-05 1.30E-04 < LLD
'08:15 ^4: 15 1.01E-04 9.45E-05 1.30E-04 < LLD 2.00E-03 1.01E-04 < LLD 2.00E-03 t 08:30 Our 7 < LLD 9.45E-05 1.30E-04 < LLD 08:45 0 5 1.01E-04 1.30E-04 < LLD 2.00E-03 1.01E-04 < LLD 9.45E-05 2.00E-03 09:00 01:vJ < LLD 9.45E-05 1.30E-04 < LLD 09:15 01:15 1.01E-04 1.30E-04 < LLD 2.00E-03 1.01E-04 < LLD 9.45E-05 2.00E-03
! 09:30 01:30 < LLD 9.45E-05 1.30E-04 < LLD 09:45 01:45 1.01E-04 7, .0 0E-0 3 9.90E-03 8.00E-05 1.52E-01 2.54E-04 < LLD 1.52E-01 09:50 01:50 < LLD 7.20E-03 9.90E-03 8.00E-05 10:00 02:00 2.54E-04 1.52E-01 p 2.54E-04 < LLD 7.20E-03 9.90E-03 8.00E-05 l 10:15 02:15 < LLD 7.20E-03 9.90E-03 8.00E-05 1.52E-01 10:30 02:30 2.54E-04 8.00E-05 1.52E-01 2.54E-04 < LLD 7.20E-03 9.90E-03 1.52E-01 10:45 02:45 < LLD 7.20E-03 9.90E-03 8.00E-05 11:00 03:00 2.54E-04 8.00E-05 1.52E-01 2.54E-04 < LLD 7.20E-03 9.90E-03 11:15 03:15 < LLD 7.20E-03 9.90E-03 8.00E-05 1.52E-01 11:30 03:30 2.54E-04 8.00E-05 1.52E-01 2.54E-04 < LLD 7.20E-03 9.90E-03 11:35 03:35 < LLD 7.20E-03 9.90E-03 8.00E-05 1.52E-01 11:40 03:40 2.54E-04 8.00E-05 1.52E-01 2.54E-04 < LLD 7.2CE-03 9.90E-03 1.52E-01 11:45 03:45 < LLD 7.20E-03 9.90E-03 8.00E-05 12:00 04:00 3.54E-04 8.00E-05 1.52E-01 2.54E-04 < LLD 7.20E-03 9.90E-03 1.52E-01 12:15 04:15 < LLD 7.20E-03 S.90E-03 8.00E-05 ["2:20 04:20 2.54E-04 8.00E-05 1.52E-01 2.54Ee04 < LLD 7.20E-03 9.90E-03
\ -.2:25 04:25 2.54E-04 < LLD 7.20E-03 9.90E-03 8.00E-05 1.52E-01 12:30 04:30 < LLD 7.20E-03 9.90E-03 8.00E-05 1.52E-01 12:35 04:35 2.54E-04 8.00E-05 1.52E-01 2.55E-04 < LLD 7.20E-03 9.90E-03 12:40 04:40 < LLD 7.20E-03 9.90E-03 8.00E-05 1.52E-01 12:45 04:45 2.55L-ds 8.00E-05 1.52E-01 2.59E-04 < LLD 7.20E-03 9.90E-03 13:00 05:00 < LLD 7.20E-03 9.90E-03 8.00E-05 1.52E-01 13:15 05:15 2.59D 04 8.00E-05 1.52E-01
< LLD 7.20E-03 9.90E-03 13:30 05:30 2.!9L-04
< LLD 7.20E-03 9.90E-03 8.00E-05 1.52E-01 13:45 05:45 2.59E-04 8.00E-05 1.52E-01 2.59E-04 < LLD 7.20E-03 9.90E-03 1.52E-01 14:00 06:00 < LLD 7.20E-03 9.90E-03 8.00E-05 14:15 06:15 2.59E-04 8.00E-05 1.52E-01 2.59E-04 < LLD 7.20E-03 9.90E-03 1.52E-01 14:30 06:30 < LLD 7.20E-03 9.90E-03 8.00E-05 14:45 06:45 2.59E-04 8.00E-05 1.52E-01 2.59E-04 < LLD 7.20E-03 9.90E-03 1.52E-01 15:00 07:00 < LLD 7.20E-03 9.90E-03 8.00E-05 15:15 07:15 2.59E-04 8.00E-05 1.52E-01 2.59E-04 < LLD 7.20E-03 9.90E-03 1.52E-01 15:30 07:30 < LLD 7.20E-03 9.90E-03 8.00E-05 15:45 07:45 2.59E-04 8.00E-05 1.52E-01 2.59E-04 < LLD 7.20E-03 9.90E-03 16:00 08:00 9.1.13 o
l
1
)
Torus Water Concentrations l Hope Creek Nuclear Generating Station gs 10/25/94 ; (_-) Total Sr-89 Sr-90 Xe-133m Xe-135 Noble Gas Rb-88 Clock Drill uCi/cc uCi/cc uCi/cc uCi/cc Tima Time uCi/cc uCi/cc < LLD < LLD 5.61E-06 2.18E-04 2.45E-03 1.88E-04 08:00 00:00 2.18E-04 2.45E-03 1.88E-04 < LLD < LLD 08:15 00:15 5.61E-06 < LLD < LLD 5.61E-06 2.18E-04 2.45E-03 1.88E-04 08:30 00:30 2.'4E-04 2.45E-03 1.88E-04
< LLD < LLD 08:45 00:45 5.61E-06 < LLD < LLD 09:00 01:00 5.61E-06 2.1sE-04 2.45E-03 1.88E-04 < LLD < LLD 09:15 01:15 5.61E-06 2 .E-04 2.45E-03 1.88E-04 < LLD < LLD 5.61E-06 2. UE-04 2.45E-03 1.8BE-04 09:30 01:30 < LLD < LLD 09:45 01:45 5.61E-06 2.~8E-04 2.45E-03 1.8BE-04 < LLD < LLD 09:50 01:50 4.27E-04 1.66E-02 1.86E-01 2.02E-04 < LLD < LLD 10:00 02:00 4.27E-04 1.66E-02 1.86E-01 2.02E-04 < LLD < LLD 10:15 02:15 4.27E-04 1.66E-02 1.86E-01 2.02E-04 < LLD < LLD 10:30 02:30 4.27E-04 1.66E-02 1.86E-01 2.02E-04 < LLD < LLD 10:45 02:45 4.27E-04 1.66E-02 1. 8 6E -01 2.02E-04 < LLD < LLD i
11:00 03:00 4.27E-04 1.66E-02 1.86E-C1 2.02h-04 < LLD < LLD 11:15 03:15 4.27E-04 1.66E-02 1.86E-01 2.02E-04 < LLD < LLD 11:30 03:30 4.27E-04 1.66E-02 1.86E-01 2.02E-04 < LLD 1.66E-02 1.86E-01 2.02E-04 < LLD i 11:35 03:35 4.27E-04 < LLD < LLD 11:40 03:40 4.27E-04 1.66E-02 1.86E-01 2.02E-04 < LLD 11:45 03:45 4.27E-04 1.66E-02 1.86E-01 2.02E-04 < LLD
< LLD < LLD 12:00 04:00 4.27E-04 1.66E-02 1.86E-01 2.02E-04 < LLD < LLD
/~5 4.27E-04 1.66E-02 1.86E-01 2.02E-04 < LLD < LLD
\s_)1:1504:15 4.27E-04 2:20 04:20 1.66E-02 1.86E-01 2.02E-04 < LLD 12:25 04:25 4.27E-04 1.66E-02 1.86E-01 2.02E-04 < LLD
< LLD < LLD 12:30 04:30 4.27E-04 1.66E-02 1.86E-01 2.02E-04 < LLD < LLD
.12:35 04:35 4.27E-04 1.66E-02 1.86E-01 2.02E-04 < LLD < LLD 12:40 04:10 4.27E-04 1.66E-02 1.86E-01 2.02E-04 < LLD < LLD 12:45 04:45 4.27E-04 1.66E-02 1.86E-01 2.02E-04 < LLD < LLD 13:00 05:00 4.27E-04 1.66E-02 1.86E-01 2.02E-04 < LLD < LLD 13:15 05:15 4.27E-04 1.66E-02 1.86E-01 2.02E-04 < LLD < LLD 13:30 05:30 4.27E-04 1.66E-02 1.86E-01 2.02E-04 < LLD < LLD 13:45 05:45 4.27E-04 1.66E-02 1.86E-01 2.02E-04 < LLD < LLD 14:00 06:00 4.27E-04 1.66E-02 1.86E-01 2.02E-04 < LLD < LLD 14:15 06:15 4.27E-04 1.66E-02 1.86E-01 2.02E-04 < LLD 14:30 06:30 4.27E-04 1.66E-02 1.86E-01 2.02E-04 < LLD
< LLD < LLD 14:a5 06:45 4.27E-04 1.66E-02 1.86E-01 2.02E-04 < LLD < LLD 15:00 07:00 4.27E-04 1.66E-02 1.86E-01 2.02E-04 < LLD < LLD 15:15 07:15 4.27E-04 1.66E-02 1.86E-01 2.02E-04 < LLD < LLD 15:30 07:30 4.27E-04 1.66E-02 1.86E-01 2.02E-04 < LLD < LLD 15:45 07:45 4.27E-04 1.66E-02 1.86E-01 2.02E-04 < LLD < LLD 16:00 08:00 4.27E-04 1.66E-02 1.86E-01 2.02E-04 9.1.14 ;
