ML20238A354
| ML20238A354 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 08/18/1987 |
| From: | DETROIT EDISON CO. |
| To: | |
| Shared Package | |
| ML20238A353 | List: |
| References | |
| PROC-870818, NUDOCS 8708310038 | |
| Download: ML20238A354 (499) | |
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{{#Wiki_filter:. O Qi FERMI 2 EXERCISE MANUAL FERMEX B7 l AuDust 18,1987
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FERMEX 87 August 18,1987 Page 2. , O FERMI 2 EXERCISE MANUAL TABLE OF CONTENTS Page PART1: GENERAL DESCRIPTION AND OVERVIEW SECTION 1 - INTRODUCTION . 4 SECTION 2 - PURPOSE 6 SECTION 3 - SCOPE, OBJECTIVES, AND SIMULATIONS FOR FERMEX 87 8-3.1 Detroit Edison 9 3.2 Offsite Response Organizations 12 SECTION 4 - CONDUCT AND ORGANIZATION OF EXERCISE 14 0 4.1 Exercise Rules 15 4.2 Exercise Organization 17 4.3 Exercise Facilities 20 4.4 Exercise Conduct 20 4.5 Evaluation and Critique 21 SECTION 5 - EMERGENCY FACILITIES AND PARTICIPANTS 22 5.1 Emergency Response Facilities 23 5.2 Participants 27 SECTION 6 - MISCELLANEOUS 29 6.1 Transportation 30 6.2 How to get to the Site 30 6.3 Accommodations 30 SECTION 7 - ABBREVIATIONS AND DEFINITIONS 32 7.1 Abbreviations 33 7.2 Definitions 35 PART 11: SEQUENCE OF EVENTS EXERCISE SCENARIO 39 O
FERMEX 87 August 18,1987 l Page 3 ) O 1
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l I I i i PART f: GENERAL DESCRIPTION AND OVERVIEW f O 1 l O
ugust 18 1987 Page 4 9 SECTION 1 INTRODUCTION l l l O
FERMEX 87 August 18,1987 Page 5 SECTION 1 - INTRODUCTION The Radiological Emergency Responso Preparedness (RERP) Program for Fermi 2 consists of the RERP Plan, the RERP Implementing Procedures (EPs), RERP Administrative Procedures (EPAs), and related emergency preparedness plans and procedures of Federal, State, and local government agencies. The purpose of the program is to provide protection of plant personnel and the general public, to restrict the release of radioactivity, and to secure plant systems in a stable and safe configuration in the event of an emergency situation at Fermi 2. The Fermi 2 RERP Program has the following objectives: o Effective coordination of emergency activities among onsite and offsite organizations having an emergency response role, o Early warning and clear instructions to the general public in the affected area in the event of a radiological emergency. o Continued assessment of actual or potential consequences both onsite and offsite. o Effective and timely implementation of emergency measures. o Continued n.alntenance of an adequate state of emergency. The RERP Plan describes the RERP Program, including the nature of emergency response activities and the available emergency response resources and facilities. O The RERP Plan is applicable to Fermi 2 and its environs, including a plume exposure pathway , Emergency Planning Zone (EPZ) extending 10 miles and an ingestion pathway EPZ extending 50 i miles. The 10-mile EPZ for the plume exposure pathway includes all areas within 10 miles of i Fermi 2 in Monroe County, Michigan, a small portion of the southern tip of Wayne County, Michigan, and a small portion of the Province of Ontario, Canada. The 50-mile ingestion pathway includes portions of Michigan, Ohio, and Canada. l The Michigan Emergency Preparedness Plan, the Monroe County Emergency Operations Plan, the ) l Wayne County Emergency Operations Plan, and the Brownstown Township Emergency Operations l Plan describe the emergency planning and response for the respective government agencies. The l Fermi 2 RERP Plan describes the interrelationships between the various Emergency Response Organizations. The RERP Plan provides a description of the RERP Program as required by 10 CFR 50, Section 50.47. Appropriate criteria from NUREG-0654/ FEMA-REP-1, Revision 1, November 1980, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" are also considered. lO
FERMEX 87 August 18,1987 Page 6 O ! SECTION 2 PURPOSE O 3 O l l
FERMEX 87 August 18,1987 Page 7 O section 2 - ruarose Radiological Emergency Respense Preparedness (RERP) planning for an incident at Fermi 2 is a cooperative effort Irivolving Detroit Edison; local government agencies (county, city, village, and township); the States of Michigan and Ohio; Federal Government agencies; local and provincial agencies in Ontario, Canada; and various organizations that provide support for these agencies. Emergency Planning Zones (EPZs) have been established to assist in the planning effort. Each organization has the responsibility to assure, through coordinated planning and regularly scheduled exercises, such as FERMEX '87, that it can provide an effective ernergency response 24 hours a day. O l lO
1 1 FERMEX 87 i August 18,1987 Page 8 O l SECTION 3 4 i SCOPE, OBJECTIVES, ! AND SIMULATIONS FOR FERMEX 87 O i O
FERMEX 87 August 18,1987 Page 9 I O seco" 3 - = core .o=>ccrive= >='o s'au'a=as roa.rea=ex => 3.1 DETROIT EDISON i j 3.1.1 SCOPE FERMEX 87 is scheduled cs a "ucensee-Only" exercisc to be evaluated by the'NRC. However, the Counties of Monroe, Wayne and Brownstown Township may participate. Since it is not a scheduled year for" local participation, the local Emergency Response ( Organizations will not be evaluated byfEMA. As a result, the State of Michigan will ' participate on a limited basis to pass through the intermation needed by the Cobnties to exercise their response organizations. The EXERCISE is slesigned to test Edison's " response to various plant emergencies; to establish the communications and coordination' between Edison and offsite gewernmental Emergency Response Organizations and Facilities; and address the specific responsibilities, capabilities, and interfaces of each organized element of the Fermi 2 ftE6F Man and implementing Procedures. A simulated abnormal radiologicalincident at Fermi 2 willescalate from an UNUSUAL EVENT to a GENERAL EMERGENCY. As the capabilities of Edison and the various offsite governmental response organizations are brotsght into play, the effectiveness and efficiency of Fermi 2's response wiel be indepenaiently evaluated by the NRC. O i O
FERMEX 87 August 18,1987 j Page 9 l 1 i
? SECTION 3 - SCOPE, OBJECTIVES, AND SIMULATIONS FOR FERMEX 67 J
l 3.1 DETROIT EDISON j 3.1.1 SCOPE f FERMEX 87 is scheduled as a " Licensee-Only" exercise to be evaluated by the NRC, However, the Counties of Monroe, Wayne and Brownstown Township may participate. Since it is not a scheduled year for local participation, the local Emergency Response Organizations will not be evaluated by FEMA. As a result, the State of Michigan will participate on a limited basis to pass through the information needed by the Counties to l exercise their response organizations. The EXERCISE is designed to test Edison's response to various plant emergencies; to estabhsh the communications and coordination , between Edison and offsite governmental Emergency Response Organizations and j Facilities; and address the specific responsibilities, capabilities, and interfaces of each I organized element of the Fermi 2 RERP Plan and Implementing Procedures. A simulated abnormal radiological incident at Fermi 2 will escalate from an UNUSUAL EVENT to a GENERAL EMERGENCY. As the capabilities of Edison and the various offsite governmental response organizations are brought into play, the effectiveness and j efficiency of Fermi 2's response will be independently evaluated by the NRC. j 1 l l
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FERMEX 87 August 18,1987 ; Page 10 ! O C/ OBJECTIVES The specific objectives of FERMEX 87 will demonstrate: , . l
- 1. The adequacy of the RERP Plan and its Implementing Procedures and test the proficiency ;
of the Emergency Response Organization to select and use the appropriate procedures for ! response to the emergency.
- 2. The capability of the Control Room operators to respond to a radiological incident at Fermi 2, by manipulating the simulator controls, with a minimum of exercise messages and exercise Controller interface and to use the Simulator Control Room communications to conduct an exercise. (The Simulator is not being evaluated).
3, The integrated capability of the Emergency Response Organization to respond to a simulated emergency event.
- 4. The effectiveness of the interfaces among the Simulator Control Room and the permanent Emergency Response facilities, (Operational Support Center, Technical Support Center, and Emergency Operations Facility).
- 5. The adequacy and effectiveness of the permanent TSC emergency communications network between Fermi 2, the State of Michigan, Monroe County, Wayne County and Canada.
- 6. Proficiency in recognizing, understanding, and applying the Emergency Action Levels in
' classifying emergency events.
- 7. The capability of the Simulator Control Room to properly use the procedures and forms provided for notification of the State and local governmental agencies within 15 minutes of classification of the emergency event and provide followup reports on a periodic basis.
- 8. The capability of the Control Room to notify the NRC within 1 hour of declaration of the emergency event.
- g. The capability of the Control Room to recognize when a release limit from an effluent stack is exceeded.
- 10. The capability of the TSC and EOF (when functional) to properly notify State and local governmental agencies within 15 minutes of classification of the event, and provide followup reports on a periodic basis. j I
- 11. The capability to perform timely and effective offsite dose assessment based on plant l conditions, potential / actual radiological releases, and meteorological conditions through j the use of computer software. l l 12. The capability to recommend to the responsible State officials protective actions for the general public in the 10-mile EPZ based on plant conditions, potential and/or actud radiological releases and meteorological data on a timely basis (within 15 minutes of j declaring a GENERAL EMERGENCY).
) 13. The capability to recommend to the responsible State officials protective actions for the general public in the 10-mile EPZ based on meteorological forecasts.
- 14. The capability of the Offsite RETs to locate and track the plume, to obtain air samples (if requested) and collect environmental samples and deliver them to the EOF Laboratory.
1 FERMEX 87 - l August 18,1987 j Page 11 !
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- 15. The use of personnel dosimetry by the Emergency Response Organization in the Control Room, OSC, TSC and EOF.
- 16. The capability of Health Physics personnel to establish control points at the TSC'and EOF and perform routine radiological surveys in the facilities.
- 17. The capability of Health Physics personnel to perform inplant surveys with the proper procedures and instrumentation.
- 18. The capability to authorize exceeding 10 CFR 20 exposure limits within the plant when requested.
- 19. The capability to use inplant iodine monitoring.
- 20. The capability to obtain lodine grab samples, analyze, and properly use the results in offsite dose assessment.
! 21. The capability to obtain and analyze PASS samples as may be requested.
- 22. The capability to evacuate an injured / contaminated worker from the site to a hospital offsite for decontamination and treatment.
- 23. The capability of the Offsite RETs to observe ALARA monitoring practices while performing offsite monitoring. .
O 24. To perform Assembly and Accountability within 30 minutes.
- 25. The capability to conduct a shift change of the Emergency Response personnel within the TSC and EOF.
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FERMEX 87 August 18,1987 Page 12 3.1.3 SIMULATED CONDITIONS
- 1. Simulator For purposes of FERMEX 87, the simulated power level history and other aspects such as nonoperational equipment are defined in the scenario summary by the initial Simulator conditions.
There are conditions the Simulator is not programmed to provide as described below; I
- a. The area radiation monitor (ARM) channels will respond and indicate offscale. The ARM readings are simulated within the plant according to the location of the release and the area of concern.
- b. Stack effluent radiation monitors for SGTS, Turbine, Radwaste, and Reactor Building stacks are not available from the Simulator. Releases to the environment are simulated according to accident conditions. ,
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- 2. Other {
- a. The capability to take chemistry samples for analysis will be demonstrated.
The analytical results are simulated according to accident conditions.
- b. Participation by DECO onsite personnel directly involved in responding to an emergency shall be carried out to the fullest extent possible - including the deployment of Fire Brigade, Radiological Monitoring Teams, Damage Control and Rescue Teams, and other emergency workers.
- c. All actions are to be playr.d out, as mu'.h as possible,'in accordance with emergency plan and proc idures as if it were a real emergency. Actions that ,
cannot be played out she uld be identified to the CONTROLLER stating the ( reason why the action es,nnot be continued or must be simulated. 3.2 OFFSITE RESPONSE ORGANIZATIONS ; 3.2.1 STATE OBJECTIVES The State of Michigan will have only limited participation and will not be establishing objectives. 3.2.2 WAYNE COUNTY OBJECTIVES Wayne County will have only limited participation at the Joint Public information Center and will not be establishing objectives.
FERMEX 87 August 18,1987 Page 13 3.2.3 BROWNSTOWN TOWNSHIP OBJECTIVES Brownstown Township will have only limited participation at the Joint Public Information Center and will not be establishing objectives. < 3.2.4 MONROE COUNTY OBJECTIVES Monroe County will have only limited participation at the Joint Public Information Center and will not be establishing objectives. 3 O
FERMEX 87 q August 18,1987 Page 14 O l 1 1 SECTION 4 CONDUCT AND ORGANIZATION OF EXERCISE O 1 1 l l l l l 1
FERMEX 87 August 18,1987 Page 15 O SECTion 4 - COnouCT ^~o oaOauizariOu OF exercise 4.1 EXERCISE RULES To define the " extent of play" of the exercise PLAYERS and to meet the exercise objectives, the following exercise guidelines have been established:
- 1. The exercise will be conducted August 18,1987. Since exercise PLAYERS will not be informed of the exercise start time or initiating events, a!! personnel should follow their normal routines prior to the exercise.
- 2. The exercise will commence with postulated conditions necessitating a declaration of Notification of Unusual Event and escalate to a General Emergency.
- 3. Four groups of personnel will be in attendance at the exercise and will function as described below:
A. PLAYERS are managers; supervisors; operators; engineers, chemistry, health physics, and maintenance personnel, etc., who have been assigned to the Emergency Response Organization during an emergency. These people serve to take necessary actions to mitigate, terminate, correct, and/or recover from the simulated emergency. O. B. CONTROLLERS are those designated Edison or contractor personnel who U serve an active role in the exercise by providing data to PLAYERS. The CONTROLLERS may also initiate certain actions in order to assure continuity of the events described in the exercise scenario. CONTROLLERS are the only personnel who will provide information to the PLAYERS, other inputs of information from personnel not designated as CONTROLLERS will be ignored by the PLAYERS. CONTROLLERS may also serve as EVALUATORS. C. EVALUATORS are personnel designated by Edison and the NRC to provide documentation and assessment of the exercise. They serve a passive function and will only note actions taken by PLAYERS. EVALUATORS may ask questions of CONTROLLERS to clarify actions taken or procedural concerns but may not interfere with the flow of events. D. OBSERVERS are personnel who serve no evaluation, control, or participatory function in the exercise. Visitors from NRC, state agencies, and other utilities are expected to be included as OBSERVERS. OBSERVERS shall not interfere with EVALUATORS, and particularly, PLAYERS. Questions from OBSERVERS should be directed to a CONTROLLER. Identification of Personnel: A. CONTROLLERS (Controllers / Evaluators): White on red CONTROLLER arm band. O B. EVALUATORS: White on orange EVALUATOR arm band. C, OBSERVERS: White on blue OBSERVER arm band.
FERMEX 87 August 18,1987 Page 16 (3 V D. PLAYERS: Black on white PLAYER arm band. ! l E. EXEMPT: (Personnel exempt from assembly but not accountability) White on green EXEMPT arm band. t
- 4. Personnel will be assigned as CONTROLLERS at all key functional areas to monitor (
and control the exercise in addition, they wl:1.accornpany radiological monitoring I I teams, plant health physics personnel, and maintenance repair / rescue teams.
- 5. The Control Room operators will initiate and orchestrate the events comprising the overall scenario from the Simulator Control Room. The CONTROLLER will use message forms only when necessary to place the scenario events in effect and to trigger responses from the involved personnel.
- 6. Each CONTROLLER will have the time-related plant and radiological parameters of the exercise scenario. This information will be issued to the exercise PLAYERS as appropriate.
- 7. The CONTROLLERS will not provide information to the exercise PLAYERS regarding scenario development ci resolution of problem areas encountered. The exercise PLAYERS are expected to obtain information through their own organizations and exercise their own judgement in determining response actions and resolving problems.
s 8. Plant / Monitoring Data: Data will be provided at specified intervals only. Data for
) the time period between updates and data for future times are not available to PLAYERS. PLAYERS should request from the CONTROLLERS any data which they feel !
are necessary for the performance of their functions.
- 9. Some PLAYERS may insist that certain parts of the scenarlo are unrealistic. The CONTROLLERS have the authority with the approval from the EXERCISE DIRECTOR, to 4 l
clarify any questions regarding scenario content. ; i l
" Free play
- by the players is encouraged. However, in some cases, it may be !
necessary to exercise " CONTROLLER'S perogative" of countermanding PLAYERS' actions to preserve the continuity and object ves of the exercise. The player must accept his/her word as final and proceed. Inappropriate actions can delay or speed j l up the entire exercise and impact other groups, i
- 10. Note that the scenario events are hypothetical. Any portions of the scenario j depicting plant system operationaktransients are initiated by the plant simulator ;
i events. Control Room actions or reactions involving operation of plant systems j shall be initiated via the Simulator. All exercise scenario announcements shall be j l j prefixed and suffixed with the words: "THIS IS A DRILL *. j
- 11. Postulated accident conditions will result in a simulated radiological release which )
necessitates the consideration of protective actions for the general public and will l provide the mechanism for offsite authorities to exercise their respective emergency j response plans. l l q 12. The postulated accident conditions may warrant the assembly and simulated j h evacuation of selective non-essenti_al site personnel. If required by the exercise ; scenario, emergency alarms should be sounded.
- 13. Actual and Simulated Events: During the emergency drill / exercise, certain events and activities will only be simulated rather than utilize the actual employment of resources.
1 l l FERMEX 87 ) August 18,1987 i Page 17 j 0 Simulation - involves identification and utilization of requirements and procedures short of actual employment. o Actual - movement of resources and/or physical implementation for this exercise. I
- 14. Provisions for Actual Emergency: Exercise PLAYERS, CONTROLLERS / EVAL.UATORS, l and OBSERVERS should not take any actions which would preclude maintaining emergency preparedness of the organization and community. If an actual emergency occurs.during the exercise, the Plant Control Room.has responsibility nnd authority to terminate the Exercise. Should a group terminate its participation in the exercise due to a real emergency, they should notify the EXERCISE DIRECTOR. All messages concerning actual emergency events should be preceded with "THIS IS NOT, REPEAT, NOT. A DRILL".
- 15. Communications: Communications between all exercise PLAYERS shall occur in l l
accordance with the procedures of all applicable emergency response plans. All communications, including initial telephone conversations, radio transmittals, Hi Com . announcements, etc., should begin and end with "THIS IS A DRILL, REPEAT, THIS IS A DRILL".
- 16. Compliance With All Laws: Intentional violation of any laws is not permitted during any exercise. Exercise PLAYERS, CONTROLLERS / EVALUATORS, and OBSERVERS .
n should comply with all federal, stata and local legal restrictions. - Specifically, all () local traffic laws, such as speed limits, should bs observed.
- 17. Avoid Property Endangerment: . Exercise PLAYERS, CONTROLLERS / EVALUATORS, and OBSERVERS should avoid endangering property (public or private), members of the general public or the environment.
- 18. Minimize Public inconvenience: It is not the intent to arouse or inconvenience the public during the conduct of an exercise. Also, all communications, particularly in the public relations area, should be prefaced with "THIS IS A DRILL".
- 19. Closeout of Exercise o At the appropriate point in the exercise scenario, the EXERCISE DIRECTOR will initiate termination of the exercise. The EXERCISE DIRECTOR will notify all off-site points of contact to advise that the exercise is being terminated.
- 20. Debriefing and Critique o Each LEAD CONTROLLER shall debrief exercise PLAYERS in his/her functional area.
o CONTROLLERS within each facility shall meet at the EOF and conduct a critique following exercise termination. 4.2 EXERCISE ORGANIZATION The exercise organization for FERMEX '87 will consist of the Exercise Director, the Players, the Controllers, the Evaluators, Observers and Escorts as follows:
FERMEX 87 August 18,1987 Page 18 THE EXERCISE DIRECTOR coordinates EXERCISE preparations; including the development of the EXERCISE plan, and the scenario and controller input messages. The Director controls all aspects of the conduct of the EXERCISE; prepares a consolidated evaluation and critique report at the conclusion of the EXERCISE; and prepares and follows up on an itemized list of corrective actions recommended as a result of the evaluation and critique. THE PLAYERS include all plant and other Detroit Edison personnel assigned to perform functions in the Emergency Response Organization as described in the RERP Plan Procedures, in add: tion, there are the non 7etroit Edison players of off-site Emergency Response Organizations whose roles are delineated in Section 5.0 of this Manual. The success of the EXERCISE is largely dependent upon Player reaction, knowledge of the RERP Plan Procedures, and an understanding of the exercise Plan and objectives. Some situations affecting Player action or reaction exist at the time the exercise play begins. However, most is introduced through the use of the Simulator Control Room, controlled exercise message forms, and messages generated by Players as a result of the RERP Procedures for the particular emergency activity they perform. The exercise will be conducted in the Simulator Control Room by a shift of Plant Control Room operators. Plant parameters are provided operators by the Simulator except in those cases where the Simulator is not programmed to provide the information. Players, tnerefore, are responsible for initiating actions during the EXERCISE according to procedures, responsibilities, and tasks outlined for their particular function in the RERP Plan and Procedures. O Players are reminded not to be overly concerned with the mechanics of or situations created in the EXERCISE scenario. The EXERCISE is designed to test Detroit Edison's RERP Plan and Procedures and is not concerned with the probability, feasibility, or detailed mechanics of the simulated accident. While the EXERCISE is conducted to evaluate the emergency plan, procedures and training, it is also a training vehicle for Detroit Edison personnel to practice working together and with outside organizations in a simulated emergency environment. Players should make note of any needed improvements that come to their attention during the EXERCISE and submit them to the appropriate Controller at the conclusion of the EXERCISE. Players will be identified by wearing black on white PLAYER arm bands and identification badges. CONTROLLERS are Detroit Edison personnel or other qualified personnel selected to perform functions as follows: o The Lead Controller for each facility is the individual responsible for coordinating all controller activitier within a facility. He/she is also responsible for critiquing the facility players upon termination of the exercise. , 1 o The Exercise Director and Lead Controller Team is made up of the Simulator CR, OSC, TSC and EOF controllers. Only Lead Controllers can modify exercise messages or initiate freeplay messages.
FERMEX 87 August 18,1987 Page 19 ! n o The Controllers will deliver Exercise MessaCes* to designated exercise Players at i various times and places during the EXERCISE; inject or deliver additional messages as may be required to initiate the appropriate Player response and keep the exercise action moving according to the scenarlo and exercise objectives; observe the EXERCISE at their assigned locations; prepare evaluation forms and submit written i recommendations on corrective actions to the Exercise Director prior to the j scheduled critique. The Controllers are provided with a list of instructions in the Exercise Scenario. Controllers are identified by wearing white on red CONTROLLER arm bands and identification badges. EVALUATORS are Detroit Edison or other qublified personnel who are assigned to evaluate the effectiveness of selected organizations, personnel, functions, and/or activities of the plant emergency reponse plan and procedures. Selection of Evaluators is based on expertise or qualifications to evaluate the activity or area assigned. When feasible, persons designated as Controllers for a given function will also be assigned as Evaluators of that function. Evaluators will record their observations using an evaluation form and provide recommendations on corrective actions to the Exercise Director prior to the scheduled critique. They critique exercise performance on the basis of standards or requirements contained in the RERP Plan, Procedures, and exercise messages. They take steps whenever possible to collect data on the time and motion aspects of the activity observed for post exercise use in designing system improvements. I Evaluators will be identified by wearing white on orange EVALUATOR identification I badges. When an Evaluator is serving also in a Controller role, he/she will wear a white on red CONTROLLER arm band. OBSERVERS from various Detroit Edison organization and from other organizations may be authorized, on a limited basis, to observe the EXERCISE solely for the purpose of observing exercise activity. Observers report initially to the EOF for credential review and admittance as authorized. They are provided with orientation information and appropriate I exercise publications. Escorts will be assigned to observers as required. I Observers are identified by wearing a white on blue OBSERVER arm band. Requests to participate as an Observer are made in writing and contain Observer's full name, home address and phone, and Company or organization affiliation. Requests to participate as Observers will be submitted to the Supervisor, Radiological Emergency Response Preparedness, no later than one week before the EXERCISE. EXEMPT PERSONNEL are personnel whose function is critical to the normal operation of the plant. These personnel are exempt from assembly but not from accountability. These personnel will be identified by wearing white on green EXEMPT arm bands. These personnel will be identified by the Shift Supervisor, Operations or Maintenance Engineers, or Plant Manager. ESCORTS are designated to serve as guides for Observers. Escorts are identified by name tag or other identification. f3 1
FERMEX 87 August 18,1987 Page 20 O' 4.3 EXERCISE FACILITIES Simulator Control Room The Simulator Control Room is the central point for organization of the EXERCISE and exercise messages as required and is the key to ensuring that the EXERCISE progresses on schedule. Since it is necessary that the emergency escalate to the General Emergency level to exercise off-site activities, it may be necessary to postulate q non-credible situations. The operators should accept the Scenario as developed. If . ] corrective actions could be postulated that would terminate the emergency, they should 1 be identified to the Lead Controller and indicated as a credit to the player (s). However, the scenario should progress as designed. l I The exercise Players are expected to " free play" the scenario to the extent practical. Notifications of and contact with, supervision, plant management, and off-site agencies should be made in accordance with the RERP Procedures. Since there are several off-site parts of the scenario that depend on proper messages from the Simulator Control Room, the Controller should review notification messages prior to their issuance. The Lead Controller may inject other information or change a , message in order to ensure that the drill progresses as planned. { 1 Technical Support Center and Emergency Operations Facility The Technical Support Center (TSC), for on-site activities, and subsequently the O Emergency Operations Facility (EOF), for off-site activities, become the central coordination points for the emergency response after their activation. TSC and EOF personnel should understand that if the EXERCISE is to proceed as planned and if the off-site organizations are to be exercised, it may be necessary to postulate non-credible situations. This is done to ensure that various aspects of the site and offsite emergency l response organizations are tested. TSC and EOF personnel should accept exercise conditions as given. The intended response is not to explain why a situation could not occur, but to react as if it did, if corrective actions could be postulated that would terminate the emergency, they should be noted to the Lead Controllers. l The exercise Players in the TSC and EOF are expected to " free play" the scenario to the extent practical. Notifications and contact with supervision, plant management, and offsite agencies should be made in accordance with the RERP Plan and Implementing procedures. The scenario is designed to activate onsite and offsite emergency response capabilities. Since there are several offsite parts of the EXERCISE that depend on propar messages from the Control Room /TSC/ EOF, notification messages from these contact points should be reviewed by the Lead Controllers prior to their issuance. They may inject other information or change a message to ensure that the drill progresses as planned. 4.4 EXERCISE CONDUCT The EXERCISE simulates an abnormal radiological incident at Fermi 2 and usually starts with an Unusual Event and escalates to a General Emergency and requires: accident recognition and classification; assessment of onsite and offsite radiological consequences; p) g alerting, notification and mobilization of various organizations and personnel; in-plant corrective actions; use of emergency facilities and equipment; effective use of communications; preparation of reports, messages, and records; recommending protective action; and maintaining public relations.
FERMEX 87 August 18,1987 Page 21 O' Derieo the coerse of tae EXERCISE. inciaents arise taet reauire resPoese bv offsite agencies and deployment of Detroit Edison and other radiological monitoring teams for offsite monitoring. The SCENARIO and time schedule of simulated plant conditions is contained in Part 11 -(Exercise Scenario) of this documerit. THIS WILL BE CONTRQLLED INFORMATION AND WILL ONLY BE RECEIVED BY THE NRC, EVALUATORS, AND CONTROLLERS. An actual emergency operation usually requires the extensive use of both telephone and radio. This EXERCISE, simulating an emergency, requires separate communications mersns for the Controller function. This applies to separate radio channels; otherwise, the Players could learn in advance of the situation to which they are to be subjected in testing their response capability. Because the demand for both telephone and radio communications i usually exceeds supply, all participants must be aware of this and be prepared to accept communications services which are less than desired some of the time. The telephone is the primary communications means and should be tried first. Radio is secondary; however, in some cases it may be the only means. Close cooperation and coordination between Controllers and Evaluators is essential due to the number of persons who will be assigned the dual Controller / Evaluator role. 4.5 EVALUATION AND CRITlQUE The EXERCISE will be evaluated by Evaluators, as well as the Lead Controllers who are assigned to key locations and emergency response activities. This includes the ' Emergency Response Facilities as noted in Section 4.0, as well as emergency responso activities to be evaluated. Following the EXERCISE, Evaluators and Controllers will present their findings and i critiques, as scheduled. ) Any improvements in the RERP Plan and Procedures, training, etc., that are identifled through the critique process are documented by the Exercise Director and corrccted by the organizations and individuals who have responsibility for the areas of def!ciency identified. l l l l t O u
FERMEX 87 August 18,1987 Page 22 O V ,i
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l t l l t I s l l \: , .. i SECTION 5 l EMERGENCY FACILITIES
'AND PARilCIPANTS
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' FERMEX 87 August 18,1987 Page 23 SECTION 5 - EMEf ?GENCy gt:ACILITIES AND PARTICIPANTS 8
\ , 5.1 EMERGENCY RESPONSE FACILITIES
- The Emergency Resp nse Facilities (ERFs) have been establistied at Fermi 2 to assist Control Room personnel in mitigating the consequences of accidents and responding to abnormal operating ccnditions; they are the Technical Support Center (TSC), the ,
Operational Support Center (OSC), and the Emergency Operations Facility (EOF). ! l The ERFs are staffed by the Emergency Response Organizathu and are activated as soon I as possible after an emergency is declared. The personnel injhe emergency organization are trained according to their assigned functions. The ERFs are linked by a comprehenalve communications network to provide reliable and j y timely communications between the Control Room, the ERFs and offsite Emergency Response Organi,!ations. The comrnunication network provides dedicated telephone lines, general business lines, intercoms, public address speakers, microwave communications, 1 and rista transmission capabilities. l
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Thi TGC and EOF have information centers containing the necessary up-to-date plant j i reinrds, procedures, technical specifictitions, and "as-bulh" drawings to aid emergency personnel in their technical analysis enq evaluation of emergency conditions. f l f'T U
\ 1 The ERFs provit!e adequate space to accommodate assigned personnel while performing I
their functions. There is sufficient space Nr the operation and maintenance of the communication,s and data transmission equipment, the data acquisition and display i equipment, and the instrumentation required at the respectiv,s facilities. Storage space is i provided for the neccssary emerpency t,upplies, protective equipment, plant documentation, and administrative materia!G. The TSC and EOF sach provide a consultation room and provisions for a small staff of Nuclear Regulatory Commission (NRC) personnel. Provisions include desks, chairs, and telephone lines. 5.1.1 CONTROL ROOM , The Control Room is located on the third n'or of the auxiliary building and is designed to j meet the habitability standards as describe) in Chapter 6 and Appendix H of the FSAR. The Control Room contains instrumentauon, controls, and displays for monitoring and controlling the piant operating and safety systems during the evaluation of emergency conditions and for mitigating the conucquences of an emergency. Safe operation of the reactor and plant manipulations are pe:6 armed by licensed Control Room personnel under the supervision of the Nuclear Shift Supervisor, initial amergency response measures, as shown below, are exercised from the Control l Room under the direction of the Emergency Director (Nuclear Shift Supervisor). , i o Plant operations j i(3 4 V o Direction and control I o Accident assessment 1 o Corrective actions
FERMEX 87 August 18,1987 1 Page 24 O o Radiological assessment o Protective actions # o Communications (licensee /offsite response organizations) 1 When emergency conditions escalate to an Alert status or higher, coordination of the emergency response measure shifts from the Control Room to the Technical Support Center under the direction of the Emergency Director. The Plant Control Room is the initial onsite communications center during an emergency. It has a reliable system providing capabilities to the NRC, Offsite Emergency Response Organizations, OSC, TSC, EOF, and all areas of the plant. J FERMEX 87 will be conducted from the Simulator Control Room located on the second floor of the Nuclear Operations Center (NOC). The Simulator is designed to simulate plant-conditions and provides the Control Room Staff the opportunity to demonstrate hands on manipulation of the controls under simulated plant conditions. The Simulator Control l Room has been modified to provide those communications necessary for emergency j response for use during an exercise with the exception of the direct ring (Hot lines) lines l to the NRC and offsite response organizations. 5.1.2 TECHNICAL SUPPORT CENTER (TSC) > 0 '"e Tsc i tae emeraeacv operetioae *ork eree 'or eea'or teena'ce'. eaa'aeeriaa ead management personnel; other licensee designated technical and administrative support personnel; and a small staff of NRC personnel. The TSC provides plant management and technical support to Control Room personnel and relieves the reactor operators of peripheral duties and communications not directly related to reactor system manipulations during an emergency. The Emergency Director coordinates activities in the TSC and the interfaces with the Control Room, the OSC, and the EOF. TSC personrel perform EOF functions for an ALERT, and for a SITE AREA ano GENERAL EMERGENCY as listed below until the EOF is functional: o Direction and control l o Accident assessment l l o Corrective actions { o Plant system engineering o Radiological assessment o Protective actions (inplant; offsite until EOF is activated) o Site access control o Communications (licensee /offsite response organizations) O
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'When functional the TSC becomes the primary onsite communications center during an qmergency. It has a reliable communications system providing communication capabilities with the Control Room, (or F' wetor Control Room), the OSC, the EOF, the NHC, and other offsite agencies. TtJ oystem provides for the immediate exchartge of information on plant status and operations, notifications to Federal, State, and local l agencies and intercommunications within the TSC. The communications system consists !
' of dedicated and general business telephone !!nes, d microwan system, radios, the plant l intercom, a public address system. and data transmission eqiflpment. J i
The TSC is located at the southeast enrdof the plant within the security perimeter on the i ground f!oor of a two-story office servhdis building. The TSC is habitable during postulated radiological emergencies to the same degree as the Control Room (Design s Cr'teria 19), but does not have redundant systems. TSC construction provides special q shulding and an HVAC system designed to facilitate the occupation of all necessary j
- personnel for winter and sur mer environmendsl radiological accident conditions. !
Airborne and area radia+1on monitors that read continuously and alarm Iacally are { .s l provided. In the event that the TSC becomes uninhabitable, TSC funr:tions are divided ( s between t're Control Room and an alternate facility s'uch as the EOF as directed by the j Emergen t Director. 5.1.3 OPERATIONAL SUPPORT CENTER (OSC) j The OSC is a des @nstet bsembly point near the Control Room. It is a two-story J structure located .A the n ,ita end pf the third floor of the Turbine Bulloing. The OSC 4 _ s Rovides an area for the ciordinadon of shift personnel to support emergency response
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( opr[ations without causi?g congestion in the Control Room. Personnel reporting to the 05"7 normally include the Fire Brigade, the Damage Control and Rescue Team, the brennel Monitoring Teams, the Onsite Radiological Emergency Teams, instrument 6( (s ,, s &chnicians, engineers not assl3neo to the Control Room or other ERFs, and general b n,dntenance personnel, ta required. Tt'e OSC Coordinator integrates OSC activities and l disTches emergency personncJon asdgnments as directed by the Emergency Director, The OSC has deoicated telephone lines so both the Control Room and the TSC and a dial 1 telephone for communications with other onsite, a well as offsite, locations. Portable raoics are also P,Vailable to complemertt or serve aF DaCkup to the telephones. in the event that the OSC becomes uninhabitable, an area at the. north end of the machine shop is designated as the alternate OSC. The machine shop is located on the first tioor of the Office Services Building. 5.1.4 EMERGENCY OPERATIONS FACILITY (EOF) The LOF is a command post for the overall management of the offsite emergency
' ~ response including the coordination of radiological and environmental assessments, the s~ determinatfori of recomtrandeo brotective actions for the public, and the managemeat of
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I FERMEX 87 August 18,1987 Page 26 o Public information o Communications (llcensee/offsite response agencies) I The EOF is in the basement of the Nuclear Operations Center (NOC) and is approximately 6000 feet southwest of the Fermi 2 plant on owner-controlled property. The EOF will have the NOC as a supporting facility which includes the plant simulator, plant training l offices, training classrooms, space for news reporters, etc. Access is available to the ) facility from two directions via roads under the control of Detroit Edison. Additionally, the Technical Assistance Center which houses the engineering staff is accessible by dial-up ) phones. l l The EOF has been designed for habitability in the event of a postulated accidental radioactive release from Fermi 2. The design includes shielding (protection factor of 20), an HVAC system with HEPA filters, and airborn radioactivity and area radiation monitors that read continuously and alarm locally to assure that personnel exposures to l radiological hazards do not exceed 10 CFR 20 limits. I The Emergency Officer is responsible for the Licenseo's offsite emergency response and is the Licensee's Senior Management person onsite. The Radiation Protection Coordinator is responsible for offsite radiological and environmental assessments. The Environmental Assessment Team performs radiological dose assessment and projection functions using i the ERIS and associated software and procedures. A microcomputer dose assessment software package is an available backup method. The Radiological Emergency Team (RET) Coordinator coordinates the Offsite RET field surveys by radio, as directed by the Radiatior: Protection Coordinator, from the radio room in the EOF. Direct radiation and contamination readings are transmitted promptly back to the RET Coordinator. The EOF counting laboratory is available for the analysis of environmental samples collected by the RET, as well as a backup f acility to the in-plant laboratories. An extensive communications system is provided in the EOF, which includes communications to the Control Room, the TSC, the Offsite RETs, the NRC, the State and local Emergency Operations Centers (EOCs), and Intercommunications within the EOF. The system consists of dedicated and general business telephone lines, a microwave system, portable radios, the plant intercom, a public address system, and data transmission equipment. An alternate EOF is located at the Wayne-Monroe Division Headquarters,22 miles nortiawest of the Fermi 2 site. The facility has adequate communications equipment and sufficient space to accommodate the additional personnel required for continuity of dose projection and d3 cision-making capability, including coordination of the offsite teams. Portable equipment is provided for the personnel to perform their assigned functions. 5.1.5 JOINT PUBLIC INFORMATION CENTER (JPIC) Since the plant operations and technical staff must remain isolated from tasks that p distract them from their immediate responsibility of containing the emergency and V restoring the plant to normal operating conditions, additional Detroit Edison personnel have been assigned to organize and implement all communications measurec that serve the news media; the public; company employes; and public officials from Federal, State, and focal levels.
