ML20236N868
| ML20236N868 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 08/05/1987 |
| From: | PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML20236N852 | List: |
| References | |
| PROC-870805, NUDOCS 8708120138 | |
| Download: ML20236N868 (405) | |
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1 EXERCISE MANUAL FORT ST. VRAIN NUCLEAR GENERATING STATION NRC/ FEMA GRADED EXERCISE AUGUST 5, 1987 PUBLIC SERVICE COMPANY OF COLORADO l 3 w) 8708120133 G70622 PDR ADOCK 05000P 7 F J
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'FOSAVEX 87 GRADED EXERCISE MANUAL
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TABLE OF CONTENTS. SECTION PAGE 1 i 1.0 Schedule of Events. .1.0-1 2.0 Scope and Objectives 2.0-1 2.1 Scope 2.1-1 < 2.2 .0bjectives 2.2-1 3.0 Guidelines and Instructions 3.0-1 3.1 Guidelines- 3.1-1 3.2 Player Instructions 3.2-1 4.0 Controller / Observer Information 4.0-1 4.1 Precautions and Limitations 4.1-1 4.2 Assignments 4.2-1 4.3 Instructions 4.3-1 4.4 Emergency Response Facilities 4.4-1 4.5 Evaluation Sheets 4.5-1 5.0 Scenario 5.0-1 5.1 Narrative Summary 5.1-1 5.2 Initial Conditions 5.2-1 5.3 Detailed Scenario 5.3-1 5.4 Scenario Time Line 5.4-1 6.0 Scenario Data Package 6.0-1 o Plant Messages o Offsite Messages o Plant Parameters 1 O
J {' ' TABLEOF' CONTENTS (Cont.) [: SECTION PAGE' ,
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-7.0.' Onsite Radiological Data 7.0-1 I
-7.1 Plant Monitoring Data 7.1-1 7.2 Radiation / Chemistry Data 7 2-1 7.3 Plant Area Radiation Levels 7.3-1 8.0' Offsite Radiological Data
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8.0-1 - 8.1 Meteorological Data 8.1-1 8.2 Release Rate / Dose Assessment 8.2-1 8.3 Field Monitoring Data 8.3-1 8.4 Maps 8.4-1 9.0 References 9.0-1 9.1 Procedure Index 9.1-1 9.2 Key Documents- 9.2-1 :l O ii
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10 V 1.0-1 SECTION 1.0 SCHEDULE OF EVENTS Figure 1-1 provides the schedule for the 1987 Fort St. Vrain NRC/ FEMA Graded Exercise (FOSAVEX 87) which will be conducted on August 5, 1987. At the Controller /0bserver briefing scheduled for August 4, 1987, the specific details of the scenario will be presented. It will also provide a forum for discussing any problems encountered during the June 24, 1987 Dress Rehearsal. Additionally, key milestones will be identified and corresponding Controller / Observer actions will be discussed. Final Observer assignments will be made and any questions relating to the scenario, or the responsibilities of the Controller /0bservers, will be answered. The Controller / Observer debriefing will occur immediately after the exercise is terminated by PSCC/NRC/ FEMA. Each Controller / Observer A will be expected to provide a brief synopsis of his/her findings () (both positive and negative). The Lead Controller / Observer will summarize these findings and will serve as Lead Exercise Spokesperson at the PSCC/NRC Critique.
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O 2.0-1 i SECTION 2.0 SCOPE AND OBJECTIVES SECTION PAGE. 2.0 Scope and Objectives g,g_3 2.1 Scope _ 2.2 Objectives g,g_3 O I l l i f O
{ L.) 2.1-1 SECTION 2.1 ; SCOPE OF FOSAVEX 87 The 1987 Fort St. Vrrin NRC/ FEMA Graded Exercise, known as F0SAVEX 87, will be held on August 5, 1987. FOSAVEX 87 is intended to provide a mechanism by which Public Service Company of Colorado (PSCC), the State of Colorado, and Weld County can test their respective Radiological Emergency Response Plans (RERP's). FOSAVEX 87 will also provide the means by which all three entities can coordinate activities and test their ability to " protect" the health and safety of the general public. As more fully described in Section 5.0, the scenario depicts a series , of simulated events which will necessitate a number of specific response actions to be taken by PSCC. These response actions are well defined in the Fort St. Vrain Radiological Emergency Response Plan and Implementing Precedures, and are intended to safeguard the general public, plant personnel, as well as utility property. The scenario has been plannec such that major elements of the FSV Plan
>a .j and Procedures are tested. It has also been structured to allow the )
State and County to practice their response activities at the State l EOC (50EC). It will also allow the State / Local Agencies to practice Ingestion Pathway response activities. Since, by necessity, certain elements of FOSAVEX 87 are simulated, whenever practicable, the exercise will incorporate provisions for
" free play" on the part of the participants. The only restrictions on this concept will be if Player actions would prematurely terminate the Exercise, or would restrict the scenario in such a manner that it would not provide an opportunity for PSCC, or the State / Local Agencies to meet their objectives (see Section 2.2).
As previously stated, certain elements of FOSAVEX 87 are simulated. Table 2-1 depicts which activities are simulated and which ones are to actually occur. Activities associated with F0SAVEX 87 will be observed by qualified observers from PSCC. Section 4.0 provides information on how and to what criteria the exercise is to be graded. A critique will be conducted after the exercise. Any deficiencies will be noted, and will form the basis for establishing corrective actions.
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2.1-2 TABLE 2.1 ' SCOPE OF FOSAVEX 87. ACTUAL VS. SIMULATED EVENTS EVENT ACTUAL SIMULATION
- 1. ACCIDENT ASSESSMENT Ability to properly recognize .
X and characterize simulated events. Perform dose calculations- X~ using simulated meteorological and release rate data. Perform field monitoring - X establish radiation levels
.onsite and offsite.
- Establish extent of core X l i
damage. Perform equipment repair. X
- 2. ACTIVATION OF EMERGENCY FACILITIES Activate and staff all primary X Emergency Response Facilities (ERF's).
Establish functional adequacy X of ERF's. Use appropriate equipment X and suppltes to respond to emergency. l O
2.1-3 TABLE 2.1 (Cont.) EVENT- ACTUAL SIMULATION
- 3. NOTIFICATION AND COMMUNICATION Notify Plant, Corporate, X Federal, State and Local emergency response personnel. !
Conduct follow-up notifications - X verify. communications. Communicate with onsite X and offsite response teams. Support " rumor control" X activities. Conduct press conferences. X Notification of general X public via sirens and Tone Alert Radios. fN V. Direct notification of persons living on X PSCC property. 1
- 4. ORGANIZATION CONTROL Augment the on-shift X emergency organization. j Activate the PSCC emergency X response organization.
Coordination with State / Local X response organizations. Coordination with Federal X , response organizations. (NRC only) l Provide management control X - of the emergency.
- 5. HEALTH PHYSICS / SECURITY Receive and analyze field X monitoring data.
Estimate total population X exposure.
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2.1-4 TABLEE.1(Cont.)
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EVENT- ACTUAL SIMULATION Provide adequate radiation X protection services (dosimetry, monitoring, habitability,etc.). . [ Conduct a search and X rescue operation. Site evacuation of X : non-essential personnel. Use of protective clothing. X Simulate use ; outside owner controlled area. ) Provide first aid for X Note: Transportation l an injured and contaminated to hospital will individual, be simulated. l l Decontaminate personnel X i and equipment. l O. i Conduct initial accountability. X Maintain onsite accountability. X Maintain plant Security X . under emergency conditions. l
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- 6. PROTECTIVE ACTIONS Assess and recommend X j protective actions. !
Warn / advise onsite personnel X about emergency situation.