v
Torus Water Concentrations Hope Creek Nuclear Generating Station 10/25/94 Te-132 Cs-134 Cs-137 Ba-140 Mo-99 Te-129 Clock Drill uCi/cc uCi/cc uCi/cc uCi/cc uCi/cc Time Time uCi/cc < LLD 6.88E-06 1.84E-06 < LLD 3.02E-04 < LLD 08:00 00:00 < LLD < LLD 6.88E-06 1.84E-06 < LLD 08:15 00:15 3.02E-04 < LLD 6.88E-06 1.84E-06 < LLD 3.02E-04 < LLD < LLD 08:30 00:30 < LLD < LLD 6.88E-06 1.84E-06 08:45 00:45 3.02E-04 < LLD 6.88E-06 1.84E-06 < LLD 3.02E-04 < LLD < LLD 09:00 01:00 < LLD < LLD 6.88E-06 1.84E-06 09:15 01:15 3.02E-04 < LLD 6.88E-06 1.84E-06 < LLD 3.02E-04 < LLD < LLD 09:30 01:30 < LLD < LLD 6.88E-06 1.84E-06 09:45 01:45 3.02E-04 < LLD 8.19E-06 2.21E-06 < LLD 09:50 01:50 3.2SE-04 < LLD < LLD
< LLD < LLD 8.19E-06 2.21E-06 10:00 02:00 3.25E-04 8.19E-06 2.21E-06 < LLD 3.25E-04 < LLD < LLD 10:15 02:15 < LLD < LLD 8.19E-06 2.21E-06 < LLD 10:30 02:30 3.25E-04 8.19E-06 2.21E-06 < LLD
< LLD < LLD 10:45 02:45 3.25E-04
< LLD < LLD 8.19E-06 2.21E-06 < LLD 11:00 03:00 3.25E-04 8.19E-06 2.21E-06 < LLD 3.25E-04 < LLD < LLD 11:15 03:15 < LLD < LLD 8.19E-06 2.21E-06 < LLD 11:30 03:30 3.25E-04 8.19E-06 2.21E-06 < LLD
< LLD < LLD 11:35 03:35 3.25E-04
< LLD < LLD 8.19E-06 2.21E-06 < LLD 11:40 03:40 3.25E-04 8.19E-06 2.21E-06 < LLD 3.25E-04 < LLD < LLD 11:45 03:45 < LLD < LLD 8.19E-06 2.21E-06 < LLD 12:00 04:00 3.25E-04 8.19E-06 2.21E-06 < LLD 3.25E-04 < LLD < LLD 12:15 04:15 < LLD < LLD 8.20E-06 2.22E-06 < LLD 2:20 04:20 3.25E-04 8.21E-06 2.22E-06 < LLD 3.25E-04 < LLD < LLD
\ 2:25 04:25
< LLD < LLD 8.20E-06 2.22E-06 < LLD 12:30 04:30 3.25E-04 8.24E-06 2.23E-06 < LLD 3.26E-04 < LLD < LLD 12:35 04:35 < LLD < LLD 8.28E-06 2.24E-06 < LLD 12:40 04:40 3.26E-04 8.32E-06 2.25E-06 < LLD 3.27E-04 < LLD 2.06E-06 12:45 04:45 < LLD 5.79E-06 8.63E-06 2.34E-06 7.27E-06 13:00 05:00 3.32E-04 8.63E-06 2.34E-06 7.27E-06 3.32E-04 < LLD 5.78E-06 13:15 05:15 < LLD 5.77E-06 8.63E-06 2.34E-06 7.26E-06 13:30 05:30 3.32E-04 8.63E-06 2.34E-06 7.26E-06 3.32E-04 < LLD 5.76E-06 13:45 05:45 < LLD 5.75E-06 8.63E-06 2.34E-06 7.26E-06 14:00 06:00 3.32E-04 8.63E-06 2.34E-06 7.25E-06 3.32E-04 < LLD 5.73E-06 7.25E-06 14:15 06:15 < LLD 5.72E-06 8.63E-06 2.34E-06 14:30 06:30 3.32E-04 8.63E-06 2.34E-06 7.24E-06 3.32E-04 < LLD 5.71E-06 7.24E-06 14:45 06:45 < LLD 5.70E-06 8.63E-06 2.34E-06 15:00 07:00 3.32E-04 8.63E-06 2.34E-06 7.24E-06 3.32E-04 < LLD 5.69E-06 7.23E-06 15:15 07:15 < LLD 5.68E-06 8.63E-06 2.34E-06 15:30 07:30 3.32E-04 8.63E-06 2.34E-06 7.23E-06 3.32E-04 < LLD 5.66E-06 7.22E-06 15:45 07:45 < LLD 5.65E-06 8.63E-06 2.34E-06 16:00 08:00 3.32E-04 O 9.1.15 .
I
}
Torus Water Concentrations Hope Creek Nuclear Generating Station 10/25/94 Total Gross Ce-144 Particulate Activity Clock Drill La-140 La-142 uCi/cc Time Time uCi/cc uCi/cc uCi/cc uCi/cc '
< LLD 4.99E-04 3.44E-03 08:00 00:00 < LLD < LLD
< LLD < LLD < LLD 4.99E-04 3.44E-03 08:15 00:15 < LLD 4.99E-04 3.44E-03 08:30 00:30 < LLD < LLD 3.44E-03 08:45 00:45 < LLD < LLD < LLD 4.99E-04
< LLD < LLD < LLD 4.99E-04 3.44E-03 09:00 01:00 < LLD 4.99E-04 3.44E-03 09:15 01:15 < LLD < LLD
< LLD < LLD < LLD 4.99E-04 3.44E-03 09:30 01:30 < LLD 4.99E-04 3.44E-03 09:45 01:45 < LLD < LLD
< LLD < LLD 5.38E-04 1.88E-01 09:50 01:50 < LLD
< LLD < LLD 5.38E-04 1.88E-01 10:00 02:00 < LLD
< LLD < LLD 5.38E-04 1.88E-01 10:15 02:15 < LLD
< LLD 5.38E-04 1.88E-01 10:30 02:30 < LLD < LLD
< LLD <-LLD < LLD 5.38E-04 1.88E-01 10:45 02:45 < LLD 5.38E-04 1.88E-01 11:00 03:00 < LLD < LLD 11:15 03:15 < LLD < LLD < LLD 5.38E-04 1.88E-01
< LLD < LLD 5.38E-04 1.88E-01 11:30 03:30 < LLD 1.88E-01
< LLD < LLD < LLD 5.38E-04 11:35 03:35 5.38E-04 1.88E-01 11:40 03:40 < LLD < LLD < LLD
< LLD < LLD 5.38E-04 1.88E-01 11:45 03:45 < LLD
< LLD < LLD 5.38E-04 1.88E-01 12:00 04:00 < LLD
< LLD < LLD < LLD 5.38E-04 1.88E-01
< LLD < LLD 5.38E-04 1.88E-01 01:1504:15
.:20 04:20 12:25 04:25
< LLD
< LLD < LLD < LLD 5.39E-04 1.88E-01 12:30 04:30 < LLD < LLD < LLD 5.39E-04 1.88E-01
< LLD < LLD < LLD 5.43E-04 1.88E-01 12:35 04:35 1.88E-01 12:40 04:40 < LLD < LLD < LLD 5.46E-04
< LLD < LLD 5.50E-04 1.88E-01 ;
12:45 04:45 < LLD
< LLD 5.77E-04 1.88E-01 13:00 05:00 7.36E-06 2.66E-06 7.33E-06 2.37E-06 < LLD 5.76E-04 1.88E-01 13:15 05:15 < LLD 5.76E-04 1.88E-01 13:30 05:30 7.30E-06 2.12E-06 1.88E-01 13:45 05:45 7.27E-06 < LLD < LLD 5.76E-04 1 7.24E-06 < LLD < LLD 5.75E-04 1.88E-01 l 14:00 06:00 5.75E-04 1.88E-01 1
14:15 06:15 7.21E-06 < LLD < LLD 7.18E-06 < LLD < LLD 5.75E-04 1.88E-01 14:30 06:30 < LLD 5.75E-04 1.88E-01 14:45 06:45 7.15E-06 < LLD l 15:00 07:00 7.11E-06 < LLD < LLD 5.74E-04 1.88E-01
< LLD 5.74E-04 1.88E-01 l 15:15 07:15 7.08E-06 < LLD 1.88E-01 7.05E-06 < LLD < LLD 5.74E-04 15:30 07:30 1.88E-01 15:45 07:45 7.02E-06 < LLD < LLD 5.74E-04 6.99E-06 < LLD < LLD 5.74E-04 1.88E-01 16:00 08:00 I
O 9.1.16