FERMEX 87 August 18,1987 Page 27 A Company officer who has access to all necessary information (Group Vice President or alternate) has been designated as the spokesperson for Detroit Edison in the event of an emergency at Fermi 2. This spokesperson and his/her staff have communications access to Detroit Edison's emergency centers. Information is released to the news medja via this person through the Joint Public information Center (JPIC). In order to ensure that accurate and consistent information is presented to the public, a JPIC office will be located at the Monroe County Community College, The public. i information officers from Detroit Edison and Federal, State, and County groups may l congregate here to review all public information releases. 5.2 PARTICIPANTS Participants are listed as onsite Detroit Edison FERMEX '87 and off-site (all other). 1 5.2.1 ONSITE DETROIT EDISON COMPANY o Fermi 2 o Simulator Control Room (SI'R) o Technical Support Center (TSC) o Operational Support Center (OSC) ) O o Emergency Operational Facility (EOF) o Joint Public Information Center (JPIC) o Detroit Edison General Offices o Emergency Response Teams Onsite and Offsite Radiological Emergency Teams (Onsite/Offsite RET) Damage Control and Rescue Team 4 Fire Brigade Nuclear Security Force 5.2.2 OFFSITE (OYHER THAN DETROIT EDISON COMPANY) Federal o Nuclear Regulatory Commission (NRC) State of MichlDan o Limited participation to provide informatiu6 :o Counties. ' O Canada (informal Participation) o Province of Ontario, Ministry of the Solicitor General, Emergency Planning
FERMEX 87 August 18,1987 Page 28 O O o Ministry of Labor o Local Canadian government , Local (informal Participation) o Wayne County o Monroe County o Brownstown Township o Seaway Hospital, Trenton, MI o Mercy Memorial Hospital l 1O i l 0
I l FERMEX 87 l August 18,1987 ); Page 29
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O ! l a i I i l l l SECTION 6 4 1 I MISCELLANEOUS O ; I (
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f FERMEX 87 August 18,1987 Page 30 A V SECTION 6 - MISCELLANEOUS 6.1 TRANSPORTATION Air: o Detroit Metropolitan Airport (30 miles from Fermi 2) o Toledo Express Airport (45 miles from Fermi 2) O Persons traveling by air to Fermi 2 are recommended to arrivs at Detroit Metropolitan Airport. It is closer to the plant and travel to Fermi 2 via auto is relatively easy. Bus: o Direct bus service by Greyhound and Trailway to Detroit, Toledo and Ann Arbor. Train: o Amtrak connections in Detroit, Toldeo and Ann Arbor 6.2 HOW TO GET TO THE SITE Car; o The plant is 35 miles southeast of Detroit and 27 miles north of Toledo. o Fermi 2 is located approximately 5 miles from I-75 via the Newport Road Exit or the Nadeau Road Exit. Persons traveling I-75 South or 1-275 South may choose to use the Newport Road Exit or persons traveling I-75 South may also choose to use the Nadeau Road Exit. l If using the Newport Road Exit, take Newport Road (Swan Creek Road) east to North Dixie Highway south. Fermi Drive is about two miles on your left. If using the Nadeau Road Exit, take Nadeau Road east to Ncrth Dixie Highway north. Fermi Drive is about three miles on your right. l 0 Persons using 1-75 North should exit onto North Dixie Highway north (turn right). Fermi Drive is about 5 miles on your right. 6.3 ACCOMMODAT.ONS o Detroit Metropolitan Airport (approximately 30 miles from Fermi 2) Abbey Inn 8230 Merriman Road h (313) 729-7600 Hilton Airport inn 31500 Wick Road 1 (313) 292-3400
FERMEX 87 August 18,1987 Page 31 Holiday Inn 31200 Detroit Industrial Expressway (313) 728-2800 Marriott Detroit Metropolitan Airport (313) 941-9400 Howard Johnson's 45945 Willow Run Expressway (313) 697-9144 Ramada Inn 8270 Wickham Road (313) 729-6300 Sheraton Motor inn Airport 8600 Merriman Road (313) 728-7900 o Monroe (within 10 miles of Fermi 2) Holiday Inn 1225 North Dixie Highway (313) 242-6000 0 - Howard Johnson's 1440 North Dixie Highway Toll Free: 1-800-654-2000 (313) 289-4000 Knights inn 1250 North Dixie Highway (313) 243-0597 o Trenton (approximately 20 miles from Fermi 2) Best Western Hotel 21700 West Road (313) 676-8000 Toledo Express Airport The Airport is located 18 miles from downtown Toledo. It is another 27 miles to Fermi 2. Persons arriving at Toledo Express Airport would be best served by hotels in downtown Toledo or in Monroe. l
FERMEX 87 August 18,1987 Page 32 0 4 I SECTION 7 ABBREVIATIONS AND DEFINITIONS O , I
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FERMEX 87 August 18,1987 Page 33
- $ECTION 7 - ABBREVIATIONS AND DEFINITIONS 7.1 ABBREVIATIONS AB -
Auxiliary Building APRM - Average Power Range Monitor ARM - Area Radiation Monitor BWR - Bolling-Water Reactors CAS - Central Alarm Station CBX - Computerized Branch Exchange CCTV -
' Closed Circuit Television CHRRM - ' Containment High Range Radiation Monitor CR -
Control Room CWH - Circulating Water Pump House DID ' Direct inward Dialing EBS - Emergency Broadcast System ECCS - Emergency Core Cooling System EDG - Emergency Diesel Generator EECC - Employe Emergency Communications Center O escw EMD Emerae"cvea"'ame"tcooi'"o
- ter Emergency Management Division ENS -
Emergency Notifications System (NRC) EOC - Emergency Operations Center EOF - Emergency Operations Facility EPA - Environmental Protection Agency EPAs - Radiological Emergency Response Preparedness Administrative Procedures EPs - Radiological Emergency Response Preparedness implementing Procedures EPZ - Emergency Planning Zone ERF - Emergency Response Facility, ERIS - Emergency Response Information System FEMA - Federal Emergency Management Agency FRERP - Federal Radiological Emergency Response Plan , FSAR - Final Safety Analysis Report GE - General Electric GMJ - General Main:enance Journeyman GPM - Gallons per minute GSW - General Service Water GTOC - General Training and Orientation Center HPCI - High Pressure Coolant injection HVAC - Heating, Ventilation, and Air Conditioning l&C - Instrument & Controls h INPO IRM Institute of Nuclear Power Operations Intermediate Range Monitor JPIC - Joint Public information Center JPIT - Joint Public information Team I L__---_.---___-------_ - _ _ - - - -
' FERMEX 87 August 18,1987 Page 34 O LOCA -
Loss of Coolant Accident LPCI - Low Pressure Coolant injection MBT - Michigan Bell Telephone Company e MEPP - Michigan Emergency Preparedness Plan i MREM - Millirem
' MSIV -
Main Stream isolation Valve I UCl/cc - Microcuries per cubic centimeter uCl/g - Microcuries per gram uCl/kg - Microcuries per Kilogram uCi/l - Microcuries per Liter uCl/sec - Microcuries per second NASS - Nuclear Assistant Shift Supervisor NOAA - National Oceanic and Atmospheric Administration NOC- - Nuclear Operations Center NRC - Nuclear Regulatory Commission NSO - Nuclear Supervising Operator NSRG - Nuclear Safety Review Group NSS - Nuclear Shift Supervisor OSC - Operational Support Center OSEOC - On-Scene Emergency Operations Center . OSRO - Onsite Review Organization PAG - Protective Action Guldeline PRM - Process Radiation Monitor PRMS - Process Radiation Monitoring System RB - Reactor Building RBCCW - Reactor Building Closed Cooling Water RERP - Radiological Emergency Response Preparedness RET - Radiological Emergency Team RHR - Residual Heat Removal RWB - Radwaste Building SAS - Secondary Alarm Station SGTS - Stand-by Gas Treatment System SRV - Safety Relief Valve SSE - Safe Shutdown Earthquake TAC - Technical Assistance Center TB - Turbine Building TLD - Thermoluminescent Dosimeter TSC - Technical Support Center O
FERMEX G7 August M,1987
'P' age 35 l
l (Vh DEFINITIONS ALERT: The second level of emercancy classification. indicates events are in progres which involve actual or potential substantial degradation of plant safety levels. , ASSESSMENT ACTIONS: Those actions taken during or after an accident to obtain information necest.),ry to determine if protective action recommendations are warranted ATMOSPHERIC STABILITY CLASS: (P::::qu!!l Stability Classification) A method of classifying meteorological conditions, used for calculating plume dispersion. I CLADDING: The outer meta! jacket of nuclear fuel rods. It prevents corrosion of tin ) fuel by the coolant and the release of fission products into.the coolant. Thc most ! common cladding material is zircaloy, a zirconium alloy. COLD SHUTDOWN: The condition of e reactor when the fission procass hr been halted by the insertion of control rods irito the core and decay heat it the core has decreased to the goint where natural. circulation can keep the coolant water below the ) boiling point (212 F or 100 UC) et atmospheric pressure. 1 CONDENSATE: Water that has been condensed from steam after passing threagh tin. j turbine to the condenser. This high-purity water is then pumped to the reactor for ] reuse. ) CONDENSATE BOOSTER PUMPS: Pumps located between the condensate pumps and l ' the main feedwater pumps CONDENSATE FILTER /DEMINERAllZERS: Devices which remove dissolved minerals l from the water of the condensers prior to being returned to the core. CONDENSATE PUMPP Pumps in the reactor fe*dwater system that pump water from the condensers to tl , condensate filter /demineralizors. CONDENSER: A dewca. tim coc.!:: stetra to water after the steam has passed through ; the turbine. j h CONTAINMENT: The structure housing the nuclear reactor and its supportive equipment. ItJ! designed to contain radioactive solids, gases anci liquids which might i be released from the reactor system in an accident. CORE DEGRADATION: impairment of the central part of the reactor that contains the fuel assemblies, usually resulting from reduced levels of coolant or breach of fuel cladding. CORE MELT: The situation in which all tar part of the corc becomes overheated to the l extent that the fuel melts through the cladding. 1 CORRECTIVE ACTIONS: Emergency measures taken to terminate an emergency ! situation at or near the source of the problem to bring the plant to a stable condition and to prevent an uncontrolled release of radioactive material or to reduce the magnitude of the release (e.g, shutting down equipment fire fighting, repair and damage l control). DECAY HEAT: Heat generatr D. eng rad active products of the fission process.
FERMEX 87 August 18,1987 Page 35 .O V 7.2 DEFINITIONS ALERT: .The second level of emergency classification. Indicates events are in progress which involve actual or potential substantial degradation of plant safety levels. , ASSESSMENT ACTIONS: Those actions taken during or after an accident to obtain I information necessary to determine if protective action recommendations are warranted, i ATMOSPHERIC STABILITY CLASS: (Pasquill Stability Classification) A method of classifying meteorological conditions, used for calculating plurne dispersion. CLADDING: The outer metal Jacket of nuclear fuel rods. It prevents corrosion of the fuel by the coolant and the release of fission products into the coolant. The most common cladding material is zircaloy, a zirconium alloy. COLD SHUTDOWN: The condition of a reactor when the fission process has been i halted by the insertion of control rods into the core and decay heat in the .: ore has l decreased to the goint where natural circulation can keep the coolant water below the boiling point (212 F or 100 UC) at atmospheric pressure. 4 1 CONDENSATE: Water that has been condensed from steam after passing through the turbine to the condenser. This high-purity water is then pumped to the reactor for reuse. 1 CONDENSATE BOOSTER PUMPS: Pumps located between the condensate pumps and the main feedwater pumps. f CONDENSATE FILTER /DEMINERALIZERS: Devices which remove dissolved minerals from the water of the condensers prior to being returned to the core. j CONDENSATE PUMPS: Pumps in the reactor feedwater system that pump water from the condensers to the condensate filter /demineralizers. CONDENSER: A device that cools steam to water after the steam has passed through the turbine. CONTAINMENT: The structure housing the nuclear reactor and its supportive equipment. It is designed to contain radi.oactive solids, gases and liquids which might be released from the reactor system in an accident. CORE DEGRADATION: Impairment of the central part of the reactor that contains the fuel assemblies, usually resulting from reduced levels of coolant or breach of fuel cladding. CORE MELT: The situation in which all or part of the core becomes overheated to the extent that the fuel melts through the cladding. CORRECTIVE ACTIONS: Emergency measures taken to terminate an emergency situation at or near the source of the problem to bring the plant to a stable condition and to prevent an uncontrolled release of radioactive material or to reduce the magnitude of the release (e.g., shutting down equipment, fire fighting, repair and damage control). DECAY HEAT: Heat generated by decaying radioactive products of the fission process.
FERMEX 87 August 18,1987 Page 36 O V DESIGN BASIS ACCIDENTS (DBA): Hypothetical accidents evaluated during the safety review of nuclear power reactors. Plants are required to have safeguards that will ensure that radiation releases off-site will be within NRC limits should any of these accidents occur. DEW POINT TEMPERATURE: The temperature at which a vapor begins to condense. DRILL: A supervised instruction period aimed at testing, developing and maintaining skills in a particular operation. EMERGENCY ACTION LEVELS: Specific information about plant status, such as that received from instruments and alarms, indicating an abnormality in plant operations. The information is categorized as an initiating condition, which is used in turn to determine the appropriate emergency classification. EMERGENCY CORE COOLING SYSTEM: A series of backup safety systems designed to dump thousands of gallons of cooling water into the reactor, thus preventing overheating of the core in the event the normal core cooling system fails. EMERGENCY PLANNING ZONES (EPZ): The land areas encompassed within 10 and 50 mile radii of the nuclear plant, in which protective actions may be necessary to protect the public in the event of a nuclear plant accident. The 10 mile zone is referred to as the Plume Exposure Pathway; the 50 mile zone is termed the Ingestion Exposure Pathway. O exeacise: ^ co#troiiee eve #t *"ich teste the i#teoreteo ceneoiiitv emo e meior nor4'o# of the basic elements existing within emergency preparedness plans and organizations. FEEDWATER: Condensate water that has been reheated and is pumped to the reactor for steam production. FISSION PRODUCT BARRIERS: Structural deterrents to the release of radioactivity into the environment. The three primary barriers are: (1) the fuel cladding, (2) the reactor pressure vessel, and (3) the containment. FUEL DAMAGE: The failure of fuel rods (cladding, structural or fuel material) which may or may not result in the release of the radioactive fission products trapped inside the fuel rods. Fuel damage can occur without a melting of the reactor's uranium. FUEL MELT: The melting of some of the uranium oxide fuel inside a reactor. Melting occurs at 5000UF and above. GENERAL EMERGENCY: The fourth and most severe level of emergency; declared by the utility if an incident at a nuclear power plant results in potential or actual radiation release that could affect the general public. HOT SHUTDOWN (OR HOT STANDBY): The situation in which the control rods have been inserted to bring coolant below the boiling point but reactor vessel pressure is not reduced to atmospheric pressure. INGESTION EXPOSURE PATHWAY: The principal exposure from this pathway would be O from imoestioa of co#temimetee weier or foods. soch es miix or fresh veoeteeies. Tae time of potential exposure could range in length from hours to months. L__________.__
s FERMEX 87 August 18,1987 Page 37 O INGESTION DOSE: The amount of radiation which concentrates in the vital organs of the body, usually through ingestion of contaminated food supplies or drinking water. ISOLATION (OR CONTAINMENT ISOLATION): The closing of all penetrations to containment to contain any radioactive materials which might be released in a nuclear accident inside the containment building. LOSS-OF-COOLANT ACCIDENT: An accident involving a broken pipe, stuck-open valve or other leak in the reactor coolant system that results in a loss of cooling water, l MAXIMUM PERMISSIBLE DOSE: An estabilshed limit on the radiation exposure a person can legally receive from any source of radioactivity. MET TOWERS (METEOROLOGICAL TOWERS): Steel towers located on-site which are equipped with instrumentation to measure wind speed and direction, air temperature precipitation, dew point temperature and sigma theta. OFF-SITE: Areas which lie outside the owner-controlled area. ON-SITE: Areas which lie inside the owner-controlled area. OWNER-CONTROLLED AREA: The land area surrounding a nuclear plant which is owned and secured by the utility. PARTICULATE: Minute radioactive substances suspended in air or water. PLUME EXPOSURE PATHWAY: The principal exposure sources for this pathway are (1) whole body external exposure to gamma radiation from the plume and from deposited material and (2) inhalation exposure from the passing radioactive plume. The time of potential exposure could range from hours to days. POST-ACCIDENT SAMPLING: The acquisition of liquid and gaseous samples from primary containment for the purpose of determining and monitoring reactor status under accident conditions. PROTECTED AREA: That portion of the owner-controlled area which includes in part the Reactor Building, Auxiliary Building, Residual Heat Removal Complex, and Turbine Building and to which access is restricted. PROTECTIVE ACTIONS: Those emergency measures taken after an accident or an uncontrolled release of radioactive materials has occurred, for the purpose of preventing or minimizing radiological exposures to personnel that would likely occur if the actions were not taken. PROTECTIVE ACTIONS GUIDELINES (PAGs): Projected radiological dose or dose commitment values to individuals in the general population, which warrant protective action following a release of radioactive material. Protective actions would be warranted provided the reduction in Individual dose expected to be achieved by carrying out the protective action is not offset by excessive risks to individual safety in taking protective action. RADIOLOGICAL EMERGENCY TEAMS (RETs): Two-person teams responsible for i monitoring radiation levels in the environment and collecting soll, air and water samples for laboratory analysis. E__ ___ _ _ _ _ _ _ _ __ _ _ _ _ _ _ . _ _ _ i
FERMEX 87 August 18,1987 ; t Page 38 TURBINE BUILDING: A structure housing the steam turbine, generator and much of the feedwater system. UNUSUAL EVENT: The first level of emergency classification, where. events ard in progress or have occurred that indicate a potential degradation of plant safety levels. No releases of radioactive material' requiring offsite. response or monitoring are expected unless further degradation of safety systems occurs. 1 I l f
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a e . r r d e i 2. pl l E t 0 a9 d e a r r sd ced I s e t a d s ar 4 m a af uo t 2 c u t nra l m s - s i e r e rw oo r ro ss s P d ec n s p t t un oE e I rs is h % ei r0 no t r . C eal L t i 0 nn o0 Ui g 5 P wee vl 0 i o p7 t s n r H ol u m d ra 1 l m e0 si ni e4 pef a 7 S e em pr ms r es r o od w t r e e t ue t m ir o3 n r t 8 T a a aa yo ap t o p e o ph S N r Sh eg rr l ac n t t at X E t r t f tf cs cc ro r cg n E V f m o sf s ee ia oi e a g i M E o ed t o i1 d m f t t v e% n a R t e c n m3 u ie ca E Y % s : a d R5i M E id e1 S s t d ac a - F 5 y . e an h - S s oa ei n K 8 S r R Ma CI N a Nm Rf I oo o Y R A %7 M 20 M 0 U , S 36 3 6 r 00 0 0 f f , , , E 25 2 5 V 00 0 0 E 1 4 1 1 4 R 00 0 0 0 O - - - - - T 77 3 7 7% A 77 5 7 72 L 7 1 1 0 1 % 1 U 1 - - % - - 2 - M - 1 1 2 1 1 6 1 I C 22 4 2 27 S I DD@ - E De D O I N R I A M NE 0 5 0 0 0 EM: 3 4 2 3 2 CI R 0 0 1 1 2 STH 0 0 0 0 0 E M O I I RT RU AOK NHC 0 0 5 0 0 0 E O 0 3 4 2 3 2 C4L 7 7 7 8 8 9 S2C 0 0 0 0 0 0
w n m r r i t y n a h o a5 t c gr i h n c t m a a . nd c o i mf i e e i d i e n u o d r . d d o e p t r o S a s o at v o a u m 2 r s e m e i n i s t s t rd e i d o n ne e g e e a . c e c: / a l o n c l s r r s et e r c i va i x o t i oa r n l t EP l e s r c t e e a D e a i a e il ei c / v i m a e t r ne b s s C l . . d v m s or n p / a d d a e e e o M l a u B v e e r t i t o t s l r / p p s l s t ne i t n A n p p a e y u s os w o o i i e n r s a t i a e i l i r r r i f t g sh t e t t t a a o n m i a mt a n a m t o e h i n r i n l 2 2 t i t s d o af d a o A B n h n t s ai l o a h s / / e g e a y n R s a r c i 1 1 m i p l S o s t A B n h o i i ei t l e e e i o t t t gf nu n n n s s a s n n a n . as i i i r r t t e e e l aon c e l l l o o n v v m i R t o i r t t o e l t t i f m m m a a c u a . g a n h et i e a a a u u d ver n e e gua nh e e . e t t I i r v i d v gt t t e t c c I a m f u d T H i i s sl s a a / es l m rt s s . a . I r i s i s o tH c a np nc np p p c l e u a o n/a g ii i s ii i i v s er r p b G R es mdV nm ar ap ar r r i i o M t M u Mt T T D S T r o yl r o y l o naR wo b i RS oR - - - - - - N t t e t d r a l E c es c n t t 0 m l l 2 3 6 3 4 3 V a f s a a n n0 o oo 8 8 8 7 7 4 E e a e e t o o8 r f r D D D D D D R S v R S C C6f t 3 3 3 3 3 3 Y en E h o K o o o o o o TC o o o o o o 0 0 1 0 0 1
% X 02 3 73 >
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C R 23 P O - - R T 77 1 A 77 2 L 1 1 D U - - - M 1 1 F I 22 D S DD T O I N R I A M NE EM : CI R STH E M O I I RT RU AOK NHC E O C4 L S2 C
y i d l f Y E e r w n i a n e C m a5 a b t w l N L n m e a s o o E Ai C mf c s t d h G R a I uo n t n m w R E t C S a n u og E N n R t 3 d r e o c on r M E o m Ri H E G c n n e o n c l / o e g c r a l o . R A ay va c e oo l 1 E r s EP a v d r c o R ea p n o g n a t nr r t d e A raim l o i y oo n e E l r e
. l Cf o c T c p v d T a l c x I e e e . R c b es e S df d m t E o m hd l o r r L l e T o a s a y k a a A s h u l as a t
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e
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- S l s o5 mo u n t i n w T c h n - ol r u a r1 D e o G e ot nP cl o f i o0 t .
L S d ti aE o t d t 1 yo k w sf d a . c - c p a I I r e rh i o e r e eP n e _ I I o d e ot e t r g rE ea l ac
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_ t t i nh i _ I I c e mn c w wt n l nk Dh r n e _ a e o w c i a t eo nt v v r . sd r e df o e d e yi m i i i i9 nr ic l o d d l l c w Ed l _ D D D oo D n o w i n e S T - - ya b i c t c yd a oy c n l o i s ul bl ee gc es h a m ai N 4 cT aa c r a: B e r n Tb e E n no V 4 7 1 D e1 c i n ec r r I C CI V C rw oy ea t D g0 gc ot o PCR S md s E. 7 f i t ct T t r E r : _ 2 1 r1 i r a c ec HRS cd o E Cb e Y e - t C al a e a ec T I E o o mP EE oR NN mn eee h eo h c O C K Ei R s r ooo T R t T a N R _ 0 0 1 1 R 0 O - T 2 A 5 L 0 U - M 1 I S 5 E O I N y R I g A M NE y 5 0 0 EM : z 3 0 4 CI R 2 3 3 STH o 0 0 0 E M O I I RT v RU y AOK y NHC 5 0 0 E O p 3 0 4 C4L 9 0 0 S2 C 0 1 1
a n e e a5 m d o i a e el i t I nD U C so ii voe R nth mf t t s e n iO R t i t e uo ua r o v R N F a r h S h r s M i yP Od oir t 4 st e ae D c e E n t ao . t hb n nN h e pf ne ne eg on t e , o o r o eO gI t em me a r n i c i h m n va p et t f rS d t o e o na EP s v a eS n c t di ot l l l s i 3 mI a f e nt ss il ae d EF i r r2 a ri ae vu a l n i c es f w n R e l E a rn aai ps y ni n aE g oo p d a 7 r ot s n rR i t i ed n d 0d i n s a eH h ct r ni el 0 t o e h nT c ec a r a F n ac c C e i r a a e uc i l o GF M i ns . ji 1 om r M O D e sou L nd 53 s a P X a f v eif A i e ET i e A S o yi h t N m t t sS e ct can O n ed d s n n eO nc t l w I ae va r e o rL t . ee aoo T t l e af u a a0 gt psl C fi al oo l c l . t 9 r o sib N os v y b f c c9 S2 er . i U f t t f / e - mpn dC e F df nl o p un . E c db eP E a I h eo ouo eg u a hE ( ag rCt d i i p ) rT t i oR e f g t u C mn 4 0 o o rsh t f r i n as I aa 4 0 t 1 ot eec aeo a ti _ l C l D 8 c0 t cki nh l or _ or Rl f 3 e1 g i aM i t e c ni _ s e l ( g r - s n f m d s e u i w .at n iP ni f f rf u d mq _ S d p . o 8 0 me sl o r i d DE od i r O) o l ooa o c s oe or _ r f r A 0 n t a yh . t o yae C e i r f a r5 F ai a . e ct S ac cnt s e g E oo0 - i e r niR cc noa C uh F l n _ V E b t 1 no-1 d e cl B ewe g i a eit S at . O oi _ 5 nh nb I f gt S O c e E rd _ Y I mX E at u u no 2 reR ecR i e t d r c ene eet l ev e t l ni _ E nr T mnA oa muh hh aa h ou K o o AT C E aB Nm Ef t Tt gv T CB n nw h oo t il i t b % wacd r 0 0 7 ino l 0d at @ 0 n a Fif c 9 R - fi 2 O 1 nod - T 5 o n 7 A Ei si 7 L t t 1 U li h e - M i s gs 1 I aoiu 2 S F plf D O I N R I A M NE 0 0 5 EM : 5 0 0 CI R 3 4 4 S T,H 0 0 0 E M O I I RT RU AOK NHC 0 0 5 E O 5 0 0 C4L 0 1 1 S2 C 1 1 1
B h m r p c M
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r t gt p t t n e n o t a5 o f n n o o k n r a m t o Ci se o m c a o t mf c I vk g c t c n d uo a e C r ca n d o e S e s R eek s e e l e c z 5 R u sh a i p r l h i t a eb ce o u i t e g ne eg o c h o l n j w h r t t m o s n m t e va EP d t e f oea mam s r t r i e g o r o n e e a ort e e o h n f t - h g f t p p t a e es e c i y i h d d r t t tlh d r w c e e a p s i et e e t t s e nn l r r l t a r i s v i nfb u e a f r o . i n coI i j t t i a p 7 s d i i s d n n i h p e 0 t m o vre .a u i C e p s s e r 0 u
- s. Fh a t epe t o a d - s e h g .de a l h e n 1 t d t enen h o . 0 b . a 57 e d avi t . rr r 0 A E0 e . h nul l m e t o o 3 . o5 d 0 un c i l f ar d t nt f 1 C t0 e eF co ss t
a see c vet e i s oa C n e S 1 r v-er p i dT d - i l 1 l rh ne f i t . n nX a a5 re s ept od i n rd il ad u p vE . p i v i t o or sa n on e s l d eymt e o t o u 5 a f o r rd e od l aoab n s oo sd 4 i on t re s mrl e MC ti 1 F st s f a a t r i n f ol s v rv 1 O i a i n nu oj on sl i i tC ai - E r rr i m i oeii r aS pd n 3 t 3 ee m cn a t i g w m r O en ee Te T l t r i e at ad o a m di eh n l n e S d ne t . n iak rt o ao wt d e d oe t U d caaa r e et ed t ap a rC I av d o aoeoe c t c e en e e t e E o ni Rl l b s l n 3 nt Bi ll l nl s V E em ge ot o a rT aa l oo i ca : r l i l n : re r C r c ar el E t u ad ui E ow o t r Y m so T n b pa b m T t y t en e E ao s O o m ee ma O or o h o x K Dt Ai N C A Rl At N Md M TC E R O T A L U M I S O I N R I A M NE 5 5 0 5 0 5 5 5 EM : 1 3 4 4 5 1 2 4 CI R 4 4 4 4 5 6 6 6 STH 0 0 0 0 0 0 0 0 E M O I I RT RU AOK NHC 5 5 0 5 0 5 5 5 E O 1 3 4 4 5 1 2 4 C4L 1 1 1 1 2 3 3 3 S2C' 1 1 1 1 1 1 1 1 IL
4 O 0 l I MESSAGES f t
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x...._ SCEl:ARIO FERl'E1 C7 CLOCM TIME = 0700 IfESSAGE PC. 00 SCEMARIO TI!;E = 0900 ( . FERMI - 2 E!:ERGEi:CY PREPAREDNESS EXERCISE MESSAGE FOPl! *: MESSAGE FOR: !!uclear Shif t Supervisor
!!ES SAGE: Announce over HIC 01::
Attention all personnel, Fermi 2 is conducting an Er.icrgency Preparedness Drill from the Simulator Control Roor in the I?uelcar Operations Center. All personnel tre pcrtic pcnte. Plcnt announcements stcting "THIS IS A LRI.I.I." crc for 6:il; participants. If c rec. cvent si:ould occur, recponse w;11 be directed fio. ti.e Cor.tz o; Eocu for the cctuc:. crergency. e FC), C0;;Ti r: M Lf; C; LY: CO :TROLLEE 1:C'iES: L l 1 i ACTI0ll EXPECTED: O
SCEIARIO- FER4EX 87 CIOCK TILE = 0730 MESSME 10. 02 SCDWIIO TITE = 0030 0 FEM 4I '
- l DEiGDCY PREPAREDNESS EXETISE MESSAGE FOR1 MESSME FOR: Simulator Console Operator
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MESSME: Acting as System Supervisor request Fermi to increase j generator electrical output to 1100 Mie or 100% reactor J pwer. l 1 1 i i l *********************************** O FOR CONTROLLER USE ORY: 1 ( l l CO TfICLLER.IDTES: )! ACTION EXPECfED: Control room acknowledges request and commences to. increase reactor power and generator loading. ,
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<[CLOCKTIME= 0818 ' .(. ' jk i ,-(
MESSAGE NO. CHEMISTRY TECHNICIAN' SCENARIO TIME = 0118 FERVI-d', k ii , EMERGENCY PREPAREDNESS _Elly.CISE MESSAGE FORM MESSAGE FOR: Chemistry Techniciab d'
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MESSAGE: The reactor coolant sample taken at 0700 has 4.2 micro ~ . curies per gram dose equivalent I-131. #j>
.s A, , -
. t l Noble Gases also' indicate slightly higher than' normal.,
0 -!>
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w (L FN 1 O p, FOR CONTROLLER USE ONLY: [k i i CONTROLLER NOTES: Give to Chemistry Technician in lab at above time. O t ACTION EXPECTED: Report results to Control Room. (
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j.t. 3 f il'n f n, . 'a - i i SCENARIO FERMEX 87 CLOCK TIME = 0830-1000 MESSAGE NO. CHEMISTRYCOUTNhLER-SCENARIOTIME= 0130-0300
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O' FERMI - 2 , EMERGENCY PREPAREDNESS EXf,RCISE MESSAGE FORM l: MESSAGE FOR: Chemistry Controller - MESSAGE: Prdvide the.following information to the. Chemistry
. Technician'if r confi matory sample is drawn for I
; iodines.
.-- 1. If reactor power is held constant:
, o 4.17 micro curies per gram dose equivalent I-131.
' t.
. /g 2. If reactor power is decreased:
-o 4.06 micro curies per gram dose equivalent I-131.
t
.(Note:
General area for the normal sample station will (i increase to 500 mr/hr after flow is established to obtain the sample. -
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FOR CONTROLLER USE ONLY:
/
CONTROLLER'F0TES: ACTION EXP,ECTED: Results reported to the Control Room. I i' t i 1 O E
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SCEhARIO FERMEX 87 CLOCK TIME = 1050-1200 MESSAGE NO. OSC C0hTROLLER SCENARIO TIME = 0350-0500 m (JI FERMI - 2 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM . I MESSAGE FOR: OSC Controller l MESSAGE: 1) Initial investigation - overloads are tripped.
- 2) If overloads reset - fuse for L1 opens
- 3) When motor continuity checked 3 2 reads 4.2 T -T T -T reads 0.0 3 3 i 2 3 reads 0.0 T -T l
l J l U *********************************** 1 1 FOR CONTROLLER USE ONLY: CONTROLLER NOTES: Provide the above information to repair team at ]' MCC 72F-4A. ACTION EXPECTED: Results reported to Control Room /OSC. O
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+
eg s l' s 1/
/ SCEllARIO FERMEX 87 CLOCK TIME = 0700-1500 t
- MESSAGE 110. 20F/TSC Cor, troller SCEIMRIO TIME = '0000-0800
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i4 EMERGEl:C'i PREPARED 11ESS EXERCISE MESSAGE F0FJ , s.. . S .f 's 1 % g \.' ' g ,1 %. ') i j V$ MESSAGE FOR: EOF /TSC Controller [ , 1 MESSAGE: Provide meteorological data sheets to meteorologist if l N ERIS fails. j 1 S. - T l s i
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SCE!;ARIO FERMEX 87 CLOCK TIME = 0700-1500 MESSAGE 110. EOF /TSC Controller SCE!!ARIO TIME = 0000-0800 t FERMI - 2 ) 1 EMERGEt)CY PREPAREDNESS EXERCISE MESSAGE FORM , l MESSAGE FOR: EOF /TSC Controller MESSAGE: Provide WSI report to meteorologist af ter WSI report is obtained from QUI!C. l l FOR Cor TROLLER USE 01 LY: l C01. TROLLER :;0TES: I ACTIO!! EXPECTED: l l 1 0
SCENARIO FERMEX 87 CLOCK TIME = 1040 MESSAGE NO. Simulator Control Rm. SCENARIO TIME = 0340 FERMI - 2 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Control Room Staff MESSAGE: RCIC isolates and E51-F008 shuts. E51-F007 loses indication and the annunciator for thermal overload actuation sounds. FOR CONTROLLER USE ONLY: CONTROLLER NOTES: Provide the above information to the control staf f if the siculator malfunctions. ACTION EXPECTED:
)
_ _ - - - - - - - - _ - - - - - _ - - - - J
SCENARIO FERMEX 87 CLOCK TIME = 0920-1500 MESSAGE NO. Chemistry Controllers SCENARIO TIME = 0220-0800 (3 u_J FERMI - 2 i EMERGENCY PREPAREDNESS EXERCISE MESSAGE FOPJ4 MESSAGE FOR: Chemistry Controllers MESSAGE: Provide the following readings at the PASS when measured by the Chemistry Technician. I. PASS General Area drywell air: background reactor coolant: 100 Mr/Hr torus water: backgrot:nd 1 Contact with bare simple vial (no other radiation sources present) drywell air: 530 Mr/Hr 10cc sample reactor coolant: 8 R/Hr 9m1 cample torus water: 41 Mr/Hr 9m1 sample Centact with pig holding sample (no other radiation sources precent)
}
drywell air: 2.0 Mr/Hr reactor coolant: 37,2#r/Nr torus water: 0.0 Mr/Hr
*****************w *****************
FOR CONTROLLER USE ONLY: e CONTROLLER NOTES: ACTION EXPECTED: O w - -- ----
l 4 SCEllARIO FERMEX 87 CLOCK TIME = 0920-1500 i MESSAGE 110. Chemistry Controllers SCE!;ARIO TIME = 0200-0800 O FERMI - 2 i ! EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM I MESSAGE FOR: Chemistry Controllers MESSAGE: Provide following readings when measurements are taken.