- 7. RECOVERY ;
Coordinate recovery operations X ! with outside (State / Local) ! support groups. 1 1 O I
2.2-1 SECTION 2.2 l O OBJECTIVES OF L O FOSAVEX 87 The objectives of.the Fort St. Vrain (FSV) 1987 Emergency Preparedness Exercise Program are based on Nuclear Regulatory Commission (NRC) requirements set forth in 10CFR50.47, Appendix E. Additional guidance provided in NUREG's 0654 (Rev.1), 0696, and 0737 (Supplement 1) as well as previous FSV exercise results were used in developing the objectives. The exercise will include the activation of the PSCC Emergency Response Facilities. It will also include full participation by State and Local support groups. The FSV Early Warning Alert (EWA) System within the five mile planning zone will be activated in association with FOSAVEX 87. The exact time of the EWA System activation will be coordinated with FEMA, Region VIII Rehearsal. The overall objective of F0SAVEX 87 is to evaluate the effectiveness and capabilities of the FSV Emergency Preparedness Program. The scenario is. structured to provide a mechanism which will accurately test the adequacy of both the onsite and offsite elements of the Emergency Preparedness Program. A primary objective of FOSAVEX 87 is to demonstrate the ability of O the Observers / Controllers to conduct an exercise, and evaluate the response of the FSV Emergency Response Organization. At the conclusion of the exercise, a critique will be held.to evaluate the various activities of FOSAVEX 87, accordingly, another objective of this process is to demonstrate the ability to conduct an effective self evaluation of the exercise. Another major objective of FOSAVEX 87 is to establish the effectiveness of the new RERP Implementing Procedures. Approximately 12 new procedures have been developed using a new format (ie checklists). Any procedural deficiencies discovered will be noted, and corrected in future rey'isions to the plan and procedures. O
2.2-2 The specific FOSAVEX 87 objectives are listed below. rs '
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ACCIDENT AS_SESSMENT
- 1. Demonstrate profichncy in recognizing and classifying emergency conditions according to pre-established emergency action levels.
- 2. Demonstrate the ability to perform dose calculations using radiological and meteorological information to establish the impact to the environment.
- 3. Demonstrate the effectiveness of the radiological monitoring teams (onsite and offsite) to establish radiation levels and to effectively, track the plume.
4.Demonstrateabilitytocoordinateactivitieswithstatefield teams. ACTIVATION OF EMERGENCY FACILITIES 1"^\ t
- 1. Demonstrate the ability of station and corparate personnel to activate and staff the emercancy responso facilities within 90 minutes of a declaration of an ALERT.
- 2. Demonstrate the transition of responsibilities between emergency facilities as a result of escalating accident classifications.
- 3. Demonstrate the functional capabilities of equipment (including status boards, radiation monitoring equipment, etc.) in the Technical Support Center, Forsard Command Post and the Executive Command Post.
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- 4. Demonstrate the ability of the onsite response organization '
to properly select the correct location for the Personnel Control Center (Training Center vs. Nuclear Licensing - Operations Complex). l O
2.2-3
' NOTIFICATION AND COMMUNICATION
- 1. Demonstrate the effective' notification of Plant, Corporate, Federal, State and Local emergency response personnel.
- 2. Demonstrate that- initial notification,s (and follow-up) are verified and logged.
- 3. Demonstrate the effectiveness and reliability of the emergency communications equipment.
- 4. Demonstrate the ability to communicate with in plant monitoring teams, search and rescue parties, and other station pr.rsonnel as needed.
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- 5. Demonstrate the ability to ' communicate with the offsite radiological monitoring teams.
- 6. Demonstrate the capability to obtain, coordinate and assemble emergency ~information for timely dissemination to the public via the media. ;
- 7. Demonstrate the ability of PSCC to respond directly to simulated input from the public concerning "real" vs.
" rumored" events.-
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2.2-4 ORGANIZATIONAL CONTROL
- 1. Demonstrate the capability to technically evaluate the accident conditions and implement appropriate response procedures.
- 2. Demonstrate the ability of the Control Room Director, TSC Director, PCC Director, Corporate Emergency Director and the Director-Executive Command Post to manage the emergency organization ircaccordance with the FSV Emergency Plan and Implementing Procedures.
- 3. Demonstrate the abilities of the FSV response organizations to coordinate decision making actions with NRC/ State / Local representatives in the TSC, FCP and SEOC.
- 4. Demonstrate the ability to coordinate activities with NRC/ State / Local agencies in de-escalating and terminating the emergency.
- 5. Demonstrate the ability of FSV supervisory personnel to properly brief Search and Rescue, Fire Brigade, Repair Team and other response personnel of the emergency situation.
- 6. Demonstrate the ability to coordinate ingestion pathway response activities with offsite agencies.
(m 7. Demonstrate the ability to coordirate activities with FSV outside support groups in responding to the emergency.
- 8. Demonstrate the ability of the PSCC response organization to follow established procedures.
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f L 2.2-5 HEALTH PHYSICS / SECURITY 1.. Demonstrate the ability to perform site assembly, maintain accountability and evacuate.the site, as appropriate.
- 2. Demonstrate the ability to provide adequate radiation protection services such as dosimetry, personnel monitoring, and habitability determinations.
- 3. Demonstrate the ability to perform area surveys under emergency conditions.
- 4. Demonstrate the ability to monitor and control emergency worker exposure _ (i..e. repair teams) within the plant.
- 5. Demonstrate the ability to enter a contaminated area for the purpose of rescuing casualties.
- 6. Demonstrate the ability to provide on-site first aid for an injured individual'who has been contaminated. (Note:
Transportation to the off-site medical facility will be conducted at a later date.)
- 7. Demonstrate the capability of offsite radiological monitoring g . teams-to collect samples.
- 8. Demonstrate the ability to maintain plant security under
- O. . emergency conditions.
- 9. Demonstrate the ability to conduct timely dose projections in accordance with established RERP Procedures.
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2.2-6 l PROTECTIVE ACTIONS , 1. I r (
- 1. Demonstrate knowledge of the Protective Action Guides (PAG's).
- 2. Demonstrate the ability to make protective action recommendations to offsite authorities.
- 3. Demonstrate ability to recognize that appropriate protective actions have been implemented by the offsite agencies.
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2.2-7 The State and Local agencies have established the following
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objectives for F0SAVEX 87: I ! fV) Primary Objective: To evaluate the effectiveness of the Colorado l Radiological Emergency Response Plan and to determine if each level l of the Radiological Emergency Response organization can effectively carry out it's responsibilities. Summary Objectives:
- 1. Notification procedures and public warning dissemination systems, including activation of the NOAA Weather Radio Network, the Platteville Siren and transmission of exercise warning messages to the Emergency Broadcast System. The exact time for siren activation will be coordinated with FEMA.
- 2. Deployment of response elements and their direction and control, including activation of the Forward Command Post and establishment of a secure area and traffic access control.
- 3. Radiological monitoring, assessment, and reporting by field-deployed State Health Department radiological monitoring teams, through the FCP to the State Emergency Operations Center.
- 4. Operational communications and associated direction and control procedures at all levels-
- 5. Food and agriculture control procedures; and
- 6. Dissemination of official information to the news media (if present for FOSAVEX 87 activities) and to the general public.
Specific Objectives:
- 1. Demonstrate the ability to mobilize staff and activate facilities promptly.
- 2. Demonstrate the ability to make decisions and to coordinate emergency activities.
- 3. Demonstrate the ability to communicate with all appropriate locations, organizations and field personnel.
- 4. Demonstrate the ability to mobilize and deploy field monitoring teams in a timely fashion.
- 5. Demonstrate the appropriate equipment and procedures for determining re% tion levels.
- 6. Demonstrate appropriate equipment and procedures for measurement of airborne radiciodine concentrations.
- 7. Demonstrate appropriate equipment and procedures for collection and transport of samples of soil. vegetation, water, and milk.
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- 8. -Demonstrate the ability to process various samples through lab resources other than within the State Health Department.