Feed Water Concentrations Hope Creek Nuclear Generating Station 10/25/94 O Total Iodine I-133 I-134 I-135 I-132 Clock Drill I-131 uCi/cc uCi/cc uCi/cc uCi/cc Time Time uCi/cc uCi/cc 2.68E-03 2.09E-03 9.66E-03 1.03E-03 1.56E-03 2.29E-03 08:00 00:00 1.56E-03 2.29E-03 2.68E-03 2.09E-03 9.66E-03 08:15 00:15 1.03E-03 2.68E-03 2.09E-03 9.66E-03 1.03E-03 1.56E-03 2.29E-03 08:30 00:30 1.56E-03 2.29E-03 2.68E-03 2.09E-03 9.66E-03 08:45 00:45 1.03E-03 2.68E-03 2.09E-03 9.66E-03 1.03E-03 1.56E-03 2.29E-03 09:00 01:00 2.29E-03 2.68E-03 2.09E-03 9.66E-03 09:15 01:15 1.03E-03 1.56E-03 9.66E-03 1.03E-03 1.56E-03 2.29E-03 2.68E-03 2.09E-03 09:30 01:30 2.29E-03 2.68E-03 2.09E-03 9.66E-03 09:45 01:45 1.03E-03 1.56E-03 9.66E-03 1.03E-03 1.56E-03 2.29E-03 2.68E-03 2.09E-03 09:50 01:50 2.29E-03 2.68E-03 2.09E-03 9.66E-03 10:00 02:00 1.03E-03 1.56E-03 9.66E-03 1.03E-03 1.56E-03 2.29E-03 2.68E-03 2.09E-03 10:15 02:15 1.56E-03 2.29E-03 2.68E-03 2.09E-03 9.66E-03 10:30 02:30 1.03E-03 2.68E-03 2.09E-03 9.66E-03 10:45 02:45 1.03E-03 1.56E-03 2.29E-03 1.56E-03 2.29E-03 2.6BE-03 2.09E-03 9.66E-03 11:00 03:00 1.03E-03 2.68E-03 2.09E-03 9.66E-03 11:15 03:15 1.03E-03 1.56E-03 2.29E-03 1.56E-03 2.29E-03 2.68E-03 2.09E-03 9.66E-03 11:30 03:30 1.03E-03 2.68E-03 2.09E-03 9.66E-03 11:35 03:35 1.03E-03 1.56E-03 2.29E-03 9.66E-03 1.56E-03 2.29E-03 2.68E-03 2.09E-03 11:40 03:40 1.03E-03 2.68E-03 2.09E-03 9.66E-03 11:45 03:45 1.03E-03 1.56E-03 2.29E-03 9.66E-03 1.56E-03 2.29E-03 2.68E-03 2.09E-03 12:00 04:00 1.03E-03 2.68E-03 2.09E-03 9.66E-03 1.03E-03 1.56E-03 2.29E-03 9.66E-03 1:15 04:15 1.56E-03 2.29E-03 2.68E-03 2.09E-03 \ .:.0 2 04:20 1.03E-03 2.68E-03 2.09E-03 9.66E-03 12:25 04:25 1.03E-03 1.56E-03 2.29E-03 1.56E-03 2.29E-03 2.68E-03 2.09E-03 9.66E-03 12:30 04:30 1.03E-03 2.68E-03 2.09E-03 9.66E-03 ; 12:35 04:35 1.03E-03 1.56E-03 2.29E-03 9.66E-03 1.56E-03 2.29E-03 2.68E-03 2.09E-03 12:40 04:40 1.03E-03 2.68E-03 2.09E-03 9.66E-03 , 12:45 04:45 1.03E-03 1.56E-03 2.29E-03 9.66E-03 1.56E-03 2.29E-03 2.68E-03 2.09E-03 13:00 05:00 1.03E-03 2.68E-03 2.09E-03 9.66E-03 13:15 05:15 1.03E-03 1.56E-03 2.29E-03 2.29E-03 2.68E-03 2.09E-03 9.66E-03 , 13:30 05:30 1.03E-03 1.56E-03 9.66E-03 1.56E-03 2.29E-03 2.68E-03 2.09E-03 13:45 05:45 1.03E-03 2.09E-03 9.66E-03 1.03E-03 1.56E-03 2.29E-03 2.68E-03 14:00 06:00 2.29E-03 2.68E-03 2.09E-03 9.66E-03 14:15 06:15 1.03E-03 1.56E-03 9.66E-03 1.56E-03 2.29E-03 2.68E-03 2.09E-03 14:30 06:30 1.03E-03 2.68E-03 2.09E-03 9.66E-03 14:45 06:45 1.03E-03 1.56E-03 2.29E-03 1.56E-03 2.29E-03 2.68E-03 2.09E-03 9.66E-03 15:00 07:00 1.03E-03 2.68E-03 2.09E-03 9.66E-03 15:15 07:15 1.03E-03 1.56E-03 2.29E-03 1.56E-03 2.29E-03 2.68E-03 2.09E-03 9.66E-03 15:30 07:30 1.03E-03 2.68E-03 2.09E-03 9.66E-03 l 15:45 07:45 1.03E-03 1.56E-03 2.29E-03 2.29E-03 2.68E-03 2.09E-03 9.66E-03 i 16:00 08:00 1.03E-03 1.56E-03 ! O 9.1.17 l 1
I Feed Water Concentrations Hope Creek Nuclear Generating Station /~N 10/25/94 (_) Kr-88 Xe-131m Xe-133 Kr-87 Clock Drill DEI Kr-85 uCi/cc uCi/cc uCi/cc uCi/cc Time uCi/cc uCi/cc < LLD 1.98E-03 ! Time 1.98E-03 < LLD 9.36E-05 1.29E-04 1.98E-03 l 08:00 00:00 < LLD 9.36E-05 1.29E-04 < LLD ' 08:15 00:15 1.98E-03 < LLD 1.98E-03 1.98E-03 < LLD 9.36E-05 1.29E-04 1.98E-03 08:30 00:30 < LLD 9.36E-05 1.29E-04 < LLD 08:45 00:45 1.98E-03 < LLD 1.98E-03 1.98E-03 < LLD 9.36E-05 1.29E-04 1.98E-03 09:00 01:00 < LLD 9.36E-05 1.29E-04 < LLD 09:15 01:15 .9FE-03 < LLD 1.98E-03 1.98E-03 < LLD 9.36E-05 1.29E-04 1.98E-03 09:30 01:30 < LLD 9.36E-05 1.29E-04 < LLD 09:45 01:45 1.98E-03 < LLD 1.98E-03 1.98E-03 < LLD 9.36E-05 1.29E-04 1.98E-03 09:50 01:50 < LLD 9.36E-05 1.29E-04 < LLD 10:00 02:00 1.98E-03 < LLD 1.98E-03 1.98E-03 < LLD 9.36E-05 1.29E-04 1.98E-03 10:15 02:15 < LLD 9.36E-05 1.29E-04 < LLD 10:30 02:30 1.98E-03 < LLD 1.98E-03 1.98E-03 < LLD 9.36E-05 1.29E-04 1.98E-03 10:45 02:45 < LLD 9.36E-05 1.29E-04 < LLD 11:00 03:00 1.98E-03 < LLD 1.98E-03 1.9BE-03 < LLD 9.36E-05 1.29E-04 1.98E-03 11:15 03:15 < LLD 9.36E-05 1.29E-04 < LLD 11:30 03:30 1.98E-03 < LLD 1.98E-03 1.98E-03 < LLD 9.36E-05 1.29E-04 1.98E-03 11:35 03:35 < LLD 9.36E-05 1.29E-04 < LLD 11:40 03:40 1.98E-03 < LLD 1.98E-03 1.98E-03 < LLD 9.36E-05 1.29E-04 1.98E-03 11:45 03:45 < LLD 9.36E-05 1.29E-04 < LLD 12:00 04:00 1.98E-03 < LLD 1.98E-03 1.98E-03 < LLD 9.36E-05 1.29E-04 1.98E-03 12:15 04:15 < LLD 9.36E-05 1.29E-04 < LLD I 2:20 04:20 1.98E-03 < LLD 1.98E-03 1.98E-03 < LLD 9.36E-05 1.29E-04 1.98E-03
.2:25 04:25 < LLD 9.36E-05 1.29E-04 < LLD 12:30 04:30 1.98E-03 < LLD 1.98E-03 1.98E-03 < LLD 9.36E-05 1.29E-04 1.98E-03 12:35 04:35 < LLD 9.36E-05 1.29E-04 < LLD 12:40 04:40 1.98E-03 < LLD 1.98E-03 1.98E-03 < LLD 9.36E-05 1.29E-04 1.98E-03 12:45 04:45 < LLD 9.36E-05 1.29E-04 < LLD 13:00 05:00 1.98E-03 < LLD 1.98E-03 1.98E-03 < LLD 9.36E-05 1.29E-04 1.98E-03 13:15 05:15 < LLD 9.36E-05 1.29E-04 < LLD 13:30 05:30 1.98E-03 < LLD 1.98E-03 1.98E-03 < LLD 9.36E-05 1.29E-04 1.98E-03 13:45 05:45 < LLD 9.36E-05 1.29E-04 < LLD 14:00 06:00 1.98E-03 < LLD 1.98E-03 1.98E-03 < LLD 9.36E-05 1.29E-04 1.98E-03 14:15 06:15 < LLD 9.36E-05 1.29E-04 < LLD 14:30 06:30 1.98E-03 < LLD 1.98E-03 1.98E-03 < LLD 9.36E-05 1.29E-04 1.98E-03 14:45 06:45 < LLD 9.36E-05 1.29E-04 < LLD 15:00 07:00 1.98E-03 < LLD 1.98E-03 1.98E-03 < LLD 9.36E-05 1.29E-04 1.98E-03 15:15 07:15 < LLD 9.36E-05 1.29E-04 < LLD 15:30 07:30 1.98E-03 < LLD 1.98E-03 1.98E-03 < LLD 9.36E-05 1.29E-04 1.98E-03 15:45 07:45 < LLD 9.36E-05 1.29E-04 < LLD 16:00 08:00 1.98E-03 i l