- 1. Zeolite Cartridge 0920-1040 contact with cartridge <.1 Mr 1040-1500 contact with cartrid 6 e <.1 Mr/Hr
- 2. !!oble Gas 0920-1040 ,
/3 contact with sample 1 Mr/Hr - 1 Liter Sample
() 1040-1500 96 Mr/Hr j *********************************** FOR C0l! TROLLER USE OI!LY: 1 I (
)
I C01; TROLLER t40TES: i 1 ACTIO!4 EXPECTED: i l O l l __ _o
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r r r t mEL - G N M M M 2 5 1 l l
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SCEllARIO FERMEX 87 CLOCK TIME = 1145 MESSAGE NO, EOF CONTROLLER SCENARIO TIME = 0445 FERMI - 2 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM < I l l MESSAGE FOR: EOF Controller l l MESSAGE: Inform individual in charge of facility that a shif t change needs to be accomplished by 1315. I l e
*******************c***************
l FOR CONTROLLER USE Ol1Y: CONTROLLER 110TES: I I ACTION EXPECTED: Relief personnel notified of shift change and I assembled and briefed by oncoming Emergency Officer for EOF. l 1 l (2) l l 1
I SCEllARIO FER!!EX 87 CLOCK TIME = 1115 MESSAGE NO. TSC COITTROLLER SCE12ARIO TIME = 0415 FERMI - 2 EMERGE 11CY PREPARED?iESS EXERCISE MESSAGE FORM ;. MESFAGE FOR: TSC Controller MESSAGE: Inf orm individual in charge of facility that a shif t change needs to be accomplished by 1230. FOR C0!! TROLLER USE Ol:LY: l l C0!iTROLLER 110TES: l I d ACTIOt1 EXPECTED: Relief personnel notified of shift change and assembled and briefed by oncoting Emergency Director for the TSC. l l O
SCE!ARIO PER'EX 87 CLOCK TILE = 0935 MESSAGE 10. SIfUUdO:1 O!TI1WJrR - SCDMRIO TI!E = 0235 E"I-2 CEICEfKN PREPAPIDlESS EXERCISE fESSAGE FOR1 MESSti;E FOR: Siraulator Controller MESSIGE: Provide the following information on cool down progress ted. It is asstned to thethe that Control RoTarate cool down staffwill as requeg/Hr. be 85 Refer to attached graph to determine Psat for times requested. IME: Do not provide graph to Cbntrol Room operators. l
/
O FOR CO!TfPJM USE O!TuY: CDITTROLLER IMES: ACTION EXPECTED: O E
jf1I)l jiill- .i i T. g i i!III ' s P 4 7 6 g j i
~
iIi! g ^ _
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~
s P ~ 4 5 ii 6N 1 1 3 x 1
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nii a l l Ne iii t3 / e . lii n1 F t N lii o 0 a ' iii zs 5 r it 8 N tIi r n n sw lIi iIi tIi iIi h s h r oe e eo md ul _. L N _ _. g-iIi c p ae so so lIi E r Ac g _
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iIi _. iIi iIi : P s,iII-N lIi E _. 3 N _ lIi T O 0 ~ iIi N 4 _. _ en tli s w 5 3 - i L _ 0 1 T 1 s c su s '1 e s s I 3 s E r s e N 8 9 V ' 9 t x as s vs 3 l m ;3 u P x w s T w \ s k tN
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0
' 9 9 D D
SCENARIO FERMEX 87 CLOCK TIME = 0920-1400 MESSAGE NO. Chemistry Controller SCENARIO TIME = 0220-0700 FERMI .2 (, EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Chemistry Controller I MESSAGE: Give chemistry sample sheet for the time the sample was : t aken l l l 1 1 l l I l l O FOR CONTROLLER USE ONLY: CO!TIROLLER NOTES: ACTION EXPECTED: Results reported to Control Room /TSC. O
i 1 SCENARIO FERMEX 87 CLOCK TIME = 1050-1200 MESSAGE NO. OSC Controller SCEf!ARIO TIME = 0350-0500 0 FEFJ'I - 2 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM l MESSAGE FOR: OSC Controller MESSAGE: Steam leakage can be heard going through shut valve. t FOR CONTROLLER USE ONLY: CONTROLLER NOTES: DO NOT ALLOU E51-F008 TO BE OPERATED. Provide the above inf ormation when E51-F008 is inves tigat ed . Steam leakage persists even when valve in clanually torqued shut. T ION EXPECTED: AC. O L_--_____---_____________________________________
SCENARIO FERMEX 87 CLOCK TIME = 1200-1330 MESSAGE NO. OSC CONTROLLER SCENARIO TIME = 0500-0630 0 FERMI - 2 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM I MESSAGE FOR: E51-F007 Valve Repair Team MESSAGE: Repairs completed in drywell penetration X-105A. FOR CONTROLLER USE ONLY: ColTIROLLER I;0TES: DO NOT /1 LOW THE COVER TO BE REMOVED FR0!! PENETRATION X-105A. Give to repair team leader 20 minutes af ter initial r.c s s a ge . i l ACTION EXPECTED: Results reported to Control Room or OSC. l j
SCEl:AR:0 FERMEX 87 CLOCK TIME = 1040-1330 MESSAGE NO. OSC CONTROLLER SCENARIO TIME = 0340-0630 0 FERMI - 2 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: E51-F007 Repair Team MESSAGE: T3 motor phase power lead (TBS-39) is separated from connector in terminal box for penetration X-105A. Approximately 15 minutes required to repair, l *********************************** FOR CONTROLLER USE ONLY: 1 O C011 TROLLER 10TES: DO 110T ALLOU THE COVER TO BE REMOVED FR0!! PEliETRATION X-105A. Give to repair team leader when suf ficient time has 1cpeed to open terminal box and locate leads. ACTIOl; EXPECTED: Reported to Control Room or OSC. ,1 l { () 1 l l
SCE!:ARIO FERMEX 87 CLOCK TIME = 0700-1500 MESSAGE NO. Sno Control Root SCENARIO TIME = 0000-0800 (). Controllers FERMI - 2 i EMERGENCY PREPARED?'ESS EXERCISE MESSAGE FORM MESSAGE FOR: Senio:- Reactor Operator Control Room Controllers MESSAGE: Provide inf orection on attached sheets at the time indicated if the simulator malfunctions. Provide any additional data requested that is not contained on the status sheets.: FOR CONThCLLEE USL 0::LY:
?
k i CONTROLLL1,:20TES: ACTIOM EXPl:CTED: i e l O
AIM 10 FrRMrx 87 IATE Aucust'-18: 1987 CLOCK T!tE 0700 J ESCAE k0. SCENARIOTitt 0000 PLANT- STATUS 4 PEXTOR v i l e WATER LD.EL 196 IN. e RECIRC. FLOW i LOOP A NVI GPM x 1000 e PFISSURE 10/5 PSIC. ' LOOP B Wf GPM X 1000
]
l
)
e PCAER LE\EL: APRM 85' o RX SCRAM VERIFIED? ES - No
% ]
1RM Tite l i SRM- COUNTS j e STANDBY LIQUID CONTROL SYSTEM ! 1 a RX PODE SWITCH POSITla; Run T E LEVEL 120 IN, j SLC MPs a CONTROL ROD DRI\E (CRD) A E 5 CPD PfjpS PEP. , X X n UPIP. A E STEY. Op. ! STPY. X DISCH. PPfes. OP. X nw . m m a a Iw n rlai a STM. FLOW //. f L&VHR X 10 6 i 1 e FEED FLOW /L F LBMil X 106 l j i i O
-- -___--_________-__-_--____--______-_a
SEf#10 FERMEX 87 DATE August 18, 1987 CLOCK Tim 0700 ESSAI NO. ,_., SCD#10 Tim 0000 0 PLANT STATUS t CONTAlffENT . a IfCEGRITY l%lhTAlfED: e STANDBY GAS TREATEtU SYSTEM PRIMRY CTMT. YES Y NO DIV. REP SM OP ALIGtED T0: SEC0fDRY CTNT WS y NO I y PRIMRY C0fRAlftOR 11 X SEC0fEARY X C0fRAlffENT e DR%El PRESS, .5 PSIG e EFFLLENT RADIATION poi! TORS UCl/CC e DRWEli TEtP. 132 Cp PARTinI ATF 10Diff Nn4 F MS UCl/CC UCl/CC UCl/CC e g CONCENTRATION 0.1 % CH PJADING CH RFASING CH RrADING 1 SGTS e 0 C0fCDUMT10N 0.8 g AyM 2 RX R DG g.,dSWATER TtRoltE R M LEVEL 0 IN. TEfP. 85 0F PAmtSTE R M e CONTAltfEfC WIR. LEVEL N/A IN. e F.O!ATION PDNITORS j OFF GAS RAD foi! TOR (0GRM) m/HR ! e m!N STEAM ISOLATION VALES PRIEY CORAlfENT POilTORING SYSTEM CPM OPEN _ x CLOSED C0fJAlt(ENT HIGH RANI RADIATION t041 TOR (CRPM) _ 25 R/m ) AREA RADIATION K)NITORS (ARM) NOPM A1 ' R A C k' C D O f f M B ITVrlR e THIRD MSIVs OPEN X CLOSED l e MSIV LEAfME C0fRROL INITIATED? YES NO X e ADDIT 10fAL Iff0RMAT10N I e VEfGILATION C0tJ. RAD TLES. Rm REAC. i ROT ktSE R M. COT. 4 m.
^ X X X X X l'1 PR 1RC.
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.-y __me ._ ._- -
. _ uyu ESSE NO. SCEtAR10T!E 0000 PLANT STATUS l
1 E ER EtCY CORE C00 Lit 6 SYSTEM (ECCS) I e HIGH PRESSLRE C00lAffi IfLECTION e RESIDlR WAT ret 0V/L 4 REPAIR STNCBY X OPERATE (DECK /PPROPRIATE MODE OF OPERATI&i)
~SUCTIONSOURCE X CST TORUS CONTAlffENT SPRAY FLW 0 GPM _
SHlRDOWN COOLING DISC $ RE PRESSUPI PSIG TORUSCOOLING X LPCI e REET0R COPE ISOLATION C00Lif6 FLEL POOL C00Lif4G NO ASSIST REPAIR STN0BY X OPERATE SUCTION SOURCE X CST TORUS Rm PLM FLW 0 GPM A c B D DISCF%RE PRESSLFE PSIG pfp. STEY. X X X X e fTa% TIC DEPPESSLRIZATION SYSTEM op, h ARE X If0PERARE FLOW 0 epn i e COPE SPRAY (CSS) e EDITIGA ItF0P?ATl&d csPws A C B D PEP. STBY. X X X X l T. FLOW 0 cpg l l O l
SCEMRIO FERMEX 87 IATE Auaust 18 1987 CLOO( Tim 0700 ESSAE No, SCEMRIO TIE 0000. m V PLANT STATUS Bq.ANCE OF PLANT (IOP) e. e TANK LEVELS e RX FEEDWATER PLffS e MIN UNIT CONDENSER AVAILABLE AS EAT SIE? __ YES __ff CST 2[ N A CRT o71 REP. e ECH. VAC. PlffS e GSW PRESS, 150 ps10 j oST /7 STnY. 1 2 ) OP. X X PEP. e RBCCW PPESS. 56 p3;g STRY. X X l e OFF GAS Op. e TBCCW PRESS. __2.fL_ PS!G M STER C0f(fROL POSITION AUTO
, e Rm SW PLIPS e OTER PLffS A C B D e R $ RESERVOIR LEVEL CO'U NF E WAER FID WAFP DPAIN P!P . 28.5 N C S E C W N C S STRY. X X X X
.l
,. OP.
1 Y. X GP. X X X X X X X i X X e EDG's e CTG j TRANS. 3 1 12 13 14. 11-1 D. 1 e ELECTRICAL PEP. 41M/ F9F STRY. X X X X X OFF9fF DIU. 1 Div 11 130r>60V DC OP. X MeeV 1hv 6ta r# ErI E5F DIV. 1 DIV. If BSD EtfR. X X X X X X ENFP. X X X IITN . e AUX. BOILERS e FIPI PLffS ITTN. N 9 E n
^
e AIR COPRESSORS
^
CONTM- RTATION
^
^
1 7 E C W PEP. ' X X X X e FlPI K ADER PRESSURE 150 ps]G STRY. l P- X e ADDITIOML IWORMTION O b.JTROL AIR PPISSLFI 100 PS]G
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l FERMEX'87 MTE August 18, 1987 10CF, TIE O745 SCEMRIO - O745 i ESSAGE NO. SCEMR10 TIE PLANT STATUS M.ANCE OF PLANT (BOP) /. l e RX FEEDWATER PltPS e MIN UNIT CONDEtiSER AVAILABLE AS EAT Sit? X._YES _.N0 - l e TANK LEVELS m 2f N A CRT #2 PFP . e ECH, VAC. PltPS e GSW PRESS. 150 psyg DST /7 STRY. 1 7 OP. X X REP. e RBCCW PRESS. 56 p3]g STEY. X X OP. 28 p3;g e OFF GAS e TBCCW PRESS. MSTER CONTROL POSITION AUTO e R$ SW PltPS e OTER P!tPS A C B D e R$ RESERVOIR LEW1. C&tTNecTr WATTP FFFD WATTP MAIN REP. 28.5 N C S E C W N C S STBY. X X X X . OP. PY. X , OP. X X X X X X X X e EDG's e CTG l TPANS. _11 _ .22 23 .Ili. 11-1 m. 3 y 0 ELECTR1 CAL PEP. l incM FT STBY, X X X X X TFSITF DPt. I DIV 11 13nnf0/ Dr OP. X 3t&V 1hv FAP F# ESE ce; DIV. 1 DIV 11 R'O ETR. X X X X X X ENFP. gg, g e AUX. BOILERS e FIPI PLtPS N S E n RTP. PFP ^ s AIR COPPPISSORS STEY. X gg, X X CUTPol STATION
^
3 2 E C W REP. y y e FIPI KADER PRESSURE 150 psig gy y y OP. X e ADDITIOML IWORMTION UR0L AIR PPISSlRE 100 pg;g 0
PES %I fC. SCEtiARIO TifE 0045 (3 PLANT STATUS g i I EFERIfCY COPI COOLING SYSTEM (ECCS) ,,. e HIGH PPISSLEE C00lJtG ltLECTION e RESIDUAL FEAT REtO#L l PIPAIR ST40BY X OPERATE (DECK APPROPRIATE PODE OF OPERATlai) SUCTIONSOURI X CST TORUS CONTAlffENT TRAY FLOW 0 GPM SHUTDOWNCOOLING DISOFRI PPISSUfE PSIG TORUS COOLING X LPCI e REACTOR C0FI ISOLATION COOLING FLEL P03. C00LifG NO ASSIST REPAIR STNE6Y X OPERATE SUCTION SOURg X CST TORUS PMPMS RW 0 g A C B D l l DISOFRI PPISSLFI PSIG prp. STry, x x x X y NWATIC DEPPISStr,12AT10N SYSTEM OP. , () g X INOPERABLE FLW 0 gpn e COPE SPRAY (CSS) e EDITIGA lif0FyATlyi j CS PWS A C B D FrP. - < STAY. X X X X OP. FLOW n GPM I lO \ G l l
SIfARIO FERMEX 87 IATE August 18, 1987 CLOCY. Tite O745 0045 I tiSSAGEfo. SCEt# 10 Titt l
!) 'u/ PLANT STATUS l 1
1 C0fRAltittU I l e ifEEGRITY f%1NTAINED: e STAtGY GAS TREATEf6 SYSTEM l PRif%RY CTMT. YES X f6 DIV. REP STBY OP ALIGED TO: X I X SEC0tC#Y CTMT. YES NO PRlPARY C0tGAlflilU 11 X SEC0 TOV,Y X C0tiTAlltEtC e DRWELL PPISS. cI PSIG e EFFLLEtU RADIATION foilTORS UCl/CC e DRY, ELL TEW, /32 % PADTini ATF 100lff PO9 F CAS UCl/CC UCl/CC UCl/CC e g C0tCEfGRAT10N O,/ % CH RFAhlN1 04 PFADING CH PIADING SGTS e 0 C0tCEtGRAT10N 2 0e E % Aci RX B DG CO .sLtS y WATER TLPEINC R M v LEVEL O IN. TEff. 68 % PMIASTr am o CONTA!!fENT VR, LEVEL IN. s PADIAT!Cti KrilTOPS
/fS'l OFF GAS RAD t041 TOR (00Pfd W/ ff M e PAIN STEAM ISOLATION VALVES PRIPARY C0tJAlffEtU foi!TORING SYSTEM CPM OPEN / CLOSED C0fGAlttENT HIGH PRE PADIATION tDilTOR (CHRP?d AC RAfl l AREA RADIATION PDilTORS (ARM) A/wa/ 69Iwd ifM e THIRD MSIVs d
OPEN / CLOSED e MSIV LEAVASE CONTROL INITIATED? YES to / e ADDIT 10tAL ltf0 % T10N e VEtiTILATION C0f.T . PAD TLF.B. R$ REAC. __ i RD1 WASTE R M. Com RM
, / / V V V ~
1eil . RCCIDC j
ESSed.fo.. SCEfM10 TIE C6Vf- l PLANT STATUS ne n ., e WATEF. LEEL /f4 IN. e RECIRC. FLOW LOOP A +'f / GPM X 1000 e PfESSURE /O/I PSIC LOOP B S' C ,M GPM X 1000 e PGER LEWL: APRM /do % e RX SCRAM VERIFIED? YES to IRM TIE SRM C0utiTS e STANDBY LIQUID C0fiTROL SYSTEM e RX PODE SWITCH P051T!0fi Tan TAT LEVEL /,9 6 IN. SLC >tf9S A B e C0tiTROL ROD DRIVE (CRD) CP9 ) LIPS PFP. , A E STRY. s/ / REP. OP. STPY. / DISCH. PPrge, OP. [ R 01 e ADDIT 10fML ltf0Pl%T104 e STM. FLOW /6/ LIMIR X 106
/8/ 6 e FEED FLOW LBMR X 10 i
O
K SSNI No. SCEfARIO TIE o A /4"" q PLANT STATUS 1) B4.ANCE OF PLN(i (BOP) 9 i e TANK LEVELS e RX FEEDWATER PLtPS e PAIN tri!T C0f0EfER AVAILABLE AS EAT Sl*? [YES N0 CST 2/ N A CRT ), 2- PIP. e ECH. VAC. PLfPS e GSW PRESS. /fd PSIG , DST /7 SmY. 1 7 OP. [ / REP. e RBCCW PRESS. M PSIG STBY. e (FF GAS Op. e TBCCW PPISS 2 P PSIG MSTER C0fiTROL POSITION Av
, e R m SW PLffS e OT ER PlfPS A r B D e Rm PISERVOIR LIE.
C&NN9AE WAFD FFD FEt.EP DPAIN PIP. J f7,4~~ N C S E C W N r S STBY. V' / / 7 ocP. OP. 8,v. - y / ,/ / / v ' / w_ , gpgag , c3s TP#iS. 11 22 ,13 A 11-1 NO. 3 t ELECTRKAL pep. c1mvrm_, spy, - y y / /
&FSITr DI" 1 DIV 11 BS/2f,0V DC OP. /
%Sev iny 942 w rer Err DIV. I Div. 11 av FTR. / / v' / V EN p / l l ff FN. e AUX. BOILERS e FIPE PLPPS ryTN N S E n
^
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e AIR C0FPPISSORS CorttP3 STAT 10N
^ ^
1 2 E OP. / g-C W PED. ppy, y g e' ,,- / e FIPI K ADER PRESSURE /CO PS!G OP. / - e ADDIT 10tst Iff0RMT10N A (JTROL AIR PPISSLFI /CO PSIG
SGr%lo ffRn1Fr V2 DATE b us N 7 /9V7 CLOCK T1% _ O f / f
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i 3 , { ,. .. K SSAGE NO, SCEMRIO TIK Oghf ' h -(
^
PLANT STATUS .; EEREfCY COPI COOLING SYSTEM (ECCS) ,
*.-\. '
i . e HIGH PRES $$E COOLANT INICTION e RESIDUAL E AT REf0 VAL 1 REPAIR STNOBY / OPERATE __,. (OECK APPROPRIATE POE OF OPERAT10t0 Y; SUCTIONSOURE / CST TmVS C0f(TAlffENT SPRAY R0W D GPM SHlHDOWi COOLING DISONI PRESSUPI PSIG TORUSCOOLING l
.LPCI s, e REACTOR COPE ISOLATION COOLING F!EL POOL C0a.ING NO ASSIST REPAIR STANDBY / OPERATE SUCTIONSOURI # CST TORUS b PM PtfPF
,i FLOW /3 GPM ,
A C B D DISCMRI PPISSIE PSIG pfp. i n r. v / / / ,
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Om ""a^'I - imum et, o ceM 1 e CORE SPRAY (CSS) e ADDITIOML Iff0RPAT10N
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CS PifPS *~ l A C B D . PEP. STBY. / / / w. Ft0W O GPM 1 3
'1 9
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y- y .. FGA rHEX R7 It,TE $ 9us l /V,'/927 %fR10
/ CLOCK TltE _Q.9ff J l
]SSAGEf0. SCD#10 T!rE Q2/f e' ~
\ PLANT S T'A T U S i ,,
STAllEf6 s
) 1 j
) IfEEGRilY MlfGAlfG : e STANDBY GAS TREATtENT SYSTEM PRIMRYCTMT. YES NO D1V. PEP EM OP ALIGG T0: -) SECOMY CTfU. YES
/ NO I / PRIMRY ' CQUAlftEl4T 11 SEC0fMY CQUAlfENT L m'AELL PRESS. e[ PSIG j
'1 e EFFLLENT PADIATION fOilTORS UCl/CC
) m% ELL TDP. /32 % PADTint ATF 10Diff NnR F C# UCl/CC UCl/CC UCI/CC ) H C0fCDURAT104 De / '% CH PIABING fH READING CH READIN3 2 SGTS > 0 C0fCDURAT10N 2 Or I % AXM RX B_DG O<uSutR -- LEVEL O IN. 1EPP, til % RtNASTr a m ) CORA!ME!G WR. LEVEL #/4 IN. e PADIATICt4 FONITMS 0FF CAS RAD f041 TOR (0GRM) 700 TAR ) m!N STEAM ISOLATION VALVES PRIMRY CONTAlffEf6 f041TORING SYSTEM CPM OPEN / CL0 FED C0fGAlffENT HIGH RANGE PADIATION MONITOR (DERM) M PAR AREA RADIATION t041 TORS (ARM) th6no [ /*Iomu IMiR > THIRDf51Vs OPEN CLOSED > MSlV EAKAGE C0fGROL INITIATED ES N0 e ADDITIOML Iff0RMT10N ) YEfGILATlui C0fU. RAD TURB. Rm REAC. Pff)M WASTF R TG. Com R Dr.. = / / / / V RFilRC.
c SCD#10 F###1 A A' F7 DATE daw rN /( /ff7 CLOCK TIE __.dfff
./
ESSAGE NO. SCEfM10 TIE _. Q,alg PLANT STATUS l REACTOR %- e WATEF. LEVEL / 9 /J IN. e RECIRC. FLOW LOOP A ' N 6'S GPM X 1000 e PPESSURE 976 PSIC LOOP B 7 MM" GPM X 1000 e POER LEVEL: APPN '56 _% e RX SCRAM VERIFIED? YES N0 IPM TIE j SPN COUNTS i e STANDBY LIQUID CONTROL SYSTEM e RX PDDE SWlTCH POSITION IuM TAfK LEVEL 12 o IN. St r >tfPS A B e C0ffiROL ROD DRitE (CPD) CPD )#S REP. A E STBY. [- # REP. OP. STpy. [ LISGL PPFRS. OP. / FLnu e ADDIT 10fW. lif0P.%T10N e STM FLO1 T. T LBMR X 106 6 e FEED FLG1 F.[ LBME X 10 _ i O I' L----_------------_---------.-----------------._-- l
fffft EP f7 _7 h&D SCE%Rio IATE
]t A a d W Q Y a CLOCK TlW 1
, E,AI $ to.. /r/ % /[/) C 97 6 __:_ '
, SCEMRio TIE 2 ,0
~
p - fg PLANT STATUS
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t , P1 ACTOR .,., .. g s , o WATsi (BEL ,_8 A 3 .l}L s PICIRC. FLOW
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;, LOF A J1L( GPM x 1000 q e PFESSUPI _ /M Mf PSIC LOOP B 39 ( GM x 1000
)
i e POER LE\EL: /Pc 6[ % e RX SCPAM \ERJFtED? YES _ _ L 1 to t ' Tit 1E _ .._, i IPs ,'
^
SRM C0JNTS e STNEf L10J1D SEOL SYSTEM e RX tODE SWITCH POSITION @ t e? ',. TAT LIEL /J O ]N. 9_C lWPS j _._ A D l e G M R0D DRI\E (CRD) l CCDPJPS PFP si A l E .3Y. _ / / At gs,.) 3' g;: , 19 ,_ eTPY. DISOL PPfcS. Op. if , I I 5N I
#1 ADDIT 10W4. ItF0PIATION n
e STM. FLOl //. 9 LB%iR X 10 ,_.'
- 7. 7 k s FEED FLOW 1.FAfi X 10 , __ _ . :
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S1tyslo WAsHGX P7 D4TE h 4 W 1 Y M ' / f f 7 CLOCK TlW 892 D _ _ .
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ESSAI to, /e/ 2 d B924 SCEMRIOTIT CA2 A $ O I O PLANT STATUS j i) . ( DERIrCY C0FI C00Lif6 SYSTEM (.~ e HIGH PRESSLRE C0l#6 INICTION e RESIDUAL {AT PItO/AL i REPAIR STNOBY OPERATE (DECK APPROPRIATE MXE OF OPERAT100 SUCTIONSOURCE / CST TORUS C0fRAltM:NT SPPAY FL(M M a O GPM SKUDOWNCOOLING , 4 TORUSCOOLING DISO@I PPISSUPI /o eo PSIG LPCI REL POOL COOLING NO ASSIST e REACTOR COPI ISOLATION COOLING REPAIR STNEY OPERATE
# CST TORUS- RP PtfPF SUCTIONSOURI FLOW d GPM A C B D DISC MR I PPISSLPI PSIG pfp.
STEY. / V # V TOMTICDEPPISSLRIZATIUiSYSTEM g , (PERABLE INDPERAELE FLOW D GPM-3 CQ)I SPRAY (CSS) e EDWGA IWGNTION Wd LW CS P W S A C B D REP. m v. CP. z/ / ( / I fl FLOW O GPM 1 i
)
i
~ f fA' M F Y T7 %TE X b a d c ? / b / f R Y 0.0CY. TltE 'D 9;t D j
- S1tGB10 j ' 1 ESStd NO. / #1 d o 9J O SCEMRIO TIE O 21 B v '
O ELAN 1 STATUS { C0fRAlfEtli e INTEGRITY MlfGAl O : e STAfEY GAS TREATENT SYSTEM PRIMRY CTMI. YES // NO DIV. PP ETEY OP ALIGfED T0: I SEC0fEARY CT!G. YES [ N0 i PRIMRY C0fRAlfEf6 11 SECONMRY
# C0fRAlfEf6 'l I
e DR% ELL PRESS. A~~ PSIG e EFFLlENT RADIATION milTOPS UCl/CC e IR% ELL TEW, ' /J A % PARTint ATF 10Diff NOR F GAS UCI/CC UCl/CC UC1/CC O, / CH RFADIM CH READING CH READING e g C0fEfRRATION SGTS e 0 C0fENTRATiON 8, I % AXM 2 RX a M OauSmu mm LEWL D IN. TEfP, R[% RtMSTF R M e CGRAIME!U m. LEVEL _ff//// IN. e WIATICri M41 TORS
! 0FF GAS RAD milTOR (0GRM) fCM PMR PRIMRY C0rlTAlffEf6 milTORING SYSTEM CPM e MIN STEAM ISOLATION VALVE 5 OPEN / CLOSED C0fiTAlfEf6 HIGH RATE RADIATION milTOR (C@RM) /[ f APIA RADIATION milTORS (ARM) A/waI 1>-[ ems AIR l e TlilRD EIVs .
l au / ct0 sed e f51V LENJE C0fGROL INITIATED? YES N0 r e ADDITI0fAL IWORMT10f1 e VEf61LAT10N C0r5. RAD TlEB. RFE PIAC. RrIN WASTE R M. Corf. R m. l
/ V V l l Im fEC1C
i ESSAGE No, / e/ 2 d M 9.2 o SCEMR10 TIE 6 71 #> PLANT STATUS BU44CE OF PLAfv7 GOP) y, e TA't: LEELS e RX FEEDWATER PLfPS e MIN UNIT C0f0ENSER AVAILABLE AS EAT SifE7 .V._TES J CST S '/ N E CRT AA PIP. e ECH VAC. PLffS e GSW PPISS. . / f 6 PSlG
!)ST /4 Smy. 1 2 l
Op. /[ / PIP. e RBCCW PRESS. 5 h PSIG l STEY. e OFF CAS OP. e TBCCW PRESS. 2 7 PSIG ' MSTER C0fv7ROL POSITION A/
, e PJE SW PLffS e OTER P&PS A C B D e R$ PISERVOIR LEW1.
C0'C M STr [ER FTD [ATrP DPAIN Prp. MCI fl C S E C W N C S STBY. V ' V # ,
~~o. OP.
BY. op, / / / / / / / g /~ / e EDG'S e CIG TMNS. H' O. 3 J.1_. 22 23 ; l 4. LQmV FCF STRY. W V WW / OFF9fTT Dit'. I DIV 11 BSMGOV DC OP.
%5rV 1XkV EAP r# ESE E5F DIV. 1 DIV. 11 RP EtER. t/ v / *' V / EtFR. / / W TITN. Drry.
e AUX. BOILERS e FIRE PLffs N S E n
^ ^
W e AIR COPRESSORS C0f W 1 STATION SEY. STBY. /
^
1 2 E C W PIP. gpy, y y g / e FIPI EADER PRESSUDI AFC PSIG OP. / e ADDITIOML Iff0RMT10N (.0NTROL AIR PPISSTI /6O PSIG
f SCENARIO FERMEX 87 CLOCK TIME = 0921 MESSAGE NO. CONTROL ROOM STAFF SCEllARIO TIME = 0221 FERMI - 2 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Control Room Staff MESSAGE: The following annunciator window (s) alarm: 3D82 - Main Steam Line Radiation upscale /Inop channel trip. 3D83 - Main steam Line channel A/B/C/D Radiation monitor upscale. 3D86 - Main Steam Line isolation valve closure channel trip. l 3D73 - Trip actuators A1/A2 tripped. 1 3D74 - Trip actuators B1/B2 tripped. 3D43 - Div I/II containment area radiation monitor trouble. ID61 - SRV open. j () 2D74 - Div I/II Low-low set armed. I I 17D14 - Div I/II SGTS auto start. FOR CONTROLLER USE Ola,Y: CONTROLLER !!OTES: PROVIDE THIS MESSAGE O!ILY IF THE SIMULATOR j MALFUNCTIONS. Give this message to Control Room operators with Plant Status Sheets at specified time. ACTION EXPECTED: Operators take appropriate action for reactor scram with MSIV isolation. A V
m. ESSAGE NO. 1o/ M M 69AC- SCEfva10 TIE' OD49 O = PLANT STATUS 4 REACTOR o.. q e WATER LEVEL E/O IN. e REClRC. FLOW LOOP A D GPM X 1000 e PRESSiRE 996 PSIC LOOP B 6 GPM X 1000. l e RX SCRAM VERIFIED? YES ND' e PGER LEWL: APRM %
'1RM # 4 e>< 1 ee 1. TIE 4#26 SRM COUfGS e STANDBY LIQUID CONTROL SYSTEM e RX PDDE SWITCH POSITION Toe Tate: LEVEL /2 D IN.-
SLC MPS A B e C0fRROL R0D DR M (CRD) CPD MPS PEP. A E STBY. Om m. STDY. / DISCH. PPrcS.
- w. /
R uf e ADDIT 10fW. Iff0Pf%T10N k S/M M A4 AA i+tSL TdkN. s/t/'s e STM. FLOI 0 LWS X 106 h $'t h a -b ,s s d a b U A / i~ dob) 6 s FEED FLOW D LBME X 10 O
SCEty&lo CEWM6x @7 ' LATE $ 1 a u S O'C / f 8 ? CLOCK TltE O92 D J ESSAGE NO. - O//2 b Of4 O-SCEMRIO TIE 6J A O
^
PLANT- STATUS EERIfCY CORE CCOLlfG SYSTEM (ECCS) o HIGH PRESSlRE C(0.AhT ltLECTION e RES!DLML KAT ret 0 VAL REPAIR STAf0BY OPERATE [ (CE CK APPROPRIATE MDE OF CPERATIGO SUCTIOi SOURE 7 CST TORUS C0fRAlifENT SPRAY FLOW M 6 O GPM SH!RDOWNCOOLING TORUS COOLING DISCWAI PRESSUPI / 6 Y (S PSIG V LPCI [ e REKTOR COPI ISOLAT10fi COOLING FLEL POOL C0OLING Ato ASSIST REPAIR GTAtCSY
# OPERATE SUCTIONSOURE / CST TORUS PJP PtrPF
! FLOW 6 GPM A C B D DISC $RE PPISSJI PSIG pfp, STRY. [ / T0MATIC DEP?ISSURIZATION SYSTEM y, IWN FLOW O GPM e COPI SPRAY (CSS) e ALDITIGAL Iff0RMT104 CS P' FPS A C B D l PIP. STnY. w.
/ V
( V FLN O GPM O ,
S11%Rlo FERMEX 97 DATE AdaCllY /9[7 ' 0.0CK TlW C%20
]
ESSAGEfO. O </ o7 O D fc2 C SCDMRIOT!T MH8 r] PLANT STATUS CONTAlf W R e INTEGRITY 1%1NTAlfED: e STANDBY GAS TREATENT SYSTEM ; PRlf%RY CTMT. YES P to DIV. REP STBY OP ALIGtEDT0: I SEC0fEARY CTMT. ES NO I PRit%RY CONTAlfETH 11 SEC0fEARY # C0f4TAlffEfC e DRMit PRESS. o[ PSIG e EFFLlEtR RADIAT10fi tDilTORS UCl/CC e DRYiELL TEW, /33 CF PARTini ATE 1001tf f0R F GAS UCl/CC UCl/CC UC1/CC l e h CONCEtiTRAT10N 6e / % CH RFAhlfr- CH RFADING CH RrADING
)
scTS e 0 C0fCEfRRAT10N O, 8 % AXM , 2 Rx a m ORijs WATER TLFDIT R 16 j LEVEL D IN. TEW. &7 0F RANASTr a rG , a C0tRA!NDiT W. LEEL 8/A IN, a P.OlAT!0N F m l10RS OFF GAS RAD MilTOR (0GRM) 7o O d PP M e PAIN STEAM ISOLATION VIO ES PRlPARY CONTAlfENT tDilTORING SYSTEM CPM OPEN CLOSED / C0fJAlftDG HIGH RANGE PADIATION MONITOR (ORRM) & PM/u APIA RADIATION M ilTORS (ARM) / h AA2*o W/HR e THIRD MSIVs OPEN V CLOSED e tElv LENAGE C0fHROL INITIATED? W.S to e ADDIT 10fAL Iff0 PRAT 10N e E NTILATION C0fJ. RAD TlRB. Rm REAC. PSJM WASTE B_IO . Com R_DG.
/ / V
- m. 7 PR lRC [
w_______-_-__---__-____-_-_-__-_______
SCEMR10 fMAIAN ff ? %E bd OU < b I'T" / V E Y G00(TIW o 92 n J ESstE NO. )d 2 N OfBC SCEleRIO TIE n17o O PLANT STATUS WLANCE OF PLANT (BOP) 4 e TANK LIVELS e RX FEEDWATER PttPS e t%1N LFilT CONDENSER AVAILABLE AS TAT SINK 7 YES _ _fC - CST SY N A CRT M2 PEP. e ECH. VAC. PLIPS e GSW PPISS. /C27 PSIG DST /4 smY. 1 2
- m. I / ## REP.
e RBCCW PRESS. M PSIG EmY. / 7 e OFF GAS OP. e TBCCW PRESS. 2. f PSIG PASTER C0fiTROL POSITION Au
, e RW SW PitPS e OTER PLFPS A C B D e RW PISERVOIR LEWL CD'm M W M PFWD WATrP DPAIN PIP .
N C S E C W N C S STPY. .
/
- w. V V / ./ / / / V e EDG's e CTG 1RANS.
n1 J.1_22 ,13 A 11 -1 wmrm stay. / / - / / OFF9fF Df" i DIV ff 1M/2rE/ DF OP. W MV MV FAE F# FY C5F DIV. I DIV. 11 B00 EtEP. V V V V V V ETR . d d / tv N. e alm. BOILEPS e FIPE PLffS W N. N S E n e AIR C0rPPLSSORS
^
#^ --
CONTR'l STATION STFY. 57Pv. / /
^
^
1 2 F C W PIP. gpy, f g y e FIPE KADER PRESSURE /M PSIG e ADDIT 10fvl IWOR'% TION W /n' a $ >e n AuATROL AIR PPISSLFI /66 PSIG
/
ESSE N0, SEMR10 TifE O9? 4 PLANT STATUS I l DEREfCY COPE COOLING SYSTEM (ECCS) ,, . - e HIGH PRESSLEE C00LkR INICT10f4 e RESIDUAL KAT REf0 VAL REPAIR STNOBY OPERATE (DECK APPROPRIATE N0DE OF OPERATION) ] SUCTI&iSOURE [ CST TORUS C0tHAlftENT SPRAY FLOW D GPM _ SHLUDOWi COOLING o DISCHARE PPESSUPI PSIG TORUS COOLING LPCI e REACTOR COPE ISOLATION COOLING FLEL P0OL C00Lif4G NO ASSIST REPAIR ST40BY OPERATE [ SUCTION SOURE / CST TORbS PM PL*PS FLOW /4 o o GPM A C B D DISCMRI PRESSLFE 4 c' o PSlG pgp, STBY. / V J e 70f% TIC DEPPESSLE!ZATION SYSTEM y, [ v3LI / if@ERARE - FLOW / ford GPM s COPE SPRAY (CSS) s MDITIM INTI&i TCf( / CS P KPS USA 0 t't>o/4 & af A C B D 9 # L/. PJP. STBY. / / 7 l 1 (p, -- 1 FLOW O GPM i O
TSSAE NO. SCENARIO TIT (Als p PLANT STATUS U PEACTOR ,. e WATER LEW L 19OO IN. e RECIRC. FLOW LOOP A 6 GPM x 1000 e PPESS.RE PSIC LOOP B O GPM X 1000
<{4 #~)
e POER LEWL: APPM % e RX SCRAM VERIFIED? YES- / to IRM TIT /) f> d SPM p czM > COUNTS e STANDBY LIQUID C0fRROL SYSTEM e PX PODE SWITCH POSITION f a >an t TAT LEVEL /A# ' IN. SLC Mrs e C0fGROL ROD DRlW (CPS) A B CPB MIPS PEP . _ ,
~
A B STBY. op. 1 OP1 . STvY. / DISCR PESS'. op. [ F101 e ADDIT 10f R ltF0 PRAT 10N I e STM. FLOl (O L&MR X 106 e FEED FLOW O LBMR X 10 E l i O
SCEf# lo S Ef M M r 77 IAE . Asu d & /fK'7 ' CLOCKTlW 'O93f
/
K SSAI f0. SCDM10 Titt 62ff PLANT STATUS . C0fRAlf0EfR . i e INTECRITY t%It#AlfED: e STANDBY CAS TREATEtU SYSTEM PRlr%RY CTMI. YES / NO Div. prP STBY OP AllGr[D T0: SEC0fEARY CTMT. YES 7 NO I PRif%RY C0f5AlfElR - II / SEC0fCARY / C04TAlltD R l e DRWELL PRESS. ,d PSIG l e EFFLLENT RADIATION PONITORS UCl/CC e DRYiELL TEff. /f? 6/ % PADTint ATr 10DFF NSR F CAS UCI/CC UCl/CC UCl/CC e H COCDJRATION 2
/L 1 % N RFADH6 N RFQ1NG G RFADING scTS Wrps e 0 C0fCEtRRAT10N 2
Of % AXM RX R_EG ; l O20s = == - LEVEL O IN. TElf. 92 0 F PK UASTr R CG l o CNA!ffDU WTR. LEVEL 1//A IN. e P.O!ATICt! M ilTORS 0FF CAS RAD MilTOR (0GRM) m4R l e PMIN STEAM ISOLATION VAL \ES PRlFARY C0f6AltEfR MilTORING SYSTEM CPM OPEN CLOSED I C0fRAlftENT HIGH PAfE RADIATION t041 TOR (CEM) R/fR AREA P/O!ATION K)NITORS (ARM) A // A O u I / [ s 4 m/HR e THlkD tElvs wlfA 32n N1 W ff!E6 '7, ?! 9. / 0, / /. OPEN CLOSED V I2. I
- lCb McLef .1
/
/
e f61V LE N/ E CO UR0L INITIATED? YES NO 7 e ADDIT 10fAL Iff0Rt%TIGi e VEf61LATlai _ CO.T. RAD TLFS, Rm REAC. RD'N WASTE RI6. MP. R rc,
= / e/ /
~
1ca / i Ru w. / !
SCEfGRlo F2fM16X f? 7 1%TE bu du t f I8 /9f7 ' CLOCK TIW D29 r
./
ESSE NO. SCEMRIO TlW 'CA P3' j PLANT STATUS
'^
BUNCE OF PLAtJ (BOP) i e TRt' LIVELS e RX FEEDWATER PtWS e MIN tillT C0f0EfER AVAILABLE AS WAT SlfE7 _._YES CST iv N R , CRT M PrP. e ECH. VAC. PttfS e GSW PPISS. Is73 PSIG BST /4 STAY. t/ / 1 2 OP. RrP. e RBCCW PPISS. & PSIG STEY. / e TF MS OP. e TBCCW PPISS. E PSIG f% STER C0fRRQ. POSITION A
. e PM SW PLfPS e OTER PLtPS A C E D e R$ RESERVOIR LEW1.
C&CEtAF WAFR FID WAER IRAIN P9. J ,5Pf
. N C S E C W N C f, STBY. -
Op. / /
. Y. / / / / /
- m. ( / / / e EDG's e CTG TPANS.
._11_ .22 13 .24. 2_1-1 m.1 e ELECTRICN. pcp.