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- 9. Demonstrate the ability to project dosages to the public via ingestion pathway exposure and to determine appropriate protective. measures. '
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- 10. Demonstrate the ability to implement protective actions for ingestion pathway hazards.
- 11. Demonstrate the ability to alert the public within the effected EPZ.
.12. Demonstrate the ability to formulate and distribute appropriate
-instructions to the public.
- 13. Demonstrate the ability to brief the media in a clear, accurate and timely manner (if the media is present for FOSAVEX 87 activities).
- 14. Demonstrate the ability to provide advance coordination of information released to the media.
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- 15. Demonstrate the ability to establish and operate rumor control k in a coordinated fashion. ;
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- 16. Demonstrate the ability to identify the need for, request and !
obtain Federal assistance. !
- 17. Demonstrate the ability to estimate total' population exposure to ;
radiation releases. ! 9
- 18. Determine if the areas shown below and identified as "needing improvement" in the FOSAVEX-85 Exercise Report, August 26, 1985, have been improved:
- a. Access control into the Colorado Emergency Operations Center. i
- b. Plume tract plotting in the State E0C.
- c. Improved frequency by Colorado Department of Health and PSC representatives to the State E0C of field conditions and dose i assessment briefings. ;
- d. Adequacy of telephones within the FCP. I l
- e. Access control between the Fort Lupton PSC business office l and the FCP Staff area.
- f. Updated access rosters for use at the FCP.
- g. Improved physical layout for staff operations within the FCP.
- h. Improved equipment issue procedures for field monitoring
-O teams.
2.2-9
- 1. Improved field monitoring team deployment briefings.
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- j. Improved procedures and capability for radio communications by field monitoring teams.
- k. Formalized procedures for environmental and air sampling equipment operations.
- 1. Formalized procedures for field monitoring team equipment issue and operation,
- m. Field monitoring equipment has current calibration.
- n. Physical identification of field monitors and vehicles.
- o. Plans for increasing communications support to the media center,
- p. Improved procedures for transmitting hard copies of news releases or proposals between the FCP and the State E0C.
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3.0-1 SECTION 3.0 EXERCISE GUIDELINES AND INSTRUCTIONS SECTION PAGE 3.1 Guidelines 3.1-1 3.2 Player Instructions 3.2-1 O O
1 3.1-1 I SECTION 3.1 GUIDELINES FOR. CONDUCTING FOSAVEX 87 -) _[] A .. J This section of the manual is intended to provide guidance for conducting F0SAVEX 87. All Players will have had an opportunity to review this material-prior to the exercise. D 1 Simulati,ng Activities ) 4 Since drill exercises are intended to demonstrate actual emergency response capabilities, the participants of the 1987 Dress Rehearsal should act as they would during a real energency situation. However, since exercise Players are " graded," it is important that a certain level of " acting" be done. This is especially important in areas that would normally be accomplished quickly without much notice because the events are simulated (e.g., checking monitoring equipment, conducting habitability surveys, etc.). In these types of situations the participant should inform the Controller /0bserver chat a " habitability survey" has just been completed and that, for example, the TSC Director was informed of the " findings." Since this is an opportunity to test the response organization, wherever possible, actions should be carried out to the fullest extent practicable. Only when it is not feasible to perform an action should it be simulated. Any orders given, that for any reason '0 cannot or should not actually be performed, should be prefaced with the word " Simulate." For example, you would simulate, carrying a co_ntaminated, injured individual up a flight of stairs to the ambulance. Where.such actions arc being simulated, it is suggested that participants inform any Controller (s)/ Observer (s) in the area what specific actions would have been taken had the emergency been real. In the example cited above, specific radiological / medical precautions that would be taken.should be discussed with the Controller / Observer. Radiation Work Permits (RWP's) will not be issued for FOSAVEX 87. If scenario events direct Players to areas that are actually RWP controlled, Players will simulate activities that would have occurred inside the area. Under no circumstances should anyone enter an RWP controlled area even if they are authorized to do so. Public Protection , Intentionally violating the law is unacceptable during any exercise. Participants should not ignore posted traffic laws (e.g., speed limits, stop signs, etc.). Additionally, offsite field monitoring teams should pay particular attention to public/ private lands (e.g., farming operations, livestock, etc.).
3.1-2 Since the actions of Federal, State, Local and Utility organizations receive continuous public scrutiny, it is possible that the
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-activities associated with F0SAVEX 87 could be misrepresented.
Therefore, it is imperative that all communications that can be monitored by members of the general public (radios, loudspeakers, etc.) be prefaced a This is a drill." g concluded with the words, "This is a drill; Maintaining Emergency Readiness During F0SAVEX 87 the ability to recognize a real emergency, terminate the exercise, and respond to the new situation must be maintained. Therefore, the exercise scenario and actions of participants will not include any actions which seriously degrade the condition of systems, equipment or supplies, or affect the detection, assessment, or response capability to radiological or other emergencies. Actions taken by the participants will also avoid actually reducing plant'or public safety. The potential for creating real radiological i or other emergencies will be specifically avoided. If a real emergency occurs during the exercise, requiring the actions l of' plant and corporate personnel, the exercise will be terminated. All messages about real events will be clearly identified as such. For example, precede a real message with: "This is NOT, repeat, NOT an exercise message." l I l i
3.2-1 SECTION 3.2 PLAYER INSTRUCTIONS Since the primary purpose for conducting the annual emergency exercise is to enhance the effectiveness of the FSV Emergency
. Preparedness Program, it is important that the program receives feedback from both Players and Observers. As previously stated, it is important that the scenario events be treated as "real" situations .
requiring immediate actions and. responses. As part of this response, l certain procedures, equipment, and facilities may prove.to be- 1 inefficient or totally. inadequate. To improve the program, Players are requested to review the attached questionnaire before-the Dress Rehearsal. At the conclusion of the exercise, you should complete the form and forward it to a PSCC Controller / Observer or 0. J. Clayton.at FSV. The Lead Controller /0bservers have' additional forms if needed. O O
r? 3.2 ! O PARTICIPANT-QUESTIONNAIRE In order to identify areas requiring improvement within the FSV Radiological Emergency Response Plan, you are. requested to answer the following questions. Please be candid, constructive criticism is appreciated.. Please make comments, identifying any deficiencies you feel' exist. Upon completion, please. return to a PSCC Controller / Observer or return via Company mail to 0. J. Clayton, Technical Services Department, Fort St. Vrain. . Thank you for your assistance.
- 1. Name (optional)
Emergency Response Center
'2. Approximate time you received initial notification:
- 3. Approximate time.of your arrival at your emergency response
' center:
- 4. 'Please briefly describe your functions / responsibilities:
- 5. Do you feel as though you have been adequately ti ained to fulfill your duties? ._
- 6. What RERP Implementing Procedures, if any, did you utilize or reference?
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- 7. Were the procedures easy to locate?
- 8. Did the procedures adequately describe your functions and/or responsibilities?
- 9. Did you utilize checklists provided in the procedures?
If so, were the checklists:
- a. Compatible with the procedure?
- b. Able to be used without referring back to the procedure?
- c. Complete, (i.e., did they contain all appropriate steps)? __
If not, would a checklist have been helpful to you in complete i your assigned duties?
- 10. Was the equipment and/or material available at your response center adequate? If not, please list any items that I
would have been helpful to you:
- 11. Were the communications systems used (i.e., radio, telephone, etc.) at your facility adequate?
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- 12. Were internal communications (i.e., messages, status boards, etc.) handled effectively?
- 13. Were you aware of events as they occurred? ,
- 14. Comments: Please use this space to comment on any aspect of the exercise. Again, constructive criticism is appreciated.