l 9.1.18
)
i Feed Water Concentrations Hope Creek Nuclear Generating Station ' 10/25/94 ( Total Noble Gas Rb-88 Sr-89 Sr-90 Clock Drill Xe-133m Xe-135 uCi/cc uCi/cc uCi/cc uCi/cc uCi/cc Time Time uCi/cc 2.42E-03 1.86E-04 < LLD < LLD 08:00 00:00 5.55E-06 2.16E-04 < LLD 5.55E-06 2.16E-04 2.42E-03 1.86E-04 < LLD 08:15 00:15 2.16E-04 2.42E-03 1.86E-04 < LLD < LLD 08:30 00:30 5.55E-06 1.86E-04 < LLD < LLD 5.55E-06 2.16E-04 2.42E-03 08:45 00:45 2.16E-04 2.42E-03 1.86E-04 < LLD < LLD 09:00 01:00 5.55E-06 1.86E-04 < LLD < LLD 2.42E-03 1 09:15 01:15 5.55E-06 2.16E-04 < LLD < LLD 5.55E-06 2.16E-04 2.42E-03 1.86E-04 09:30 01:30 2.42E-03 1.86E-04 < LLD < LLD 09:45 01:45 5.55E-06 2.16E-04 < LLD < LLD 5.55E-06 2.16E-04 2.42E-03 1.86E-04 09:50 01:50 2.42E-03 1.86E-04 < LLD < LLD 10:00 02:00 5.55E-06 2.16E-04 < LLD 5.55E-06 2.16E-04 2.42E-03 1.86E-04 < LLD 10:15 02:15 2.42E-03 1.86E-04 < LLD < LLD 10:30 02:30 5.55E-06 2.16E-04 < LLD < LLD 5.55E-06 2.16E-04 2.42E-03 1.86E-04 10:45 02:45 2.42E-03 1.86E-04 < LLD < LLD 11:00 03:00 5.55E-06 2.16E-04 < LLD < LLD 5.55E-06 2.16E-04 2.42E-03 1.86E-04 ' 11:15 03:15 2.42E-03 1.86E-04 < LLD < LLD 11:30 03:30 5.55E-06 2.16E-04 < LLD < LLD 5.55E-06 2.16E-04 2.42E-03 1.86E-04 11:35 03:35 2.42E-03 1.86E-04 < LLD < LLD 11:40 03:40 5.55E-06 2.16E-04 < LLD 5.55E-06 2.16E-04 2.42E-03 1.86E-04 < LLD 11:45 03:45 2.42E-03 1.86E-04 < LLD < LLD 12:00 04:00 5.55E-06 2.16E-04 < LLD < LLD 5.55E-06 2.16E-04 2.42E-03 1.86E-04 1.86E-04 < LLD < LLD 5.55E-06 2.16E-04 2.42E-03 O'2:1504:15 2:20 04:20 2.42E-03 1.86E-04 < LLD < LLD 12:25 04:25 5.55E-06 2.16E-04 < LLD < LLD 5.55E-06 2.16E-04 2.42E-03 1.86E-04 12:30 04:30 2.42E-03 1.86E-04 < LLD < LLD - 12:35 04:35 5.55E-06 2.16E-04 < LLD < LLD 5.55E-06 2.16E-04 2.42E-03 1.86E-04 12:40 04:40 1.86E-04 < LLD < LLD 12:45 04:45 5.55E-06 2.16E-04 2.42E-03
< LLD < LLD 5.55E-06 2.16E-04 2.42E-03 1.86E-04 13:00 05:00 1.86E-04 < LLD < LLD 13:15 05:15 5.55E-06 2.16E-04 2.42E-03
< LLD < LLD 5.55E-06 2.16E-04 2.42E-03 1.86E-04 13:30 05:30 1.86E-04 < LLD < LLD 13:45 05:45 5.55E-06 2.16E-04 2.42E-03 2.16E-04 2.42E-03 1.86E-04 < LLD < LLD 14:00 06:00 5.55E-06 < LLD 5.55E-06 2.16E-04 2.42E-03 1.86E-04 < LLD 14:15 06:15 1.86E-04 < LLD < LLD 14:30 06:30 5.55E-06 2.16E-04 2.42E-03 < LLD 2.16E-04 2.42E-03 1.86E-04 < LLD 14:45 06:45 5.55E-06 < LLD < LLD 5.55E-06 2.16E-04 2.42E-03 1.86E-04 15:00 07:00 2.42E-03 1.86E-04 < LLD < LLD 15:15 07:15 5.55E-06 2.16E-04 2.16E-04 2.42E-03 1.86E-04 < LLD < LLD 15:30 07:30 5.55E-06 < LLD < LLD 5.55E-06 2.16E-04 2.42E-03 1.86E-04 '
15:45 07:45 2.42E-03 1.86E-04 < LLD < LLD 16:00 08:00 5.55E-06 2.16E-04 i O 9.1.19
)
I
~__
Feed Water Concentrations Hope Creek Nuclear Generating Station 10/25/94 Te-132 Cs-134 Cs-137 Ba-140 Clock Drill Mo 99 Te-129 uCi/cc uCi/cc uCi/cc uCi/cc uCi/cc Time Time uCi/cc < LLD 1.71E-05 4.89E-06 < LLD 2.99E-04 < LLD 08:00 00:00 < LLD < LLD 1.71E-05 4.89E-06 < LLD 08:15 00:15 2.99E-04 < LLD 1.71E-05 4.89E-06 < LLD 2.99E-04 < LLD 08:30 00:30 < LLD < LLD 1.71E-05 4.89E-06 < LLD 08:45 00:45 2.99E-04 1.71E-05 4.89E-06 < LLD 2.99E-04 < LLD < LLD 09:00 01:00 < LLD < LLD 1.71E-05 4.89E-06 < LLD 09:15 01:15 2.99E-04 1.71E-05 4.89E-06 < LLD 2.99E-04 < LLD < LLD 09:30 01:30 < LLD < LLD 1.71E-05 4.89E-06 < LLD 09:45 01:45 2.99E-04 1.71E-05 4.89E-06 < LLD 2.99E-04 < LLD < LLD 09:50 01:50 < LLD < LLD 1.71E-05 4.89E-06 < LLD 10:00 02:00 2.99E-04 1.71E-05 4.89E-06 < LLD 2.99E-04 < LLD < LLD 10:15 02:15 < LLD 1.71E-05 4.89E-06 < LLD 10:30 02:30 2.99E-04 < LLD < LLD
< LLD < LLD 1.71E-05 4.89E-06 10:45 02:45 2.99E-04
< LLD 1.71E-05 4.89E-06 < LLD 11:00 03:00 2.99E-04 < LLD
< LLD < LLD 1.71E-05 4.89E-06 < LLD 11:15 03:15 2.99E-04 1.71E-05 4.89E-06 < LLD
< LLD < LLD 11:30 03:30 2.99E-04
< LLD < LLD 1.71E-05 4.89E-06 < LLD 11:35 03:35 2.99E-04 1.71E-05 4.89E-06 < LLD
< LLD < LLD 11:40 03:40 2.99E-04
< LLD < LLD 1.71E-05 4.89E-06 < LLD 11:45 03:45 2.99E-04
< LLD < LLD 1.71E-05 4.89E-06 < ~ (D 12:00 04:00 2.99E-04 1.71E-05 4.89E-06 4 LLD
< LLD < LLD 12:15 04:15 2.99E-04
< LLD < LLD 1.71E-05 4.89E-06 < LLD 2.99E-04 1.71E-05 4.89E-06 < LLD
< LLD < LLD O'2:20 2:25 04:20 04:25 2.99E-04
< LLD < LLD 1.71E-05 4.89E-06 < LLD 12:30 04:30 2.99E-04
< LLD < LLD 1.71E-05 4.89E-06 < LLD 12:35 04:35 2.99E-04 1.71E-05 4.89E-06 < LLD
< LLD < LLD 12:40 04:40 2.99E-04
< LLD < LLD 1.71E-05 4.89E-06 < LLD 12:45 04:45 2.99E-04
< LLD 1.71E-05 4.89E-06 < LLD 13:00 05:00 2.99E-04 < LLD < LLD 2.99E-04 < LLD < LLD 1.71E-05 4.89E-06 13:15 05:15 < LLD < LLD 1.71E-05 4.89E-06 < LLD 13:30 05:30 2.99E-04
< LLD 1.71E-05 4.89E-06 < LLD 13:45 05:45 2.99E-04 < LLD 4.89E-06 < LLD 2.99E-04 < LLD < LLD 1.71E-05 14:00 06:00 < LLD < LLD 1.71E-05 4.89E-06 < LLD 14:15 06:15 2.99E-04 < LLD