41FDJ FRF gTyy. g/ / / / / OFF9fF Dit/. I Div 11 13nnrM DF OP. / 30erV MV FAD FAC rrI E5F DIV. 1 DIV. 11 RT EffR. ErFR. tTrN. AUX. BOILERS e FIPI PLtPS DrFN. N S _ F n
^
EE-e AIR CCtPRESSORS Co @ D STAT 10N
^
^
^
1 2 F C W PEP. STEY. / / / e FIPI WADER PRESSUPI /473 PSIG
- g. / /
e ADDIT 10 fit Iff0RmT10N i 'OfJROL AIR PPIS $tFI /dd PSIG C- _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
ESSf4E l0. __ SCEfARIOT!!i M. W@ .j PLANT STATUS REACTOR e WATER LE E L MO O IN. e REClRC. FLOW LOOP A d GPM X 1000 e PPISSLRE 32 I PSIC LOOP B O GPM X 1000 e PGER LEVEL: APRM % e RX SCPM VERIFIED? W.S [ ND . 1RM TIE f/9hf) SPt1 GM C0)NTS e STANDBY LIQUID CONTROL SYSE e RX f0DE SWITCH POSITION 8e C# f TAE LEVEL /8O IN. l- sc wS 1 e CONTROL ROD DRIVE (CPJ)) A B CRD PtfPS REP. A B STBY. # Om m STBY.
# DISOL PP%
OP. / R 0=1 e ADDITI'#L lif0PtnT10N e STM. FLOf d L& VdR X 10 6 e FEED FLOW O LIME X 10 6 3
)
O
y _ - . _ E SSAGE NO. SEN610 Tite oW4 i l PLANT STATUS DEREfCY COPE C00Lif6 SYSTEM (ECCS) ,,, i e HlGH PPISSLE C00tRU IfLECTION e RESID#L ILAT REf0/AL PEPAIR ST40BY OPERATE (DECK APPROPRIATE MDE OF OPERAT10fD SUCTION SOURE / CST TORUS . C0f(TAlffENT SPRAY FLOW [ GPM SHlRDOWN COOLING DISCWR E PRESSUPE PSIG TORUSCOOLING , i LPCI REACTOR C0FI ISOLATION C00Lif6 REL P0OL C00LifG #0 ASSIST REPAIR STAfCBY [ OPERATE SUCTION SOURE / CST TORUS PM PLPPc FLOLI O GPM A C B D DISCWRE PRESSLFI PSIG pgp, STBY. / e TOPATIC EPPISSLElZATION SYSTEM gp, / /
~'
L INOPEPRLE - R0W yn/'() GPM e COPE SPRAY (CSS) e EDITlWL IWOPyATidW TC-tsPMs ISrb b$t sv //bl $bou f/nu2 ' A C B D PIP. STPY. [ / cP. nw 0 wM - l 1 l l 0
SCEl#lo FA 17 M&Y ff 7 WTE /]u aus f/Fi '
/9 f 7 CLOCKTlw /D M
'[/ l K SSEE NO. SCEfARIO Tlft O 4VO j PLANT STATUS 1
C0fGAlffEl# I e ItJEGRITY MlfRAINED: e STANDBY CAS TREATENT SYSTEM . PRimRYCTMT. YES NO DIV. PFP STW OP ALIGtED T0: SEC0fMY CTMT. YES NO I / PRIt%RY _C0fRAlfff)H 11 // SEC&MY / CORAlltEfG e DRWELL PPISS. Os 6 PSIG e EFFLlENT RADIATION Milt 0RS UCl/CC e DRYiEU. TDP. / 7I 0F PARTfcliATF 1001ff f0R C GAS J UCl/CC UCl/CC UCl/CC CH PFAnffr, fH READING CH READlN3 . e g C0fCEhTRAT10N Oe 3 % SGTS b de // 6o m I e g CacEfama x PJ I m US WArtR TIF21Nr Pi16 . O IN. TUP. 9/ OF RANASTE R D3 1 o C0'HAlffE!J WTR. [B.EL N/A IN. e PAD!AT!?i NN!TCOS OFF CAS RAD MilTOR (OGRM) A;'/# WAR e f%1N STEAM ISCLATION VALVES PRIMRY C0f6AlffEf6 f0NITORING SYSTEM CPM l OPEN CLOSED / C0fRAlffEf6 HIGH PRi3E RADIATION milTOR (C$PM) 3s4 PAR J AFIA RADIATION M ilTORS (ARM) PE/HR e TMlRD MslVs $CC A<b<l hr~ucelv Al e /n b \ OPEN CLOSED c3 h 4/'N/ tvhe/ur _ e m!v LEkWE C0fGRCL INITIATED? YES NO e ADDIT 10ft lif0RM T10N e VENTILATION CO.T. RAD TLEB. R$ REAC. RCm WASTE E1IG. Carg_ADE, v v' / km . # wc,w. /
1 SCDGRlo OEMMGV ?7 1%TE b dt n b / IG / f 2 7 CLOO( TIK
/ 0 V ()
/
ESSAGE No, SCDMRIO TIE & 74'M A PLANT STATUS l l IMLANCE OF PLM (BOP) .- 1 e Tfm IIVELS e RX FEEDWATER PLtPS, e P%1N UNIT C0 fell 5ER AVAILABLE AS KAT S!fC? CST 2V N S CRT 2A PEP. e ECH, VAC. PLFPS e GSW PPISS. M r> PSIG DST /4 Smy. / / 1 2 Op. REP. e RBCCW PRESS. is~4 PSIG _SWY. V / e OFF GAS Op. e TBCCW PPISS. A 7 PSIG PMSTER C0fTROL POSITION 6 ((
, e PM SW PLtPS e OTER PLffS A C B D e R $ PISERV0lR LEW L CUMN?AE [ATrP FID FEATrP DPAIN pro, 8 F, s '
N C S E C W N C S STBY. / / . y, / / / / / OP. / /./ / e ED3's e CTG TRANS. 11-1 ro.1 11 ,12 ,13 14 inrnv FT Spy, / v' V ./ / OFF9fTr pin, ; plV 11 13V2f0/ DC OP. / ]
%5:V MY FAE FAC EST E5F Dly. 1 Dly. If Epp EfER. / V'/ / / EtFP. V /
DirN. e AUX. BOILERS e FIPE PLffS TrFN, N $ E n 1
^
E#^ e AIR C0ffPISSORS CO M STRY. / grpy, / / STATIM
^
j y 1 7 E C , P.EP. STRY. / / y e FIPE EAIER PRESSUPI / Cf7 PSIG l (1P. / / l iTROL. AIR PPISSLFI PSIG i t
SCEt:%l0 f H nt n r T7 DATE Ainu e YlW) /9K7 CLOCK TIFE ~12D f J ESSAI to, . SCEt#10 TIE orv> c ' _
^
PLANT STATUS PIACTOR - 1
. .i e WATER LEWL 196 IN, e PEClRC, FLOW LOOP A 6 GPM X 1000 e PFESS'JPE d7) PSIC LOOP B O GPM X 1000 e POER LE\EL: APRM % e RX SCRAM VERIFIED? YES / NO IPM TIE d4AO SRM . ? do C00tRS e STANDBY LIQUID CONTROL SYSTEM e RX MODE SWITCH POSITION Ab _SoM TNK LEVEL /AD IN, St C VPS A B e C0kTRQ. R0D MlW (CRD)
CRD MFS RFP. .- A C STEY. O PEP. OP. STRY. DISCH. PPFM. OP. / ' R 01 e ADDITI0r#L ltf0RFATION e STM, FLOf d L&MR X 106 e FEED FLOW D LIMR X 106 l t A :
PESSE N0. SCEfM10 TifE d r7)I PLANT STATUS Q E ER IfCY CM E COOLING SYSTEM (ECCS) ,,, e HIGH PRESS $E C00L#6 INICTION e RESIDyl WAT REf0/AL REPAIR STAT 0BY OPERATE (DECK APPROPRIATE f0% OF OPERATION) SUCTIONSOURE / CST TORUS C0fGAlffENT SPRAY FLOW O GPM / SHLTil)0WN COOLING DISO M E PRESSURE PSIG / TMUS COOLING trCl e REETm CORE ISOLATION COOLING FLEL POOL COOLING #0 ASSIST REPAIR ST40BY / OPEDATE SUCTIONSOUR2 CST TORUS PM PLff9 FLOLI ( GPM A. C B D DISCfMRI PRESSLFI PSIG ppp ,. STEY. . WATlc DEPPISSLElZATION SYSTEM g, / y / /
#ERABLE INOPERABLE FLOW 2 M e'0 0 GPM $4 e W I W sY (CSS) e ADDIT 10fAL Iff0RrAT10N ds /5 cs Pits i r, Slxl,/1wm NO s A C B D uNns 4l> E un$$/AtNE pyp, s Ac Aml>la MG-
/ - - - /
s7py, m FLOW 6 CPM l O
SCEt#lo ffA'M MX ? ? %TE Aua u r f~ / <% <
/9 P Y 0.0CY T1m /2Of 1 ESSAGEfio. SCDARIO TIE o ro f
^
PLANT STATUS I C0fRAlfEf6 e IfGEGR11Y M lfRAINED: e STANDBY CAS 1REATENT SYSTEM PRif%RY C1N, ES / to DIV. REP STM - OP ALlGtCDT0: SEC0f0ARY CTM. YES [ No I PRifW Y C0fRAlffff6 11 / SECONMRY CONTAlftEf6 e DR% ELL PPESS, e3 _PSIG e EFFLLENT RADIATION milTORS UCl/CC e IR% ELL TEff. /3 $ % PADTi(11 AF 10Diff NDR F GAS UCl/CC UCl/CC UCl/CC e g C0fCEfRRAT10N 6e #/ % G PIAniff, (H PFADING m READING scTS &Af e 0 C0fCEfRRAT10N 2 b6 % AXM RX R M
.JS WATER TUPPBlfF BIG O IN. TEtP, N7 % PMMASF R M J
o C0HAlffE!J WR. LEVEL #/4 IN. s P.0!AT!C4 9 4!TCo.S
/
OFF CAS RAD milTOR (0GRM) MME e MIN STEA9 ISOLATION Vt0ES PRIM RY CONTAlfE fR t0NITORING SYSTEM CPM OPEN CLOSED C0f6AlffENT HIGH RANGE RADIATION milTOR (CW,RM) R4R AREA RADIATION m ilTORS (ARM) Set _ iMEuS S Moe/_-fMR e THIRD ffalVs A I - /or h / J M at r v a d e-OPEN CLOID i l e MSlv LEAfRE C0fiTROL INITIATED? YES to e ADDIT 10fAL Iff0Pt%T10f4 e EfGILATION C0f,T, RAD TLRB, RFE REAC, ROOM WASTE B_I6. (Ctp R m. ,
/
PJf1Df.
SCE@l0 Cfd of Ex ff? LATE Aous /C//A'? CLOCKTlE / 2 O c~~
.-l .
ESSAGE NO. SCEfMR10 TIE On[ , PLANT STATUS 1 IML/EE OF PLNiT (BOP) e Tt* LEVELS e RX FEEIMATER Pll'PS e P%lN UNIT C0fLTJ1SER AVAILABLE AS KAT Sl*? ___YES JC l CST JV N R CRT M PEP. e ECH. VAC. PltPS e GSW PRESS. / S C PSIG DST /4 STEY. / / 1 2 OP. PID. e RBCCW PRESS. f4 PSIG 1 SnY. // f/
.- - e - S,. s r PS,,
P% STER CONTROL POSITION 6Af
. e Rm SW PLFPS e OTER PtfL A C B D e R$ RESERVOIR LEVEL CfrLTP6ATr FEAER FTD WMR DMIN PEP. M@5 N C S F C W N C S STBY. . ,
). OP. / / /
gpy _ / / / / / / V V W e e Ews e C1e TRANS. H-1 M.1 _11_ .12 ,13 lif e ELECTRICK PFP. IMn/FW spy, / / / / J l CFFSITr Div. I DIV 11 133/pgyj pc ap, / 3'&V 190KV FAE 9f Erf ErI DIV. I DIV. 11 BE FPER . # 7 ## # / EfFR. # # W trrN. mq, e AUX. BOILERS e FIRE PLffS N S E n l PED. PIP ^ l e AIR C0rPPISSORS CoffiR1 STEY. / STEY. V. V STATIM
^
1 2 E C W ! PIP. STEY. / / / / e FIPI FEADER PRESSUPI- /(7) PSIG OP. 7 e ADDITi&ML Iff0P?AT10N r b)d0f0ROLAIRPPISSME /O O PSIG 1 f
4 O i l l i INJURED MAN O
SCE!7JtIO FER'Ex 87 CLOCIL TITE = 1105 IESSMS 10. OSC CDITI'PTHR SCCARIO TI!E = ~0405 O FERE - 2 EEIGE!CI PREPAPIDIESS EXEICTSE f ESSAGE FOR1
- fESSME FOR OSC Controller ICSSME
- Have operator sent to investigate RCIC Isolation.
Simulate injuries in accordance with the attached drawing. Tae injury should occur in the basement of tno corner roco. III'E: Provide vi a1 statistics from Sheet 2 as requested. Sneet 1 is for personnel at scene to Vieir for extent of inj ury. O POR CD'HTOLLER USE OLY: CO!Ti'R11ER !!X'ES: ACI'IO'l EXPECI'ED: 6
- e SHEET 1 b .
s L CONTAMINATED AREA LOCATIONS DEGREE OF CONTAMINATION '- LOCATION OF WOUNDS
. 1
.pp 4 .
.. s -
?~
i s_ j
.~
j
& 2.m g '
- f. f- (7 i
//
3 og\!j@/[,f
\,#@ h A
.,..e a. i.
o 3, , b
- h. { nll 5
,we
- Y i
i _I (.5 , .. l' f
. TORN PROTECT!
[ ,
' ". " 5 ,
]a%
1
.r s
.e :s7
- f' OUGH g J 9 (./
' SKIN 9, %,2(e .-
'l l l
-; .. . o y Nn >
e i Y O
SHEET 2 Vital Signs o Pu er e1 pe minut'e o Respiration 21 per minute o Blood pressure 110/60 o Patient not in shock as yet CONTAMINATED AREA LOCATIONS '- o Complains of pain DEGREE OF CONTAMINATION LOCATION OF WOUNDS -
\ '?
?
*c
& s -
1 9 d._s ~ 1 x a.o-. g,; 9 s . 0 \. d. 1 , 2 1 2
/:.~iG3ff ?I o ~
( Ca n n aT10N ~- - , (%yh)f/ A . Y g ys ,r - r. f1 ( J. ! , m d( .
\
j k o J. LOWER BODY CONTAMINATION VARIES FROM 2000 CPM TO 2800 CPM
- 2. UPPER BODY CONTAMINATION VARIES FROM 2000 CPM TO 2200 CPM
_ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ __n
1 i SCE!!ARIO FERf4EX 87 CLOCK TIME = 1100-1230 9 l I l'ESSAGE !;0. OSC C0ffrROLLER SCENARIO TIME = 0400-0530
/ i O FER!tI - 2 l
1 E!:ERGENCY PREPARED'!ESS EXERCISE MESSAGE FORM .. I i l MESSAGE FOR: OSC Controller MESSAGE: L' hon injured individucis TLD is read: , o Time on Floor l 1 l 10 Minuten - 5 Rer i 20 Minutec - 9 Ree 30 Mir.utcc - 12.5 Ren s t
+s s i. <v s. s <s t s +. <s s 1 ci + 1; et + + 1- 1 t t t i. t 1. +
U. Fui. CD:Gi,0LLLh USL Di.L'1; Col. TROLLER 1;0TES: Provide the above inferr ation only if the ind iv it u t.. u. inj u; td in tLo !.'.r. cornc: 10c; ] i bacocent. The time the indiv;dua2 is on the faoor .l 1.uot be k.nown, l ACTION EF.PLCTLD: Eetu'.t c r epcrt ed t o the TSC. l l
'l.
l s
\
g)
\. ,
u
1 SCE!;ARIO FERMEX 87 CLOCR TIME = 1100-1230 l l
!!ESSAGE IJ0. OSC COI; TROLLER SCEl:ARIO TIME = 0400-0530 I 4 \
9 FERMI - 2 l EMERGE 11CY PREPARED!!ESS EXERCISE MESSAGE FORM , MESSAGE FOR: OSC Controller MESSAGE: The individual will receive approximately 5 Rem in the let IC minut ec, 9 Rem in 20 minutec, and 12.5 Rera in 30 minutes.
) /3 *************g: ( ***,,,,t ,,,,,,,,,,,g.
U FOR CO::T::OL'.r!: l'SE 013,Y : CO TEOLLEP 110TES: Provide the above infort;ation if injured f.ndividualc DPS is read. Range of DRD ::.ust bt I kn ow:4. , i l ACTIO!! EXPECTED: Recult:, report ed to Cont rol Roor /TSC. l l i
;(
l t l
IO CT-28 READINGS 1 l l O i O
- - - - - -J
- s. - U y n 4" \
N[' , ..g f \ ). 's_ f , (. g .v ,5 . . s L t. g +
\
..!- : s. :( ,'(
p + {' ,, .
.j' ,
't < ,
Cc1711ARIO FEPJ:D: 87 CLOCl TIl2 = 0700-!400\ s , i
, MESSAGE I!O. Sir.2uletor Controller SCEl:ARIO ,'IO:E= 0000-0700 i f~\ i'
.Q) ; .\; .,
FER!!I - 2 s
.i y D:ERGDICY PEEPARD1'ESS OfERCISE !!ESSACE FORf!
o. L % 1 ITESSAGE FOR: Siculator Controlicr j I s r 1;!ESS, AGE: Post CT-23 Readings Sheet 1 at 0920. Post CT-2B 3' 1 Readingc Sheet 2 at 1040, .) 1 - i s .- t. s _1 f 1 4 l
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0940 SGTS DIV 1 7 1.20E-01 0950 SGTS DIV 1 7 1.76E-01 1000 SGTS DIV 1 7 2.28E-01 1010 SGTS DIV 1 7 2.78E-01 1020 SGTS DIV 1 7 2.70E-01 1030 CPTS DIV 1 7 2.61E-01 1040 SGTS DIV 1 7 2.55E-01 1050 SGTS DIV 1 7 2.47E-01 1100 SGTS DIV 1 7 2.41E-01 1110 SGTS DIV 1 7 2.35E-01 1120 SGTS DIV 1 7 2.29E-01 r) 1130 SGTS DIV 1 7 2.24E-01 1140 SGTS DIV 1 7 2.18E-01 1150 SGTS DIV 1 7 2.14E-01 1200 SGTS DIV 1 7 2.09E-01 j 1210 SGTS DIV 1 7 2.05E-01 . I
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1220 SGTS DIV 1 7 2.00E-01 I i 1230 SGTS DIV 1 7 1.95E-01 I l l 1 Sheet 1 I i
CT-2B READINGS TIME SYSTEM CHANNEL READINGS (uc/cc) 1050 SGTS DIV 1 03 8.00E+02 1100 SGTS DIV 1 03 7.45E+02 1110 SGTS DIV 1 03 6.92E+02 1120 SGTS DIV 1 03 6.42E+02 1130 SGTS DIV 1 03 5.96E+02 1140 SGTS DIV 1 03 5.53E+02 1150 SGTS DIV 1 03 5.14E+02 1200 SGTS DIV 1 03 4.79E+02 1210 SGTS DIV 1 03 4,45E+02 1220 SGTS DIV 1 03 4.14E+02 1230 SGTS DIV 1 03 3.85E+02 1240 SGTS DIV 1 03 3.59E+02 1250 SGTS DIV 1 03 3.34E+02 i 1300 SGTS DIV 1 03 3.11E+02 1310 SGTS DIV 1 03 2.83E+02 1320 SGTS DIV 1 03 2.70E+02 i 1330 SGTS DIV 1 03 2.5 2E+ 02
,, 1340 SGTS DIV 1 03 2.35E+02 ,
l 1350 SGTS DIV 1 03 2.19E+02 j 1400 SGTS DIV 1 03 2.05E+02 1410 SGTS DIV 1 03 1.91E+02 1420 SGTS DIV 1 03 1.78E+02 1430 SGTS DIV 1 03 1.66E+02 1440 SGTS DIV 1 03 1.55E+02 1450 SGTS DIV 1 03 1.44E+02 1500 SGTS DIV 1 03 1.35E+02 d(/ Sheet 2
4 0 CHRRM'S READINGS n. o I I lO s !; l
SC!:LAR2O FI:FJ:D: E7 ., CLOCK TI}:E = __0,920 11ESSAGE 1:0. Sinulator Cont: o1 ECEt:ARIO T21!E = 0220
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DIRGE 11CY PREPAREDNESS EXERCISE MESSAGE FORM 11ESSAGE FOR: Simulator Control Room Controller MESSAGE: Post CHRPJ1's Readings at tic.e ctated above. l 6 t FOnc C0" TROLLER USF 0:lI.Y: COI.TEOLLF.R I!OTES: I l l ACTIOl? E}:PI:CTED: l l l 6 1 l l
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l CHRPJ S TIl-lE REA1]IIC (FJC/HR) O 1250 2050 { 1300 2000 I 1310 1925 1320 1875 1330 1800 1340 1750 1350 1700 1400 1650 1410 1600 < i 1420 1550 1430 1500 1440 1475
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- H 1ST FLDOR TURFINE BLDG BLOWOUT PANEL AREA TIME H N O (HRS 3 GAMMA (R/HR3 GAMMA ER/HR3 920 0.00 0.000 930 0.04 0.004 940 0.07 0.007 >
950 0.09 0.009 2000 0.10 0.010 ! 1010 0.12 0.012 1020 0.11 0.011 l 1030 0.10 0.010 ! 1040 0.10 0.010 j 1050 0.09 0.009 l 1100 0.09 0.009 l 1110 0.00 0.006 ) 1220 0.00 0.000 j l'130 0.00 0.008 1 1140 0.00 0.006 1150 0.07 0.007 1 1200 0.07 0.007 I 1210 0.07 0.007 l 1200 0.06 0.006 1230 0.06 0.006 1240 0.06 0.006 1 1250 0.06 0.006 1300 0.06 0.006 ] 1310 0.05 0.005 1320 0.05 0.005 1330 0.05 0.005 l 1340 0.05 0.005 1350 0.05 0.005
- 1400 0.05 0.005 !
1410 0.04 0.004 1 J 1420 0.04 0.004 1430 0.04 0.004 1440 0.04 0.004 l 1450 0.04 0.004 1500 0.04 0.004 1510 0.04 0.004 1520 0.04 0.004 s J
RERJELING FIDOR DOOR 4 A
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GDiERAL AREA RADIATION DOOR C E3 AUX BUILDING STH FLOOR REACTOR BLDG AIRLOOM DOSE RATES TIME A F C D [ hrs 3 GAMMA GAMMA GAMMA GAMMA [R/HR3 [R/HR3 (R/HR1 1R/HR3 920 0.00 0.00 0.00 0.00 0 930 940 9,50 0.41 0.66 0.06 0.13 0.21 0.2/ 0.10 0.17 0.22 0.00 0.01 0.01 1000 1.04 0.32 0.26 0.01 1010 1.18 0.37 0.30 0.01 1020 1.05 0.34 0.27 0.01 1030 1.04 0.32 0.26 0.01 ! 1040 0.97 0.30 0.24 0.01 1050 0.91 0.29 0.23 0.01 1100 0.6B 0.27 0.22 0.01 1110 0.04 0.26 0.21 0.01 1120 0.01 0.25 0.20 0.01 1130 0.77 0.24 0.19 0.01 1140 0.75 0.24 0.19 0.01 1150 0.72 0.22 0.10 0.01 1200 0.70 0.22 0.17 0.01 1210 0.66 0.21 0.17 0.01 1220 0.63 0.20 0.16 0.01 1230 0.61 0.19 0.15 0.01 1240 0.59 0.18 0.15 0.01 1250 0.57 0.10 0.14 0.01 1300 0.56 0.17 0.14 0.01 ( 1310 0.54 0.17 0.13 0.01 1320 0.52 0.16 0.13 0.01 1 1330 0.50 0.16 0.13 0.01 l 1340 0.48 0.15 0.12 0.01 I 1350 0.47 0.15 0.12 0.00 l 1400 0.45 0.14 0.11 0.00 1410 0.43 0.13 0.11 0.00 ' 1420 0.43 0.13 0.11 0.00 1430 0.41 0.13 0.10 0.00 , 1440 0.39 0.12 0.10 0.00 1450 0.39 0.12 0.10 0.00 1500 0.38 0.12 0.09 0.00 1510 0.38 0.12 0.09 0.00 1520 0.36 0.11 0.09 0.00 <
REACTOR 8"1pINC Doop A On AIR LXX 1 p%1
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- II 2ND FLOOR REACTOR BLDG AIRLOCK DDSE RATES i TIME A B C D IHRS3 GAMMA GAMMA GAMMA GAMMA
[R/HR3 (R/HR3 (R/HR3 (R/HR3 O ............................._ 920 0.00 0.00 0.00 0.00 930 0.35 0.11 0.09 0.00 940 0.56 0.10 0.14 0.01 950 0.73 0.23 0.18 0.01 1000 0.00 0.28 0.22 0,01 1010 1.00 0.31 0.25 0.01 1020 0.93 0.29 0.23 0.01 1030 0.BB 0.28 0.22 0.01 1040 0.02 0.26 0.21 0.01 1050 0.70 0.24 0.19 0.01 1100 0.74 0.23 0.19 0.01 1110 0.71 0.22 0.18 0.01 1820 0.68 0.21 0.17 0.01 1130 0.65 0.20 0.16 0.01 1840 0.64 0.20 0.16 0.01 1850 0.61 0.19 0.15 0.01 1200 0.59 0.19 0.15 0.01-1210 0.56 0.10 0.14 0.01 1220 0.53 0.17 0.13 0.01 1230 0.52 0.16 0.13 0.01 1240 0.50 0.16 0.13 0.01 1250 0.49 0.15 0.12 0.01 1300 0.47 0.15 0.12 0.00 1310 0.46 0.14 0.11 0.00 1320 0.44 0.14 0.11 0.00 1330 0.43 0.13 0.11 0.00 1340 0.41 0.13 0.10 0.00 1350 0.40 0.12 0.10 0.00 1400 0.30 0.12 0.10 0.00 1410 0.36 0.11 0.09' O.00 1420 0.36 0.11 0.09 0.00 1430 0.35 0.11 0.09 0.00 1440 0.33 0.10 0.00 0.00 1450 0.33 0.10 0.00 0.00 1500 0.32 0.10 0.00 0.00 g 1510 0.32 0.,10 0.00 0.00 1520 0.30 0.10 0.08 0.00 _ - - - - _ _ - -a
REACTOR BUILDING DOSE RATES TIME CORNER ROOM 1ST FLOOR ,, EHRSJ GAMMA G+B GAMMA GAMMA G+B GAMMA ER/HR3 ER/HR3 [MR/ MIN 3 CR/HR3 [R/HR3 [MR/ MIN 3 920 0.000 O.000 O.O O.000 O.000 O.O 930 0.230 4.230 3.8 0.414 4.414 6.9 940 O.370 6.070 6.2 O.666 6.366 11.1 950 O.480 7.680 8.O O.864 8.064 14.4 1000 0.580 9.180 9.7 1.044 9.644 17.4 1010 0.660 10.460 11.0 1.188 10.,988 19.8 1020 0.610 9.610 10.2 1.098 10.098 18.3 1030 C.580 8.980 9.7 1.044 9.444 17.4 l I 1040 O.540 8.440 9.O O.972 8.872 16.2 1050 0.510 8.010 B.5 0.918 8.418 15.3 1100 0.490 7.590 8.2 0.882 7.982 14.7 ; 1110 0.470 7.270 7.8 0.846 7.646 14.1 1120 0.450 6.850 7.5 0.810 7.210 13.5 1130 O.430 6.530 7.2 O.774 6.874 12.9 1140 O.420 6.320 7.O O.756 6.656 12.6 1150 0.400 6.000 6.7 O.720 6.320 12.O 1200 O.390 5.790 6.5 O.702 6.102 11.7 , 121O O.370 5.570 6.2 O.666 5.866 11.1
+ 1220 O.350 5.350 5.8 O.630 5.630 10.5
\. 1230 0.340 5.140 5.7 0.612 5.412 10.2 124O O.330 5.030 5.5 O.594 5.294 9.9 1250 O.320 4.820 5.3 O.576 5.076 9.6 1300 0.310 4.710 5.2 0.558 4.958 9.3 1310 0.300 4.500 5.0 0.540 4.740 9.0 !
1320 0.290 4.390 4.8 O.522 4.622 8.7 1330 O.280 4.280 4,7 O.504 4.504 8.4 1340 0.270 4.170 4.5 0.486 4.386 8.1 1350 0.260 4.060 4.3 0.468 4.268 7.8 1400 0.250 3.950 4.2 0.450 4.150 7.5 1410 O.240 3.840 4.O O.432 4.032 7.2 1420 0.240 3.740 4.0 0.432 3.932 7.2 1430 0.230 3.630 3.8 0.414 3.814 6.9 q 1440 0.220 3.520 3.7 0.396 3.696 6.6 1450 O.220 3.420 3.7 O.396 3.596 6.6 1500 O.210 3.310 3.5 O.378 3.478 6.3 ) 1510 0.210 3.310 3.5 0.378 3.478 6.3 ' 1520 C.200 3.200 3.3 C.360 3.360 6.O i l l 1 I i 1
REACTOR BUILDING DOSE RATES a -----_--------_--_-__-___-_--__---_____-----________---___ TIME 2ND FLOOR 3RD FLOOR ' CHRS3 GAMMA G.+ B GAMMA GAMMA G+3 GAMMA ' [R/HR] [R/HR3 [MR/ MIN] [R/HR3 [R/HR] [MR/ MIN] 920 0.000 O.000 O.O O.000 O.000 O.O 930 0.437 4.437 7.3 0.472 4.472 7.9 940 0.703 6.403 11.7 0.759 6.459 12.6 950 0.912 8.112 15.2 0.984 8.184 16.4 1000 1.102 9.702 18.4 1.189 9.789 19.8 1010 1.254 11.054 20.9 1.353 11.153 22.6 1020 1.159 10.159 19.3 1.251 10.251 20.8 1030 1.102 9.502 18.4 1.189- 9.589 19.8 1040 1.026 8.926 17.1 1.107 9.007 18.5 1050 0.969 8.469 16.2 1.045 8.546' 17.4 1100 0.931 8.031 15.5 1.005 8.105 16.7 1110 0.893 7.693 14.9 0.963 7.764 16.1 1120 0.855 7.255 14.3 0.923 7.323 15.4 1130 0.817 6.917 13.6 0.882 6.982 14.7 1140 0.798 6.698 13.3 0.861 6.761 14.4 1150 0.760 6.360 12.7 0.820 6.420 13.7 1200 0.741 6.141 12.4 0.800 6.200 13.3 1210 0.703 5.903 11.7 0.759 5.959 12.6 1220 0.665 5.665 11.1 0.717 5.718 12.0 0 1230 1240 0.646 0.627 5.446 5.327 10.8 10.5 0.697 0.677 5.497 5.377 11.6 11.3 1250 0.608 5.108 10.1 0.656 5.156 10.9 1300 0.589 4.989 9.8 0.636 5.036 10.6 1310 0.570 4.770 9.5 0.615 4.815 10.3 1320 0.551 4.651 9. 2 0.594 4.695 9. 9 1530 0.532 4.532 8.9 0.574 4.574 9.6 1340 0.513 4.413 8.6 0.554 4.454 9.2 1350 0.494 4.294 8.2 0.533 4.333 8.9 1400 0.475 4.175 7.9 0.513 4.213 8.5 1410 0.456 4.056 7.6 0.492 4.092 8.2 1420 0.456 3.956 7.6 0.492 3.992 8.2 1430 0.4~7 3.837 7.3 0.472 3.871 7.9 1440 0.418 3.718 7.0 0.451 3.751 7.5 1450 0.418 3.618 7.0 0.451 3.651 7.5 1500 0.399 3.499 6.7 0.430 3.531 7.2 1510 0.399 3.499 6.7 0.430 3.531 7.2 1520 0.380 3.380 6.3 0.410 3.410 6.8 O
es REACTOR BUILDING DOSE RATE 5
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U TIME 4TH FLOOR STH FLOOR - CHR53 GAMMA G+B GAMMA GAMMA G+B GAMMA CR/HR] [R/HRJ [MR/MINJ [R/HRJ [R/HR] [MR/ MIN 3 920 O.000 O.000 O.O O.000 O.000 O.O < 930 0.495 4.495 8.2 0.515 4.515 8.6 940 0.796 6.496 13.3 0.829 6.529 13.8 950 1.032 8.232 17.2 1.075 8.275 17.9 1000 1.247 9.847 20.8 1.299 9.899 21.7 . 1010 1.419 11.219 23.7 1.478 11.278 24.6 l 1020 1.311 10.312 21.9 1.366 10.366 22.8 1030 1.247 9.647 20.8 1.299 9.699 21.7 1040 1.161 9.061 19.4 1.210 9.110 20.2 iv50 1.097 8.597 18.3 1.142 8.642 19.0 1100 1.053 8.154 17.6 1.098 8.198 18.3 1110 1.011 7.811 16.8 1.053 7.853 17.6 1120 0.968 7.368 16.1 1.008 7.408 16.8 1130 0.925 7.025 15.4 0.963 7.063 16.1 1140 0.903 6.803 15.1 0.941 6.841 15.7 1150 0.860 6.460 14.3 0.896 6.496 14.9 1200 0.839 6.239 14.0 0.874 6.274 14.6 , 1210 0.796 5.996 13.3 0.829 6.029 13.8 1220 0.753 5.753 12.5 0.784 5.784 13.1 O- 1230 0.731 5.531 12.2 0.762 5.562 12.7 1240 0.710 5.410 11.8 0.739 5.439 12.3 1250 0.688 5.188 11.5 0.717 5.217 11.9 1300 0.667 5.067 11.1 0.694 5.094 11.6 1310 0.645 4.845 10.8 0.672 4.872 11.2 1320 0.623 4.724 10.4 0.650 4.750 10.8 1 1330 0.602 4.602 10.0 0.627 4.627 10.5 ! 1340 0.581 4.481 9.7 0.605 4.505 10.1 1350 0.559 4.359 9.3 0.582 4.382 9.7 ( 1400 0.538 4.238 9. 0 0.560 4.260 9.3 1410 0.516 4.116 8.6 0.538 4.138 9.0 1420 0.516 4.016 8.6 0.538 4.038 9.0 1430 0.495 3.895 8.2 0.515 3.915 8.6 1440 0.473 3.773 7.9 0.493 3.793 8.2 j 1450 0.473 3.673 7.9 0.493 3.693 8.2 l 1500 0.451 3.552 7.5 0.470 3.570 7.8 1510 0.451 3.552 7.5 0.470 3.570 7.8 1 1520 0.430 3.430 7.2 0.448 3.448 7.5 { l c' \
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AUX BLDG WALLS CONTACT DOSE RATE TIME CHRSJ GAMMA [R/HR] 920 O.000 930 C.006 - 940 0.010 950 O.012 10'00 0.015 1010 0.017 1020 0.016 1030 C.015 1040 O.014 1050 O.013 1100 0.013 1110 0.012 1120 0.012 1130 0.011 1140 0.011 1150 0.010 1200 0.010 1210 0.010 0 1220 1230 O.009 0.009 124O O.009 1250 0.008 l 1300 O.008 1310 0.008 1320 0.007 1330 0.007 1340 0.007 1350 C.007 1400 O.006 1410 0.006 1420 O.006 1430 0.006 1440 0.006 1450 0.006 1500 0.005 1510 0.005 1520 O.005 29220 AUX BLDG 29230 WALLS
1 Reactor Building i Iodine Concentration Time Total % MPC 0930 323,428.1 0940 618,135.9 t 1 0950 890.644.6 1000 1,141,274.5 1010 1,374,017.8 1020 1,278,726.9 { 1030 1,194.165.6 1040 1,116,502.4 1050 1,043,683,8 1100 974.799.4 1110 910,764.1 1120 852,440.0 1130 797,242.6 1140 745,745.1 1150 698.482.5 1200 652,386.9 1210 614,996.3 1220 575,891.3 1230 538,891.5 1240 504,232.9 1250 475,941.6 1300 446,647.1 1310 420,299.5 1320 393,140.0 0 1330 1340 370,374.7 348,583.4 1350 327,842.6 1400 308,630.8 1410 290.612.7 1420 273,021.2 1430 258,399.0 i l l i
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1 REAETDR DLDB. AilD TERSOlJNEL GURFACE CONTAt11 NAT I ON e T1ME SWIFE5 PERSONNEL [HR] I100 CM23 CONTAMINATION
-LAMBD CPM CPM 920 0 O )
930 8450.64 G4.5 [ 940 32094.39 320.9 ) 950 679G8.30 679.9 .{ 1000 113G54.9 1138.5 i 1010 167G93.0 167G.9 1020 221D1U.3 221D.2 -4 { 1030 268794.G 26G7.9 i i 1040 309917.O ..099.2 ] 105i, e.4 6 0 0 0 . 4 3460.0 ,] 1100 J.7 77 3 2.1 - 3777.3 l' 1110 405679.3 4056.S ' 1120 430360.7 4303.- 1130 ~4S2218.0 4522.3 114u 471595.V 4715.9 1 15 t' 4 887 G2. ".' 4G87.B j 12vu t,04 028.1 5040.7 h 12iv 122u 517617.9 t;29 7 e>2. D 5176.2 5 2c.~. 6 - 123e > 540538.O 540D.4 124o 550078.4 5500.O j 1 2 5'. ' 550378.5 5585.G 1304 566164.1 D641.0 1310 572694.8 5720.9 1320 57DO2D 9 D7DB.3 l 1 l:.30 584042,9 5840.4 1340 500630.4 5806.4 1350 59 2e>53. 2 572ca.6 1400 596151.B 5961.5 1410 599168.6 5991.7 1420 601730.B 6017.4 1430 60391G.8 6039.2 1440 605758.4 6057,o 1450 607275.7 6072.8 1500 608495.7 6085.O 1510 609447.8 6094.4 1520 610152.1 6101.5 l 1 1 1 ~.