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4.0-1 SECTION 4.0 CONTROLLER /0BSERVER INFORMATION E SECTION PAGE 4.1 Precautions and Limitations 4.1-1 4.2 Observer Assignments 4.2-1 4.3 Instructions 4.3-1 4.4 Emergency Response Facilities 4.4-1 4.5 Evaluation Sheets 4.5-1 4.5.1 Summary Sheets 4.5.2 Detailed Evaluations Sheets Control Room Technical Support Center Personnel Control Center Forward Command Post Executive Command Post State EOC Onsite Monitoring Team Offsite Monitoring Team i Corrective Action (Repair) Team l First Aid / Search Rescue - FSV Fire Brigade O
4.1-1 SECTION 4.1 PRECAUTIONS AND LIMITATIONS Introduction Public Service Company of Colorado representatives will serve as Controllers / Observers for FOSAVEX 87. Each Controller / Observer has a complete Exercise Manual and at a minimum should be familiar with the following:
- 1. The basic Objectives of the exercise (Section 2.2).
- 2. The Guidelines and Instructions provided to the Players (Section 3.0).
- 3. The exercise scenario, including the initiating events (Section 5.1 and 5.2).
- 4. The various onsite and offsite locations that will be utilized by the Players when responding to the scenario events (Sections 4.4, 7.3, and 8.4).
- 5. The exercise evaluation form (Section 4.5).
Precautions and Limitations In addition to reviewing the five areas described above, all Controllers /0bservers must be aware of the following:
- 1. Should, at any time during the course of the conduct of this exercise, an actual emergency situation arise, all activities and communications related to the exercise will be suspended.
It will be the responsibility of any exercise Controller / Observer that becomes aware of an actual emergency to suspend exercise response in his/her immediate area and to inform the Head Exercise Controller of the situation. Upon notification of any actual emergency, the Head Exercise Controller may notify all othee Controllers / Observers to suspend all exercise activities. The Head Exercisc Cant. roller together with the TSC Director and Ccrpurate Emergency Director will make a determination at that point whether to continue, suspend, or terminate the exercise. O
4.1-2
- 2. Should, at any time during the course of the conduct of this exercise, an exercise Controller / Observer witness an exercise
/ ! participant undertake any action which would, in the opinion of
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the Controller /0bserver, place either an individual or plant component in an unsafe condition, the Controller / Observer must attempt to-terminate the unsafe activity immediately. Upon termination of the activity, the Controller / Observer is responsible for contacting the Head Exercise' Controller and informing him of the situation. The Head Exercise Controller,. together with the TSC Director and Corporate Emergency Director, will make a determination at that point whether to continue, place on nold, or terminate the exercise.
- 3. Manipulation of any plant operating systems, valves, breakers, i or controls in response to this exercise are only to be simulated. No alteration of any plant operating equipment, systems, or circuits in response to this exercise should occur.
- 4. All repair activities associated with the exercise will be simulated. Extreme caution should be used when working near operating equipment. ,
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- 5. All telephone communications, radio-transmissions, and public address announcements related to the exercise must begin and end with the statement, "This is a drill." Should a Controller /0bserver witness an exercise participant not observing this practice, it is the Controller / Observer's O responsibility to remind the individual to follow this practice.
- 6. Any motor vehicle responding in this exercise, whether for medical, rescue, fire fighting, field monitoring, etc., should observe all normal traffic laws including posted spesd limits, stop lights / signs, one way streets, etc. Controllers / Observers should ensure that exercise participants follow these requirements.
- 7. Care must be take to prevent any individual not involved with the exercise from believing that an actual emergency exists.
Any exercise Controller / Observer who believes that this situation exists, should approach that individual and explain the nature of the exercise and its intent.
- 8. If a Controller / Observer is aware of any of the above situations, he or she should immediately identify the situation to the Head Exercise Controller.
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4.2-1 SECTION 4.2 [J CONTROLLER /0BSERVER ASSIGNMENTS Provided below are'the Controller / Observer Assignments for FOSAVEX 87. The Head Exercise Controller located between the lunchroom and the Control Room, is responsible for all activities associated with the exercise. Senior Controllers / Observers are responsible for activities within a specific Emergency Response Facility or for a specific response activity (e.g., field monitoring, plant surveys, etc.). Facility / Activity Controllers /0bservers
- 1. Head Exercise Controller (s) Owen J. Clayton John Rodell, S & W
- 2. . Control Room Garson Gilbert, S & W
- 3. Technical Support Center
- 4. Personnel Control Center (Onsite Radiation Monitoring)
(Offsite' Radiation Monitoring) Les Hutchins (Corrective Action - Repair Teams) .f -(Medical Responses) (Fire BrCgade) Chris Stolley
- 5. Forward Command Post Carl Mazzola, S & W
- 6. Executive Command Post Bill Peggram
- 7. State Emergency Operations Center Dave Goss NOTE: Additional Controllers / Observers to be identified later.
i I
4.3 l SECTION 4.3-CONTROLLER /0BSERVER INSTRUCTIONS Public Service Company of Colorado personnel are assigned as Controllers / Observers at all Key onsite and offsite exercise areas to monitor and control FOSAVEX 87. The activities of.the onsite Controllers / Observers will be coordinated by the Head Exercise Controller located'in the Control Room (Ext. 1091) o'r the lunchroom (Ext. 1294). If unable to reach the Control Room, contact the Senior Controller / Observer in the Technical Support Center (TSC) .(Ext.1258). The. activities of'the offsite Controllers / Observers will be coordinated from the Forward Command Post (FCP). Any logistic problems / questions should be directed to the Senior Controller / Observer in the FCP. (857-6001 or 571-7061). Message forms and simulated Control Room data will be used to initiate, modify, and complete the events comprising the overall scenario. Selected Controllers /0bservers will use the message forms to place-the scenario events in effect and to trigger responses from the emergency response-organizations. Each Controller / Observer will have copies of the messages controlling the portion of.the exercise scenario for which he/she is responsible. Two' kinds of messages will be used: Controlling Messages used as a primary means of implementing scenario events by announcing or placing an event in effect by hypothesizing conditions resulting from previous actions. Contingency Messages used at the discretion of the Controllers / Observers with the approval of the Head Exercise Controller in the Control Room in order to maintain scenario continuity or schedule. 4 Contingency messages may have to be developed during the exercise. They should be identified with a number followed by a capital "C". Controlling messages will be presented to the designated exercise participant at the time specified in the event schedule. The Controller / Observer should follow up with an explanation of the message and answer any questions to ensure that the participant understands the message. O
4.3-2 Controllers / Observers will not provide informationJto the participants regarding scenario development or resolution of problem
/' areas. The participants are expected _to obtain information through their own organization and exercise their own judgement in determining response actions and problem resolution. In the event of incomplete responses, or if the participant indicates lack of knowledge of how to proceed, the Controller / Observer will prompt the participant with necessary instructions or contingency message cards and will so note these actions on his/her critique sheets.
l It is important to note tha't the scenario. events are hypothetical. l~ Any portions of the scenario depicting plant system operational l transients are simulated events.. No Control Room actions, or reactions' involving operation of pTa'nt systems or affecting generation capability,'will be initiated. All-exercise scenario messages are prefixed and suffixed with the words "this is a drill." Controllers / Observers stationed at areas vital to maintaining i generating capability should be especially aware and take extra precautions in issuing messages or giving instructions regarding the scenario events. Some exercise participants may insist that certain parts of the scenario are unrealistic. The Controllers /0bservers.have the authority to clarify any questions regarding scenario content.
- However, in some cases, it may be necessary to exercise Controller's prerogative" and say, "This is due to exercise requirements" to preserve the continuity and objectives of the exercise. !
Prior to commencement, all telecommunications to be used by the Observers / Controllers should be tested to ensure satisfactory communications are available to coordinate exercise activities. Additionally, all Controllers / Observers will synchronize their watches to ensure that messages are delivered at the proper time. ! Controllers should report to their assigned location approximately 20 minutes prior to any player action. Since some exercise activities will be conducted offsite, it is important to remember that members of the general public may observe some monitoring activities. Accordingly, to help alleviate any potential concerns, protective clothing will not be used outside the owner controlled area. Table 4-1 provides additional D0's and DON'T's for all Controllers / Observers. 1 l i
4.3-3 TABLE 4-1 CONTROLLER'S/0BSERVER'S RULES L 00's L
- 1. Know the overall Controller / Observer Organization (Section 4.2).