< LLD < LLD 1.71E-05 4.89E-06 14:30 06:30 2.99E-04
< LLD < LLD 1.71E-05 4.89E-06 < LLD 14:45 06:45 2.99E-04 4.89E-06 < LLD 2.99E-04 < LLD < LLD 1.71E-05 15:00 07:00 < LLD 1.71E-05 4.89E-06 < LLD 15:15 07:15 2.99E-04 < LLD 1.71E-05 4.89E-06 < LLD 2.99E-04 < LLD < LLD 15:30 07:30 < LLD 1.71E-05 4.89E-06 < LLD 15:45 07:45 2.99E-04 < LLD
< LLD 1.71E-05 4.89E-06 < LLD 16:00 08:00 2.99E-04 < LLD O l.20
l l f Feed Water Concentrations ; Hope Creek Nuclear Generating Station 10/25/94 Total Gross Ce-144 Particulate Activity l La-140 La-142 Clock Drill uCi/cc uCi/cc uCi/cc uCi/cc Time Time uCi/cc < LLD 5.08E-04 1.26E-02
< LLD < LLD 08:00 00:00 < LLD < LLD 5.08E-04 1.26E-02 08:15 00:15 < LLD 5.08E-04 1.26E-02
< LLD < LLD < LLD 08:30 00:30 < LLD < LLD 5.08E-04 1.26E-02 08:45 00:45 < LLD 1.26E-02
< LLD < LLD < LLD 5.08E-04 09:00 01:00 < LLD < LLD 5.08E-04 1.26E-02 09:15 01:15 < LLD 5.08E-04 1.26E-02
< LLD < LLD < LLD 09:30 01:30 < LLD < LLD 5.08E-04 1.26E-02 09:45 01:45 < LLD 1.26E-02
< LLD < LLD < LLD 5.08E-04 09:50 01:50 < LLD < LLD 5.08E-04 1.26E-02 10:00 02:00 < LLD
< LLD < LLD 5.08E-04 1.26E-02 10:15 02:15 < LLD
< LLD < LLD 5.08E-04 1.26E-02 10:30 02:30 < LLD
< LLD < LLD 5.08E-04 1.26E-02 10:45 02:45 < LLD
< LLD < LLD 5.08E-04 1.26E-02 11:00 03:00 < LLD 1.26E-02
< LLD < LLD 5.08E-04 11:15 03:15 < LLD
< LLD 5.08E-04 1.26E-02 11:30 03:30 < LLD < LLD
< LLD < LLD < LLD 5.08E-04 1.26E-02 11:35 03:35 < LLD 5.08E-04 1.26E-02 11:40 03:40 < LLD < LLD 1.26E-02
< LLD < LLD < LLD 5.08E-04 11:45 03:45 < LLD 5.08E-04 1.26E-02 12:00 04:00 < LLD < LLD
< LLD < LLD 5.08E-04 1.26E-02 12:15 04:15 < LLD 1.26E-02
< LLD < LLD < LLD 5.08E-04
\ 2:20 04:20
< LLD < LLD 5.08E-04 1.26E-02 12:25 04:25 < LLD
< LLD 5.08E-04 1.26E-02 12:30 04:30 < LLD < LLD
< LLD < LLD 5.08E-04 1.26E-02 12:35 04:35 < LLD
< LLD 5.08E-04 1.26E-02 12:40 04:40 < LLD < LLD
< LLD < LLD < LLD 5.08E-04 1.26E-02 12:45 04:45 < LLD 5.08E-04 1.26E-02 13:00 05:00 < LLD < LLD
< LLD < LLD 5.08E-04 1.26E-02 13:15 05:15 < LLD
< LLD 5.08E-04 1.26E-02 13:30 05:30 < LLD < LLD
< LLD < LLD 5.08E-04 1.26E-02 13:45 05:45 < LLD
< LLD 5.08E-04 1.26E-02 14:00 06:00 < LLD < LLD
< LLD < LLD < LLD 5.08E-04 1.26E-02 14:15 06:15 < LLD 5.08E-04 1.26E-02 14:30 06:30 < LLD < LLD
< LLD < LLD < LLD 5.08E-04 1.26E-02 14:45 06:45 < LLD < LLD 5.08E-04 1.26E-02 15:00 07:00 < LLD 1.26E-02
< LLD < LLD < LLD 5.08E-04 15:15 07:15 < LLD < LLD 5.08E-04 1.26E-02 15:30 07:30 < LLD 1.26E-02
< LLD < LLD < LLD 5.08E-04 15:45 07:45 < LLD 5.08E-04 1.26E-02 16:00 08:00 < LLD < LLD O
9.1.21
Reactor Building Air Concentrations Hope Creek Nuclear Generating Station 10/25/94 \,., Total i I-133 I-134 I-135 Iodine , Clock Drill I-131 I-132 uCi/cc uCi/cc uCi/cc uCi/cc uCi/cc i Time Time uCi/cc < LLD < LLD N/A j 08:00 00:00 < LLD < LLD < LLD
< LLD < LLD < LLD < LLD < LLD N/A l 08:15 00:15 < LLD < LLD < LLD < LLD N/A 08:30 00:30 < LLD < LLD < LLD N/A
< LLD < LLD < LLD 08:45 00:45 < LLD < LLD < LLD N/A 09:00 01:00 < LLD < LLD
< LLD < LLD < LLD < LLD < LLD N/A 09:15 01:15 < LLD < LLD < LLD N/A 09:30 01:30 < LLD < LLD
< LLD < LLD < LLD < LLD < LLD N/A 09:45 01:45 < LLD < LLD < LLD < LLD N/A 09:47 01:47 < LLD
< LLD < LLD < LLD < LLD < LLD N/A 09:50 01:50 < LLD < LLD < LLD N/A ,
10:00 02:00 < LLD < LLD '
< LLD < LLD < LLD < LLD N/A 10:15 02:15 < LLD
< LLD < LLD < LLD N/A 10:30 02:30 < LLD < LLD
< LLD < LLD < LLD < LLD N/A 10:45 02:45 < LLD
< LLD < LLD < LLD N/A 11:00 03:00 < LLD < LLD
< LLD < LLD < LLD < LLD N/A 11:15 03:15 < LLD
< LLD < LLD < LLD N/A 11:30 03:30 < LLD < LLD
< LLD < LLD < LLD 9.74E-15 3.62E-14 11:35 03:35 < LLD 2.32E-13 < LLD 1.86E-13 6.87E-13 11:40 03:40 1.10E-13 9.50E-14 1.10E-13 9.26E-14 2.31E-13 < LLD 1.84E-13 6.78E-13 11:45 03:45 2.30E-13 < LLD 1.79E-13 6.54E-13 52:00 04:00 1.10E-13 8.58E-14 1.09E-13 7.95E-14 2.28E-13 < LLD 1.75E-13 6.32E-13 ;
0i 12:20 J:15 04:20 04:15 1.68E-10 4.92E-10 8.25E-11 3.75E-10 1.35E-09 ) 2.37E-10 8.73E-10 3.15E-09 12:25 04:25 5.56E-10 3.84E-10 1.15E-09 1.81E-10 4.34E-10 1.33E-09 1.96E-10 1.00E-09 3.60E-09 12:30 04:30 6.43E-10 2.03E-08 7.30E-08 12:35 04:35 1.32E-08 8.66E-09 2.71E-08 3.76E-09 1.53E-08 4.91E-08 6.39E-09 3.66E-08 1.31E-07 12:40 04:40 2.39E-08 5.45E-08 1.95E-07 12:45 04:45 3.59E-08 2.24E-08 7.35E-08 8.98E-09 7.29E-08 2.44E-07 2.80E-08 1.80E-07 6.45E-07 12:50 04:50 1.20E-07 1.78E-07 6.39E-07 12:55 04:55 1.20E-07 7.11E-08 2.44E-07 2.62E-08 6.33E-07 6.93E-08 2.43E-07 2.45E-08 1.77E-07 13:00 05:00 1.19E-07 1.75E-07 6.28E-07 13:05 05:05 1.19E-07 6.76E-08 2.42E-07 2.30E-08 6.22E-07 1.19E-07 6.59E-08 2.42E-07 2.15E-08 1.74E-07 13:10 05:10 1.73E-07 6.18E-07 13:15 05:15 1.19E-07 6.46E-08 2.41E-07 2.04E-08 7.40E+00 7.57E-01 2.90E+00 2.27E-01 2.07E+00 13:20 05:20 1.44E+00 2.05E+00 7.34E+00 13:25 05:25 1.44E+00 7.39E-01 2.90E+00 2.13E-01 7.28E+00 7.20E-01 2.89E+00 1.99E-01 2.03E+00 13:30 05:30 1.44E+00 2.01E+00 7.22E+00 13:35 05:35 1.44E+00 7.02E-01 2.88E+00 1.86E-01 7.17E+00 ! 6.85E-01 2.87E+00 1.74E-01 2.00E+00 13:40 05:40 1.44E+00 1.98E+00 7.11E+00 13:45 05:45 1.44E+00 6.68E-01 2.86E+00 1.63E-01 6.96E+00 6.19E-01 2.84E+00 1.34E-01 1.93E+00 14:00 06:00 1.44E+00 1.88E+00 6.82E+00 14:15 06:15 1.44E+00 5.74E-01 2.82E+00 1.10E-01 6.68E+00 5.32E-01 2.79E+00 9.00E-02 1.83E+00 14:30 06:30 1.44E+00 1.78E+00 6.56E+00 14:45 06:45 1.44E+00 4.93E-01 2.77E+00 7.37E-02 6.44E+00 4.57E-01 2.75E+00 6.05E-02 1.74E+00 15:00 07:00 1.43E+00 1.40E+00 5.23E+00 15:15 07:15 1.18E+00 3.50E-01 2.25E+00 4.10E-02 2.37E+00 1.49E-01 1.03E+00 1.55E-02 6.28E-01 5:30 07:30 5.45E-01 2.08E-02 7.89E-02 \ 15:45 07:45 1.85E-02 4.70E-03 3.46E-02 4.30E-04 1.11E-03 6.23E-05 4.91E-04 5.05E-06 2.90E-04 16:00 08:00 2.64E-04 9.1.22