SCE!!AK 0 FEFJ1X 87 CLOCK TIME = 1040-1330
!!ESSAGE D0. OSC C01:TROLLEF SCE!!AK!C TIME = 0340-0630 0 FEP.MI - 2 E!'EEGE!?CY PREPAREDNESS EXERCISE MESSAGE FOPJi '
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ATTACHME!!T 1 1 Above 2.5 Ft. Thich Cor.ct erc Slab Above RC:C Sub-bacccent Corner 0 Dose EoOL. Ecte 3 Ft. Total Doce Rt I-Tiro Ret /Hr cec /Hr mRec/cin 1045 1.2 1200 20.0 1050 1.3 1300 21.7 1100 1.1 1100 18.3 1110 1.0 1000 16.7 1120 0.94 940 15.7 1130 0.84 840 14.0 i 1140 0.75 750 12.5 1150 0.67 670 11.2 1200 0.61 610 1C.2 1210 0.54 54C 9.0 1220 0.49 490 8.2-1230 0.44 440 7.3 1240 0.40 400 6.7 1250 0.36 360 6.0 1300 0.29 290 4.0 1310 0.26 260 4.3 ; 1320 0.24 240 4.0 l 133C C.20 200 3.3 . 1340 0.16 100 3.0 () 1350 1400 0.16 0.15 160 150 2.7 2.5 14 0 0.13 130 2.2 i 1420 C.12 120 2.0 I 1430 0.11 110 1.5 1440 0.10 100 1.7 1 l l O
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ATTACE!:E!.'T 2 Doce Kcto Duc to F.cciation Shine Tliru Doorvey of RCIC Sub-basement Corner Roora (1 Ft. f ree. Doon.ay) Total Dose Rt Tir c (Ree/Hr) 1045 2137 , l 1050 2368 1100 2189 1110 2007 1120 1836 1130 1676 1140 1530 1150 1395 1200 1273 1210 1161 1220 1060 123C 967 1240 ES3 1250 607 1300 738 131C (74 1320 617
- 1330 565 1340 517 O 1350 1400 473 434 1410 398 1420 3 65 1430 334 1440 3C7 1450 2E2 1500 259 i
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ATTACH!4CTI 3 Dos,e Esto Thru 4 Ft Thici Conc rett Wall (Dall-is the East Wall of the-Subbarctent - RCIC - Corner Ecom) l (Doce. Point is Onc Inch Fro Wall Surface) 4 Total Dose Rt Ticie Ret /H: tRet/Hr - l 1045 2.0x10[2 20.2 1050 2.2x10 22.2 -q
-2 1100 2.0x10 20.2
-2 1110 1.8x10 18*2
-2 1120 1.6x10 16.1 l i
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SCEt:ARIO FERMEX 87 CLOCK TIME = 0920-1400 MESSAGE !!O. Chemistry Controller SCEMARIO TIME = 0220-0700 0 FERMI - 2 EMERGENCY PREPARED!!ESS EXERCISE MESSAGE FORM MESSAGE FOR: Chemistry Controller MESSAGE: Give chemistry sample sheet for the time the sample was t aken O FOR CONTROLLER USE ONLY: C0!TIROLLER !!OTES: ACTION EXPECTED: Results reported to Control Room /TSC. O
PDF.TACCIDENT SAMPLEG MESSAGE NO. CAR 1-- 1 i TO: CHEMISTRY TECHNICIAN FROM: T E AM DTRC ] OE CONTRD!.LER/OSC CONTROLLER LOCATION: C H Eri i. A I;/ 0 C.C 11ME: AL REDUEST E.D Wil HIN Af PLICABLE TIME FRAT 1E i: LLE cot 1M3NTS SECTION DELOW) i El .tui , !, : 4 ._, i N O L , 'i i F 3 t li 5- L P.RT h 1 DEu. ANAL f Ul c) 16 RUUUL1 3 Wii
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@ PCGTACCIDENT SAMPLES MESSAGE NO.. CART- 2 ( TO: CHEMISTRY TECHNICIAN FDOMi- TE All E)'ERC1 F" CONTROLLER /OSC CONTROLLER LOCATIDW: ClIEh LAD /03C 11ME: AS REDLIE51ED W1TH1N APPLICABLE TIME FRAME (SEE CDhMClJTG SECTION BELOW) I' F i 'I FE- O~ '601 ; . 2LULllr F111EN Lud<T h 1 DGL - ANAL YS) f. 18 August 1987 1H15 IS A Dh1LL DG I A.i l t44 .. x t i coir , i f e.- t 2 n a rior me ] plant esperat 2 ons NU( .I Is F s nIVf1, t i lC 1/ r r ) COMMENTS 1 1._. i 1. 8eE - 0~/ IEDLI1E FILTER l!JVE N I CM @ ] 6. /2E- t ' 7 Resul t c. shalI be avaa3ab]e AW i 4 .., a, o t t., / c, t. - : .4 . Iiuus s si o a.> , 11". F. , !G F-O'? 4 c.r anv F a rnril r i d t+r , 6 4 or prior
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NWSU 0769 E L>u ) L I I H 1 UI i LORE RElIADE I'. DAbED ON NilCl J DEF 114 THF RX BL Df; AND RCI O ROOM
- 9 i . !T.. IOD]NES PFl1DVEs Ei 5GTL CHARCDAl BEli TH1f. 18 A DRILL
. . . . . . . . _ . . . . _ . . . _ - . . . . _ , ~ . . . . . . .
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1 O PODTACCIDENT SAMPLES MESSAGE NO. CART- 3 ,. TO: CHEMISTRY TECHNICIAN FROM: 1 E AM E.XERCT CE CONT ROLt.ER/DEC CONTROL.LER LOCATION: CHEM lab /OK TIME: 45 RFDllFSTED WlTHIlJ APPLICABLE TIME FRAME (SEC CONr1ENTS LECTION BELOW) r[ieHi H F..,1-1 d ai ITi F lt TLi ( sFsl R J 1EE ANAL (515 18 August 1967
'i f i l b 11 4 DRlLI DO NO! te*e ~ <: t a on s . f + e..Iino r i c r m.+ 1 plent operations l .;U F i I D; niiTV)1x i lli' I J c t i C Dl1NiiNT S
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- Nt lR E G-- 0764 EiAl3 L 113k l Uh ChiE RE L E AE.E 15 DASED Dil NULL IDEi 1N THE RY DLDG AND RClr RDDM
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POSTACCIDENT-SAMPLES MESSAGE NO. CART- 4 TO: CHEMISTRY ~ TECHNICIAN FROM: TE AM EXERCISE COlJTROL LER/05C CONTROLLER t ..OC '.1 10N : CHEN LAD /DEC FIMC: AS REQUE51El) Wi~f HIN siTL1 CABLE TIME FRAME 15EE COMMEldTS GECTIDH BELOW) i ll.l :'s
. f. .64' i i . t. .L 1 'i l . I ' l i fi E F Emi~lR1DDL ANALiS]b 18 August. 1987 ,,
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- NURE G - 07(,9 LDU I L 1 Dil] Ul1 Curd
- RELE ASE 15 BA3ED ON NiELJOE5 IN THE RX BLDG AND RCIC ROOM
- 99. 51. I OD I NE!) RE t iO'XL T. E'GT5 CHARCOAL DE L.
THIS lb A DRI LL. O l .
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@ POSTAECIDENT. SAMPLES MESSAGE NO. CART- 5 TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATIONt CHEM LAEu05C TIMES AS REDLIEST ED W31HIN APPLICABLE T IME FRAME (SEE COMMENTS SECTION BELOW> FEhld i t. ai , i '. z Eu' i l e. t lt ilk CARTRIDGE: ANALYSIS 18 August 19sy 1H]b lb A DRILL 00 idW tev e ac t i o >i. e i -i m. t i n g horna] plant operationt Ndut. j i t AL i l '.' l l - (UCJ/LCi COMMENTS 1 -- i n t 6. 5M '" ' 7 2EOLIll' F ILTER 11 WEN 7Dkt -
. 4.q ny 1 - l '. . 1.42h-u6 kesu]tt Ehsl1 be e v 6 i l' a b l (-
.i . .' t ei .. . . s livur 2 ~i , u :, W 1_1 % 1. :.' 1 F -- Oc 4 or env sanip) e. t alen at or prior to 10:in hours (T + 0: Sui APr.!5H;TIONT
- NURE G-m a EOUI LI DR 3 Uii Cu -r.
GEL.E A5E I5 BAEEb ON IJUU.L 3 LE 5 IN THC RX DLDG AND.RCIC RDOM j 9 9. 35 IODINEG PEMOVED br EU! u CHARCOAL BED i
. . . . - . . . _ . . _ . . . . . _ . . . . _ . . . _ . . . _ _ . . _ . _ . . . . _ _ _ _ . . . _ . . _ . _ _ . _ _ i
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O POSTACCIDENT SAMPLES HESSAGE NO. CART- 6 TD: CHEMISTRY TECHNICIAN-FRON: TEAM-CAERCiSC CONTROLLER /OSC CDNTROLLER LOCATION: CHEH lab /05C 11ME: AS REDUES1LD WITHIN APPLICABLE. ~ll:1E FRAME (SEE COMI1ENTS SECTION BELOW:e l 1 u- 16 August 1987 F L RMI ). Si i; e i ( q.1 T E F 1 Lli.h CAirTRI DGL ANAL'i S J b I H) d, 15 n DRILL l Du Nui t a .e e c t i cm. wt r e r ; n g n or n,a j plant operattons l IU ir.1 11 'i: AC i ! U iT i ( UC 1/ CC > COMMEN'15 1 1-JPi c. 08E -- O'/ 2LDLITE FIL1ER-INVENTORY . l
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ehal) be avai1abte ivaz6 n u'.i t s u , 4. O, I 1-1?^ 1.10E-06 (or any esmp)e ieken at or prior to 10: 20 houre (T 4 1: of ( 50 LIMP I I O!F
- NUREb-076ti EQUILibR'uh l LokE FELEASE 15 BASED ON NUCLil'EC IN THE RX DLDG AND RCIC RODM
- R ;' . 5 ",, 10 DINES REMOVED fo BG15 CHARCDAL. BED i r l1 T. 13 A DRILL
. . . . . _ . . .__ . _ . . . . _ . . . _ . . . _ _ . . _ . _ _ . _ . . . _ _ _ . . . _ _ _ . _ . _ J O !
P O S T A C C 3 D E N'1 SAMPLES MESSAGE NO. CART-- 7 TO: CHEMISTRY TECHNICIAN FROM: TEAM.EXERCIEE CON 7 ROLLER /OSC CONTROLLER LOCATION: CHEM LAB 103C IlhE: Ab REDULLTED W1 RHIN APPL 1 LADLE T)ME FRAME - (SEE COMMENTS SECT 10N BELOW) F L krn ? f. ' u.i . L u.. ; T'i . i :L iLh iAhTh.t%L ANAL 61S 18. August _192.~. l i tia u .i .. n 1 ri A' L t l
- m. W.) i . a . s.- e. .u , c i f e_ c 1 n o n co cm ; pianL operationt l N jti.1 id.
. i--i i JJi) 4UcJeQ LQ1r1EN f b J - j :?. i 5 ' 1 E -- u ? ZEOi]TE FIL'IER INVENTORY I
- 1. ;- s , rc..j p . . , ;
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} } ' i 1-135 1. WE -Oe- for anv Eamp) e tsken at cir pr ' a(<r to 10 .~.0 houro (T + 1:JOs ASSUMFT1Otx NLIREE-0769 EDilILIERIUii f ORE RELEASE IS BASED ON NUCL I DE". ;
TM THE RX I-:LDG AND RCI C ROON. !
" ; . G '< . I OD illr : REMOVED P'- -
cGTA' I i
.AARCOAL BED i
T H 1 E. IS A DRILL ;
POST ACCIDENT SAMPLES MESSAGE NO. CART ~ 8 a 10: CHEMISTRY TECHNICIAN FROM: TEAT 1 EXERCISE CONTROLLER /OSC CONTROLLER l LOCA1 ION: CHEM LAB /OSC TIME: AS REDUE5 FED W1 THIN APPLICABLE TIME FRAME (GEE Cot 1MEllT5 SECT 10ll BELOW) l 8b i t. 2 E U: . j l i'. F 11 T Li.; LAR iR1DGE ANALYLib 16 August 1987 FERNE Ob lHIS IL A DRILL DO NC. i tae ac u ent a f i ec ti ng n or rre i plant cher ati ons NUL L :i uE F T]VIit (UL1/CC, LOMMEllT5
) -- > T ] b.44E-0/ Z E DL. I ~I E FILTEli 1NVENTOPY .
I-j'. ~ .; ..,. 1-17N 1 . 1 8 F- ~ w . Results shall be eva.i l abl e O 2 -4., % . -f t u - v , o . ? ,4 E ...t:i r et i . . 4.> livur . for anv semple telPo et or orior s,
~
s 2: e
]-1'S te i0: 4.* hours i1 + 1 20.'
ASN 4n ] te
-- NUREG-07e,9 E DU1 L..l bH1 Uh cop 1
- RELEASE 15 BASED ON NUCLIDEb IN THE RX DLDG AND RC1C RODM 9 7 . S',. 10DJN26 REllOVED BY EGTE CHARCOAL BED
'i l l] 5 15 A DRILL v
l l O PDBTACCIDENT SAMPLES MESSAGE NO. CART- 9 ( TO: CHEMISTRY TECHNICIAN 1 FROM: lEAM EXERCISE CONTROLLER /OSC CONTROLLER i LOCATION: CHEM LAD /OSC l TIME: AS REDUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMEIG5 SECTION BELOW) , FEkhEX e- s<e, t 2euti1e iitits eARTR1Det sNatvsis is Auguet 19u7
'lHlb lb A i> RILL DO NOT tsEe act1ont eif e uc. La reg normaj plant cperationn NUCt IDE V. " l '.' 1 t i (UCi/CE; CONMENTS 1 .1 J 1 J Cl -C' LEOLITE F ILTER INVENTOFW
. i II 1.- j 7 - !> . 5 4 F -05 Rceultn chalI be avai1sble I 4 -..oi_
j _ ) 7 r, 4 . n ;?l- . iv - f or any E aspl e t ad-:er, s. t or et >tu-in 10 D0 hours. (T + 1 : ". v ' A E -3U: 1Pi1DNL
. . . . ~ . _ . . . _ _ _ . _ . . _ . _ . . _ . . . _ _ _ _ . _ _ . . . . _ . _ . . _ . . . - . . . _ . _
- NUREB-0769 EDUIL]DR1UM LORs l
- FELEASE 15 BASED ON NUCL]DET IN THE RX BLDG AND RCIC RDOi1 l W. S% IDDINES REMOVED Bi LG l '. .
CHARCOAL BED l l i 1 1 i i 1HIS IB A DRILL O l a
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POS1 ACCIDENT SAMPLE 5-MESSAGE NO. CART-10 }
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TO: CHEMISTRY TECHNIC 1AN' 1 FROM: TEAM EXERCISE CONTROLLER /OSC CONTn0L.LER ]1 LOCATION. CHCM LAB /05C 11ME: ' A5 REDLIESTED WITHIN APPL.1 CABLE T IME FRAME (SEE COMMENTS SECTION BELOW) FERML5 E SG ! 6 . 2 L Ut 1 TE l- ) i. 7 LR C Akl h 1 D(:iE ANALYS1 b 18 August 1987 1 ril b- .i b a DR1LL I
++Tm, ting lior me j piant operationu l Di. . NOT t r. u s( ' 3 t.> _ is NUCL I bf.- siiiV11i' t. U C I / C L .i COMMENT 5
- 1;.i 2.$6E~Ob ZEOi 11E FILTER J NW NTORY -
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.o 11r 0 hours (1 + 1:40 A5ElIMr 1 I Ot!.-
NURED- 0767 EQUI!. lithIUr1 CORE
- RELEASE I S IcAGEO ON NUCt.1 D'E 3 IN THE RX BLDG AND RCIC RODl1
' ' 7 . 5 ",. I O D I N E ~2 RE MO' ?ED P'i GFi:
CHf4RLDAL BEli E S , y,
l l F~ OST ACCIDENT sat 1PLES
. MESS 4GE NO. CART-11 TO: CHEMISTRY. TECHNICIAN I
FROt1: TF At1 EXERCIST' CONTROL L.ER/DSC CONTROLLER LOCATION: CHEli L Ab e O3r T1ME: AS RLOUE E'iEb W)'l H11J APPL ICABLE TIME FRAME (SEE COMMENTS SECTION BELOWi iLNHF, 6 & .1 : S t. ( u 11 F i li .li h LHh1R]bOL AN.-iL H. .i b 18 hugust 190' ,
. . . . _ _ . - . . l 1 Fi) u 16 6 Di:.i Li.
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- FELEABC 15 B ASED ON Nitr! iDE c-IN THE RY DLDE. AND RC)C RDDM 77 55.; JODIl4E5 REMOVEL 1 ~GTO CHARCO4L Deli TH)6 IS A DR1tJ i
.O I' DST ACC] DE NT SAMPLES MESSAGE NO, CART--12 TO: CHEt11STRY TECHNICI AN
.FROM: TEAM EYERCILE CONTROLLER /OSC CONTROLLER LOCA110N: CIlEM LArs/05C TTME: AS REDUESTED WITHIN APPLICABLE TIME FRAME (GEE COMMENT 5 GECTION BELOW's iLRML) 07 Sten D 7E(o 1TL fltTEP C Ai..TR I DbE. ANAL V5)'S -
"U"St 1W fH15 15 A DRJLL Dil NDf t+ie acL1ons ei+m ting normai p1 ant oper ati ons N(tC i I nt' Ar.l[7]TV (tic],D > CONMEj p g 1 - 1 '. ) . 1DL- % 2EOL1TE I I L ') ER I N'& N1 DR i .
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1 .1 , 4.68F-05 Res ul l t shall. be a vai .l el. 3 0 @ i .i . -i ... 'u ' .- J. ei 1 3.sv incut a +i i z. <! . 1 T - 3 ~'. r. Il.03E-05 4 c.r any yampie tapen st nr prior ~ in 11:20 hot ir e UI 4 ?- 0) A ..U hr , I O N n NUkEE--0765 EDt!1L I BRItIK CORE RE l.C ASE IS BADED ON .NUCL 3 DEE IN THl.T RX DLDG AND RCIC ROOM
- M . EP 10 DINE 5 (WMOVEi.i Di 5G'i t CHARCOAL DED l
if t1E 1R A DRILL
@ POSTACCIDENT SAMPLES MESSAGE NO. CART-13 TO: CHEMISTRY TECHNICIAN FROM: TEAtl EXERC]SE CONTR>LLER/OSC CONTROLLER LOCATION: CHEN LAI.6OSC TIME: AS RF.DUEST ED W11 HIN Af4'LICAbLE T IME FRAME (SEE COMMENTS SECTION BELOW'.i FFRhEA E. / St ,i 9 z l-l.t A.. ] *6 E f 1i 'i Eh L AF'l k 11,E.E ANAL t 515 18 Augus.t 1987 Tillb lb A I;RJLL i Dit i nu t ten e.4 m r oi i e eft-ertjiin n or n. + .i plant operatJons ._ . . . . , _ . . . . . - _ . _ _ . _ . . _ . - . _ . _ . . . . . . . _ _ - . . . . . _ _ _ . . . _ . .~
l No.N 1. 1 Di.' (#IiVITi ( Li(.1/ C f i COMMEN15 1 3 i'.i 2.06E.-Ob 7 EOt. .I l E FllTEF. INVENTDRi j , - - .a t m-
] - 1 ,5 4. 47 E H.6 be+ulte shalI be avai)aM e
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1 -. 3 ?.= , . 79F-05 4 or anv s anini e tal eri ;-( rv r"- i c 't - ta 1 1 30 h ot tr e.: (T + 2:10> E9 !!1r17 PNS
. . . _ . _ _ . - _ _ . . . . . _ . . . _ . . _ . . . ~ _
l
- NURE.G- Ol 69 EDUIL1BR1Un CUhE.
RELEASE 1b E45ED ON iluTL I DF ' IN THE RX DLDG AND RCIC ROOM 4 9 . D'. IOD]IlE R E N D'W l - B' B5i i LHARCOAL BED i l
'l H 1 h 1S A DF]LL
. . . . _ . . . . . . . _ . . . . . . . _ . . . . . . . .. . . . . . ~ ..
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F'OS1 ACCIDENT SAMPLES NESSAGE NO. CART-14 t TO: CHEMISTRY TECHNICIAN F~ ROM : lEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCAT lOlh CHEM LAD /OCC (IME: Ab REUUE.5TLD WJ1HIN Af+LICABLE T IME FRAME WEE COfir1ENTS SECTION BELOW) i'i hhl >- U S E. . L E t.t . tt 14 JLiEF CAF.Ih1 dbl ANALYb.1b I8 August'1987 Irub ab A DRALL Du Hul t a1 e e c t i oi > a r , e; L ) : a neia.e! p) ant op er e t.2 an s
. . . . _ , _ . _ _ _ _ . . . . . _ . . . . . . _ . _ . . _ . . _ . _ _ . . . _ . . . _ . _ . _ . . _ . . . _ _ _ . . . . . . _ . . . _ . . _ _ . = .
NUi.L1DL m . i 15. I 1 ',' ( Ut. J / LL 4 LOMMEN16 3 -- I '.11 i . %i 05 ZE DL 1TL F1LTLE INVENTORY
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7 1-31 4 . 2 6 E -. 0t. hecui t e. thalI be av.n1aL*]e 4
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1 177- . r, f ..n5 4or any sautpl e t al en et er rmior to 11:4v hours (. T + 2: T:0 > cm.iMT T ) nNr rluFEG- 07e9 EQUIL 3 Df:J UN EURi PELLAGE 16 DAGEL DN NUELIDEE IN THE. RX DL DG AND RCIC ROOM 0 9 . D*.; I DDINES F EMOVE'D D GCTF CHARCOAL. UED _ . . . . . _ . . . . . . . . . . _ _ . - . ~ . . . . . - _ . . . . . _ . _ . . - . _ . . . , . . . _ _ . _ _ . . _ . . . _ _ . . _ . . _ _ _ . . . _ _ . T H 1 E. IS A DRILL. l i O 1 i 4
POSTACCJDENT SAMPLES 1 MESbAGE'NO. CART-15 4 TO: CHEMISTRY TECHNICIAN FROll: TEAM EXERCISE CDMTROLLER/OSC CONTROLLER LOCATION: C HEN L AD,'OEC 11ME: AS REDUELlL1) W1"lHIN APPLICABLE TIME FRAME (GEE COMMENTS SECTION BELOW). i ' i W, f m 1 t. .Et, 4 ; i; i 1L iLF LAR1kitsE Al.:AL r El b 10 August 19G7 liud AL A bk l Lt. DU tel t e i . .: e t t .t to e. . e .. L 3 ; . c r rre mai p1ctit epwr at a vi n. 3 Ns.h_ L t DE A J. i iVili (UCI .'CL ! LOM11EN13
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A F W a.n u T 1 O N ; NUREG -0760 EQUli 1DFIUM i.OT f
- REi F AGE 19 fiASED DN NUi L ] DFE IN 1HE RX BLDG AND RC3C RDOM
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CHARCOAL DED 1 1 1111 D 10 A DRILL
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. POE.14CC I DENT 5AMFLES ME SSAGE 140. CART-16 TO: CHEMIGTPV TECHNICIAt!
FROti: TEAh EXERCISE CONTROLLER /OSC CONTF.OLLER LOCAT10N: C H E tt L A13 / 0 5f f T I ME.: AS REDUESTED WITHIN APPLICABLE 11ME FRAME (SEE CDMt1 ENTE EEC1104 BELOW) .1 F LRML ). E' : : : 2LDL3it' +at T EF LidsT R I bL,L P!aAL Y b] b 18 August 1987
. _ . . . . . _ . . - . . - . . . _ . . . . . ~ . . .
THJD lb A DRILL j l i>O I-ia l t ai e +ctaoin aff- :11ria nocinsi plent operatient
- - . . . 1
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O PO51 ACCIDE;N1 SAMPLES MESSAGE NO. CART-17 TO: CHEMISTRY TECHNICIAN 1 i FROM: TEAM EKERCISE~ CONTROLLER /OSC CONTROLLER LOCAlION: CHEM LAB /OEC
't IME: AG RL WULE.,TLD WIl HI N APf 'LI CADLE TIME FRAME (EEE COMt1ENT5 5ECTION BELOW) 1 i L l d ik. ' [- .-1: 4i L .4 4 I* } jt.ikdt L. ish 'l I .1.L'(.iE. 6!jHL Y i J [ $ b bLt9LtEl 19bk I M l. ' .i IL ti Oh1LL OU iI,I I e e- e,. ia;* 6iTt c L J r i L, r p u t ' i.% i p 3 ir i i l ul., L< r ec. L ,) UI i _
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- RiLEASE JE BA9GD DN NUCLIDr5[
IN THE Ry 1:LDG AND RCIC RODh m; 5 IOrINEB REr 10'N D Py B 7T ' CHARCOAL BED 1 a l 1 i 1H1E 15 A DRILL
j i O POc T ACLI DEtJ1 5AMr'LES MESS 4GE NO. CART-13
~10 : CHEMISTRY TECHNICIAN I7RDM: TE AN E~ XE:Pr I LE CDNTROLLER/Osr. CONTROLLER LOCATJDN: CHEM L A0 /05C I 1 MI. : at Fd. OUE 51 E.D W11 HI N AF+L IC ABLE T IME FRAht (SEE COMMENTS SL'CTION BELOW>
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.I NE55 AGE NO. CART-19 1 1
1 4 10: CHEMISTRY TECHNICIAN l rROM: T E Ali E)ERC.15i~ CONTROLLER /05C CONTROLLER L.OC WI I DI .i: CHEh LHb/OSL
.llME: AS PE DLIE STED IJI'l HI N A5'PLICAbLE TIME FRAME
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@ POSTACCIDENT SAMPLES MFS54GE NO. CART-20
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FROM: li AM EXER ( ISE CONfPOLLER/OSC CONTROLLER LOCATIOlh CHEH LAbiObL TIME: A5 RE.DtiE ST El> WI'lH]N APPLICABLE TIME FRAME - (SEE COMMENTL GECTION BELOW) F f RME. i 'i., R .' i . . E ., '; i i > 1: i f -- CABTr<1pbE Ai4AL v b 3 3 15 Augutt .1 E i _ , _ . . . . - . . . . _ . . _ . . . _ . . . . . . . . . . _ . . . _ . . . . _ _ . . . . . . _ . _ . . _ . ~ . . . . 1hli li A DR1Lt. in i n';.i i t c. *',e.ie g , , e -i. 3 A u rior m i p .I a n t oper at i ons u!o I nt w r 1 ;' f - ( OU i ' i.. (? COMMENTS 1 - :' '
- 1. 4 3i -- OD '/E Di I T F I"]l 1 Ek INVENTORY
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- e: .b. 3 00) neb REMOVED F4 i Sfii t.
C HAECDAL IED l
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T H' J 5 15 A DRILL. l O a i q
e ' s O 5 f'OSTACCIDENT SAMPLES
*1E55 AGE NO. CART--21 Q"~
TO: CHEMISTRY TECHNICIAN FPOM: TEAM EXERCISI llONTROLLER/DBC CONTROL.LER
' LOCATION: CHEM LAB /OSO. r TIME: AS REDUE.ST ED W.I'lHlN APPLICABLE ' TIME FRAME (SEE COMMElFrS SECT]ON BELOW)
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1 i i 1 0 PO5TAFCIDEN1 SAMPLES MESSAGE NO. CART-22 TO: CHEMISTRY TECHNICIAN fROM: TEAM EXERulEE CulJTROLLEFuGSC CONTROLLER I
'L.DC AT 10N : CHEli lab /OaC TIME: AB .hE DUE:-ilED W] li t) N APF'LICABL E 'l IME FRAME :
(SEE COMMENTS SECTION BELOW) iLRMF h- .i . l i, 2 L rn i i F F J L T L i< C Ah T h 1 DGE: ANAL YE j s 18 August 1%
'l H I E, JS A DhlLL DO IFi 4 i>e sct2 orn. e 5 4 6- c t .i rio nor mai r. ] ari t operations .. . -. . . .. - .. . . - . . . . . . . . . . . . . . . . .. _.._. _. + . . . . _ . . . .
N1.F. I T i >;- A C ) U J i , '
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] . 3 7. ) 1. .lesL --OS ~EOL)TE FJLTER INVENTORY
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- NUhEErO764 EQUILIBRIUM CDbE
- EEL.EAGE 15 BASEE ON NUCLIDE5 IN THE RX DLDG AND RCIC ROOM
- , 5 ', . IODINE 5 hEriOVED 6i' SG i :.
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l TO: CHEMIGTRY TECHNICIAN I FROM: TEAM EXERCJCL CDllTROLLER/OSC CONTROLLER LOCATION: CHEN LA1.4/05C IIHE: 85 RLOUESTEli WITH)W APPLICABLE TIME FRAMi_ (SEE COMMENTS SECTIDW BELOW) i i. rt hi. > t. ; - .' i t a .1 i t i itit,
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. 1 F'DETACCIDENT SAMPLES MESSAGE NO. CART-25
( TO: CHEMISTRY TECHNICIAN TROM: TE(iM EXERCISE CONTROLLER /OSC CONTROLLER LOCnT]DN: CHEH L4b/05C TIME: A5' REDUESTED WITH1H APF L ICABLE 13 ME FRf;ME (SEE COHriENTS SECTION BELOW') FERhLA i,' Ff i 7 L ut i 1 e i ),1 Eh L ART ki b6L ANAL.n J 5 16 August 1987
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lH1b I E, A DhlLL DO Nui t et i- e c; t. l on e e t i ec. t a n g nor mal plent oper e u un s tiUEi j DE s:.' . r J V 1 T i (UE1/C() COMiENTL 2LDL1TL F.1LTEh 3NVEN1ORv J-111 i.ufi-OD .
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1-17 1. e5F - 4 4 c.r an. t.enip.l e t+d en M or pr i m t ri 13:30 h oi tr e .iT + 4:TOi i.' Ulo 4 tq H 14Uhtf.- 07M L Dilli. ] BRlui; LOhE F EL E(-30 . I P PA5ED Dhi NUCL 1 Dix IN THE RX 14.DB (-ND RC]C RDDM W . 5* . J UI.'I NE L I4i.f10VE i: ba 5GTE CHARCOAL BEb l 1 i 1HIB ]S-A DR)L.L
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l lO F DETACCIDENT SAMPLES MESSAGE NO. CART-26 10: CHEMISTRY TECHNICIAN FROMi 1 E A11 EXERCISE Coif l ROL LE R / 05C CONTROLLER LOCAlION: CHEli L/,L./ 0 3L i T .l Mi : 65 FEUUE01 Eb W1 l H]IJ AfPLICABLE TIME FRAME . l (SEE CONNENT 5 SECT ION BELOW > l E. h t il , f. *r1~ i E o: i ii i ;i.iF h C Ahl R I LGE Al4ALcS35 18 August 19b7 iH;L )!, A DRILL D i .i ND1 i c i e: e c i i r ie - 'in i;i.o n.m n,c i p1 ant opr.r e li one Nili. i i i H . , -d ' i I U J l ') - J4 - cot 1NEi jl b J - ) ~.1 1 ,1 1 - t ' . 2 E Ot.11 E FILThh 1 NVE NT Din' J - 1: . 3 7 6- -ut , f- r o i t s- ciial1 be e v e i 1 e L< ] E-i4 , ..aat t.w, e, 4 ;. : t i'. nuur. (i + - : a., >
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NURE G--O ? e,4 EUli1 L 1 E;k 1 Lil i LORE fELEABE 15 EdAh.ED ON NUCLIDE: 3H THE RX BLDL AND RCIC ROUM 9 4 , 5 ?. LOD 1 JES REM 0'ED B, SGi; CHARCOi-L BED
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I FULTACCIDENT SAMPLES I MESSAGE NO. CART-2~/ 4 TO: CHEMISTRY TECHNICIAN rnOM: TEAN EXERC1LF CONTROLLER /05C CONTROLLER LOCATION: CHEli LAr./05C l TIME: A5 hEuuC51ED WJTHIN AFFLICABLE 1INE. FRAME (GCE COMMENTS SECTION BELOW) i f ittd if '. o. . ! f L t. Di. ) l i.' i' ) t . l l. h t.:Ahi RI DGE ANAL 63b 16 August 198.. lHib 1: A Lh1LL DO NOT L e. i t- in 1 ) 0 4 ... e rie .i.;ria iior um a plent operations
. . _ . . . . . . .. . _ . . _ . ~ , _ . _ . . . . _..- . _ ..__. .._ . . - . . .
NUCLJUE id i 113
, ( Uf.1/ C L i COMMENTb l 1; J . . F.SE -t eo ?EDLITE. FILTER llWEi4T Off r' y ;- - o ,..
1-1T' J . 14 E ' -( .d., h e F u l t r.- shal1 be avcoIable
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I I - 17 '.i 3 , .v.E r.E for ariv sanc l e- take r: at or pr i or to i!': % houre t1 + 4 : Si..i ) 1 1 A 9 9 U;;r 7 3 p! i . I
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- RELEALE 15 BASED DN NUCL11 TEE IN THE RX DLDG AND RCIC. RDOi!
'1 7 . M. I DD II E , EE liC'/ED T i E. i i C'HARCDAL iED l
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'lH1D IS A DRILL 1
f'USTACCIDENT SAMPLES MESSAGE NO. CART-28 l TO: CHEMISTRY TECHNICIAN
'FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER 1
LOCATION: CHEM LAD /05L .l
'i 1 ME : 45 REDUE51LD W11HIN APPLICABLE TIME FRAME (5EE COMMENTS SECTION BELOW) i i L i'ill ) L' wiu k l in. .I ! c i } ! .'l li . L Ahl RI Di.5E ANALYS.ib 18 August'1987
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l Du I EJ I t ci . r t t i cm 6{ectino n ot (.is l p) ant oper eti ons Inla iut si:i i V1 ii (iA 1 Ei , C OriME K i b i f 1--i:.3 4. Oui - ye> iF. OL 1 iE F li..TE R ] NtM NT DR t'
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he wi t s. s-lea l l be avei l eb) t-h 1 -- ! T J . 41E -0.,
. x . s. i . <. m ior ariy e e nip l e t ed: er , at or prior ii s.-
I -- J ~.b 1. ~' O F: - O s... to 14 :. U huure (T 4 4:40) AF5Ui?TTDNF NUREE-076W EDUILIIJR1Ull LDF;E fig LE ASE~ 15 '6ASED ON NUCLIDE5 114 THE RX LLDG AND RCIC ROOM cC S. 3 Olill4EL RE MOVEl> bi 5Gli CHARCUAL BED , 1 1 H .I f- 17" A DRI LL
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l POSTACC11>ENT SAMPLES MESSAGE NO. CART-29 s TO: CHEMISTRY TECHNICIAN FROl1: TEAN EXEREJEE CONTROLLER /05C CONTROLLER LOCATION: LHEli L AluOst , li TIME: AS REDUE5'iED WITHIN APPLICABLE TIME FRAME (LEE COMMENTS SECT 1DN BELOW) F ERME X E, ER 2 F at l'; L i)!1LF L6hT fs 11A ,E Alk:LYb1E 18 Augus.t 1987 I
- _ . . _ . . . . . . . _ . . . . _ . . . . . . _ . . i Trl15 Id A DR]LL D.. I L.i i . a o-
. et. .i ol i s affe.tana nor nei pi ant operetions NIK . I Di AE T 1 ('l T Y ( I..iC J / C C + COHi'iEN7 5
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-i ( . 14: J n h c.o r =- ( ~I < 4:50, AE,dilhI i i i U..
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-- NUF F G-07ee EDU l t. I BR l !.lh C ffi hE L.E AS E 15 UA3EC, ON ht.lCL IDE :.
IN lH!. RX DLD6 (4ND RCIC RODM
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__y_ PDB1 ACCIDENT BAMPLES MESSAGE NO. CART-30 o. TO: CHEMISTRY TECHNICIAN F Roll: TEAM EXERCISE CONTROLLER /05C CONTROLLER LOCATIONt L Hiiii L A B , e s t
'l ] ME : AS REDUE5'IED Wi~fHIN APPLICABLE TIME FRAME (SEC COMMENTS SECTION BELOW) fEhhl) 6 wil i 7 f ut ii t- F. 31 l i f. C Asi i h l D B E ALAL T b a' i 16 Augut.t i te ,
TH]B lb A DRILL l > G N C. . . < o 2 c.o r e e fect4no o cir irie l p1 arit r.sper a t i ons
. . . . ~ _ _ . . _ . . _. .._ . . .. _
N;ht iiC An i L. IT' ( i .'C 1 / ( F . COMMENTS J2 .; . 4 '+ E - v e. z
' f i'L } lf IllIER I NVEN I Oih
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- NUREG-076C/ EDU) L 1 BF.1 Ul1 L t.Ai:
RELEASE 15 BALED ON NULL'lLE5 IN THE RX DL DG AND RC] C ROOh
% 53 ]DDINES fillli:WE D Ui 5.BT S CHARCOAL BED
'l i a T 1 E; A DRILL
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@ POSTACCIDENT SAMPLES MESSAGE NO. CART-31 TO: CHEMISTPi TECHNICIAN FPOll: TEAM FXFRC15E CONT ROL L EFUOSC CONTROLLEP L OGI4T I ON: C HEH l. AD 05C ., {
TJME: AF. Re:.tikl L b^i E)> W] "I HI N APPLI C.AHLii ' LIME F R AliE ( 9.EC COMME.NT S 5FCT I ON BELOW) F Li- . 1 , , ,L , ,it ; ) o 'ti !' i:A':Ier i uHi ANAr. R. i E 10 August 19a7 s tiib jn ei ok 1 Lt be i s ui ; l 1. c , . .-- ii r. r p ,,s t , 7,9 4 , g , j7, g, ,, p. ) co n i. Ol e t-r ,-i l 4 ixi F j thy.1 li r ei jV1I i < Ut ,i /i.i - C O M'iEi.iTf; .l 1 5 T. j . USL -Oe '; ED;. ] i F F ) I,.,TE r: 11.r/i.14T OF 3 . i
~ ! ~~ ry r, i- '. 3 . b . E-u?, Pen 1te Eh ]1 lie n .< c, i et,j e 1.. i ~ 5 V 51E-96 4 c.e inu t:enepl o i;el-en +1 cir. pr1 of io i 41 e f.e hcn tr . ( t '. i : 1Oi f.C ~,1,lt ,r T 1 [l! I NI)F L G- O~/ a." F Ulli L.l itR I U11 - CDr p PJ i iTa-T 1E DA .FD DI.i NUr:1 - I DF ci 19 THE PY F:1.1 6 Al4D Pr.3 C ROOM
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7 HIi 'I'^ A DR)Li O
I i PD9TACCIDFNT SAMF LES (1ES5 AGE NO. CART-32 TO: CHEMTSTPY TECHNICIAN , FROM. TEAM EJEFCISE CONTROLLER /05C CONTROLLER
. L OCA11 Olh CHEN lab /DBC TIME: AS PEDUE D'1 ET) WITH1N APPL 3 CABLE T1ME FRAME (SEE COHt1ENTG SECTION HELOW)
'i I : 'i'MF D :-s: 1 a i F. U iif F .i 1.1 F. h C'4Th1DbE A N D.L'y L 1 ? I 8 A'L9'* t 190 '
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DO Nul la- e r- i > t .r. - ei r a t. 3 e o nor os +]- pieni oper att arm NitrL IDF V i)'..'.1 1 i' O 1:_ t , c i.' . C O N M Ei,iT S 1 i "a t. Li ... 7 E DL l'I E F]LlER }NVENTORY . i l-J l . 41 1 F - i d. Reso ] t t, she)3 tie e vai l at el io O i i. I 1 ~"', (.. .cn. F : , F- J + - n f n_ i ,a +, s i tu . = .i 4 c.r an. r p g,p. ) s t al'r ri e +; re
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g e r i ry in j .4 : li O I)Our9 (T + $;2OJ ( n :y"r 1->-g. NtiRE F.- Us ( S EDUJ L1DR1 Uli COliL FELEA5L IS-bH5ED OlI NULL]iE-JN THE PX DLDG AND RCIC ROOH M . S '- .I DD 1 NE , RE- MOVE. D l' i G G 'i ' C H A R C Or.il. P E D
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POSTACC.IDENT SAMPLES MESSAGE NO. CART-33 e TO: CHEMISTRY TECHNICIAN f~ ROM: 1FAM EXERCISE CONTROL.LER/05C CONTROLLER , l LOCATION: LHEN LAD /OSC TlME 45 f EDUES TED WITHIN APPLICABLE TIME FRAME. * (SEE COMMENT S SECT 1011 BELOW) Fl.i:ni e L t. i : ' E ut. i i E F ] i.1 Ek C.ARIRibbE 6NALibJe 18 ALtgust 198~/ thab .t b A DRILL fu, NOi t i.o &- c; L i crit - t e m:i 2 t ig i n. r ma i rel ar i i . opat at 2 ans. nut;i i D[ M r lI i i s U C 1 /t I.1 COMMENTE 1 - 1 ~.1 ( . _ o f ' t, 2 E OL. 1 T L I 1 Ll Ei: 11&ENTUR, . i
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] _.) " r. 1- 17F te .f or arw E amp 1 t- t aher, at o r- Ler :, o r to 14: 5'. h ou r s (1 + S: m i ,
' ' LUMP 1 ) Die Nt l RLin--O ~/ 69 L Oll] L I FO l bM t..ukl'
- RELE. AEF i F. BASED OH NUCL3 DES
'N THE PX DLDG AND REIC ROOM J
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CHARCDAL BED 1 1 H 1 F. IS A DRILL l'
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e I'OLT ACC] DENT SAMPLES I MESSAGE NO. CART-34
. i TO: CHEMIS1RY TECHNICIAN' FROM: ' TEAM LXLRClSE CONTRDL.LER/OSC CONTROLLER j LDCATION: CHEM LADcOSC IIME: Ab REUUEb1LD W11 HIN APPLIC'ABLE TIME FRAME (SELI cot 1t1CNTS SECTION BELOW) i lhhi. ;; D '- s i:, M UL1st F]t TiJi L A R il,4 D G Ei AN AL YL i t, IG August 19e, I H) i. 15 A DRlLL DO NDi t al.t- 8ct1 oii- e. f i r c 1 i o g h o n m.O r,J An L c4erationt - . . . ,. . . . .._.,4 . . , . . . _ . . . _ . . . . . . _ . . . . . . . . . . . . . _ . . _ . . . . . . . - . . ..