- 2. Remember that there may be two time designations: a scenario time and a clock time.
i
- 3. Identify the players by name and function.
- 4. Identify yourself at all times to all players. Wear T-shirts or tags as provided by PSCC.
- 5. Identify the phone (or radio for field teams) you will use to maintain communications with Lead i Controllers / Observers. '
- 6. Position yourself to maximize your effectiveness in issuing messages and observing the players.
- 7. Be sure you understand the player's scenario script and the master scenario.
- 8. Keep the play on schedule by checking your script.
- 9. Issue the message on time. Make sure the players understand it.
- 10. Remember to call the Senior Controller / Observer or Head Exercise Controller to report the status of players' actions if off schedule or if in doubt about what to do.
Call for advice if players significantly depart from the scenario script. These deviations could cause major delays or could terminate the exercise prematurely. If necessary, intervene with player action and put players back on scenario track.
- 11. Allow the players reasonable flexibility to perform their functions and demonstrate their skill, knowledge, and initiative.
- 12. Identify the federal evaluator (s). Make sure they are reasonably aware of your actions and those of the players. !
- 13. Make notes on good and bad points of players' actions, the strengths and weaknesses, and areas for improvements.
Use the Evaluation Sheets.
/" 14. Attend the post-exercise critique session to provide your comments and recommendations.
i 1
4.3-4
- 15. Identify the players' -leaders. . Work with them as '
appropriate.
- 16. If a real emergency occurs and this affects the players, call'off your portion of the exercise, and notify the Head Exercise Controller immediately.
- 17. Be at your post at least 20 minutes prior to the-beginning of any player actions. Set yourself up.
- 18. The federal evaluators will not issue " surprise" messages or direct " surprise" actions at the players. They must work through the Controller. .This is essential for the success of the exercise, 4
*19. Controllers /0bservers and federal evaluators, do not have-to follow simulated radiation exposure control practices.
- 20. Controllers / Observers will be exempt from accountability and have access to all areas.
DON'T's
- 1. Don't leave your post a key times.
- 2. Don't prompt the players to take action. :
- 3. Don'.t coach the players.
O' 4. . Don't criticize the players' actions during the play. !
'5. Don't forget to call the appropriate Senior 3 Controllers / Observers to seek advice or help as '
necessary. .i
- 6. Don't allow external influences to distract the players.
No interviews with players are allowed. 7, Don't allow simulation with respect to radiation protection practices or when equipment and facilities are available. However, don't allow any player to operate 3 any equipment which would impact plant operations. I Note:
- All participants will comply with the radiation exposure control practices existing at the station at the time of the exercise.
1
,l 4.4-1 g SECTION 4.4 ~~\ EMERGENCY RESPONSE FACILITY DESCRIPTIONS i '(O ' l i
l i The FSV Emergency Organization will function from a number of pre-established locations. This section of the Exercise Manual l identifies the five facilities which will be activated to assess and manage the accident conditions described by the scenario. All Controllers /0bservers should become familiar with their location and response function (s).
- 1. Control Room (CR)
Emergency assessment and control is initially directed from the CR by the Shift Supervisor prior to activation of the Technical Support Center (TSC). The CR, located adjacent to the Reactor Building, is designed to be habitable during Design Basis Accidents. The CR contains full plant instrumentation, technical drawings, protective breathing apparatus, radio, telephone, and intercom systems. Emergency radiological monitoring equipment and protective ! clothing are located nearby.
- 2. . Technical Support Center (TSC)
Site emergency command activities will be centered in the Technical Support Center (TSC) located immediately adjacent to the Reactor Building and within short walking distance to the Control Room. The TSC is equipped with intercoms, telephones, NRC hotline, dedicated Health Physics Network (HPN) telephone, telecopier, and radios for communications with the CR, Personnel Control Center (PCC), and Forward Command Post (FCP). The TSC is equipped with a CDC-1700 terminal for visualization of plant parameters and offsite dose calculations, essential drawings, specifications, and procedures. Radiation monitoring equipment, protective clothing, communications equipment, portable lighting, protective breathing apparatus, and first-aid equipment are located in Emergency Kits. The TSC meets habitability requirements similar to those imposed upon the CR. l
i 4.4-2
- 3. Personnel Control Center (PCC)
-[-'
s . The primary and. secondary locations for the Personnel Control Center (PCC) are the Training Center and the Licensing Trailer, respectively. Emergency radiological monitoring equipment, first-aid and decontamination equipment, protective cl. thing, communications equipment', camera, portable ~1ighting and
, protective breathing apparatus are stored in emergency kits at -
both onsite locations. There are two designated offsite areas which may be utilized as the PCC if is becomes necessary to evacuate the onsite location (s). The preferred alternate offsite location is the Johnstown County Shops. The other
. alternate offsite PCC location is the Platteville Volunteer Fire
. Department. Routes to these locations are shown in RERP Implementing Procedure RERP-PCC, Personnel Control Center Procedure.
- 4. Forward Command Post (FCP)
The Forward Command Post is the focal point for the coordination . of onsite and offsite emergency response activities. Management ! and technical personnel assigned to the FCP are responsible for. , protective action recommendations and liaison with offsite j authorities and response. facilities. The FCP serves as the i point from which the Corporate Emergency Director (CED) exercises overall control of the FSV Emergency Response Organization. 4 The FCP has work space allocated for PSC emergency personnel, state and local personnel, and the NRC. The FCP is adequately equipped with dedicated phone lines, PSC PBX phone lines, commercial phone lines, radio, and telecopy facilities to provide efficient communications with the TSC, ECP, State EOC, NRC, and the Weld County Communication Center. Onsite-offsite communication:; are channelled through the TSC and FCP. , i The FCP is located at the'PSC Customer Service Center in Ft. Lupton, well out of the plume exposure EPZ. The FCP will be activated and manned for an ALERT or more severe incident classification. The FCP is equipped with a CDC-1700 terminal to , provide' rapid access to plant parameters and to provide for l offsite dose calculations. Briefings with the media are to take place at the Ft. Lupton Methodist Church, located in close proximity to the FCP. l U
4.4 5. Executive Command Post (ECP) L .h The Executive Command Post (ECP) is located at the corporate ! ( . headquarters building in downtown Denver. Manned by senior l- corporate personnel with.acces: to other corporate ~ resources, l- the ECP provides direct augmentation to.the staffing of.onsite emergency functions by non-station personnel. The staff of the ECP is responsible for obtaining additional manpower for repair / damage control teams, survey teams, access control, and logistical assistance. The ECP will normally maintain direct i communications ~with the Forward Command Post and the State-Emergency Operations Center. l O
-l O
1 1
1 4.5-1 SECTION 4.5 EVALUATION SHEETS ( ) i This section of the Exercise Manual provides the Observer Evaluation Sheets. Controllers /0bservers should remove the appropriate evaluation sheets and be sure to complete the forms as the events occur. At the conclusion of the exercise, review the evaluation sheets. These documents will be used at the exercise debriefing and the formal PSCC/NRC critique. All of the documents should be given to the Head Exercise Controller at the conclusion of the critique. ( \ V l r\ l
Page 1 FOSAVEX 87.- OBSERVER CHECKLIST
": ,O Location: CONTROL ROOM Name:
Time-Frame: to Date: s CRITERIA EVALUATION l' . ACCIDENT' ASSESSMENT Control Room personnel rapidly and correctly' interpreted the scenario related problem (s). Control Room personnel knew'when to refer to FSV Operating Procedures, the RERP, and RERP-CLASS. Plant process information was available when required. Control Room Operators ! responded to simulated
-operational events and i: properly classified the L accident condition for:
(1) NOUE (2) ALERT (3) SITE AREA l (4) GENERAL Control Room personnel assisted in determining extent of plant damage.