Reactor Building Air Concentrations Hope Creek Nuclear Generating Station l 10/25/94 (, Xe-133 Kr-87 Kr-88 Xe-131m Clock Drill DEI Kr-85 uCi/cc uCi/cc uCi/cc uCi/cc l Time Time uCi/cc uCi/cc < LLD < LLD < LLD < LLD J I N/A < LLD < LLD < LLD 08:00 00:00 < LLD < LLD < LLD
< LLD 08:15 00:15 N/A < LLD < LLD < LLD N/A < LLD < LLD < LLD 08:30 00:30 < LLD < LLD < LLD
< LLD ;
08:45 00:45 N/A < LLD < LLD < LLD ' N/A < LLD < LLD 09:00 01:00 < LLD < LLD < LLD < LLD 09:15 01:15 N/A < LLD < LLD < LLD
< LLD < LLD < LLD 09:30 01:30 N/A < LLD < LLD < LLD N/A < LLD < LLD 09:45 01:45 < LLD < LLD < LLD < LLD
< LLD 09:47 01:47 N/A < LLD < LLD < LLD N/A < LLD < LLD 09:50 01:50 < LLD < LLD < LLD < LLD 10:00 02:00 N/A < LLD < LLD < LLD
< LLD < LLD < LLD 10:15 02:15 N/A < LLD < LLD < LLD N/A < LLD < LLD 10:30 02:30 < LLD < LLD < LLD < LLD 10:45 02:45 N/A < LLD < LLD < LLD
< LLD < LLD < LLD 11:00 03:00 N/A < LLD < LLD < LLD N/A < LLD < LLD 11:15 03:15 < LLD < LLD < LLD < LLD 11:30 03:30 N/A < LLD < LLD < LLD 9.06E-15 < LLD < LLD < LLD 11:35 03:35 < LLD < LLD < LLD < LLD 11.40 03:40 1.73E-13 < LLD < LLD < LLD < LLD 1.72E-13 < LLD < LLD 11:45 03:45 < LLD < LLD < LLD < LLD 1 1.69E-13 < LLD < LLD < LLD 1.67E-13 < LLD < LLD < LLD 2:15 04:15 < LLD < LLD O'2:0004:00 42:20 04:20 3.60E-10 8.41E-10 LLD LLD
< LLD
< LLD < LLD < LLD
< LLD
< LLD
< LLD 12:25 04:25 < LLD < LLD < LLD 12:30 04:30 9.69E-10 < LLD < LLD < LLD < LLD 1.97E-08 < LLD < LLD < LLD 12:35 04:35 < LLD < LLD 1.20E-06 12:40 04:40 3.57E-08 1.76E-06 < LLD < LLD 5.34E-08 < LLD < LLD 2.11E-05 12:45 04:45 1.68E-06 5.75E-06 < LLD 1.77E-07 < LLD < LLD 2.11E-05 12:50 04:50 < LLD 1.60E-06 5.63E-06 12:55 04:55 1.77E-07 < LLD 2.10E-05 1.76E-07 < LLD 1.53E-06 5.51E-06 < LLD 2.10E-05 13:00 05:00 < LLD 1.46E-06 5.40E-06 13:05 05:05 1.75E-07 < LLD 2.10E-05 1.75E-07 < LLD 1.40E-06 5.29E-06 < LLD 2.10E-05 13:10 05:10 < LLD 1.35E-06 5.20E-06 13:15 05:15 1.74E-07 5.93E-02 1.27E+01 2.10E+00 2.51E-02 7.72E-01 3.07E+00 1.27E+01 13:20 05:20 7.38E-01 3.00E+00 5.93E-02 13:25 05:25 2.09E+00 2.51E-02 5.93E-02 1.27E+01 2.08E+00 2.51E-02 7.05E-01 2.94E+00 1.27E+01 13:30 05:30 2.51E-02 6.73E-01 2.88E+00 5.93E-02 13:35 05:35 2.08E+00 5.93E-02 1.27E+01 2.07E+00 2.51E-02 6.43E-01 2.82E+00 1.27E+01 13:40 05:40 6.15E-01 2.77E+00 5.93E-02 13:45 05:45 2.06E+00 2.51E-02 5.92E-02 1.26E+01 2.05E+00 2.51E-02 5.36E-01 2.60E+00 1.26E+01 14:00 06:00 2.51E-02 4.68E-01 2.44E+00 5.92E-02 14:15 06:15 2.03E+00 5.92E-02 1.26E+01 2.01E+00 2.51E-02 4.08E-01 2.30E+00 1.26E+01 14:30 06:30 3.56E-01 2.16E+00 5.91E-02 14:45 06:45 2.00E+00 2.51E-02 5.91E-02 1.26E+01 1.98E+00 2.51E-02 3.10E-01 2.03E+00 1.04E+01 15:00 07:00 2.07E-02 2.24E-01 1.57E+00 4.88E-02 15:15 07:15 1.63E+00 2.25E-02 4.77E+00 7.45E-01 9.55E-03 8.98E-02 6.81E-01 1.62E-01 2.66E-03 2.17E-02 7.61E-04 015:3007:30 15:45 07:45 2.51E-02 3.24E-04 1.09E-05 2.32E-03 3.57E-04 < LLD 3.33E-05 2.93E-04 16:00 08:00 9.1.23 I
Reactor Building Air Concentrations Hope Creek Nuclear Generating Station { 10/25/94 O Total Sr-89 Sr-90 l j I Xe-133m Xe-135 Noble Gas Rb-88 uCi/cc
+
Clock Drill- uCi/cc uCi/cc uCi/cc uCi/cc Time Time uCi/cc < LLD N/A < LLD < LLD < LLD 08:00 00:00 < LLD < LLD < LLD < LLD
< LLD < LLD N/A < LLD 08:15 00:15 < LLD N/A < LLD < LLD 08:30 00:30 < LLD < LLD < LLD < LLD
< LLD < LLD N/A < LLD >
08:45 00:45 < LLD N/A < LLD < LLD 09:00 01:00 < LLD < LLD < LLD < LLD
< LLD < LLD N/A < LLD 09:15 01:15 < LLD N/A < LLD < LLD 09:30 01:30 < LLD < LLD < LLD < LLD 09:45 01:45 < LLD < LLD N/A < LLD < LLD
< LLD N/A < LLD 09:47 01:47 < LLD < LLD < LLD < LLD 09:50 01:50 < LLD < LLD N/A < LLD < LLD l
< LLD N/A < LLD 10:00 02:00 < LLD < LLD < LLD < LLD >
10:15 02:15 < LLD < LLD N/A < LLD < LLD
< LLD N/A < LLD ,
10:30 02:30 < LLD < LLD < LLD < LLD l 10:45 02:45 < LLD < LLD N/A < LLD < LLD
< LLD N/A < LLD 11:00 03:00 < LLD < LLD < LLD < LLD i 11:15 03:15 < LLD < LLD N/A < LLD < LLD
< LLD N/A < LLD 11:30 03:30 < LLD < LLD < LLD < LLD 11:35 03:35 < LLD < LLD -N/A < LLD < LLD 't
< LLD N/A < LLD 11:40 03:40 < LLD < LLD < LLD- < LLD 11:45 03:45 < LLD < LLD N/A < LLD < LLD ,
< LLD N/A < LLD
'2:00 04:00 < LLD < LLD < LLD < LLD l
< LLD < LLD N/A O 22:15 04:15 < LLD < LLD N/A < LLD < LLD < LLD
< LLD 12:20 04:20 < LLD N/A < LLD < LLD !