Niit. i. J DE W 1 l ' ' I 'i i s UC j /i.C
- COMMEN1h I 153 p . E J; L
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1-11: ) . 24 L -% Rew) L E Eba)] be Avai1able
. , ,. . t. - < t. 2s. . i , c.m. i .:
1 - j '". . M l: -l 4 f or any sanspl e t nke*: s:t cr or i rer io .i S : O hours (1 + S: F.n A90UMr T10!!B NURE6-070? EDU1L]BRIUh EUT:, I6: LEASE IS BASED.ON NUCL1D1"
]N THE RX DLDS AND RCIC ROOM 1 '5' . IODIIE I1T HD'/FD E i -
u CHARCUAL DED 1
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4 _ _ . _ . . . . . . . _ _ . . . . _ . . . . _ _ . _ . . . . _ . . _ . . . _ . _ _ . _ . . . - . . . . , . _ . _ . . . . . _ . . . _ _ . . _ . l 1 lH1E IG A DRILL i
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0~ POSi ACCIDENT sat 1PLES 'I MESSAGE NO. CART 4 TO: CHEMISTRY TECHNICIAN FRON: 1EAM EXEPCIEE CONTROLLER /05C CONTROLLER ' LOC ATI Olh CHEM LAD /OSC flME: AD REUUELTEb WI'IHIN APF'LICABLE TIME FRAME (SEE COMMENTO SECT ION F<ELOW) i ERiiL ') 6. S ti l '. 4Eu.)IE i I t, i L f s 1: Aid R1 DLil' (desd_i . : E. I b A9P51- 1987 j iiu o 16 A bkJLL DU NUi t e, , c i L 1 L 't 1, i3 i e c; t a s ig n a nie.1 p1 cr.i op or e t l og i. inn i 21K e, i1 'a i i sU':J<tf.> C L)NhElJT . S . LOi . . e l - 3 '_ - i . IPCi 11L F 3 L ~I E R 3NVENTORY i.4 - ns; .,,. .
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, , t,a = , ?
1 ', s 6. 45E--4m f c,r env c.a n,p ) e i almn ei e r - r,r : .or tc, 1N iu hours s 4 " b01 Of.P.I M P*l3[l!lO IJUF(EG L ? 6(. E UU 1 L 1 DR 1 O!i L bi i f. PELFASE li D 4 S ri b O h ht ":.i.1 D E S IN THE RX DLDS AND RCIC ROOM N .'P. IOD]NEC REMOt.'E 0' D i . GT " CHARCOnL BEL l i l 1 I I d T H l i. , 3E A DRILL
PD01 ACCIDENT Sf;MPLES l%5 SAGE NO. CART-36 e TO: CHEMISTRY TECHNICIAN FROM: TEAM i:XERCISE CONTROLLER /OSC CONTROLLER LUCATIDH: CHEli Li.ib/C SC j ilhE: Ab RLDLtESILD W11HIN APPLICABLE 11ME FRAME i' WEL COMME!T15 SECTION BELOW) 18 August i ci b , iDnL , 31. ; t Li iit i )i li h L AkI hi bGE. (iNA v51 Y irij a Ib A Dh ] L t . DO Ubi t ui re : i.. . t o u - i r s i. i r . . tit ~ ona plant op er at i ot 6s MV4 i l t. f,0 l ' 1 1 'i O.lu i / C C > COMMENFS 3 , ~. i
.1 r i. - Ti: Di.1TE FILTLR Ill'J N1 DTN i i- 1 ar.
1 - 1 .' 1 '. W -' M R e !..u l i t, shal1 b e a v a. ) e t.>'1 e
~
s . . . . . > i u. o .. s. , c i I - 1.~+; 0.41F'Uo f or ene sampl e iaken at or orini to 1:.640 hours ( i 4 6: w ( :".i. Fw r i D: ~ iJURLt , -07 c.a l'. Dull ] UR 1 Uri C Ui1 , I RETE 4!E 15 BASE D ON NUCt.1 DE'.2 IN T Hl.' RX HLDG ('ND RCIC ROOM i 7: G" 1 ODINEC. REMD'Xb E , 5G1 S , i CH4RCual BED I l THIS 15 A DRILL a i O a l
MS O SGTS NOBLE GAS SAMPLES O O
~
SCEtlARIO FERMEX 87 CLOCK TIME = 0920-1400 MESSAGE NO. Chemistry Controller SCEMARIO TIME = 0220-0700 O FERMI - 2 .,
^
EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Chemistry Controller l MESSAGE: Give chemistry sample sheet for the time the sample was taken ! FOR CONTROLLER USE O!!LY: CONTROLLER NOTES: ACTION EXPCCTED: Results reported to Control Room /TSC. O
1 I l l l 1 l 4 1 (~sT s POSTACCIDENT SAMPLES MESSAGE NO.SGTS- 1 l i
'- l TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEMISTRY LAD /OSC MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS (SEE COMMENTS SECTION FOR REQUESTED TIME) 18 August 1987 FERMEX 07 SGTS NOBLE GAS NUCLIDE ANALYSIS 1HIS IS A DRILL DO NOT take actions affecting normal plant operations -------------------- ------------------------ ---..------ ------------. i NUCLIDE ACTIVITY (UCI/CC) COMMENTE NR-85M 2.84E-04 SGTS AXM NOBLE GAS NUCLIDE ANALYSIS FR-85 4.17E-05 UR-87 4.95E-04 Results shall be available KR-88 7.20E-04 at 9: 30 hours (T + 0:10)
\ XE-133 1.29E-03 for any sanipl e taken at or prior XE-135 1.23E-03 to 9:30 hours (T + 0:10) ASSUMPTIONS
. . - _ _ _ _ . . . - . . _ . - _ _ _ . . - _ _ . j
- ANALYSIS INCLUDES REACTOR BLUG.
NUCLIDES AND RCIC STEAM LEAKAGE AFTER 1040 l l THIS IS A DRILL
- .. --- ~..- - --.-- --
3 (V POSTACCIDENT SAfIPLES MESSAGE NO.SGTS- 2 TO: CHEMISTRY TECHNICIAN i FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEMISTRY LAB /OSC MESSAGE: SGTS AXM NOBLF LA~ NUC' IDE ANALYSIS ) (SEE COMMEN~ S SECT 7 3ig EOR REQUESTED TIME) FERMEX 87 SGTS NOBLt GAS NUCLIDE ANALYSIS 19 August 19B"/ __.__ .._-___.___.__._ __ _ ______ ________ i i THIS IS A DRILL DO NOT t al:e actions af f ectina normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-85t1 5.52E-04 SGTS AXM NoliLE GAS NUCLIDE ANALYSIS KR-05 8.30E-05 RR -87 9.OOE-04 Results shal1 be avaiIable RR-8B 1.38E-03 at 9:40 hours (1 + 0:20) XE-133 2.57E-03 4 or any e,empI e t ak en at or pr i or XE-13D 2.41E-03 to 9:40 hours (T + 0:20) ASSU!1PTIONS
- ANALYSIS INCLUDES REACTOR BLDG.
NUCLIDES AND RCIC STEAM LEAKAGE AFTER 1040 l
)
i 1 i l _________ ____________________________________________________________ \ THIS IS A DRILL 1 1 l
\ I l
i l I
i POSTACCIDENT SAMPLES MESSAGE NO.SGTS- 3 f TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEMISTRY LAB /OSC MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS (SEE COMMENTS SECTION FOR REQUESTED TIME) l 1 FERMEX 87 SGTS NOBLE GAS NUCLIDE ANALYSIS 18 August 1987 l _._ ___ ..__.__..._.__.._. _..._._._ _ __ _____.... __ _. - _____.______ 1 THIS IS A DRILL i DO NOT tale actions affecting normal plant operatsons NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-85M 8.03E-04 SGTS AXt1 NOBLE GAS NUCLIDE ANALYSIS L R --85 1.24E-04 KR-87 1.23E-03 Results shall be avai l atel e.: n (j LR-8B 1.97E-03 at 9:50 hours (T 4 0:30) XE 133 3.83E-03 for any sampl e t aken at or prior XE-135 3.54E-03 to 9: 50 hourn (T + 0:30) ASSUMPTIONS
- ANALYSIS INCLUDES REACTOR LLDD.
NLICLIDES AND RCIC STEAM LEAKAGE AFTER 1040 l i
'1 i
THIS IS A DRILL __ _._._ _.____..__ ._____.-___ ._ _.__. _._.__._ _._____.-._ _._..-._____ _____ q l 4 l'
O u POSTACCIDENT SAMPLES MESSAGE NO.SGTS- 4 j TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEMISTRY LAB /OSC MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS (SEE COMMENTS SECTION FOR REQUESTED TIME) FERNEX 87 SGTS NODLE GAS NUCLIDE ANALYSIS 18 August 1987 THIS IS A DRILL DO NOT take acti ons3 affecting nornial plant operetions NUCLIDE ACTIVITf (UCI/CC) COMMENTS l l LR-85M 1.04E-03 SGTS AXM NODLE GAS NUCLIDE ANALYSIS KR-85 1.65E-04 K R- 8 ~/ 1.49E-03 Results shal) be avei 1 abl e KR-88 2.51E-03 at 10: O hours (T + 0:40) XE-13:. 5.08E-03 for any sample tal:en at or pr i or XE-135 4.61E-03 to 10: O hours (T + 0:4:0 ASSUMPT1DNS
- ANALYSIS INCLUDES REACTOR BLDG.
NUCLIDES AND RCIC STEAM LEAV. AGE AFTER 1040 l THIS IS A DRILL O
/~'N U POSTACCIDEN'I S At1F LES j MESSAGE NO.SGTS- 5 i
- l I
TO: CHEMISTRY TECHNICIAN l FROM: TEAM EXERCISE CONTROL.ER/OSC CONTROLLER 5 LOCATION: CHEMISTRY LAB /OSC MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS (SEE COMMENTS SECTION FOR REQUEETED TIME) 18 August 1987 l FERMEX 87 SGTS NODLE GAS NUCLIDE ANALYSIS l ________.._________. _ _ _ _ . _ _ _ . _ I THIS IS A DRILL DO NOT take actions e f f ecting nornial pl ant oper ati on s NUCLIDE ACTIVI'lY (UC1/CC) CONMENTS 1 KR-OSM 1.26E-03 SGTS AXt1 NDliLE GAS NUCLIDE ANALYSIS FR-85 2.06E-04 g LR-G7 1.70E-03 Resulte shalI be a vai1 ab] e KR--39 3.02E-07 at 10: 10 hours (T + 0:50) ( XE-133 6.35E-03 for any sample taken at or prior XE - 135 5.67E-03 to 10:10 hours (T + 0:50) ASSUt1PT I ONS
- ANALYSIS INCLUDES REACTOR BLDG.
NUCLIDES AND RCIC STEAM LEAKAGE AFTER 1040 7HIS IS A DRILL _ -
. . . . . . _ _ . . _ _ . _ . . . _ _ _ ~ . _ _
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POSTACCIDENT SAMPLES MESSAGE NO. SOTS- 6 i TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCAT I'ON : CHEMISTRY LAB /OSC MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS (SEE COMMENTS SECTION FOR REQUESTED TIME) i FERMEX 87 SGTS NOBLE GAS NUCLIDE ANALYSIS 18 August 1987 l I THIS IS A DRILL DO NOT take actions affecting normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-85M 1.23E-03 SGTS AXM NOBLE GAS NUCLIDE ANALYSIS KR-GS 2.05E-04 - KR-87 1,54E-03 Results shal1 be avai 1 ebI e KR-GB 2.88E-03 at 10:20 hours (T + 1: O) i XE-133 6.31E-03 for any sample tal:en at or prior XE-135 5.54E-03 to 10:20 hours-(T + 1 0) ASSUMPTIONS
- ANALYSIS INCLUDES REACTOR BLDG.
N'JCLIDES AND RCIC STEAM LEAKAGE AFTER 1040 i 4 l l 4 i THIS IS A DRILL O
POSTACCIDENT SAMPLES I MESSAGE NO.SGTS- 7 l I l
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TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER l I LOCATION: CHEMISTRY LAB /OSC MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS (SEE COMMENTS SECTION FOR REQUESTED TIME) FERMEX 87 SGTS NOBLE GAS NUCLIDE ANALYSIS 18 August 1987 THIS IS A DRILL DO NOT take actions affecting normal plant operations . i NLICLIDE ACTIVITY ( LIC I /C C ) COMMEN15 1.18E-03 SGTS AXM NODLE GAS NUCLIDE ANAL YSIS LR-85M 2.02E-04 I:R.- 85 ' KR-87 1.39E-03 Results shall be available
~S FR-GG 2.73E-03 at 10:30 hours (T + 1:10)
(d X E - 133 6.22E-03 ior any sample taken at or pr i or XE-135 5.38E-03 to 10:30 hours (T 4 1:10) ASSUMPTIONS l 1
- ANALYSIS INCLUDES REf;CTOR BLDG.
NUCL. IDES AND RCIC STEAM LEAKAGE ! l AFTER 1040
. l l
1 1 1 1 1 l l 1HIS IS A DRILL
i i j O POSTACCIDENT SAMPLES
)
MESSAGE NO.SGTS- 8 1 TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER ) LOCATION: CHEMISTRY LAB /OSC MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS (SEE CDP.MENTS SECTION FOR REQUESTED TIME) l SGTS NOBLC GAS NUCLIDE ANALYSIS 18 August 1987 FERMEX 87 THIS IS A DRILL DO NOT take actions affectsng normal pl ant oper ati ons NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-85M 1.15E-03 SGTS AXM NOE:LE GAS NUCLIDE ANALYSIS . UR-85 2.01E-04 UR-87 1.26E-03 Resul ts shalI be avai1able O UR-S3 2.61E-03 at 10:40 hours (T + 1:20) for any sampie talen at or. prior XE-133 6.20E-03 XE-13b 5.2BE-03 to 10:40 hours (T + 1:20) ASSUMPTIONS
- ANALYSIS INCLUDES REACTOR DLDG.
NUCLIDES AND RCIC STEAM LEAKAGE AFTER 1040
~l l
l l l 1 THIS IS A DRIL.L
l n POSTACCI DENT SAMF'LES , MESSAGE NO.SGTS- 9 TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEMISTRY LAB /OSC MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS (SEE COMMENTS SECTION FOR REQUESTED TIME) FERMEX 87 SGTS NOBLE GAS NUCLIDE ANALYSIS 18 August 1987
~IHIS IS A DRILL DO NOT take actions efiecting normal plant operations !
NLIC L I DE ACTIV]TY ( LIC I / CC ) COMMENTS KR-05M 8.46E+00 SGTS AXM NOBLE GAS NUCLIDE ANALYSIS KR-- 85 1.24C+00 l'R-87 1.47E+01 Results shall be available O lf R- 88 2.14E+01 at 10:50 hours (T + 1:30) XE-133 3.84E+01 for any sample taken at or prior XE -135 3.66E+01 to 10:50 hours (T + 1:30) l I ASSUMPTIONS
- ANALYSIS INCL.UDES REACTOR BLDG. I NUCLIDES AND RCIC STEAM LEAKAGE l I
AFTER 1040 THIS IS A DRILL O
ID v PORTACCIDENT SAMPLES MESSAGE NO.SGTS-10 TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER l LOCATION: CHEMISTRY LAB /OSC MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS -) (SEE COMMENTS SECTION FOR REQUESTED TIME) l
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SGTS NOBLE GAS NUCLIDE ANALYSIS 18 August 1987 F'ERME X 87 ' lHIS IS A DRILL i { DO NOT t al'e actione affecting normal plant oper at i on s NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-85M 7.88E+00 SGTS AXM NODLE GAS NUCL]DE ANAL'(SIS KR-G5 1.19E+00 a 3 G KR-87 1.28E+01 Results shalI be avai1 ab1e 1.97E+01 1: 40) f k) UR-83 at 11: O hours (T + XE-133 3.67E+01 4or any sample t al:en at or p r i cer X E-- 135 3.44E+01 to 11: O hours (T + 1:40) ASSUMPT I O)G
- ANALYSIS INCLUDES REACTOR BLliG.
NUCLIDES AND RCIC STEAM LEARAGE AFTER 1040 j l l
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1 l l THIS IS A DRILL
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4 i 1 i 1 i I n i i b/ POSTACCIDENT SAMPLES MESSAGE NO.SGTS-11 i i e i TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER
, LOCATION: CHEMISTRY LAB /OSC MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS (SEE COMMENTS SECTION FOR REQUESTED TIME) 18 August 1987 i FERMEX 87 SGTS NOBLE GAS NUCLIDE ANALYSIS 1
1 THIS IS A DRILL DO NOT take actionn affecting normal plant operations NUCLIDE ACTIVITY (UCJ/CC) COMMENTS KR-85M 7.30E+00 EG15 AxM NODLE GAS NUCLIDE ANALYSIS i l'R-85 i.13E+00 KR-87 1.12E+01 Results shall be available K R--8B 1.794+0'i at 11 10 hours (T + 1:50) XE-133 3.49E+01 for any semple taken at or prior XE -1"5 3.21E+01 to 11 : 10 hot..tr s (T + 1:50) ASSUMPTIONS y --. ._ __ _ .__ - .- _....-_- - .__-
- ANALYSIS INCLUDES REACTOR BLDG.
NUCLIDES AND RCIC STEAM LEAKAGE AFTER 1040 t
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..w.... .. ___-__ _ _ .__ -_- -_ __ _-_ __ _. -
l s THIS IS A DRILL _.-.,s._...._.._..--_._,-___-_-____.__.___---___....__
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I POSTACCIDENT SAMPLES i MESSAGE NO.SGTS-12 TO: CHEMISTRY TECHNICIAN l FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEMISTRY LAB /LSC MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS (SEE COMMENTS SECTIO: 4 FOR REQUESTED TIME) FERMCX 87 SGTS NOLLE GAS NUCLIDE ANALYSIS 18 August 1987 THIS IS A DRILL DO NOT take actions affectino normal plent operations l l NUCL1DE ACTIVITY (UC1/CC) COMMENTS KR-85M 6.76E+00 SGTS AXM NODLE GAS NUCLIDE ANALYSIS KR-G5 1.07E+00 KR- 07 9.68E+0D Results shall be availeble q at 11:20 hours (T + 2: O) U KR-83 XE-133 1.64E+01 for any semple taken et or prior 3.31E+01 XE-135 3.OOE+01 to 11:20 hours (T + 2: 0) ASSUMPTION 5 {
- ANALYSIS INCLUDES REACTOR l<LDG.
l NUCLIDES AND RCIC STEAM LEAKAGE AFTER 1040 l l THIS IS A DRILL
s e 1
- o POSTACCIDENT SAMPLES MESS AGE - NO. SGTE- 1 . ,
TO: CHEMISTRY TECHNICIAN FROM: T(AM EXERCISE CONTECLLER/OSC CONTROLLER LOCATION: CHEMISTRY LAB /OSC MESSAGEt SGTS AXM NOBLE GAB:hJUCi IDE ANALYSIS (SEE COMMENTS SECTION FOR REQUESTED TIME) FERMEY G7 SGTS NOSLE GAS NUCLIDE ANALYSIS 18 August 1987 1
. _ _ . _ _ . . . _ . _ _ _ _ _ _ . - . . , _ i THIS IS A DRILL DO NOT take ections affectit ; normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-85M 6.26E+00 SGTS AXM NOBLE GAS NUCLIDE ANAr.YSIS VR-BS 1,02E+00 Os iR-87 g,4CC+00 Results shall be avai l abl e I.R-8F 1.49E+01 at i1:30 hours (T + 2:10)
X E 1 ~ ~. 3.14E+01 ior any sample taken at or prior X E- 1 5'5 2.81E+01 to 11:30 hours (T + 2:10) l ASSUMPTIONS
- ANALYSIS INCLUDES REACTOR BLDG.
NUCLIDES AND RCIC STEAM LEAKAGE AFTER 1040 1 l i s' l l i THIS IS A DR1LL
Q C POSTACCIDENT SAMPLES MESSAGE NO.SGTS-14 9 TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEMISTRY LAB /OSC MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS ; (SEE COMMENTS SECTION FOR REQUESTED TIME) ! i FERMEX 87 SGTS NOBLE GAS HUCLIDE ANALYSIS 18 August 1987 THIS IS A DRILL DO NOT take actions affecting normal plant operations NUCLIDE ACTIVITY ( LIC I / CC ) COMMENTS KR-SDM 5.79E+00 SGTS AXM NOBLE GAS NUCLIDE ANALYSIS ' KR- G5 9.66E-01 KR-87 7.28E+00 Results shalI be avai1able
-O KR-8B X E-- 13' 1.36E+01 2.9BE+01 at 11:40 hours (T + 2:20) for any sample taken at or pr2ar XE-135 2.62E+01 to 11:40 hours (T + 2:20) i ASSUMPTIONS j
- ANALYSIS INCLUDES REACTOR BLDG.
NUCLIDES AND RCIC STEAM LEAKAGE ( AFT E' '040 ; THIS IS A DRILL l o- - - - - - --- - - - 1
[ t POS'lACCIDENT SAMPLES MESSAGE NO.SGTS-15 , TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEMISTRY LAB /OSC MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS (SEE COMMENTS SECTION FOR REQUESTED TIME) 18 August 1987 FERMEX 87 SGTS NOBLE GAS NUCLIDE ANALYSIS THIS IS A DRILL DO NOT take actions affecting normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-85M 5.36E+00 SGTS AXM NOBLE GAS NUCLIDE ANALYSIS . KR-85 9.18E-01 I KR-87 6.31E+00 Results shall be aveilable KR-88 1.24E+01 at 11:50 hours (T + 2:30) XE-133 2.83E+01 for any sample tal:en at or prior XE-135 2.44E+0i to 11:50 heurs (T + 2:30) ASSUMPTIONS
- ANALYSIS INCLUDES REACTOR BLDG. !
NUCLIDES AND RCIC STEAM LEAKAGE I AFTER 1040 l THIS IS A DRILL
1 1 POSTACCIDENT SAMPLES MESSAGE NO.SGTS-16 TO: CHEMISTRY TECHNICIAN q FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEMISTRY LAB /OSC MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS (SEE COMMENTS SECTION FOR REQUESTED TIME) FERMEX 87 SGTS NOBLE GAS NUCLIDE ANALYSIS 18 August 1987 THIS IS A DRILL DO NOT take actions affecting normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-85M 4.96E+00 SGTS AXM NOBLE GAS NUCLIDE ANALYSIS KR-G5 8.72E-01 KR-87 5.48E+00 Re s.ul t s shall be aveilable l IER-GG 1.13E+01 at 12: O hours (T + 2: 40) XE-133 2.68E+01 for any sample taken at or prior XE-135 2.28E+01 to 12: O hours (T + 2:40) ASSUMP1 IONS
- ANALYSIS INCLUDES REACTOR BLDB.
NUCLIDES AND RCIC STEAM LEAKAGE AFTER 1040 THIS IS A DRILL _ _-.-. - _ -_ -------- ~ -- --- .-------------- ----- - ------ i r -_-.---.--------_--__u
r POSTACCIDENT SAMPLES MESSAGE NO.SGTS-17 TO CHEMISTRY TECHNICIAN ; k j FROM: TEAM CXERCISE CONTROLLER /OSC CONTROLLER i LOCATION: CHEMISTRY LAB /OSC MESSAGE: SG1S AXM NOBLE GAS NUCLIDE ANALYSIS (SEE COMMENTS SECTION FOR REQUESTED TIME) SGTS NOBLE GAS NUCLIDE ANALYSIS 18 August 1987 FERMEX 87 THIS IS A DRILL DO NOT take actione affecting normel plant. operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-85M 4.58E+00 SGTS AXM NOBLE GAS NUCLIDE ANALYSIS KR-85 8.28E-01 q KR-87 4.74E+00 Results shall t> e avai l abl e Q KR-88 1.03E+01 at 12:10 hours (T + 2:50) for any sarnpl e taken at or prior XE-133 2.54E+01 XE-135 2.13E+01 tc 12:10 hours (T + 2:50) ASSUMPTIONS
- ANAL' SIS INCLUDES REACTOR F(LDG.
NUCLIDES AND RCIC STEAM LEAKAGE AFTER 1040 THIS IS A DRILL
O POSTACCIDENT SAMPLES MESSAGE NO.SGTS-18 TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER l LOCATION: CHEMISTRY LAB /OSC MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS (SEE COMMENTS SECTION FOR REQUESTED TIME) l FERMEX 87 SGTS NOBLE GAS NUCLIDE ANALYSIS 18 August 1987 j THIS IS A DRILL DO NOT take actions af f ecting normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-85M 4.24E+00 SGTS AXM NOBLE GAS NUCLIDE ANALYSIS
}:R-85 7.86E-01
("' \ KR-87 L:R-88 4.12E+00 9.39E+00 Results shalI be avai1able at 12:20 hours (T + 3: O) XE-133 2.42E+01 for eny sample taken at or prior XE-135 1.99E+0! to 12:20 hours (T + 3: 0) ASSUMPTIONS
- ANALYSIS INCLUDES REACTOR BLDG.
NUCLIDES AND RCIC STEAM LEAVAGE AFTER 1040 i THIS IS A DR1LL l
t POSTACCIDENT SAMPLES MESSAGE NO.SGTS-19 ,, ; TO: CHEMISTRY TECHNICIAN 1 FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEMISTRY LAB /OSC MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS 'i (SEE COMMENTS SECTION FOR REQUESTED TIME) SGTS NOBLE GAS NUCLIDE ANALYSIS 18 August 1987 FERMEX 87 THIS IS A DRILL DO NOT take actions affecting nornial plant operations NUCLIDE ACTIVITY (UCI/CCi COMMENTS KR-85M 3.92E+00 SGTS AXM NOBLE GAS NUCLIDE ANALYSIS KR -85 7.45E-01 O KR-87 3.56E+00 8.55E+00 Resul ts shall be available at 12:30 hours (T + 3:10) KR-88 XE-133 2.29E+01 for eny sarnpl e taken at or prior XE-135 1.85E+01 tc 12:30 hours (T + 3:10) ASSUMPTIONS
- ANALYSIS INCLUDES REACTOR BLDG.
NUCLIDEG AND RCIC STEAM LEAKAGE AFTER 1040 THIS IS A DRILL i > 1
O POS1 ACCIDENT SAMPLES MESSAGE NO.SGTS-20 ' TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEMISTRY LAB /OSC MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS (SEE COMMENTS SECTION FOR REQUESTED TIME) F E.RME X 87 SGTS NOBLE GAS NUCLIDE ANALYSIS 18 August 1987 THIS IS A DRILL DO NOT take act3cns at f ecti ng nornial plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS IJR-85M 3.62E+00 SGTS AXM NOBLE GAS NULLIDE ANALYSIS ( KR-85 7.07E-01 6 :.'R- 8 7 3.09E+00 Results shall be availab}e KR-GG 7.79E+00 at 12:40 hours (T + 3:20) G 1J3 2.17E+01 ior any e anip] e tal.en at or prior AE'13b 1.73E+01 to 12:40 hours (T + 3:20) ASSUMP1 IONS
- ANALYSIS INCLUDES REACTOR BLDG, NUCLIDES AND RCIC STEAM LEARAGE AFTER 1040 I
i THIS IS A DRILL O 4 l 1
POSTACCIDENT SAMPLES "s MESSAGE NO.SGTS-21 TO: CHEMISTPY TECHNICIAN
< I FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEMISTRY LAB /OSC MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS (SEE COMMENTS SECTION FOR REQUESTED TIME) i 1
.I FERMEX 87 SGTS NOBLE GAS NUCLIDE ANALYSIS 18 AUGUST 1987 )
l ___________________________________________________________--_________ \ THIS IS A DRILL DO NOT take actions affecting normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-85M 3.35E+00 SGTS AXM NOBLE GAS NUCLIDE ANALYSIS KR-85 6.71E-01 KR-87 2.67E+00 Results shall be available VR-88 7.09E+00 at 12:50 hours (T + 3:30) XE-133 2.06E+01 for any sample taken at or prior XE-135 1.61E+01 to 12:50 hours (T + 3:30) (]) ASSUMPTIONS
- ANALYSIS INCLUDES REACTOR BLDG, NUCLIDES AND ADDITIONAL NUCLIDE INVENTORY FROM RCIC ROOM AFTER 1040 HOURS l _________-____________________________________________________________
THIS IE A DRILL i ______________________________________________________________________ l l 1 1 l l I
POSTACCIDENT SAMPLES MESSAGE NO.SGTS-22 TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEMISTRY LAB /OSC MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS (SEE COMMENTS SECTION FOR REQUESTED TIME) FERMEX 87 SGTS NOBLE GAS NUCL.IDE ANALYSIS 18 AUGUST 1987 THIS IS A DRILL DO NOT take actions affecting normal plant operations ) NUCLIDE ACTIVITY (UCI/CC) COMMENTS i KR-85M 2.79E+00 SGTS AXM NOBLE GAS NUCLIDE ANALYSIS ] KR-85 5.88E-01 l KR-87 1.95E+00 Results shall be available ! KR-88 5.72E+00 at 13: O hours (T + 3:40) XE-133 1.80E+01 for any sample taken at or prior XE-135 1.37E+01 to 13: O hours (T + 3:40) ASSUMPTIONS
- ANALYSIS INCLUDES REACTOR BLDG. l NUCLIDES AND ADDITIONAL. NUCLIDE INVENTORY FROM RCIC ROOM AFTER 1040 HOURS THIS IS A DRILL l
O i ! ) l L-__--_-_---_-_-______
POSTACCIDENT SAMPLES (} MESSAGE NO.SGTS-23 TO: CHEMISTRY TECHNICIAN , FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEMISTRY LAD /OSC MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS (SEE COMMENTS SECTION FOR REQUESTED TIME) l FERMEX 87 SGTS NOBLE GAS NUCLIDE ANALYSIS 18 AUGUST 1987 l 1 l THIS IS A DRILL DO NOT take actions affecting normal plant operations l
---------------------------------------------------------------------- 1 NUCLIDE ACTIVITY (UCI/CC) COMMENTS '
l KR-85M 3.09E+00 SGTS AXM NOBLE GAS NUCLIDE ANALYSIS KR-85 6.36E-01 KR-87 2.31E+00 Results shall be available KR-88 6.45E+00 at 13:10 hours (T+ 3:50) XE-133 1.95E+01 for any sample taken at or prior
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(, XE-135 1.50E+01 to 13:10 hours (T + 3:50) ASSUMPTIONS l - ANALYSIS INCLUDES REACTOR BLDG. NUCLIDES AND ADDITIONAL NUCLIDE l INVENTORY FROM RCIC ROOM AFTER I 1040 HOURS
---__-__---________-___________-_______________--__-----(_--_---_-__--
THIS IS A DRILL ($) , 1 1 ( l ?
(\ POSTACCIDENT SAMPLES MESSAGE NO.SGTS-24 TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEMISTRY LAB /OSC MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS (SEE COMMENTS SECTION FOR REOUESTED TIME) FERMEX 87 SGTS NOBLE GAS NUCLIDE ANALYSIS 18 AUGUST 1987 THIS IS A DRILL j
)
DO NOT take actions affecting normal plant operations , NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-85M 2.64E+00 SGTS AXM NOBLE GAS NUCLIDE ANALYSIS . KR-85 5.'/1E-01 KR-87 1.73E+00 Results shall be available > KR-88 5.34E+00 at 13:20 hours (T + 4: 0) () XE-133 XE-135 1.75E+01 1.31E+01 for any sample taken at or prior to 13:20 hours (T + 4: 0) ASSUMPTIONS
- ANALYSIS INCLUDES REACTOR BLDG.
NUCLIDES AND. ADDITIONAL NUCLIDE INVENTORY FROM RCIC ROOM AFTER 1040 HOURS i I i I THIS IS A DRILL k 1 4 j i
i gg POSTACCIDENT SAMFLES 5) s
- MESSAGE NO.SGTS-25 TO: CHEMISTRY TECHNICIAN ,
FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEMISTRY LAB /OSC MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS (SEE COMMENTS SECTION FOR REQUESTED TIME) FERMEX 87 SGTS NOBLE GAS NUCLIDE ANALYSIS 18 AUGUST 1987 THIS IS A DRILL DO NOT take actions affecting normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-85M 2.44E+00 SGTS AXM NOBLE GAS NUCLIDE ANALYSIS KR-85 5.43E-01 KR-87 1.50E+00 Results shall be available KR-88 4.86E+00: at 13:30 hours (T + 4:10) XE-133 1.66E+01 for any samp1R taken at or prior (~)' ss XE-135 1.22E+01' to 13:30 hours (T + 4:10) ASSUMPTIONS
- ANALYSIS INCLUDES REACTOR BLDG.
NUCLIDES AND ADDITIONAL NUCLIDE INVENTORY FROM RCIC ROOM AFTER 1040 HOURS i THIS IS A DRILL O
I l l POSTACCIDENT SAMPLES l MESSAGE NO.SGTS-26 !
)
1 TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER ' LOCATION: CHEMISTRY LAB /OSC MESSAGE: SGTS AXM NOBLE GAS NUr' IDE ANALYSIS (SEE COMMENTS SECTION i-OR REGUESTED TIME) FERMEX 87 SGTS NOBLE GAS NUCLIDE ANALYSIS 18 AUGUST 1987 THIS IS A DRILL ; DO NOT tal:e actions affecting normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-85M 2.25E+00 SGTS AXM NOBLE GAS NUCLIDE ANALYSIS LR-85 5.14E-01 KR-87 1.30E+00 Results shall be available KR-88 4.42E+00 at 13:40 hours (T + 4:20) XE-133 1.57E+01 for any sample tal:en at or prior XE-135 1.13E+01 to 13:40 hours (T + 4:20) ASSUMPTIONS
- ANALYSIS INCLUDES REACTOR BLDG.
NUCLIDES AND ADDITIONAL NUCLIDE INVENTORY FROM RCIC ROOM AFTER 1040 HOURS THIS IS A DRILL ________-_____-_________-_______________________________t________-____
(~ POSTACCIDENT SAMPLES k MESSAGE NO.GGTS-27 I
- l TO: CHEMISTRY TECHNICIAN I j
a FROM: TEAM EXERCIt'E CONTROLLER /OSC CONTROLLER LOCATION: CHEMISTRY LAB /OSC MESSAGE: SGTS AXM ,10BLE GAS NUCLIDE ANALYSIS , (SEE COMMENTS SECTION FOR REQUESTED TIME) l FERMEX 87 SGTS NOBLE GAS NUCLIDE ANALYSIS 18 AUGUST 1987 THIS IS A ORILL DO NOT take actions affecting normal plant operations {' NUCLIDE ACTIVITY (UCI/CC) COMMENTS i KR-85M 2,ost+00 SGTS AXM NOBLE GAS NUCLIDE ANALYSIS KR-85 4.87E-01 KR-87 1.12E400 Results shall be available KR-88 4.02E+00 at 13:50 hours (T + 4:30) () XE-133 XE-135 1.48E+01 1.06E+01 for any sample taken at or prior to 13:50 hours (T + 4:30) ASSUMPTIONS
- ANALYSIS INCLUDES REACTOR BLDG.
NUCLIDES AND ADDITIONAL NUCLIDE INVENTORY FROM RCIC ROOM AFTER 1040 HOURS 4 THIS lb A DRILL O l
I POSTACCIDENT SAMPLES MESSAGE NO.SGTS-28
)
TO: CHEMISTRY TECHNICIAN I FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER j LOCATION: CHEMISTRY . LAB /OSC l i MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS (SEE COMMENTS EECTION FOR REQUESTED TIME) FERMEX 87 SGTS NOBLE GAS NUCLIDE ANALYSIS 18 AUGUST 1987 THIS IS A DRILL DO NOT tal:e actions af f ecting normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS i UR-85M 1.92E+00 SGTS AXM NOBLE GAS NUCLIDE ANALYSIS ; KR-85 4.61E-01 ! KR-87 9.72E-01 Results shall be available KR-88 3.66E+00 at 14: O hours (T + 4:40) XE-133 1.40E401 for any sample taken at or prior O XE-135 9.85E+00 to 14: O hours (T + 4:40) ASSUMPTIONS
- ANALYSIS INCLUDES REACTOR BLDG.