- 2. ACTIVATION OF FACILITIES ;
Control Room personnel responded to the escalating severity of O events and began call-outs for activating the TSC. L___-_____________-.
Page 2 CONTROL ROOM CHECKLIST (Cont.) r'\ V; CRITERIA EVALUATION The Technical Advisor was notified, reported to the Control floom, and provided assistance as required, s 0 Control Room personnel aided in establishing the proper location of the PCC. Transition of responsibilities, as plant conditions degraded, was effectively executed.
- 3. NOTIFICATION / COMMUNICATION s es Notifications to (j State / Federal authorities were timely; and properly completed per RERP-NOTIFICATION for:
(1) NOUE ' (2) ALERT All notifications were verified and logged per proper procedures. Communication networks were operational and efficiently utilized. Communication flow was adequate to ensure that information was timely and accurate. Phone lists were available and complete, r1 1 i l I i L _ - -------_-----_--__-------_-_------__d
- 7 ,,s 1 y, ,
,'l Page 3' 'O p.
CONTROL ROOM CHECKLIST (Cont.) . A s.
'I 4 CRITERIA EVALUATION.
General status 5 announcements were madep
.and updat4d' periodically by.the Shift' Supervisor / Control Roon i_
Director. Logs were. maintained. Data flow between the . Control Room and TSC was ' maintained. 1 AmbientnoitelevelSn the Control Room wg's not a problem. 1 4 There was no i interaction / confusion between CR operating (mj personriel, "CR Players" ! CR Controllers /0bservers. 1 Transfer of information within the Control Room was clearly and completely understood. .;
- 4. ORGANIZATION CONTROL The Shift Supervisor in conjunction with other I Control Room personnel - 1 evaluated the plant conditions and implemented appropriate response actions. j The Shift Supervisor took over management control per RERP-NOVE.
O )
Page 4 CONTROLROOMCHECKLIST(Cont.) O 1 CRITERIA EVALUATION i
.-Transfer 'of ' control between the Shift 1 Supervisor (acting as the Emergency Coordinator) and the' Superintendent of Operations was effective and in accordance with procedures.
The proper management chain of command was followed throughout the exercise. Emergency control snd
- authority were effectively transferred from the Control Room to the TSC, Transfer and control of authority'were announced and logged.
- 5. HEALTH PHYSICS / SECURITY The Shift Supervisor performed and maintained Control Room accountability per Procedure G-5. !
l Control Room habitability d was monitored per j procedures posted adjacent to the RT-7312 ' recorder on I-14. Access to the Control Room was limited per , appropriate procedures. ] 1 l O 4 l
Page 5 CONTROL ROOM CHECKLIST (Cont.) q
.Q . CRITERIA EVALUATION
- 6. PROTECTIVE ACTIONS / MEDICAL
,I Control. Room personnel supported the FSV emergency organization in developing and
. recommending protective
. actions.
Supplies such as respirators, protective clothing, etc. were available to Control Room personnel. HP personnel were available to Control Room personnel as needed. Shift Supervisor requested medical , transportation services. i Shift Supervisor completed Attachment 2 to the Medical Emergency , Plan (MEP). Shift Supervisor notified hospital of victim's pending arrival and j provided details of injury / contamination. Shift Supervisor notified I appropriate PSCC management personnel per the MEP. , Shift Supervisor was. periodically notified of victim's status - information relayed to TSC Director.
Page 6 CONTROL ROOM CHECKLIST (Cont.) O i CRITERIA EVALUATION i Shift Supervisor notified LSO of transportation arrangements. I 1 1 I i - - _ - _ - _ _ - - - - - - - - - - l
l, b_ Page 1 l FOSAVEX 87
. -- OBSERVER CHECKLIST i
Location: TECHNICAL SUPPORT CENTER Name: Time Frame: to Date: CRITERIA EVALUATION
- 1. ACCIDENT ASSESSMENT Plant process information was available when required.
TSC personnel responded' to simulated events and properly classified the accident condition for:
- p( . (1) SITE AREA EMERGENCY-(2) GENERAL EMERGENCY TSC personnel assisted in determining extent of plant damage.
- 2. ACTIVATION OF FACILITIES The first person arriving at the TSC verified '
habitability and began TSC activation. The first technical / management individual verified that habitability tas checked and that all communication systems were operable. RERP-TSC Attachments D .I and E were used when 1 activating the TSC.
Page 2 TSC CHECKLIST (Cont.) ( )- CRITERIA EVALUATION All copies of the Emergency Plan, ' Procedures, Updated Safety Analysis Report, Tech. Specs., drawings, etc. were available for TSC personnel. ,
- 3. NOTIFICATION / COMMUNICATION Communications with Control Room was established. Primary and secondary communication links were available.
Communications with the Persoanel Control Center (PCC) and the Forward Command Post (FCP) were O- established. Plant status and/or radiation parameters needed to determine existing conditions were available via Status Boards. Status Boards were updated as required. Information regarding major changes in plant status was disseminated to key personnel effectively. Information relative to Protective Action Recommendations was disseminated to key personnel effectively. Communication with onsite monitoring teams were
- effective.
Logs were maintained.
Page 3 TSCCHECKLIST(Cont.) O CRITERIA EVALUATION Ambient noise level in-TSC was not a problem. Transfer of scenario information within the TSC was clearly.and completely understood.
- 4. ORGANIZATIONAL CONTROL-Transfer of command from the Control Room was effective.
Transfer of command from the TSC to the Forward Command Post was effective. .A The proper management
- hain of command was followed throughout the exercise.
Transfer and control of authority was announced and logged. Per RERP-TSC, the TSC Director assumes overall responsibility for the coordination and direction of the onsite emergency response centers. The TSC Director recommended de-escalation or initiation of post-emergency recovery efforts in a timely manner; per the RERP (Section 4 or 9). O
Page 4 L TSC CHECKLIST (Cont.) lO CRITERIA EVALUATION The TSC Director requested additional support.from the Corporate Emergency Director. Radiological, Engineering, and Administrative personnel coordinated their activities effectively.
- 5. HEALTH PHYSICS / SECURITY HP coverage in TSC (air sampling instrumentation and dosimeter) was adequate.
Initial
?- accountability / continued accountability was performed satisfactorily.
In plant Radiation Monitoring was
. coordinated with TSC.
Offsite dose assessment evaluations were conducted per procedures (RERP-DOSE). Initial and subsequent dose calculations were performed in a timely manner. Computing aids were properly utilized. Exposure plume was well defined and tracked. Communications with O monitoring teams were maintained.
~
.Page 5 TSC CHECKLIST (Cont.)
i CRITERIA EVALUATION j Dose Assessment Team j Leader ensured' I comparisons between projected and. actual l 1 field measurements were made. Field survey teams were. I provided' sufficient information to perform j duties. ' Coordination of HP criteria for exposure control with TSC Director waseffective(RERP-EXP). TSC HP personnel considered implementing RERP-THYROID. TSC HP personnel obtained airborne contamination. and radiation surveys in the Control Room and informed TSC Director or results. TSC HP personnel coordinated activities with the Radiological Assessment Manager in the FCP.
- 6. PROTECTIVE ACTION TSC HP personnel coordinated activities with the TSC Director and Radiological Assessment Coordinator.
Protective equipment and associated supplies were available to TSC i personnel.
Page I ~ FOSAVEX 87
'. OBSERVER CHECKLIST 3 .
Location: PERSONNEL CONTROL CENTER Name: Time Frame: to . Date: CRITiiRIA EVALUATION
- 1. ACCIDENT ASSESSMENT Emergency.In-Plant Repair Teams were dispatched effectively.
Repair teams evaluated the extent of plant damage and reported information to PCC and TSC personnel.
- 2. ACTIVATION'0F FACILITIES The proposed location of the PCC was known by all personnel.