12:25 04:25 < LLD < LLD < LLD < LLD 12:30 04:30 < LLD < LLD N/A 2.41E-11 1.83E-06 5.10E-06 1.81E-13 1.02E-10 12:35 04:35 < LLD 1.85E-10 4.37E-11
< LLD 3.30E-06 9.21E-06 2.70E-13 12:40 04:40 3.34E-13 2.78E-10 6.56E-11 12:45 04:45 < LLD 4.92E-06 1.37E-05 9.27E-10 2.19E-10 5.09E-07 1.63E-05 4.54E-05 9.14E-13 12:50 04:50 7.52E-13 9.27E-10 2.19E-10 1.62E-05 4.51E-05 12:55 04:55 5.08E-07 6.18E-13 9.27E 2.19E-10 13:00 05:00 5.08E-07 1.61E-05 4.48E-05 9.27E-10 2.19E-10 5.07E-07 1.60E-05 4.45E-05 5.08E-13 13:05 05:05 4.18E-13 9.27E-10 2.19E-10 13:10 05:10 5.06E-07 1.59E-05 4.43E-05 9.27E-10 2.19E-10 5.07E-07 1.58E-05 4.40E-05 3.57E-13 ;
13:15 05:15 2.64E+01 1.71E-05 5.60E-02 1.32E-02 13:20 05:20 3.05E-01 9.49E+00 5.60E-02 1.32E-02 ! 3.05E-01 9.43E+00 2.62E+01 1.40E-05 13:25 05:25 2.61E+01 1.15E-05 5.60E-02 1.32E-02 13:30 05:30 3.05E-01 9.37E+00 5.60E-02 1.32E-02 i 3.04E-01 9.31E+00 2.59E+01 9.49E-06 13:35 05:35 2.58E+01 7.80E-06 5.60E-02 1.32E-02 s 13:40 05:40 3.04E-01 9.25E+00 5.60E-02 1.32E-02 3.04E-01 9.19E+00 2.56E+01 6.41E-06 13:45 05:45 2.52E+01 3.56E-06 5.60E-02 1.32E-02 ? 14:00 06:00 3.03E-01 9.02E+00 5.60E-02 1.32E-02 l 3.02E-01 8.85E+00 2.48E+01 1.98E-06 14:15 06:15 2.44E+01 1.10E-06 5.60E-02 1.32E-02 14:30 06:30 3.01E-01 8.69E+00 5.60E-02 1.32E-02 3.00E-01 8.52E+00 2.40E+01 6.12E-07 14:45 06:45 2.37E+01 3.40E-07 5.59E-02 1.32E-02 15:00 07:00 2.99E-01 8.36E+00 4.62E-02 1.09E-02 2.46E-01 6.78E+00 1.93E+01 1.56E-07 B.76E+00 4.00E-08 2.13E-02 5.03E-03 15:30 07:30 1.13E-01 3.06E+00 1.71E-04 015:1507:15 15:45 07:45 3.82E-03 1.02E-01 2.93E-01 7.54E-10 7.22E-04 1.03E-05 2.44E-06 5.47E-05 1.44E-03 4.155-03 6.00E-12 16:00 08:00 9.1.24 ;
Reactor Building Air Concentrations Hope Creek Nuclear Generating Station 7s 10/25/94 Te-129 Te-132 Cs-134 Cs-137 Ba-140 Clock Drill Mo-99 Timo Time uCi/cc uCi/cc uCi/cc uCi/cc uCi/cc uCi/cc
< LLD < LLD < LLD < LLD < LLD < LLD 08:00 00:00 < LLD < LLD < LLD 08:15 00:15 < LLD < LLD < LLD
< LLD < LLD < LLD < LLD < LLD < LLD 08:30 00:30 < LLD < LLD < LLD 08:45 00:45 < LLD < LLD < LLD
< LLD < LLD < LLD < LLD < LLD < LLD 09:00 01:00 < LLD < LLD < LLD 09:15 01:15 < LLD < LLD < LLD
< LLD < LLD < LLD < LLD < LLD 09:30 01:30 < LLD
< LLD < LLD < LLD < LLD 09:45 01:45 < LLD < LLD
< LLD < LLD < LLD < LLD < LLD < LLD 09:47 01:47 < LLD < LLD < LLD 09:50 01:50 < LLD < LLD < LLD
< LLD < LLD < LLD < LLD < LLD < LLD 10:00 02:00 < LLD < LLD
< LLD < LLD < LLD < LLD 10:15 02:15 < LLD < LLD '
< LLD < LLD < LLD < LLD 10:30 02:30 < LLD < LLD
< LLD < LLD < LLD < LLD 10:45 02:45 < LLD < LLD
< LLD < LLD < LLD < LLD 11:00 03:00 < LLD < LLD
< LLD < LLD < LLD < LLD 11:15 03:15 < LLD < LLD 11:30 03:30 < LLD < LLD < LLD < LLD
< LLD < LLD < LLD < LLD < LLD < LLD 11:35 03:35 < LLD < LLD 11:40 03:40 < LLD < LLD < LLD < LLD
< LLD < LLD < LLD < LLD < LLD < LLD 11:45 03:45 < LLD < LLD 12:00 04:00 < LLD < LLD < LLD < LLD
< LLD < LLD < LLD < LLD < LLD < LLD f)g : 15 04:20 04 : 15 < LLD < LLD 6.30E-13 1.81E-13 < LLD
( ;:20 1.08E-11
< LLD 3.57E-14 1.48E-12 4.24E-13 < LLD 12:25 04:25 2.52E-11 9.91E-12 3.99E-13 7.02E-12 5.82E-13 1.67E-13 9.53E-12 12:30 04:30 12:35 04:35 2.03E-10 7.76E-12 1.44E-10 1.19E-11 3.41E-12 1.95E-10 12:40 04:40 3.68E-10 1.34E-11 2.61E-10 2.16E-11 6.21E-12 3.55E-10 12:45 04:45 5.51E-10 1.91E-11 3.91E-10 3.25E-11 9.31E-12 5.32E-10 12:50 04:50 1.84E-09 6.07E-11 1.30E-09 1.08E-10 3.10E-11 1.77E-09 12:55 04:55 1.84E-09 5.77E-11 1.30E-09 1.08E-10 3.10E-11 1.77E-09 13:00 05:00 1.83E-09 5.49E-11 1.30E-09 1.08E-10 3.10E-11 1.77E-09 13:05 05:05 1.83E-09 5.22E-11 1.30E-09 1.08E-10 3.10E-11 1.77E-09 13:10 05:10 1.83E-09 4.97E-11 1.30E-09 1.08E-10 3.10E-11 1.77E-09 13:15 05:15 1.83E-09 4.77E-11 1.30E-09 1.08E-10 3.10E-11 1.77E-09 13:20 05:20 1.10E-01 2.71E-03 7.84E-02 6.54E-03 1.88E-03 1.07E-01 13:25 05:25 1.10E-01 2.58E-03 7.83E-02 6.54E-03 1.88E-03 1.07E-01 13:30 05:30 1.10E-01 2.45E-03 7.83E-02 6.54E-03 1.88E-03 1.07E-01 13:35 05:35 1.10E-01 2.33E-03 7.82E-02 6.54E-03 1.88E-03 1.07E-01 13:40 05:40 1.10E-01 2.22E-03 7.81E-02 6.54E-03 1.88E-03 1.07E-01 13:45 05:45 1.10E-01 2.11E-03 7.81E-02 6.54E-03 1.88E-03 1.07E-01 14:00 06:00 1.10E-01 1.82E-03 7.79E-02 6.54E-03 1.88E-03 1.07E-01 14:15 06:15 1.09E-01 1.56E-03 7.77E-02 6.54E-03 1.88E-03 1.07E-01 14:30 06:30 1.09E-01 1.34E-03 7.76E-02 6.54E-03 1.88E-03 1.07E-01 14:45 06:45 1.09E-01 1.16E-03 7.74E-02 6.54E-03 1.88E-03 1.07E-01 15:00 07:00 1.09E-01 9.94E-04 7.72E-02 6.54E-03 1.88E-03 1.07E-01 15:15 07:15 8.95E-02 7.07E-04 6.37E-02 5.41E-03 1.55E-03 8.80E-02 4.11E-02 2.80E-04 2.93E-02 2.49E-03 7.14E-04 4.05E-02 g-95:30 07:30 1.39E-03 8.17E-06 9.90E-04 8.44E-05 2.42E-05 1.37E-03 i:45 07:45