NUCLIDES AND ADDITIONAL NUCLIDE INVENTORY FROM RCIC ROOM AFTER 1040 HOURS i
------------------~~-------------------------..----------g-------------
THIS IS A DRILL O
I
" I POSTACCIDENT SAMPLES q MESSAGE NO.SGTS-29 kJ TO: CHEMISTRY TECHNICIAN t
FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER I LOCATION: CHEMISTRY LAD /OSC j MESSAGE: SGlS AXM NOBLE GAS NUCLIDE ANALYSIS (SEE COMMENTS SECTION FOR REQUESTED TIME) FERMEX 87 SGTS NOBLE GAS NUCLIDE ANALYSIS 18 AUGUST 1987 THIS IS A DRILL DO NOT take actions affecting normal plant operations ! NUCLIDE ACTIVITY (UCI/CC) COMMENTS I 1 KR-85M 1.77E+00 SGTS AXM NOBLE GAS NUCLIDE ANALYSIS KR-85 4.36E-01 KR-87 Results shall be available l 8.39E-01 KR-88 3.32E+00 at 14:10 hours (T + 4:50) XE-133 1.33E+01 for any sample taken at or prior (} XE-135 9.16E+00 to 14:10 hours (T + 4:50) ASSUMPTIONS
- ANALYSIS INCLUDES REACTOR BLDG.
NUCLIDES AND ADDITIONAL NUCLIDE INVENTORY FROM RCIC ROOM AFTER ; 1040 HOURS THIS IS A DRILL
POSTACCIDENT SAMPLES f'~N MESSAGE NO.SGTS-30
\J TO: CHEMISTRY TECHNICIAN j FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEMISTRY LAB /OSC MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS (SEE COMMENTS SECTION FOR REOUESTED TIME)
FERMEX 87 SGTS NOBLE GAS NUCLIDE ANALYSIS 18 AUGUST 1987 THIS IS A DRILL DO NOT take actions affecting normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-85M 1.51E+00 SGTS AXM NOBLE GAS NUCLIDE ANALY3IS KR-85 3. 92E--01 '
~
KR-87 6.28E-01 Results shall be available VR-88 2.74E+00! at 14:20 hours (T + 5: 0) XE-133 1.19E+01 for any sample taken at or prior
/ XE-135 7. 94E+00 : to 14:20 hours (T + 5: 0)
( ASSUMPTIONS
- ANALYSIS INCLUDES REACTOR BLDG.
NUCLIDES AND ADDITIONAL NUCLIDE INVENTORY FROM RCIC ROOM AFTER 1040 HOURS 1 l THIS IS A DRILL j _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 1 /N I t
POSTACCIDENT SAMPLES (g MESSAGE NO.SGTS- 1 O TO: CHEMISTRY TECHNICIAN
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l FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER l LOCATION: CHEMISTRY LAB /OSC I l
.1 MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS )
(SEE COMMENTS SECTION.FOR REQUESTED TIME) j i FERMEX 87 SGTS NOBLE GAS NUCLIDE ANALYSIS 18 AUGUST 1987 i i i _-_________________________-____________________________________-_____ q THIS IS A DRILL I DO NOT take actions affecting normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS 1 i KR-GSM 1.39E+00 SGTS AXM NOBLE GAS NUCLIDE ANALYSIS KR-85 3.70E-01 f
. KR-87 5.42E-01 Results shall be available l KR-S8 2.49E+00 at 14:30 hours (T + 0:10) l XE-133 1.12E+01 for any sample taken at or prior i AF\ XE-135 7.38E+00 to 14:30 hours (T + 0:10)
V { I ASSUMPTIONS J
- ANALYSIS INCLUDES REACTOR BLDG.
NUCLIDES AND ADDITIONAL NUCLIDE INVENTORY FROM RCIC ROOM AFTER 1040 HOURS ! l Y _-__________-___--_____-_________________________-______7_____________ THIS IS A DRILL
POSTACCIDENT SAMPLES MESSAGE NO.SGTS- 2 TO: CHEMISTRY TECHNICIAN FROM: 1EAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEMISTRY LAD /OSC MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS (SEE COMMENTS SECTION FOR REQUESTED TIME) FERMEX 87 SGTS NOBLE GAS NUCLIDE ANALYSIS 10 AUGUST 1987 THIS IS A DRILL DO NOT take actions effecting normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-85M 1.28E+00 SGTS AXM NOBLE GAS NUCLIDE ANALYSIS KR-85 3.50E-01 KR-87 4.67E-01 Results shall be available KR-88 2.26E+00 at 14:40 hours (T + 0:20) XE-133 1.06E+01 for any sample taken at or prior f' XE-135 6.86E+00 to 14:40 hours (T + 0:20)
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A3SUMPTIONS l _-_------_______----___--__---___--- I
- ANALYSIS INCLUDES REACTOR BLDG.
NUCLIDES AND ADDITIONAL NUCLIDE INVENTORY FROM RCIC ROOM AFTER 1040 HOURS THIS IS A DRILL O I
l i POSTACCIDENT SAMPLES l O "essaec "o se's- s l i i TO: CHEMISTRY TECHNICIAN , l FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEMISTRY LAD /OSC ] I I MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS (SEE COMMENTS SECTION FOR REQUESTED TIME) FERMEX 87 SGTS ND LE GAS NUCLIDE ANALYSIS 18 AUGUST 1987 THIS IS A DRILL DO NOT take actions affecting normal plant operations I __--_______-____--_-_____________________________________--___________ l NUCLIDE ACTIVITY (UCI/CC) COMMENTS j i f KR-85M 1.18E+00 SGTS AXM NOBLE GAS NUCLIDE ANALYSIS KR-85 3.32E-01 KR-87 4.05E-01 Recults shall be available j KR-88 2.36E+00 at 14:50 hours (T + 0:30) ! XE-133 1.0LE+01 for any sample taken at or prior I O XE-135 6.39E'OO to 14:50 hours (T + 0:30) ASSUMPTIONS
- ANALYSIS' INCLUDES REACTOR BLDG.
NUCLIDES AND ADDITIONAL NUCLIDE INVENTORY FROM RCIC ROOM AFTER 1040 HOURS 1 l l l THIS IS A DRILL l O
POSTACCIDENT SAMPLES MESSAGE NO.SGTS- 4 TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEMISTRY LAB /OSC MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS (SEE COMMENTS SECTION FOR REQUESTED TIME) FERMEX 87 SGTS NOBLE GAS NUCLIDE ANALYSIS 18 AUGUST 1987 THIS IS A DRILL DO NOT take actions affecting normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-85M 1.09E+00 SGTS AXM NOBLE GAS NUCLIDE ANALYSIS KR-85 3.13E-01 KR-87 3.49E-01 Results shall be available KR-88 1.86E+00 at 15: O hours (T + 0:40) XE-133 9.46E+00 for any sample taken at or prior XE-135 5.93E+00 to 15: O hours (T + 0:40) ASSUMPTIONS
- ANALYSIS INCLUDES REACTOR BLDG.
NUCLIDES AND ADDITIONAL NUCLIDE INVENTORY FROM RCIC ROOM AFTER 1040 HOURS I I l THis IS A DRILL I l /^\ l V
F'OSTACCIDENT SAMPLES MESSAGE NO.SGTS- 5 TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEMISTRY LAB /OSC MESSAGE: SGTS AXM NOBLE GAS NUCLIDE ANALYSIS (SEE COMMENTS SECTION FOR REQUESTED TIME) FERMEX 87 SGTS NOBLE GAS NUCLIDE ANALYSIS 18 AUGUST 1987 THIS IS A DRILL DO NOT take actions affecting normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-85M 1.OOE+00 SGTS AXM NOBLE GAS NUCLIDE ANALYSIS KR-85 2.97E-01 KR-87 3.02F-01 Results shall be available KR-88 1.70E+00 at 15:10 hours (T + 0:50) XE-133 8.97E+00 for any sample taken at or prior (} XE-135 5.53E+00 to 15:10 hours (T + 0:50) ASSUMPTIONS
- ANALYSIS INCLUDES REACTOR BLDG.
NUCLIDES AND ADDITIONAL NUCLIDE INVENTORY FROM RCIC ROOM AFTER 1040 HOURS __----_-__-_--__-------_-_____________-_-______-_-_-____4-______ _____ THIS IS A DRILL l l O
f- POSTACCIDENT SAMPLES (,g) MESSAGE NO.SGTS- 6 TO: CHEMISTRY TECHNICIAN , l l FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEMISTRY LAB /OSC MESSAGE: 'SGTS AXM NOBLE GAS NUCLIDE ANALYSIS i (SEE COMMENTS SECTION FOR REQUESTED TIME) l FERMEX 87 SGTS NOBLE GAS NUCLIDE ANALYSIS 18 AUGUST 1987 THIS IS A DRILL DO NOT take actions affecting normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-85M 9.23E-01 SGTS AXM NOBLE GAS NUCLIDE ANALYSIS KR-85 2.80E-01 KR-87 2.60E-01 Results shall be available KR-88 1.54E+00 at 15:20 hours (T + 1: 0) XE-133 8.4eE+00 for any sample taken at or prior O-
% XE-135 5.14E+CV> to 15:20 hours (T + 1: 0)
ASSUMPTIONS
- ANALYSIS INCLUDES REACTOR BLDG.
NUCLIDES AND ADDITIONAL NUCLIDE INVENTORY FROM RCIC ROOM AFTER 1040 HOUPS 4
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SCE!!ARIO FERMEX 8'7 CLOCK TIME = 0920-1400 . MESSAGE !!O. Chemistry Controller _ SCENARIO TIME = 0220-0700 G FERMI - 2
'I EMERGE!!CY PREPAREDNESS EXEPCISE MESSAGE FOPJi e- -MESSAGE FOR: Chemistry Controller MESSAGE: Give chemistry sample sheet for the time the, sample was -l taken n'
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FERMEL G7 inWNELL A.lP SAMDLE '1D AUGUST 3987. lHIR 15 A DR J t L
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FROMt TEAM EXERCIEE CONTROLLER /OSC CONTROLLER
. LOCATION: CHEF LAB /05C TIME: -45 REQUESTED WITHIN APPLICABLE TIME FRAME' (SEE COMMErTT5'SECTION BELOW) 1 FERMEY 07 DRvWELt /4)P SAMPLE 18 AUGU5'i 1987' :l 1>q- IR t.:, ppIti p;, a i: ei.- . ,
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TORUS WATER SAMPLES j O O
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i I SCEt:ARIO FERMEX 87 CLOCK TIME = 0920-1400 MESSAGE !!O. Chemistry Controller SCE!!ARIO TIME = 0220-0700 0 FERMI - 2 EMERGE!1CY PREPAREDNESS EXERCISE MESSAGE FORM ,, l MESSAGE FOR: Chemistry Controller I MESSAGE: Give chemistry sample sheet for the time the sample was taken l O FOR C0tiTROLLER USE 0 iLY: ColTTROLLER tiOTES: l ACTION EXPECTED: Results reported to Control Room /TSC.
POSTACCIDENT SAMPLES
, MESSAGE NO.H2O - 1 TO: ' CHEMISTRY TECHNICIAN 4
FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEM LAB /OSC TIME: AS REQUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) FERMEA 07 TORUS WATER CHEMISTRY ANALYSIS 18 AUGUST 1987
'iH15 15 A DRILL DO NOT take actions affecting normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-85M 1.233E-02 TORUS WATER CHEMISTRY SAMPLE KR-85 1.3OOE-03 UR-87 2.OO1E-02 Result s shall be available KR-88 3.107E-02 at 9:30 hours (T + 0:10)
- XF-133 5.623F-02 for any sample taken at or pri or
() XE-135 1-131 5.215E-02 1.257E-01 to 9:30 hours (T + 0:10) I-132 1.739E-01 ASSUMPTIONS:
- - - - ~ - - - - - - - - - -
I-133 2 . 7 4 O E_- 0 1 1-134 2. 050E-0.i - NUREG 0769 EQUILIBRIUM CORE J-135 2.467E-01 - SOURCES RELEASE.D TO TOFUS FROM SRV BLOWDOWN OF RPV _B--M--.W--M---------M---------.9---M------.W-------M-65--------W'--------_ THIS IS A DRILL l i
i J PCSTACCIDENT SAMPLES MESSADE NO.H2O - 2 TO: CHEMIGTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER i LOCATION: CHEM LAB /OSC l TIME: AS REQUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) FERMEX 87 TORUS WATER CHEMISTRY ANALYSIS 18 AUGUST 1987 . THIS IS A DRILL DO NOT take acti ons af f ecting normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS 1 KR-85M 1.201E-02 TORUS WATER CHEMISTRY SAMPLE j j KR-8;. 1.~00E-03 l l KR-87 1.827E-02 Resulte shalI be avai1able j KR-88 3.055E-02 at 9:40 hours (T + 0:20) XE-133 5.618E-02 for any sample taken at or prior - X E.- 13b b.12/E-02 to 9:40 hours Cl + 0:20) O- 1 171 1.257E-01 1-132 1.655E-01 ASSUMPTIONS: 1-103 2.724E-01 - - - - - - - - - - - - - ~ - - 1 - 1 ~J.4 2.GO2E-01 - NUREG 0769 EQUILIBRIUM CORE i 1-135 2.425E-01 - SOURCES RELEASED TO TORUS FRON l SRV BLOWDOWN OF RFV H i THIS IS A DRILL 4 w
1 l I i l l POSTACCIDENT SAMPLES 'l
)
MESSAGE NO.H2O - 3 TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER l
)
l LOCATION: CHEM LAB /OSC ! J TIME: AS REOUESTED WITHIN APPLICABLE TIME FRAME f (SEE COMMENTS SECTION BELOW) FERMEX G7 TORUS WATER CHEMISTRY ANALYSIS 18 AUGUST 1987 THIS IS A DRILL DO NOT take actions affecting normal plant operations NUCL.IDE ACTIVITY (UCI/CC) COMMENTS KR-8SM 1.170E- 02 TORUS WATER CHEMISTRY SAMPLE LR --F 5 .t . S u o E - 0 ... L R-- 87 1. 668E--02 Results shall be available VR-88 3.OO3E-02 at 9:50 hours (T + 0:30) XE-13' 5.612E-02 for any sample talen at or prior -
- 5. 04 0Li- 02 to 9:50 hours (T + 0:30) j O X L-- 13b 1 - I ',1 1.?56E-01 ASSUMPTIONS:
I-132 1.574E-01 1 133 2.709L-01 - . - - - - - . - _ - _ - - - - 1-134 2.755E-01 - NUREG 0769 EQUILIBRIUM CORE 1 1-13D 2.384E-01 - SOURCES RELEASED TO TORUS FROM : I SRV BLOWDOWN OF RPV i THIS IS A DRILL O
n POSTACCIDENT SAMPLES
' MESSAGE NO.H2O - 4 s
TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER l LOCATION: CHEM LAB /OSC TIME: AS REQUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) FERMEX 87 TORUS W4TER CHEMISTRY ANALYSIS 18 AUGUST 1987 lHIS IS A DRILL .i l DO NOT take actions affecting normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS < f 1 KR-SSM 1.140E-02 TORUS WATER CHEMISTRY SAMPLE 1 KR-85 1.JuoL-03 ! k.R-87 1.523C-02 Results shall be avail abl e KR-8G 2.952E-02 at 10: O hours (T + 0:40) - X F - 1 '53 S . c />7E -0,P for any samp1e taFen at or pricm ' XE-13M 4.955E-02 to 10: O hours (T + 0: 40) O ].i'4 ) . 2r.3E ...o ; I--132 1.497E-01 ASSUMPTIONS: 1 -- 1 3 ' 2.o94E-01 ----------------
.1-13-i 2. 709E.- 01 - NUREG 0769 EQUILIBRIUM CDRC ,
1-135 2. 34 4 E--01 - SOURCES RELEASED TO TORUS FROM SRV BLOWDOWN OF RPV II i l l l THIS IS A DRILL O : 1 l 1 e -, h ___.--_________--__________.-______-_A_.__ _ . . _ . _ _ _ . _ _ _ _ _ _ _ _ . . _
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POSTACCIDENT SAMPLES ( MESSAGE NO.H2O - 5 TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER i I LOCATION: CHEM LAB /OSC TIME: AS REDUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) FERMEX 87 TORUS WATER CHEMISTRY ANALYSIS 18 AUGUST 1987 k THIS IS A DRILL DO NOT take actione af f ecting nor mal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-85M 1.111E-02 TORUS WALER CHEMISTRY SAMPLE U.R. G;. 1.DOOE-03 KR- 87 1.391E-02 Results shal] be avai1abln KR-88 2.903E-02 at 10:1O hourn (T + 0:50) XE-133 5.602F-02 for any sampie taken at or prior . X E-- 135 4 . 8 '12E- 0.' to 10:10 hours ("I + 0:50) O T-)31 1-132
.754F-01 1.424E-01 ASSUMPTIONS I-133 2.679E-01 - - - - - - - - - - - - - - - - - -
1-104 2.663E 01 - NUREO 0769 EQUILIBRIUM CORE -j 1-135 2.30SE-01 - SOURCES RELEASED TO TORUS FROM SRV BLOWDOWN Of- RPV I i I j 1 THIS IS A DRILL 4 l g ,.c- .
POSTACCIDENT SAMPLES MESSAGE NO.H2O - 6 j TO: CHEMISTRY TECHNICIAN FROM TEAM EXERCISE CONTROLLER /OSC CONTROLLER ,. l i LOCATION: CHEM LAB /OSC TIME: AS REDUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) i FERMEX 87 TORUS WATER CHEMISTRY ANALYSIS 18 AUGUST 1987 i THIS IS A DRILL DO NOT take actions affecting normal plant operations _ _ . _ . . . __. _ _ ~ _ _ _ _ , . .___.._.. _..____.-_ _ --___-___.__.__ _ ---..-__. j NUCLIDE ACTIVITY (UC1/CC) COMMENTS KR-85M 1.082E-02 TORUS WATER CHEMISTRY SAMPLE KR-SS 1.3OOE-05 i FR-87 1.270E-02 Results shal) be available l 2.854E-02 at 10:20 hours (T + 1: 0) j KR-8G XE-133 5.597E-02 for any sample taken at or prior ~ A L- 10"i 4. 7 9 vE-4.C to 10:20 hours (T + 1: O) O 2-> 1 1-132 1 =-o ' 1.35bE-01 ASSUMPTIONS: 1 - 13'. 2.664E-01 ---------------- 1-134 2.618F-01 - NUREG'0769 EQUILIBRIUM CORE I-135 2.266E-01 - SOURCES RELEASED TO TORUS FROM SRV BLOWDOWW OF kPV THIS IS A DRILL
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POSTACCIDENT SAMPLES MESSAGE NO.H2O - 7 O TO: CHEMISTRY TECHNICIAN l l e, 1 FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER ( LOCATION: CHEM LAB /OSC TIME: AS REDUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) l l FERMEX 87 TORUS WATER CHEMISTRY ANALYSIS 18 AUGUST 1987 f lHIS 15 A DRILL DO NOT take actions affecting normal plant operations NUCLIDE ALTIVITY (UCI/CC) COMMENTS KR-85M 1.055E-02 TORUS WATER CHEMISTRY SAMPLE ICR -35 1.3OOE-05 LR-87 1.159E-02 Results shall be avai l abl e KR-88 2.506E-02 at 10:30 hours (T + 1:10) * ' X E - 1 -' 5.592E-02 for any cample taken at or prior X E-- 135 4.709E-02 to 10:30 hours (T + 1:10) 1
\ ] - l '.1 1. ?S".'.E-- O 1 1-132 1.289E-01 ASSUMPTIONS:
1 - 1 L. . 2. e4 9E--01 - - - - - - - - - - - - - - - - - - 1-134 .:.674E-U1 - NUREG 0769 EQUILIBRIUM COhE I-135 2.228E-n1 - SOURCES RELEASED TO TORUS FROM SRV BLOWDOWN OF RPV p om use, eso ee see _ .g , .e. = = go gie e.e ses .gg a,e unee e,e ee me no ese amo. om me es. eism asen ese een e . upp. see .es ua> esp g.i w e.m m.> .e op emer .e ese ese _ _ my _ mem -
.uar ao em es. _.e me og am. e.e s>e es. em ene -- gum os _
THIS IS A DRILL _ _ _ _ _ . e_-..-___. -_-..__ _e_________________________ _._____ ____ __ _ 4
POSTACCIDENT SAMPLES
/
MESSAGE NO.H2O - 8 TO: CHEMISTRY TECHNICIAN FROMs TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEM LAB /OSC TIME: AS REQUEST ED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) 18 AUGUST 1987 FERMEX 87 TORUS WATER CHEMISTRY ANALYSIS TH16 IL H DRJLL DO NOT take actions af f ecting normal plant. operations - . _ _ _ _ - _ _ - . _ _ . . . . . . . . - - . NUCLIDE ACTTVITY (UCI/CC) COMMENTS IJR-85M 1.027E-02 TORUS WATER CHEMISTRY SAMPLE 1: k- 35 1.SUOE-03 1.h - D 1. 05GE--02 Resulte shall be avai l atsi s 1:20) UR-GB 2.758E-02 at 10:40 hours (T +
>T - 1 ~' ~' S.587E-02 f or any sanipl e t aten at or prior .
< esou-o te 1o=40 revre <T + 1=2o>
O > 1=s I- '. 1 1 ) , :?,7r.. n j 1-132 1.226E-01 ASSUMPTIONS:
} - 13~. 2.634E-01 1-134 z . U21 E--01 NURECa 0769 EQUILIERIL41 LORE 1 - 1 Ni ?.190E-01 - SOLIRCES RELEASED Tfi TOPilF. FROM SRV BLOWDOWN OF RPV l
~ . . _ _ _ _ _
THIS IS A DRILL 3
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[- 1 1 POSTACCIDENT SAMPLES MESSAGE NO.H2O - 9 I TO: CHEMISTRY TECHNICIAN l FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER < LOCATION: CHEM LAB /OSC i TIME: AS REQUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) FERMEX 87 TORUS WATER CHEMISTRY ANALYSIS 18 AUGUST 1987 THIS IS A DRILL DO NOT take actions af f ecting nor mal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-OSM 1. OO 1 E--02 TORUS WATER CHEMISTRY FAMPLE l'R-85 1. 2OOE- 07 KR-87 9. 664 E--03 Results shall be availeble KR-88 2. 712E -02 at 10:50 hourc (T + 1:30) XE-133 5.582E-02 for any cample taken at or prior , AL.-13b 4. SbaL 0; t. o 10:60 hours (T + 3:30) O i->as 1-15z i . 2sl e--01
- 1. l e>6E- 01 (iSSUMPT 1 ONS :
1-1T2 2. 620E --01 - - - - - - - - - - _ - - - - f-134 2.4G8f.-01 - NUREG 0769 EQUILIBRIUM CORE 1-13b 2.153E-01 - SOURCES-RELEASED TO TORUS FROM SRV BLOWDOWN OI- RPV THIS IS A DRILL i
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POSTACCIDENT SAMPLES MESSAGE NO.H2O -10 TO: CHEMISTRY TECHNICIAN
^
FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER j LOCATION: CHEM LAB /OSC TIME: AS REDUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) FERMEX 87 TORUS WATER CHEMISTRY ANALYSIS 18 AUGUST 1907 THIS 16 A ORILL , l DO NOT take actions affectinqJ normal plant operations
... _____ ..-_..-_m _ _ _ . . _ _ _ _ . .. __... .. .. ____ _ .._ .__ .._ . . _ . . . _ _ . . . j NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-85M 9. 754E -03 TORUS WATER CHEMISTRY SAMPLE KR-85 1.300C-03 KR-87 8.823E-03 Resul t s shall be available KR-88 2.666E-02 at 11: O hours (T + 1:40) -
1 XE-13-a J.576E-02 ior any samp)e taken at or pr2or 4.47SE-02 to 11: O hours (T + 1:40) O XE-135 1 '.1 1.251E-01 I-132 1.109E-01 ASSUMPTIONS: 1-133 2.oOSE-01 ----- ---------- I-134 2.446E-01 -- NUREG 0769 EDLIILIBRIUM COfeE J - 1 ~.5 2.117E-01 - SOURCEG RELEASED TO TORUS FROM SRV BLOWDOWN OF RPV 1 i J l l 1 THIS IS A DRILL l i i l I l
l POSTACCIDENT SAMPLES Of's MESSAGE NO.H2O -11 V TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEM LAB /OSC TIME: AS REQUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) 1 L'ERMEX 87 10RUS WATER CHEMISTRY ANALYSIS 18 AUGUST 1987 l
------------------------------ --------------------------------------- l TH1b lb A DRILL i i
DO NOT take actions affecting normal plant operat2ons NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-85M 9.503E-03 TORUS WATER CHEMISTRY SAMPLE KR-85 1.3OUE-03 KR-07 8.OS6E-O' Re st,u l t s shalI be Ma31able KR-88 2.621E-02 at 11:10 hours (T + 1:50)
- XF-135 5.5?)F-02 for any samp1e taken at or prior
() XE-135 1 131 4.399E-02 1.T M E-n1 to 11:10 hours (T + 1:50) 1-132 1.055E-01 ASSUMPTIONS: 1-133 2.590E-01 I-1;9 z. 405E- 01 - NUREG G769 EQUILlBRIU11 CORE I-135 2.OO1E-n1 - SOURCES RELEASED TO TORUS FROM SRV BLOWDOWN OF RPV THIS IS A DRILL O
l
/T POSTACCIDENT SAMPLES k/ MESSAGE NO.H2O -12 TO: CHEMISTRY TECHNICIAN '-
FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEM LAB /OSC TIME: AS REQUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) FERMEX 87 TORUS WATER CHEMISTRY ANALYSIS 18 AUGUST 1987 THIS IS A DRILL DO NOT take actions affecting normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-85M 9.260E-03 TORUS WATER CHEMISTRY SAMPLE KR-85 1.3OOE-03 KR-87 7.355E-03 Results shall be available . KR-88 2.577E-02 at 11:20 hours (T + 2 0) (} XE-133 XE-135 5.566E-02 4.325E-02 for any sample taken at or prior to 11:20 hours (T + 2: 0) I-131 1.249E-01 1-132 1.OO4E-01 ASSUMPTIONS: I-133 2.576E-01 ---------------- I-134 2.364E-01 - NUREG 0769 EQUILIBRIUM CORE I-135 2.046E-01 - SOURCES RELEASED TO TORUS FROM SRV BLOWDOWN OF RPV THIS IS A DRILL t O l
~.
POSTACCIDENT SAMPLES MESSAGE NO.H2O -13 O TO: CHEMISTRY TECHNICIAN ( FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEM LAB /OSC TIME: AS REDUESTED WITHIN APPLICABLE TIME FRAME-(SEE COMMENTS SECTION BELOW) FERMEX 87 TORUS WATER CHEMISTRY ANALYSIS 18 AUGUST 1987 THIS IS A DRILL DO NOT take act. ions affecting normal plant operationt NUCLIDE ACTIVITV (UCI/CC) COMMENTS KR-SSM 9.022E-05 TuRUS WATER CHEMISTRY SAMPLE KR-85 1.3OOE-0; KR-87 6.7J5E-03 Results shall be available KR-88 2.534E-02 at 11:30 hours (T + 2:10) XE-163 . 561E-02 for any sample taken at or prior . 1 XE-135 4.252E-02 to 11:30 hours (T + 2:10) I-131 1.248E-01 1-132 9.546E-U2 ASSUMPTIONS: I -- i 33 2. 562E--01 - - - - - - - - - - - - - - - - - - - I-134 2.324E-01 - NUREG 0769 EQUILIBRIUM CORE I-135 2.012E-01 - SOURCES RELEASED TO TORUS FROM SRV BLOWDOWN OF RPV 4 I
-------------------------*. =------------------------------------------
THIS IS A DRILL s
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POSTACCIDENT SAMPLES MESSAGE NO.H2O -14 , TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEM LAB /OSC TIME: AS REOUESTED WITHIN APPLICABLE TIME FRAME > (SEE COMMENTS SECTION BELOW) FERMEX 87 TORUS WATER CHEMISTRY ANALYSIS 18 AUGUST 1987 l l __ ___ _-_ _ ____ _ _ _____._ __ THlE 1E A DRILL DO NOT take actions affecting normal clant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-BSM G.790E-03 TORLIS WATER CHEMISTRY SAMFLE l:.R -05 1.50 % -03 Ida 7 6.131E-03 Results shall be avai l abl e- . KR-b3 2.491E-02 at 11:40 hourn (T + 2:20) - XE-133 5.5S6E-02 for any sample taken et or prior to 11:40 hours (T + 2:2v) O XE-13S 1 < ~.1 4.181E-02 1 NpE 01 1-132 9.081E-02 ASSUMPTIONS: 1-133 2.547E-01 - - - - - - - - - - - - - - 1-134 2.235E-01 - NUREG 0769 EQUILIBRIL11 C ORC 1-135 1.978F-61 - SOURCES RELFASED TO TORUS FROM SRV BLOWDOWN OF RPV j THIS IS A DRILL O
l i PO5TACCIDENT SAMPLES MESSAGE NO.H2O -15 j TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEM LAB /OSC TIME: AS REQUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) FERMEX 87 TORUS WATER CHEMISTRY ANALYSIS 18 AUGUST 1987 THIS IS A DRILL DO NOT take actions effecting normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-85M 8.S65E-05 TORUS WATER CHEMISTRY SAMPLE KR-C?i 1.500E-03 ER-87 5.598E-07 Results shall be available KR-8G 2.449E-02 at 11:50 hours (T + 2:30) XE-13~ 5.551F-02 for any sample taken at or pri or . XE- 13b 4.110E-02 to 11:50 hours (T + 2:30) O 1-171 I-132. 1.747F-01 8.638E-02 ASSUMPTIONS: 1 1 - 1 T', 2 m3E 01 - - - - - - - - - - - - - - - - - I-154 2.247E-01 - NUREG 0769 EQUILIBRIUM 1 CORE 1-13D 1.944F-01 - SOURCES RELEASED TO TORUS FROM SRV BLOWDOWN OF RPV l l 1 l 1
- . . . . _ _ . . _ - . . _ _ _ _ . _ _ _ . - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . . l THIS IS A DRILL A
9
POSTACCIDENT SAMPLES MESSAGE NO.H2O -16. TO: CHEMISTRY TECHNICIAN i 1 FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER , l LOCATION: CHEM LAB /OSC i TIME: AS REOUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) FERMEX S7 TORUS WATER CHEMISTRY ANALYSIS 18 AUGUST 1987 THID 10 A DRILL. j DO NOT take actions affecting normal plant operations NUCLIDE ACTIVITY (UC1/CC) COMMENTS KR-OSM D.345E-OI. TORUS WATER CHEMISTRY SAMPLE KR-Ob 1.3OOE 03 1R-07 5.133E-03 Results chall be avail able KR-88 2.40GE--02 at 12: 0 hours (T + 2:40) XE-133 5.546E-02 for any sample taken at or prior - XE lbb 4. v41 E--02 to 12: O houre (T + 2 : 4(.O O I-131 1.746E-01 1-132 8.216E-02 ASSUMPTIONS: j 1-133 2. 53 9E- 01 ---------------- I-134 2.209C-01 - NUREG 0769 EQUILIBRIUM CORC I-135 2.912E-01 - SOURCES RELEASED TO TORUS FROM SRV BLOWDOWN OF RPV i ) THIS IS A DRILL f i i l m ..
POSTACCIDENT SAMPLES j MESSAGE NO.H2O -17 (- TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEM LAB /OSC TIME: AS REQUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) FERMEX 87 TORUS WATER CHEMISTRY ANALYSIS 18 AUGUST 1987 i i THIS IS A DRIL.L DO NO1 take actions affecting normal plant operations
- . _ _ _ . . . . . _ _ _ . - . - . _ . . _ . _ _ _ . _ _ . . . . _ . - . . . _ _ - _ _ . . _ _ _ _ _ . . _ , . _ _ _ _ _ . . . . _ . j j
NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-85M 8.131E-03 TORUS WATER CHEMISTRY SAMPLE l'R-85 1.SOOE-03 i T:-87 4.666E-CO ResultE sh,11 be avai1able KR-88 2.367E-02 at 12:10 hours (T + 2:50) - XE-133 5.541E-02 for any sample taken at or prior ; 2:50) j f A li.- 135 3. 9 7 3E-- 0 2 to 12: 10 hours (T + 1 1 131 1.745E-01 1-132 7.816E-02 ASSUMPTIONS: 1-133 2.505E-01 - - - - - - - - - - - - - - - - I-134 2.172C-01 - NUREG 0769 EQUILIBRIUM CORE I-135 1.879E-01 - SOURCES RELEASED TO TORUS FROM SRV BLOWDOWN OF RPV 1 t 1 THIS IS A DRILL l \
POSTACCIDENT SAMPLES MESSAGE NO.H2O -18 TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEM LAB /OSC TIME: AS REDUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) FERMEX 87 TORUS WATER CHEMISTRY ANALYSIS 18 AUGUST 1907 THIS IS A DRILL DO NOT take actions af f ecting normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS UR-85M 7.922E-03 TORUS WATER CHEMISTRY SAMPLE LR-85 1.300E-03 UR-87 ti . 261 E- 03 Resul t s shall be avai I t,b1 e UR-88 2.327E-02 at 12:20 hours (T + 3: 0) XE-133 5.536E-02 for any r, ample taken at or prior . XE-135 3.906E-02 to 12:20 hours (1 + 3: 0) O 1 - 1 .1 1 . " \5 r - c.1 1-132 7.435E-02 ASSUMPTIONS: 1_1 ,3 2.as1E_01 1 - l'.:.4 2.135E-01 - NUREG 0769 EQUILIBRIUM CORE 1-175 1. 84GE--01 - SOURCES RELEASFD TO TORUE, FROM SRV BLOWDOWN OF RPV THIS IS A DRILL
\
POSTACCIDENT SAMPLES MESSAGE NO.H2O -19 { TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEM LAB /OSC TIME: AS REQUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) FERMEX 87 TORUS WATER CHEMISTRY ANALYSIS 18 AUGUST 1987 THIS JS A DRILL. DO NOT take actions affecting normal plant operations NUCLIDE ACTIVITY (UC1/CC) COMMENTS
}lR -85M ~7. 719 E -03 TORUS WATER CHEMISTRY SAMPLE KR-Ob 1. 3OOE- 03 I Ts'- D i 890E-03 Results shall be avail able MR-80 2.288E_02 at 12:30 hours (T + 3:10) -
XE-133 5.530E-02 for any sample taken at or pr i or AE-15b 0. 640E--02 to 12:30 hours (T + 3:los 1--171 1.744E-01 I_132 7.072E_02 ASSUMPTIONS:
]_13; 2.477E-01 I-134 2. 099E -01 -- NUREG 0769 COUILIBRIUM CORE
- SOURCES RELEASED TO TORUS FROM l I-13S 1.817E-01 SRV BLOWDOWN OF RPV THIS IS A DRILL
POSTACCIDENT SAMPLES MESSAGE NO.H2O -20 TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEM LAD /OSC TIME: AS REOUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) FERMEX 57 TORUS WATER CHEMISTRY ANALYSIS 18 AUGUST 1937 I TH]S IS A DRILL DO NOT take actions affecting normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-OSM 7.521E-03 TORUS WATER CHEMISTRY SAMPLE 6:R-E5 1. COOE -03 FR- 87 3.552E-03 Results shall be avail abl e KR-88 2.249E-02 at 12:40 hours (T + 3:20) XE-133 5.525E-02 for any sample taken at or prior - r'% XE-135 S 775E-02 to 12:40 hours (T + 3:20) i d 1-131 1.243F-01 i I-132 6.727E-02 ASSUMPTIONS: 1-133 2.463E-01 ---------------- I-134 2.064E-01 - NUREG 0769 EQUILIBRIUM CORE I-135 1.786E-01 - SOURCES RELEASED TO TORUS FROM SRV BLOWDOWN OF RPV J 1 i i 1 THIS IS A DRILL '
I i 1 i l POSTACCIDENT SAMPLES l
- MESSAGE NO.H2O -21 I III TO: CHEMISTRY TECHNICIAN f i
FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEM LAB /OSC l TIME: AS REQUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) FERMEX 87 TORUS WATER CHEMISTRY ANALYSIS 18 AUGUST 1987 lH1b 15 A DRILL l DO NOT tape actions affecting normal plant operations NUCLIDE ACTIVITY (UC1/CC) COMMENTS l l KR-8bN 7.32SE-03 TORUS WATER CHEMISTRY SAMPLE hk Ob 1.3v0E-02
R- F0 7.243E-03 Results shall be avai l abl e FR-83 2.211E-02 at 12:50 hours (T + 3:30)
)f E- 1." 5.5?OE-02 for any sample taken at or prior .
f, XL-135 3.712E-02 to 12:50 hours (T + 3:30) 1 - 1 ~.1 1.^47F n1 1-132 6.399E-02 ASSUMPTIONS: 1 - 15.; 2.449E-01 ---------------- I--134 -. 029E- 01 - NUREG 0769 EQUILIbRIU!: CORE 1-135 1.756E-01 - SOURCES RELEASED TO TORUB FROM SRV BLOWDOWN OF RPV 1 l l 1 THIS IS A DRILL O
POSTACCIDENT SAMPLES MESSAGE NO.H2O -22 O TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEM LAB /OSC l TIME: AS REQUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) I i FERMEX 87 TORUS WATER CHEMISTRY ANALYSIS 18 AUGUST 1987 l THIS IS A DRIL.L DO NOT take actions affecting normal plant operations l _....__._.. .___.._____._____ _._....___-_-_._ __ _ _-___..__.__. l -..__._....___ NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-85M 7.140E-03 TORUS WATER CHEMISTRY SAMPLE LR-85 1.3COE-03 iR-87 2.561E-03 Results shal1 be avai1able KR-G8 2.174E-02 at 13: O hours (T + 3 4G) XE-133 5.515E.-02 f or any semp) e t el en ::t or pr i or XE-135 .649E-02 to 13: O hours (T + 3:40) O T-1~1 1.242F-01 I-132 6.087E-02 ASSUMPTIONS: 1-13' 2. 4 36E--01 - - - - - - - - - - - - - - - - I-134 1.995E-01 - NURCG O > EQUILIBRIUM CORE 1-175 1.726E-01 -- SOURCE! H..L EASED TO TORUS FROM SRV BLOWDOWN OF RPV l l THIS IS A DRILL w . y
POSTACCIDENT SAMPLES MESSAGE NO H2O -23 TO: CHEMISTRY TECHNICIAN 8 FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEM LAB /OSC TIME: AS REQUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) FERMEX 87 TORUS WATER CHEMISTRY ANALYSIS is AUGUST 1987 THIS IS A DRILL DO NOT take actions affecting normal plant operations NUCLIDE ACTIV11Y (UCI/CC) COMMENTS . I V.R- OLM 6. 956E--03 TORUS WATER CHEMISTRY SAMPLE o.R-85 1.300E-03 IT-87 ..195E-O! Renultn Ehell ts e avai l abl e KR-88 2.137E-02 at 13:10 hours (T + 3:50) ~ XE-133 U.510E-02 f or any sample taken at or pr i or
..S5dE-02 ta 10:10 hours (T + 3:50)
( X E -- 1 f.5 1-131 1.241F-01 1-132 S.790E-02 ASSUMPTIONS: 1-177 2.422E-01 - - - - - - - - - - - - - - - I-134 1.961E-01 - NUREG O'769 EQUILIBRIUM CORE I-135 1.697E-01 - SOURCES RELEASED TO TORUS FRDM SRV BLOWDOWN OF RPV 1 I
---------------...--------- .--- - --------------------------- -- ..-- )
THIS IS A DRILL O , 1 l L .J
i l POSTACCIDENT SAMPLES MESSAGE NO.H2O -24 V TO: CHEMIS'IRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER J LOCATION: CHEM LAB /OSC TIME: AS REDUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) FERMEX 87 TORUS WATER CHEMISTRY ANALYSIS 18 AUGUST 1987 ! lHIS 15 A DRILL DO NOT take actions affecting normal plant operations NUCLIDE ACTIVITY (UC1/CC) COMMENTS UR-85M 6. 7 '/ 8E-03 TORUS WATER CHEMISTRY SAMPLE LR-85 1.3OOE-03 VP-8" 2.468E-03 Resulte shh11 be available KR-88 2.101E-02 at 13:20 hours (T + 4: O) XF-1~~ 5.50DE-O? f c.r any s,emp3e talen at or prior (# XE-135 3.527E-02 to 13:20 hours (T + 4: 0)
\ 1 4 ~. j j , ^ t;OE. a 1 1-132 5.508E-02 ASSUMPTIONS:
I-133 2. 4 0iE --01 - - - - - - - - - - - - - - - - - 1-134 1.92DE-01 - NLiREG 0769 EQUILIBRIUM CORE 1 - 1 ".5 1.669E-01 - SOURCES RELEASED TO TORLIS FROM SRV BLOWDOWN OF RPV l THIS IS A DRILL w----__.-___-_.-_.-.-_ - _ _ . _ _ _ _ _ . _ _ _ . _
POSTACCIDENT SAMPLES MESSAGE NO.H2O -25 J l TO: CHEMISTRY TECHNICIAN I ( i FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER 1 LOCATION: CHEM LAB /OSC TIME: AS REQUESTED WITHIN APPLICABLE TIME FRAME , (SEE COMMENTS SECTION BELOW) ( FERMEX 87 TORUS WATER CHEMISTRY ANALYSIS 18 AUGUST'1987 . l lHis 15 A DR3LL DO NOT take actions affectina normal plant operations t NUCLIDE ACTIVITY (UCI/CC) COMMENTS VR-05M 6.604E-0.! TORUS WATER CHEMISTRY SAMPLE KR 05 1. 3OOE- 03 ER U7 2.253E-07 Resulte sha)I be avai1able KR-89 2.066E-02 at 13:30 hours (T + 4:10) " X F -- 1 7' ' 5.c.nOE-02 fnr any sampl e taken at or r>r i or
; i XE-135 3.468E-02 to 13:30 hours (1 + 4:10) 1.. - ; ., ~MF - 01 I-132 5.239E-02 ASSUMPTIONS:
I-1?C 2.39LE-01 ----------------- 1--134 1. 5 75E--01 - NUREG 0769 COUILIBRIUM CORE 1-135 1. 640E -01 - SOURCES RELEASED TO TORUS FROM SRV BLOWDOWN OF RPV l _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . ] THIS IS A DRILL ________..__ __ _ ___ _________ _______ _______ ____.__ _______ \ l\ l I 4
POSTACCIDENT SAMPLES
- MESSAGE NO.H2O -26
- I TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEM LAB /OSC TIME: AS REQUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW)
FERMEX 87 TORUC WATER CHEMISTRY ANALYSIS 19 AUGUST 1997 Tl!I L IS A DRILL DO NOT take actions affecting normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS l KR-85M 6.434E-03 TORUS WATER CHEMISTRY SAMPLE IR-G5 1.3OOE-03 1:R-07 2.057E-03 Resu)ts shal1 be avai1able KR-80 2.031E-02 at 13:40 hours (T + 4:20) XE-133 5.495E-02 for any sample taken et or prior XE- 1 M : 4OVE~0; tc 13:40 hours (T + 4:20) ('/ 3 I-131 1.T39E-G1 1-132 4.984E-02 ASSUMPTIONS: 1--133 2.382E-01 ---------------- I-134 1,863E-01 - NUREG 0769 EQUILIBR1UM CORE I-135 1.613E-01 - SOURCES RELEASED TO TORUS FROM SRV BLOWDOWN OF RF'V 1 l THIS IS A DRILL O J
POSTACCIDENT SAMPLES j MESSAGE NO.H2O -27 (oh TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER *- LOCATION: CHEM LAB /OSC TIME: AS REQUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) FERMEX 87 TORUS WATER CHEMISTRY ANALYSIS 18 AUGUST 1987 THIS IS A DRILL i DO NOT take actions affecting normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS UR-85M 6.269E-03 TORUS WATER CHEMISTRY SAMPLE I R-- 05 1.300E 03 l l'.R-87 1.S70E-03 Results shell be avail able KR-8S 1.997E-02 at 13:50 hours (T + 4:30) X E - 1 :. 5.490E-02 for any sample taken at or pr i or , 136 ~.352E-02 to 13:50 hours (T + 4:30) () I 131 1-132 1.23SE-01 4.740E-02 ASSUMPTIONS: I-1~3 2.J.68E-01 ---------------- I--134 1.332E-01 -- NUREG 0769 EDUILIDRIUM COF:C 1-135 1.586E-01 - SOURCES RELEASED TO TORUS FRDM SRV BLOWDOWN OF RPV l 1 l 1 l THIS IS A DRILL i
,v.