Access to the FCC was well established and did not hinder activation. The PCC was activated in a timely and orderly manner. PCC staffing was adequate, and met the needs of the emergency ; organization. j The PCC was activated per RERP-PCC.
- 3. NOTIFICATION / COMMUNICATION Communication with the
~
Control Room and TSC was adequate.
Page 2. PCCCHECKLIST(Cont.)
/~ ~
i . CRITERIA EVALUATION. Primary. and secondary communication-links with the TSC were available - constant communication with-TSC existed. Communication links ith onsite and offsite' teams was adequate. Team briefings (prior to dispatch) were adequate. Prior to dispatching teams - the Senior HP Representati_ve at the TSC, and the TSC Director were consulted. g Individuals living on plant properly were
'~
notified. TSC was notified of need to transport , injured / contaminated i personnel offsite. St. Luke's Hospital was properly notified. Detailed logs were j maintained. ! I Plant status and emergency assessment information was readily l available to PCC personnel.
- 4. ORGANIZATIONAL CONTROL l
The PCC Director adequately supervised the activites of the PCC. O
Page 3
.PCC CHECKLIST (Cont.)
CRITERIA EVALUATION-The PCC Director coordinated activites with the TSC Director. The PCC Director utilized the checklist in RERP-PCC. An effective. chain of command was established. Team formation and briefings were completed quickly and accurately-(see RERP-PCC).
- 5. HEALTH PHYSICS / SECURITY HP cover in PCC was adequate.
The Lead Security Officer (LS0) dispacted a security guard to the PCC; access was controlled. I PCC Director coordinated access to/from the protected area with the LSO. Accountability was j initially established and l maintained throughout the emergency. ; Habitability was i initially established and verified as appropriate throughout the emergency. Appropriate briefing sheets were used to " inform teams of potential radiological areas.
,}
1 _ _____-_- Y
Page 4 PCC CHECKLIST (Cont.) O
-CRITERIA EVALUATION
-Maximum stay. times were' established and relayed.
.to survey / repair teams.
An HP was assigned to each team. ; 6.- PROTECTIVE ACTION l Protective equipment,
. clothing, decon-facilities, and associated. supplies were available to PCC personnel. Specialized i tools and equipment were available.
O i l l O
Page 1 FOSAVEX 87 OBSERVER CHECKLIST I Location: FORWARD COMMAND POST Name: Time Frame: to Date: y CRITERIA- EVALUATION
- 1. ACCIDENT ASSESSMENT
'FCP personnel coordinated Accident Assessment activities-with TSC personnel.
- 2. ACTIVATION OF FACILITIES FCP was activated and 1 manned.within a E
. reasonable time after declaration of an ALERT.
Corporate Emergency Director received briefing from TSC Director prior to assuming command and control.
'FCP personnel informed of assumption of specific responsibilities.
Facsimile machines functioned properly, status boards were available.
~ Emergency. Plan and Implement Procedures, Tech. Specs., etc. were available in current and controlled copies (see RERP-FCP Attachment C).
Page 2 FCP CHECKLIST (Cont.) (v) . CRITERIA EVALUATION Activation per RERP-FCP was accomplished effectively.
- 3. NOTIFICATION / COMMUNICATION Communications were established with the TSC; both primary (telephone)
- and secondary (radio) ,
communication lines were i established and maintained. Communications with the ; Executive Command Post (ECP) and the State Emergency Operations Center (E0C) were established and (_, /~') maintained. TSC notified FCP of location and status of PCC. Notification / Communication between PSCC, local, and State agencies was effective. Needed data was available from TSC and CR. FCP received prompt information on radiological status, both on and off site. Pertinent information was quickly (15 minutes) transmitted to offsite groups. Up-to-date meteorological T [~,). data was available.
Page 3 FCPCHECKLIST(Cont.) D V CRITERIA EVALUATION I Plant status information was promptly available; status boards used and kept current.
-Communication with offsite monitoring teams was adequate.
General status announcements and updates were made to FCP personnel throughout the exercise. FCP coordinated the supply of information to ECP Media Relations personnel. The FCP Public Information Team had sufficient information (and facilities) to prepare'and release news and related media releases. Development and presentation of initial media briefing was effective. Development and release i of initial press release was effective. Development and release of follow-up briefings and releases was I effective. Necessary documents (logs,etc.)were maintained. Effectiveness of FCP/ECP Interface. b
Page 4 l FCP CHECKLIST (Cont.)
. CRITERIA EVALUATION Effectiveness of dealing with new media.
Effective rumor control methods were employed. Spokespersons.were knowledgeable about technical aspects of plant problems.
- 4. ORGANIZATIONAL CONTROL The organizational structure and chain of command in FCP was clear.
Appropriate people made prompt decisions and recommendations. Status boards were kept current. Plume pathway was tracked and visibly displayed. Emergency classifications and action level notifications transmitted to proper authorities as required. The Corporate Emergency Director (CED) utilized RERP-FCP Attachment E efficiently. (Also RERP-CED) The CED ensured continuity of emergency resources throughout the exercise. ,
.n The CED ensured adequate administrative, technical and logistical support was available.
Page 5 FCPCHECKLIST(Cont.) i-CRITERIA EVALUATION Plant. Status updates to the ECP and State EOC was effective. The CED provided direction to, and coordination for, the TSC Director, and the PSCC personnel at the State E0C. The CEO,.in conjunction with other emergency response personnel, de-escalated the Emergency Category according to plant conditions.
- 5. HEALTH PHYSICS / SECURITY Only assigned FCP people were present.
Security Control was established and maintained. Accountability data was forwarded to Security. Computer aids were properly utilized. Plume was defined and tracked. Coordination with TSC Radiological Assessment team was effective. Offsite monitoring data ! was coordinated with State. 1 Vse of Radiological Status Boards was effective.
1 Page 6 FCP CHECKLIST (Cont.) w/ CRITERIA EVALUATION
- 6. PROTECTIVE ACTIONS Radiological Assessment Manager /CED interface on ,
Protective Action Recommendations was timely and effective. Protective action recommendations to the State were made clearly and in timely fashion.
.y
\-) i I) x_
,t.-
Page 1 FOSAVEX 87 OBSERVER CHECKLIST Location: EXECUTIVE COMMAND POST Name: Time Frame: to Date: CRITERIA EVALUATION
- 1. ACCIDENT ASSESSMENT ECP personnel, coordinated accident assessment activities with FCP personnel.
- 2. ACTIVATION OF FACILITIES The ECP was activated on a timely manner.
The Executive Command Post was fully staffed in a timely fashion. Information was received quickly from the FCP and/or TSC. The ECP Director performed personnel accountability to assure that sufficient manpower was available to staff the ECP. Activation per RERP-ECP was accomplished effectively.
- 3. NOTIFICATION / COMMUNICATION Established and maintained communication with the FCP.
Page'2
'ECP. CHECKLIST (Cont.).
p -V' . CRITERIA EVALUATION The Manager of Media-Relations assisted the ! ECP Director and PSCC Media Relations personnel-
.in preparing press releases, announcements, and interviews.
Rumor. control methods were used effectively.
)
Use of status boards was effective.
- 4. ORGANIZATIONAL CONTROL The ECP Director assumed control of-the ECP.
Major decisions were made O by.the ECP Director, his staff and the Corporate Emergency Director (CED). The Manager of Technical Support prov.ided the CED with the required support. The Manager of Resources supported the on-site emergency organization was required. The Manager of Security coordinated security operations with public law enforcement agencies. Provided additional security as required.
- 5. HEALTH PHYSICS / SECURITY Only persons with assigned emergency ;
; responsibilities were
' ' permitted in the ECP. l
Page 3 ECP CHECKLIST (Cont.) N- ~ CRITERIA EVALUATION ECP personnel were aware of monitoring team activities being coordinated from l FCP/TSC/PCC. ECP personnel were appraised on the medical emergency and the status of the victim.