()6:0008:00 1 1.98E-05 1.01E-07 1.41E-05 1.21E-06 3.47E-07 1.97E-05 9.1.25
Reactor Building Air Concentrations Hope Creek Nuclear Generating Station 10/25/94 (s) Total Gross Ce-144 Particulate Activity , La-140 La-142 Clock Drill uCi/cc uCi/cc uCi/cc uCi/cc Time Time uCi/cc < LLD N/A N/A 08:00 00:00 < LLD < LLD
< LLD < LLD < LLD N/A N/A 08:15 00:15 < LLD < LLD N/A N/A 08:30 00:30 < LLD
< LLD < LLD < LLD N/A N/A 08:45 00:45 < LLD < LLD N/A N/A 09:00 01:00 < LLD
< LLD < LLD < LLD N/A N/A 09:15 01:15 < LLD < LLD N/A N/A 09:30 01:30 < LLD
< LLD < LLD < LLD N/A N/A 09:45 01:45 < LLD < LLD N/A N/A 09:47 01:47 < LLD
< LLD < LLD < LLD N/A N/A 09:50 01:50 < LLD N/A N/A 10:00 02:00 < LLD < LLD
< LLD < LLD N/A N/A 10:15 02:15 < LLD
< LLD N/A N/A 10:30 02:30 < LLD < LLD
< LLD < LLD < LLD N/A N/A 10:45 02:45 < LLD N/A N/A 11:00 03:00 < LLD < LLD
< LLD < LLD < LLD N/A N/A 11:15 03:15 < LLD N/A N/A 11:30 03:30 < LLD < LLD
< LLD < LLD N/A 2.00E-11 11:35 03:35 < LLD
< LLD N/A 3.83E-10 11:40 03:40 < LLD < LLD
< LLD < LLD N/A 3.82E-10 11:45 03:45 < LLD N/A 3.80E-10
/~" 2 : 00 04 : 00 < LLD < LLD < LLD
< LLD < LLD N/A 3.77E-10
( !:15 04:15 < LLD
< LLD 1.15E-11 8.16E-07 12:20 04:20 < LLD < LLD
< LLD < LLD < LLD 2.72E-11 1.91E-06 12:25 04:25 3.73E-12 5.16E-11 2.55E-07 12:30 04:30 9.72E-12 4.34E-12 8.56E-11 7.62E-11 1.05E-09 5.18E-06 12:35 04:35 1.99E-10 1.90E-09 9.35E-06 12:40 04:40 3.61E-10 1.50E-10 1.39E-10 1.39E-05 12:45 04:45 5.40E-10 2.17E-10 2.08E-10 2.84E-09 6.95E-10 6.93E-10 9.45E-09 4.61E-05 12:50 04:50 1.80E-09 6.93E-10 9.41E-09 4.58E-05 12:55 04:55 1.80E-09 6.70E-10 4.55E-05 6.45E-10 6.93E-10 9.38E-09 13:00 05:00 1.79E-09 6.93E-10 9.35E-09 4.52E-05 13:05 05:05 1.79E-09 6.21E-10 4.49E-05 1.79E-09 5.99E-10 6.93E-10 9.31E-09 13:10 05:10 6.93E-10 9.29E-09 3.46E+01 13:15 05:15 1.79E-09 5.81E-10 3.44E+01 1.08E-01 3.36E-02 4.19E-02 5.59E-01 13:20 05:20 4.19E-02 5.58E-01 3.41E+01 13:25 05:25 1.08E-01 3.23E-02 3.39E+01 1.07E-01 3.11E-02 4.19E-02 5.56E-01 13:30 05:30 4.19E-02 5.54E-01 3.37E+01 13:35 05:35 1.07E-01 3.00E-02 3.35E+01 1.07E-01 2.89E-02 4.19E-02 5.53E-01 13:40 05:40 4.19E-02 5.51E-01 3.33E+01 l 13:45 05:45 1.07E-01 2.78E-02 3.27E+01 1.07E-01 2.49E-02 4.19E-02 5.47E-01 14:00 06:00 4.19E-02 5.43E-01 3.21E+01 14:15 06:15 1.06E-01 2.22E-02 3.16E+01 14:30 06:30 1.06E-01 1.99E-02 4.19E-02 5.40E-01 1.77E-02 4.19E-02 5.36E-01 3.11E+01 14:45 06:45 1.05E-01 3.06E+01 15:00 07:00 1.05E-01 1.59E-02 4.19E-02 5.33E-01 1.17E-02 3.46E-02 4.39E-01 2.49E+01 15:15 07:15 8.62E-02 1.59E-02 2.01E-01 1.13E+01 3.95E-02 4.82E-03 0 3:30 15:4507:30 07:45 1.33E-03 1.46E-04 5.40E-04 6.78E-03 3.79E-01 5.36E-03 1.90E-05 1.87E-06 7.74E-06 9.67E-05 t 16:00 08:00 9.1.26
Reactor Building Air Sample Data Hope Creek Nuclear Generating Station O Charcoal Charcoal 10/25/94 Charcoal Filter Marinelli Marinelli Cartridge Cartridge Clock Drill Cartridge Cartridge Cartridge Paper @ Contact @ 1 Foot CCPM CCPM Time Time @ Contact @ 1 Foot mR/hr mR/hr mR/hr mR/hr < 0.2 < 0.2
< 0.2 < 0.2 < 100 < 100 08:00 00:00 < 100 < 100 < 0.2 < 0.2 08:15 00:15 < 0.2 < 0.2
< 100 < 100 < 0.2 < 0.2 08:30 00:30 < 0.2 < 0.2
< 100 < 100 < 0.2 < 0.2 08:45 00:45 < 0.2 < 0.2
< 100 < 100 < 0.2 < 0.2 09:00 01:00 < 0.2 < 0.2
< 100 < 100 < 0.2 < 0.2 09:15 01:15 < 0.2 < 0.2
< 100 < 100 < 0.2 < 0.2 09:30 01:30 < 0.2 < 0.2
< 0.2 < 100 < 100 < 0.2 < 0.2 09:45 01:45 < 0.2
< 100 < 100 < 0.2 < 0.2 09:47 01:47 < 0.2 < 0.2
< 100 < 100 < 0.2 < 0.2 09:50 01:50 < 0.2 < 0.2
< 100 < 100 < 0.2 < 0.2 10:00 02:00 < 0.2 < 0.2
< 100 < 100 < 0.2 < 0.2 10:15 02:15 < 0.2 < 0.2
< 100 < 100 < 0.2 < 0.2 10:30 02:30 < 0.2 < 0.2
< 100 < 100 < 0.2 < 0.2 10:45 02:45 < 0.2 < 0.2
< 100 < 100 < 0.2 < 0.2 11:00 03:00 < 0.2 < 0.2
< 100 < 100 < 0.2 < 0.2 11:15 03:15 < 0.2 < 0.2
< 100 < 100 < 0.2 < 0.2 11:30 03:30 < 0.2 < 0.2
< 100 < 100 < 0.2 < 0.2 11:35 03:35 < 0.2 < 0.2
< 100 < 100 < 0.2 < 0.2 11:40 03:40 < 0.2 < 0.2
< 100 < 100 < 0.2 < 0.2
< 0.2 < 0.2
< 100 < 100 < 0.2 < 0.2
\/~')11: 4504:00 2:00 03 : 4 5 < 0.2 < 0.2
< 0.2 s,
< 0.2 < 100 < 100 < 0.2 12:15 04:15 < 0.2
< 100 < 100 < 0.2 < 0.2 12:20 04:20 < 0.2 < 0.2
< 100 < 100 < 0.2 < 0.2 12:25 04:25 < 0.2 < 0.2
< 100 < 100 < 0.2 < 0.2 12:30 04:30 < 0.2 < 0.2 2.29E+02 1.65E+02 < 0.2 < 0.2 12:35 04:35 < 0.2 < 0.2 4.13E+02 2.99E+02 < 0.2 < 0.2 12:40 04:40 < 0.2 < 0.2 6.13E+02 4.47E+02 < 0.2 < 0.2 12:45 04:45 < 0.2 < 0.2 2.02E+03 1.48E+03 < 0.2 < 0.2 12:50 04:50 6.57E-01 < 0.2 2.01E+03 1.48E+03 < 0.2 < 0.2 12:55 04:55 6.51E-01 < 0.2 1.99E+03 1.47E+03 < 0.2 < 0.2 i 13:00 05:00 6.46E-01 < 0.2 >
< 0.2 1.97E+03 1.47E+03 < 0.2 < 0.2 13:05 05:05 6.40E-01 '
< 0.2 6.34E-01 < 0.2 1.95E+03 1.46E+03 < 0.2 13:10 05:10}}