POSTACCIDENT SAMPLES
+ MESSAGE NO.H2O -28 TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEM LAB /OSC TIME: AS REQUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW)
FERMEX 87 TORUS WATER CHEMISTRY ANALYSIS 18 AUGUST 1987 THIS IS A DRILL DO NOT take actions affectina normal plant operations
- - - - - . . - - . . - . . - - - - - - . - ~ - . . - - - - . . - - - - - - - . . - - . - - - . . - . - - - - - . - - . . . . .
NUCLIDE ACTIVITY (UC1/CC) COMMENTS KR-85M 6.10SE-03 TORUS WATER CHEMISTRY SAMPLE KR-85 1.3OOE-O! KR-87 1.715E-07 Resul ts shalI be av a21 abl e KR-89 1.963E-02 at 14: O hours (T + 4:40) YE 153 5 . 4 8 5 E - 0.~.' for any sample taken at or prior . XE-135 3.295E-02 to 14: O hours (T + 4:40)
\ 1- : 71 1. r 37 F- O .!
I-132 4.509E-02 ASSUMPTIONS: 1-133 2.355E-01 ---------------- I-134 1.801E-01 - NLIREG 0769 EQUILIBRIUM CORE I-1'n 1.559E-01 - SOURCES REL FASED TO TORUB FROM SRV BLOWDOWN OF RPV THIS IS A DRILL (
POSTACCIDENT SAMPLES MESSAGE NO.H2O -29 .g) v. TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEM LAB /OSC i TIME: AS REQUESTED WITHIN APPLICABLE TIME FRAME j (SEE COMMENTS SECTION BELOW) FERMEX 87 TORUS WATER CHEMISTRY ANALYSIS 19 AUGUST.1987 THIS IS A DRILL DO NOT take actions afiecting normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS FR-85M 5.952E-03 TORUS WATER CHEMISTRY SAMPLE kh-55 1.3OOE-03 ] l'R-87 1.566E-03 Results shell be avail able KR-88 1.930E-02 at 14:10 hours (T + 4:50) XE-133 5.4BOE-02 for any sample taken at or prior - (' XE-135 3.240L-02 to 14:10 hours ( ~1 + 4:50) 1-171 1.236E-h1 1-132 4.289E-02 ASSUMPTIONS: 1-107, 2.342E-01 ---.-_---------- 1-134 1.771C-01 - NUREG 0769 EQUILIBRIUM CORE I-135 1.533E-01 - SOURCES RELEASED TO TORUS FROM SRV BLOWDOWN OF RPV l
-- ----- ----~~~~~___-~~~ _----~~----~~_--_-__-----~~-~~~~~----_-~~--- b THIS IS A DRILL
------_---_--~~~-_~~~~-~~-_--_________-~~_---_--_______-_-__--_----_--
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~
POSTACCIDENT SAMPLES MESSAGE NO.H2O -30 ,s TO: CHEMISTRY TECHNICIAN i j FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER , LOCATION: CHEM LAB /OSC TIME: AS REQUESTED WITHIN APPLICABLE TIME FRAME j (SEE COMMENTS SECTION BELOW) ) l FERMEX 87 TORUS WATER CHEMISTRY ANALYSIS 18 AUGUST 1987 j i
--------------- .-- --------------- . --- l THJS IS A DRILL DO NOT take actions affecting normal plant operations NUCL'IDE ACTIVITY (UCI/CC) COMMENTS i:R-85M b.799E-O! TORUS WATER CHEMISTRY SAMPLE
):n -OS 1 ,..,0 0 E - 0 3
) R- 07 1. 4 3 0 E - O~'. Results shalI be avai1 abl e KR-88 1. 895E--02 at 14:20 hours (T + 5: O)
XE-133 5.475E-02 ior any samp1e t aken at or r" 2 or , g X E -- 13 L ... 18 bE -- 0 2 to 14:20 hours (T + 5: Os V J-131 1.236E-01 1-132 4.080E-02 ASSUMPT1ONS: 1-15~ 2. 32 9E--01 - - - - - - - - - - - - I-134 1.741E-01 NUREG 0769 EQUILIBRIUM CORE 1-135 1.507E-01 - SOURt!ES RELEASED TO TORUS FROM SRV BLOWDOWN OF RPV i THIS IS A DRILL O
i POSTACCIDENT SAMPLES
- MESSAGE NO.H2O -31 TO: CHEMISTRY TECHNICIAN i
FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER f LOCATION: CHEM LAB /OSC TIME: AS REQUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) FERMEX 87 TORUS' WATER CHEMISTRY ANALYSIS 18 AUGUST 1987 1HIS 15 A DRILL DO NOT take actions af f ecting normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS VR-85M 5.650E-03 TORUS WATER CHEMISTRY SAMPLE Kk-85 1.3OOE-03 KR-87 1.305E-03 Results shall be avai1able KR-88 1.866E-02 at 14:30 hours (T + 5:10) XE-133 5.470E-02 for any sempl e t alen at or prior . XE-135 3.131E-02 to 14:30 hours ( -) + 5:10) Os 1-3'1 1, '~.5E -01 1-132 3.881E-02 ASSUMPTIONS: 1-13: 2.316E-01 ---~~----------- I-134 1.712E-01 - NUREG 0769 EQUILIBRIUM CORE I-175 1.491E-01 - SOURCES RELEASED TO TORUS FROM SRV BLOWDOWN OF RPV 1 l THIS IS A DRILL S G
i j l' POSTACCIDENT SAMPLES ! MESSAGE NO.H2O -32 TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATIOM: CHEM LAB /OSC TIME: AS REQUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS.SECTION BELOW) FERMEX 07 TORUS WATER CHEMISTRY ANALYSIS 18 AUGUST 1987 l l l T H l E. IS A DRILL DO NOT take actions affecting normal p1 ant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS UR-BbM 5.505E-03 TORUS WATER CHEMISTRY SAMPLE hh-G5 1.300E-03 11R-P7 1.192E-03 Results shall be avai 1 abl e KP-88 1.834E-02 at 14:40 hours (T + 5:20) X E 5.465E-02 for any sampie taken at or prior - XE-! a .:. 07 9 E. -'.s2 to 14:40 hours (T + 5:20) Os 1 171 i ?L1F-01 I~13' 3.692E-02 ASSUMPTIONS: 1 - 1 c. s s. . u. t -- 01 --~~~----------- I-134 1. d is . il - NUREO 0769 EQUILIBRIUM CORE I-135 1. ASM -.1 - SOURCES RELEASED TO TORUS FROM i f SRV BLOWDOWN OF RPV i
.e. een ese e es ese me e.s e a .e - me e.= ao em e=e e == een m. me me a m. -e - um em e es - .s- .e a - em - - == .m - ene ao see - ,mm a en em me ans - see es amo me em amm - em eum em THIS IS A DRILL
l l 1 l l POSTACCIDENT SAMPLES
- MESSAGE NO.H2O -33 %.) l J
TO: CHEMISTRY TECHNICIAN )l i FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEM LAB /OSC ! l TIME: AS REQUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) FERMEX 87 TORUS WATER CHEMISTRY ANALYSIS 18 AUGUST 1987 THIG IS A DRILL DO NOT take actions affecting normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-85M 5.364E-03 TORUS WATER CHEMISTRY SAMPLE KR-G5 i.3OOE-03 KR-87 1.088E-03 Results shall be avail abl e KR-83 1.803E-02 at 14:50 hours (T + 5:30) XE-133 5.460E-02 for any sample taken at or prior-XE-135 a. 027E-02 to 14:50 hours (T + 5:30) { I-131 1.234E-01 1-132 3.512E-02 ASSUMPTIONS: 1-133 2.290E-01 1 I 1-134 1.654E-01 - NUREG 0769 EQUILIEtRIUM CORE 1-135 1.432E-01 - SOURCES RELEASED TO TORUS FROM SRV ELOWDOWN OF RPV THIS IS A DRILL l 1
1 1 POSTACCIDENT SAMPLES MESSAGE NO.H2O -34 O TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEM LAB /OSC TIME: AS REQUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) FERMEX 07 TORUS WATER CHEMISTRY ANALYSIS 18 AUGUST 1997 THiS IS A DRILL DO NOT take actions affecting normal plant operations l NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR BLM 5.226E-03 TORUS WATER CHEMISTRY SAMPLE LR-GS 1. 3 OOC-O:... 1 ER-D7 9.934E-04 Results shall be avai l abl e i KR-88 1.773E-02 at 15: O hours (T + 5:40) - XE-133 5.455E-02 for any sample taken at or prior < f'i XL-135 2.976E-02 to 15: O hours (T + 5: 40) , V 1 - j ~',1 1.?'3E-01 I-132 3.341E-02 ASSUMPTIONS: 1-133 2. 27 7E- 01 ---------------- I--134 1.627C-01 - NURED 0769 EQUILIBRIUM CORE I-135 1.408F-01 - SOURCES RELEASED TO TORUS FRDM SRV BLOWDOWN OF RPV THIS IS A DRILL 1
POSTACCIDENT SAMPLES MESSAGE NO.H2O -35 8 TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEM LAB /OSC LIME: AS REQUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) FERMEX 87 TORUS WATER CHEMISTRY ANALYSIS 18 AUGUST 1907 l THIS Ib A DRILL i
}
DO NOl take actions affecting normal plant operations NUCLIDE ACTIVITY (UCI/CC) COMMENTS j l' VR-85M 5.092E-03 TORUS WATER CHEMISTRY SAMPLE KR-55 1.300E-03 UR- 07 9. 070E -04 Results shall be avai l abl e KP-8G 1.743E-02 at 15:10 hours (T + 5:50) XE-133 5.450E-02 for any sample taken at or pri or
# XE-135 T - l ?.1 1-132 2.92SE-02 1 ?32F-41 3.178E-02 to 15:10 hours (T + 5:50)
ASSUMPTIONS: 1 - 1 T1 2.265E-01 ---------------- 1-134 1.599E-01 - NUREG 0769 EQUILIBRIUM CORE I-135 1.384E-01 - SOURCES RELEASED TO TORUF, FROM SRV BLOWDOWN OF RPV l l L i 1 1 THIS IS A DRILL
i i POSTACCIDENT SAMPLES MESSAGE NO.H2O -36 8 TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEM LAB /OSC TIME: AS REDUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) FERMEX 87 TORUS WATER CHEMISTRY ANALYSIS 10 AUGUST 1987 THIS IS A DRILL l DO NOT take actions affecting normal plant operations l - - . . - - . . . . - . . . . . . . . - . . . . - . . - . - - - - - . . - _ . . - . . . . . . - - . - - - _ . . . - . . NUCLIDE ACTIVITY (UCI/CC) COMMENTS KR-SSM 4.961E-03 TORUS WATER CHEMISTRY SAMPLE l KR-OS 1.3OOE-O' l }R-87 8. 281 E -04 Results shall be available l KR-88 1.714E-02 at 15:20 hours (T + 6: 0) XE-13' 5. 4 4 5E--02 for ariy sample taken at or prior 4 X E-- 13b 2.076E-02 to 15:20 hours (T 4 o: 0)
/ ') 1- 17'.1 1. 2~ 1 E -01 V I-132 .f. 023E-02 ASSUMPTIONS:
1-137 2.252E-01 - - - - - - - - - - - - - - - - - - 1-1^i 1. 5 7 2 E --01 - NUREG 0769 EQUILIBRIUM CORE 1-135 1.361E-01 - SOURCES RELEASED TO TORUS FROM SRV BLOWDOWN OF RFV l i l l
-__--._ - -- --- _-_-_- ~ ---_. _ .._ ______._.___---_--_.-_ _ . _ -
THIS IS A DRILL
1 l O l 1
\
i l REACTOR COOLANT SAMPLES l l-m O i 1 j l l l l
I SCEt'ARIO FERMEX 87 CLOCK TIME = 0920-1400
,s MESSAGE il0. Chemist ry Controller _ SCENARIO TIME = 0220-0700 t \
.V FERMI - 2 i
<. 1 EMERGEllCY PREPAREDNESS EXERCISE MESSAGE FORM .;
1 MESSAGE FOR: Chemistry Controller MESSAGE: Give chemistry sample cheet f or the time the sample was taken 9 l l
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1 m *********************************** FOR CONTROLLER USE O!ILY: C0!TTROLLER tJ0TES: ACTI0tl EXPECTED: Results reported to Control Room /TSC. l
POSTACCIDENT SAMPLI:S [$ - MESSAGE ND.H2O - 1 o 10: CHEMISTRY TECHNICIAN FROM: TEMI EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEN LAD /OSC TIME: AS REDUESTED WITHIN APPLICAELE TIME FRAME (SEE COMMENTS SECTION BEL.OW) FERMEX 07- REACTOR COOLANT SAMPLE ANALYSIS 18 AUGUST 1987
"' H ) 5 19 A DH.I L L DO NOT tab ac tj ont af4+_ ting not mal p) ant operations 'l NUCLIDE AC'T IV1 TV (UCI/CC> COMMENTL I T.'-- D W 3 .15 3E - e5 klACTOii COOLANT SAMPLi' LR-05 1 . 1 5'. E - 0 6 l'R - D'; a oS::L~OD ResuliE En al l ne wv si 1 at;) e ..
Urc. nc q @ E~ - M et 9 : ~.0 hos.. (T -i- 0:10)
>1. - 1 7..c. ' . . i ce l E -M 4 or any sanipl e uta: t. L or pri or X E - 15~. 4 . E' 1.3 E - C " to 4:30 hours (1 - 0:107 1 ; .. .1 a 4 W i.it.O 1 - 1 T.: 1 /ie E e> AL5UHF T I ON'~ :
I-; . A . c r,% 41..') . -NUFEG_O/o9 E CC.ii L ) bill :.1/i '(10i4. 1 ;3; ; . 8 #E a m:. SDURCES fELEEE.D JD COth f2 41 j - ; '.S .. 'i c. E 4 >/> r Rol-i F UEL CL AD 0.R THIS IS A DRILL i.
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1 1 l l
-l < POS1 ACCIDENT SAMPLES <N MESSAGi" NO.H2O - 2 Q
TO: CHEMIGTRY TECHNICIAN l FROt1: TEAM EXERCISE CONTROLLER /DSC CONTROLLER l LOCATION: CHEM LAB /OSC T I ME~ : AS REDUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) FERMEX 87 REACTOR COOLANT SAMPLE ANALYSIS. 18 AUGUST 1987 THIS IS A DR)LL l l DO NOT tes. actions e i f ec.ti ng nor m61 r,l a n t operations NUCLIDE ACTIVIlv (UC1/CE COMMENTO l R-8% ..i28E-05 REAC, TOR COOLANT E;AhPL E KR :E.- 1. i W. O . 6.R.O/ i . F;.. ,i .OE Re.t u) t s. sha)] t> e avalla6 e . f(R - G3 2 . 8 4 r11 - 0 L at 9: 40 hout s ( 'l + 0 : ' . s>>
). i i s. '.; . j r b M. -l o r a n ., s vopl e i al.eq 4.t or prior p/
( /E .1." D a . 7 M t. - O'- to 9: 40 hout u ( ~i + 0:20) i j
) . 3 "', , c j p ., a0 ,
i 1 ^. .I . e , 219 00 ASSUHPT]ON5: 1 - 1 '. .6t.E 'u . IIUhE G..( , z 9 E cjuli II,F 1 UN CW.L
-S .'iJi, CE:s R[iLii ASED T O LOOL Al'.1 1-3'4 .. 6 2 1 E ". ".
l r R 0+, r Ui .._, r,1 m y J 1 .; : .! , . t E.. i i. . l [ 1 THIS IS A DRILL 4 (ah
/, ~~} PODTACC1 LENT SANPLES
- V 11EC560E 140.H2O -
C HElll 3 Tin' T E.Clil4ICI AN ' . ,. TO: I l FROM: TEAi1 EXERCISE CONTROLLER /OSC CONTROLLER LOCATIOM: CHEM LAD /OGC l TIME: AS REDUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENT 5 SECTION BELOW) j l FERMEX D7 REACTOR COOLANT SAMPLE ANALYSIS 18 AUGUST 1987 I T F 10 15 A DRILL , DO NOl ta- a c t i o n .. a f i r c: t i n o , cir m a l p l ar: L op er at i om. - - . . . - . -
. . . . . . . . . . - . . - ~ . ~ . - -
N!K L i E L AC T l'.'I T i (iR. I / CC , COMMENit I h G! .' 1.E ' i OS RLat:1 OR COOL 0NI S alii- u L.! t - D r., i.., n -o3 l T, f - , i s .: t >A F c t. > 1 t s ctial1 b .. c . i. 3ci.]+ l F .- N. . , e ..i . .F.
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i c>r an3 r. n o p 'i f- t n , t. ' i.' (.c p r ., cv Af-l' (] XE.. ~i . RJ. F - O '- i t c, 9;50 houru i. T < 0: , l '1 . t- -* i ' 1 1 :~. ' i .'- . si > AG E UMi" 1 1 Co J b : T-, .c.vi,.,~. . NURi 64- (O6 E. DU 'i L Ii 1.1 v. i (. t &
- "1 -50UhCi: , RE.I. E A5i 1 N.G.; . AN 8 1i , ., ii. .'
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l 1 THIS IS A DRILL ( l l O 1 j
lie 1 H - 4 TO: CHL?i11LTio' T ECHNICI AN ,, FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEM L/4D/05C TIME: AS REQUESTED WITH1N APPLICALLE TIME FRAME (SEE COMMENTS SECTION BELOW) l FERMEX 87. REACTOR COOL.fiNT SAMPLE ANALYSIG '18 AUGUST 1987 I
'IHis 15 A DRILL
'l DO NDi t44e a c t .t on s: af-fect2ng normt1 pl ant operatione . . - - - . .
NUC L I EE: Ar11W I Y (dC1/CC) COMMENTL l'Fe- W.H 1. 071L ~OD RFACTOR CODLA!JT SAMPLE w .c . , . > w u. l .F/ i ^ l . 4 D9) -o.. Thsu)tr shal3 t. e a vai ] Et.1 r UN -re i . 8 .2 r - .S at 10: O houro (T 4 0:40) 1 e i: - ) 2 ..' E.. ' ii. -QD -( & eny E anip l e t.e k e:a r at or pr,or O XE 1 75 J , ~' i
- 4. 574F -05
. a'yia00 to 10: a hourr. (T 4 0:40'
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+
.4T!!4Ou 435tJni T I DNS:
1 - - 3 .e111+60 --NURLE-0*; 69 L OU ll I DR 1 Uri C BRT l I - l .. . ..,2/LsOu -SDURCEL RELEASED TO CDDL41;T
-17 z . J L A i OO l'ROn FUEL CL4D GAP l
1 I I i THIS IS A DRILL
. . . . . . - . - ~ . . . . . . - . . . . . . . . . . . . . . .
L0 l l l l l l
e f OLT ALC.1 DF.NT SAMPLES h HE % GE NO.H2O -- S TO: CJIENISTR / l Ei.HNI CI AN e F' ROM: TEAM EXERCISC CONTROLLER /OSC CONTROLLER L.OCAT I ON : CHEM LAB /05C TIME: AS REQUESTED WITHIN APPLICABLE TIME FRAME (5EE COMMENTS E.ECTION BELOW) FERMEX 87 RE ACT OF: COOLANT SAKPLE ANALYSIS 18 AUGUST 1987
'l i il 9 3E A DR]Li.
D:.i NUl talw a c i I cu i < ..'._. . ....niecting n or a.a i p .i o n t operat3ons . . . , _ . . .. . . . _ _ . _ _ . NU'i. L J LE. A '; J W T i W.:)/CE, C OdhEN ( E l 1 nE,n 1. < i; 7.I ,:.. hE id T UR COULANT SANM l~ Ki,: s
, . 1 y i. <, .
i I. < l I ')". f ., e t. u l ' - !sh s-) ] t f-
, 2 < s. 3 at.1 e
} T .- . . ' S!- . . F. er! . 1u:10 hourn (f + V: 50 -
<r an, e an.p,) e i ed , , ;i ;,i- prio-d i * , , i , ? r_ , , ,
to 10:10 hours .T 4 0 : F;W h,m Xl 1 4. M 71i . .
- 1. .
1-3' , , e c.' ' i.- t A55UMPTIDNB:
. s i- i.. - UtihE , - t.i7i i 1,G L ] bR ] Uli CDf T 3 -): .c 1- .,c . E. . > -5 DUiG S RE' .Us.LEl. TO CDDt. ANT 1 -- 1. . i ., i F;tfl i F lh , t t ( .! ' gar f i
1H3S 15 A DRIL'L . _ . _ _ _ _ . O
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<y p POSTACCIDENT S4MPLES i ME.5 GAGE NO.H2O - 6 TO: CHEMISTRY TECHNICIAN FROM: TEAM EXERCIEE CONTROLLER /DSC CONTROLLER LOCAT 1014: CHEM LAD /OSC TIME: AS REDUESTED WITHIN APPLICABLE TIME FRAME (GCE COMMENTS SECTION BELOW)
FERME)' B7 REfLTOR COOLANT SAMPLE ANALYSIS 18 AUGUST 1987 I 1HIS 15 A DR)LL DO NOi t el e ac t i on ri. e4focting normal p1 ant oper ati ons . _ . . . . _ _ . . .
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NUC i . I DF. AC'T l 'd i Ti ( UC 'l / CC ) COMMENT 5 ret 4rTOR CGOL AN1 S AMf 'L E ! LR- 8!.h 1. 01 al Ot. ! I:n -Gt; 1. I P.9 L-O . l.h. h 7 . : 1 (A -OF. F mu.itt thei1 t+ evni 1 etd o. .
~
J 'h . '6m 2. 7 0M -Ori wt j 0 : :;'O hourn M + ): O) AF? 17 . t . .l e ~ i - O". 4 c.r an ,- nample taken at r .- praor X E - 1 '.: 4. 4 ? 1 E -0:: to 10: 20 hours (T + 1: O)
- 1. I ".1 . . a c' j E .; %
1 - .1 ' ~ .i . T,2.l tOO A55UMPTIONS: 2 . - 1 ' -- ; . rge ,;: ,,c -NUR E b--07 c,0 EDUILIER1 Ll!1 CDi't 1-174 ' . 6T4 E +00
/ -50di:CE'S RE L EASED ~i O COOL ANl 1 - 1:7. ' . /. t oH : 0.. F ROM F UE.i. CLM G,f,i' 1
I i i i a I TH]5 IS A DRILL. 80A'."'O?M_'_..D.$. Q W , See gggg, ggg g4 ggg_u- .._8 *.i.- *."M_, e & 9b.y ge .O*e p.g Aggs a A y. g .pg.g.. W..h.WPa.D.'_D__M___..:."8. I j
i r PDE.i ACCIDElfi SAMFLES ! I ME5%GE NO. H2O -- 7 l TO: C HEMI STI:, TELHNICIAN ,., FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEM L AD/OSC TIME: AS REDUESTED WITH]N APPLICABLE TIME FRAME ! I (SEE COMMENTG SFCTION BELOW) FERME3 87 REACTOR COOLAN1 SAMi'LE ANALYSIS 10 AUCaUST 1987 i
. . . _ _ . . . . - . . _ . . . ~ . _ . _ _ . . . _ _ _ . _ . _ . _ _ _ . _ . _ _ . _
h l 1 E, 10 A Dh1LL DD N '.i i t Ed e a: t 11.s c- ic+:tli.g n a r ron '] p1 ant oporatlens NUEL]I,i 4fl i .I 's' i 1 i (th.[. C.
- COMMINT5 6R N ,1 i ' :' . ' . > ?,1. .. n RE: ACTOR CDDL Al J , SAM,'Li iR / 1 , l'.: ii. O, i I. j . 1 i t ,- ?, he :i'i t i s! i r . :1 'l tm e v c a 1 abi 6-I K- E 7. 6 a 3 F O'u trt )'0: ?.O h ot..r n (T + 1:10
' lf J:
, .. .I c . ~ . i . O', (c c cris e eunr.l t i At t 4! cn pr4
(.,, xt'-1:, - .; . iC[ . M, to 10;70 hours (T . 153.,i J..;, , .4 7 e , . I J- 1. 7 i E + ,. . A9 i.UI ;l- T I ONE -
]- J .r ' 4 ! : -. " - N' fr F D ' ? (. i in i?i il L 1 bf e ) t 4 . 1 i- 3.
1 i -, ',ijL4 o, -Di tuRE E ' RE l. E AE1CD 'i 0 C. U' K W > " l ; '
>', 41 >> F FM i F UE i LI Ar, E. AT-I THIS 19 A DRILL ri O
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, L. F'DBT ACC I DF.NT SAMRLEE
() s.- ME55 AGE NO.H2O -- G 10: CHEM 151In' T ECHNIC1 AN . FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCAT10N: CHEli L A1;/OGC TIME: AS REDUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) FERMEK L'7 hEACTOR EDDLANT SAMPLE ANALYSIS 18 AUGUST 1987 T i ; .! i ];. A Dill i i. DO NUT tMe a c t i co- ~ f f i;+ t a rm rior ne l p1 ant op rer ,a t 2 or m N E L1 bl. A .~ l j ' ' i ' t ( .X ! / a. 4 COMMUNTL 1 F - EGh 4 . c . ai c i d 'n REAE1DL E D ui. A N T SAhF ..L
) h -U. J .1 b & -i. .
Netuite s.l ie li t.+
}- h - i 1. ;4i .H- n s e. 3 ] i4' J +
s .l f E - 05 at 10 : 4 .' hours (T + .1 : <.) l Ta-GE
- i. E - J T '.. 2 Eu O. tcr m, t.anp)o t c.. F t..r i i, (q prsue
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(_/ XF 1: '. -; ~~. m '?, tc 10:40 h o u '~ s t' l + 1 : 2 '.> ) 1 1 ~.T.; .,.,9- .i , u 1 - l '.. . 1, a.. & 4 . - ALGUMs: T I GN5. 1-3~ ..ii > NUR:.E /G e :. E D .)T L i bi i U!) C DF.F 1-l'- . . .J: E , c.' . -10UT CC' REL EnF ED i D CDiiL A!;T
- r. ,i ., F pr.n F t ;E L Ct p,b bi-6 1 i c i
l THIS 15 A DRILL O }
f 'DLl ACL ll.iElll SAMPLES MED54E NO.lCO - 1 [J~D !l 1U. CHEMI51hi '1 E Ll IN I C I AN l FROM: T L 411 E).ERCI SL CONTROLLER /OSC CONTROLLER J l l
+
LOCATION: CHEM L AEUOSC T I ME- : AS REDLIESTED WITHIN APFLICABLE TIME FRAME l (GEE:. CONMENTS SCC T ION BCLOW) l l REAL10k LOOLANT LAMPLE ANAL.YSIS 1G AUGUST 1987 FERMD: 87
~( H 1 1 10 A DRILL DO IDT t n ,1 ac t i cv 1 h 6! s e .:t i n cJ n or mc.1 pl arit op e r at i on .,
Nur t.1 DL ,~d. ! I ' ' j i y (UC1/CL> COMMENTis I
)
- 1. R - t t';.11 ./it.t .-4 , o . i hi;;-d;1 DR CDUL AN1 E.AMI LL {
l t i- ut .ei s '. ! t t. t a . .'; . v: O.> Resolth tha)] tw ana ' s.J o - is t 1O:'jU hDur9 (l 4 O: .I ' - f l - L' L. ...'[i 4(rr ist i y C. is qip 'I L i s f t !i i: ! e i il 2 ; et* ,/N AL- 1 .i . ' ';C . f b. . (,/ 4 x ib j ?.'. 3 , c.E 5 6 ( c. id): D. hourt (1 4 0: l.3 - 3 ., ( c a .a . . II
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I l PulfACCIDEN1 SAMPLES ME55/,GE NO.H2O - :- TO: CHEMIGTio' TECHNICIAN ,. FROM: TEAM EXLRCISE CONTROLLER /OSC CONTROLLER LOCATION; CHEM LAD /OSC T l MF_ : AS REDUESTED WIT HIN APF LICABLE TIME FRAME (SEE COMMENT 5 SECTION BELOW) FERMEX 07 RL/:CTOR COOLf4NT SAMPLE ANALYSIS 18 AUGUST 1987 ,
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{ lHib JL A DRlLL DO NUT \ e l r. i.: t.; c:i - a f f e r. t i n :.3 n or ait.1 p1 ant opei at i org I nJ?.L i L';. M.1 I ' ' ) i i ( Ui. [ H ) C O N N E Al '.
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i l r i l I POL 1AECIDE.NT SAMi LE , q f MEEBAGE NO.H2'< - 3 . i TO: CHEMISTRY TECHIJICT Af . FROM: TEAM EXERC]5E CONTROLLER /05C CONTROLLER LOCATION: C6EH LAL/05C 1 llME: AS REDUESTED WITHIN APPLICABLE TIME FRAME I (SCE COMMENTG SECTION BELOW) FERME). 87 RLACTOR COOLANT SAMPLE ANALYSIS 18 AUGUST 1987 I TH]b IS A DR 1 L L. LU IKi t ai+ e..c t a e n = nfieutanu noia.u: p] ant
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POS1 ACCIDENT SAMPLES { (m) s.- MESSAGE NO.H2O - 4 ) TO: ChE1115TRY TCCHNICIAN *.,, FRDN: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEH LAD /OSC TIME: AS REQUESTED WITH1N APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) FERMEX 87 REAClDR COOLANT SAMPLE ANALYSIS 18 AUE,UST 198'i THIS IS A DRILL DU hiD T t. a l e actiont eifecting n or nia l plant op t:.r a t i on s NUCL1DE ATT1Vili (UC1/CC) C D11 MENT 5 I:R- inh . 974 E.t O. ) . REACTUF: COOLANT DihFLE I. T. ~F . . . o l y f. 0; 6s F- ~ tl O?i O., hr:r ii) i r 5. ri c. ] 1 be se 1 a!.. ] c.- . l . I. O. 7 . c,t. :! E -W. ".i et i1:20 hottre (T + 0:40) X i. 1. s
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- - . - . . . - - . . . . . . . - - . . . . . . - - . . . - . - - . . . - - . . . . ~ . - - - . - . . - .
NUCLIDE ACTIVITT (UCI/CCe COMMENTS I LP --f 2M 2. LC'/d 4 00 REACTOR COOLAN'l SAMPLE I R 55 ~~ . 6- 10E - 01 1, f . - 8 ' 3.106EiOs RPEd}tE E.h al .I (M.* MVei}hh3O - lR-GO 7 . E l?T.+ 0 0 at 1i:30 hourz. (T + Cu 50,
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- 1:10) 3-171 6. c;n l i;d o, I - 1 ~1 ? ~ . 7 0sE 4.'0 ASSUMPTIONS:
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POSTAC.CIDENT SAMPLES ( ' MESSAGE NO.H2O - 8 TO: CHEMISTRY TEEHNICIAN 4 FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEM LAB /OSC TIME: AS REQUESTED WITHIN APPLICABLE TIME FRAME (SEE COMMENTS SECTION BELOW) FERMEX 67 REACTOR COOLAN~l S/4MPLE ANALYSIS 18 AUGUST 1907
._.. _._.__ ...._ ______ . ______ _. ~_ __ _ _
THlO IS A DRILL DO NOT t. e h+ at t i ont isf+etting norat1 p1 ant op er a t.1 on s NJCLIDE ACTIdiTi (ULi/CC) COMMENTE LF DUi . . o!K E l u ) i<E ACT OR CDOLAN'1 SAMPLE lir~ l ." . . o 3 O E .. t ILR. D' . . N.e 4E 4 0.i Ret.U] ' t ! Ehn)1 be evni1eb)r. *
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( t ;EiiEAGE NO. iCO -10 i l l 1 To: catMicirn' TECHN]Ci AN 4 ,, t l i FROM: 'lEAM EXERCISE CONTROLLER /OSC CONTROLLER i LOCATION: CHEM LAD /05C TIME: AS REDUF5 iED WITHIN APPL ICABLE TIMF FRAME (EEE CDMMENTS GECTION DELOW) FERMEX 87 RE AC'7 0E COOL ANT SAMPLE ANALYSIS 10 AUGUST 19Fa7
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PDB1 ACCIDENT sat 1PL ES (, MC5GAGC NO.H2O -13 . t j TO: CHCHISTRY TECHNICIAN <., j 1 i FROM: TEAM EXERCISE CONTROLLER /OSC CONTROLLER LOCATION: CHEN LAB /05C TIME: AS REQUESTED WITHIN APPLICABLE TIME FRAME , l (SEE COMMENTS GECTION BELOW) FERMEX 67 REAClDR COOLAN7 SAMPLE ANALYSIS 18 AUGUST 19G7 I _ _ _ _ . . . . _ _ _ . _ _ _ . . _ . . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ 1 THIS IG A DRILL DO ND1 l 4 1. e actiom u i .att ) na normal p1 ant operatiors NUC L 11;L AClTV1Ty i UE .i / CE i COMiiENTE. I LR-b5h . W4l..vu fiEACl uii COUL Alif DMiitE t '.R - G S T . e . Ol" -i 1 6.R-07 3 L.GOF.,4 d R e c u ) t s. e im j ? L. rr 6: s s.i 1 E. i .1 o I:R -Ob , J. r. f. $ i.J., et i;.:50 htur.s i' 4 ,:16 .
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