- 6. PROTECTIVE ACTIONS i
ECP personnel were aware of recommendations being made at FCP. ECP personnel were aware of the actions ('~} State / local governments (_) were taking with respect ta. Protective Actions. b'/ )
L Page 1
. FOSAVEX'87 M'
OBSERVER CHECKLIST n Location: STATE EOC Name: Time Frame: to' -Dats: u CRITERIA EVALUATION
- 1. ACCIDENT ASSESSMENT' SE0C personnel coordinated accident assessment with FCP personnel.
12 . ACTIVATION OF FACILITIES PSCC representative pe'eformed accountability _ (s to ensure adequate staffing. Established communications with FCP inform them SE0C is manned. Activation per RERP-SEOC was accomplished effectively. Information flow between FCP/SOEC was effective.
- 3. NOTIFICATION / COMMUNICATION Established and maintained communications with FCP. >
Maintained communications-with SEOC representatives. Rumor control methods ' were employed.
o
~
q Page 2 j 1
.SE00 CHECKLIST (Cont.)
n. t < i I I CRITERIA EVALUATION Use~of status boards, meetings / briefings was ; e f fecti ve'. Proper media coordination l was established. ' Clerical assistants , maintained logs. ] Up-to-date t.ite informatier. was provided to Public Information Coordination Team. i
- 4. ORGANIZATIONAL CONTROL ;
PSCC representatives' coordinated PSCC
. ^ g. . emergency response i
. J activities with those of -]
State / local officials. 1 PSCC technical assistar,ce was available was required.to support the Vice President, Governmental Affairs and State / local ~ I representatives. Media Relations Manager (PSCC) coordinated activities with news ! releases, background j material, rumor control,. etc.
]
1
- 5. HEALTH PHYSICS / SECURITY SEOC personnel were aware
)
of monitoring activities occurring i on-site /off-site. L l
- _ _ _ = _ _ _ _ _ _ - _ _ . . _ _ _ 1
Page 3 SE0C CHECKLIST (Cont.) b;cy CRITERIA EVALUATION
- 6. PROTECTIVE ACTIONS PSCC personnel were aware of P. A.R. 's being rnade at the FCP.
PSCC personnel were aware
'of P.A.R. status.
l O O
Page 1 FOSAVEX 87-
;s. OBSERVER CHECKLIST k)
Location: ONSITE RADIOLOGICAL- Name: MONITORING Time Frame: to Date: CRITERIA- EVALUATION Onsite monitoring , equipment was easily accessible'and properly distributed. Equipment was checked for proper operability prior to its use.
- Actions by the Onsite Monitoring Teams to make initial surveys outside the plant buildings and perimeter fence were cor. rect. As appropriate, ,
the Senior HP ~! Representative in the TSC , was notified. Standard HP practices were employed for entry ; into actual or potential i radiation areas. l Proper survey records, l dosimetry, stay time, etc. were maintained ; during entry. Survey results were ' reported to the appropriate personnel in i the TSC/PCC. Follow-up actions were taken on survey results. l
Page 2 ONSITE TEAM CHECKLIST (Cont.) (D %) CRITERIA EVALUATION Pocket dosimeters were frequently checked and properly logged. Team members had adequate understanding of proper utilization of equipment (survey instruments, radios,SCBA's,etc.). Inplant survey results were systematically collected; appropriate datasheets of RERP-SURVEY were used. The correct procedure was used to establish emergency dose limits if needed. Authorization to exceed 10CFR20 Exposure Limits was documented. Use of survey and decontamination techniques at designated control point prior to entry in the pCC. Debriefing conducted, records and logs collected. appropriate radiological data were available t the teams as needed.
f Page.1 FOSAVEX 87
,Ot, OBSERVER CHECKLIST
( I i Locationi 0FFSITE MONITORING TEAMS Name: Time Frame: to Date: 1
~
. CRITERIA EVALUATION I'
Initial team briefings were held. (See RERP-PCC). Teams assembled with field kits, vehicles, and communications; equipment in a timely manner. Contents of the Field Monitoring Kits were
.( checked before leaving site. (See RERP-FIELD Section'2.3)
Instruments checked for proper. operability and current calibration. (See RERP-FIELD Checklist 1-). Teams received explicit instructions of where to go and what to sample, i
, I Teams found sampling i locations easily.
l Procedures for conducting , offsite monitoring were consulted and followed, q t Vehicles were readily , available. ] Vehicles checked for
. ._ contamination after L survey was completed. )
Page 2 0FFSITETEAMCHECKLIST(Cont.) f~') NJ CRITERIA EVALUATION Sampling locations'were readily located. Samples were properly packaged, identified, and labeled. Appropriate documentation was maintained. Pocket dosimeters were periodically checked. Use of respirator equipment and personnel monitoring was appropriate. Pocket dosimeter readings r were logged in upon ( return to FSV. Communications were maintained with the TSC and/or PCC throughout sampling activity. l 1 _ - - _ - _ _ _ _ _ _ - - _ - - __a
l Page 1 FOSAVEX 87 l s n OBSERVER CHECKLIST
% )s Location: CORRECTIVE ACTION (REPAIR) Name:
TEAMS Time Frame: to Date: CRITERIA EVALUATION Need for Repair Team established by TSC Director; activities coordinated with PCC Director. Team members briefed in accordance with RERP-PCC and RERP-TEAMS. Safety and first aid equipment available as needed. c Team accountability was maintained. Radio checks performed. Communications maintained during repair activities, j i Log of activities kept. l Debriefing conducted, records and log ' collected. As applicable, RERP-EXP was followed by repair team. Personal dosimetry used, if needed. TSC informed of results.
Page 1 FOSAVEX 87
.q- OBSERVER CHECKLIST
}-
Location: FIRST AID / SEARCH AND RESCUE Name: AT FSV Time Frame: to Date: CRITERIA EVALUATION The EMT was properly notified and First Aid Team. assembly was timely following notification. First Aid Team assembled with the proper first aid equipment. Accident / injury
- assessment made by the First Aid Team.
Level and extent of contamination was properly determined. Appropriate decontamination measures were taken. Maintained communications with Control Room (via Gaitronics). The HP escort reacted , properly to the simulated event. The request for transportation by the Shift Supervisor was ir, accordance with procedures. Patient was made ready
-for transport by the First Aid Team.
(- - _ - _ - _ _ - _ - _ _ _ _ _
Page 2 l FIRST AID / SEARCH AND RESCUE AT FSV (Cont.)
~v Il CRITERIA EVALUATION Appropriate methods were used to identify victim, the extent of injuries, contamination levels and locations, first aid administered, etc.
(Attachment MED-4 should be used.) Periodic Status Reports are provided to the Shift Supervisor regarding the injured individual's status. i
Page 1 F0SAVEX 87
.s .
OBSERVER CHECKLIST J\.._) Location: FIRE BRIGADE Name: Time Frame: to Date: CRITERIA EVALUATION Reaction time between fire alarm and fire team activation was timely. Fire fighting personnel response time to the scene of the fire was timely. Fire team members
-(~~N reported to scene of fire
\ with appropriate fire fighting gear and equipment.
Initial assessment of
. fire situation was adequately performed.
When it was apparent team cannot control the fire, offsite support is requested and obtained in a timely manner. Communications were maintained between the fire team leader and the CR (Control Room). Adequate information was provided by the fire team ' to the Control Room for their assessment. Smooth transition and O. coordination was between plant fire team and local ' fire department. ;
Page 2 FIRE BRIGADE (Cont.) (3 V CRITERIA EVALUATION Arrival of local fire department to fire scene was timely. k O
= .e. .
ef7 5.0-1 SECTION 5.0 EXERCISE SCENARIO Section .
'5.1 Narrative Summary 5.2 - Initial Conditions 5.3 Detailed Scenario 5.4- Sc'enario Time Line A- ,
O e 9 _ _ _ _ _ . _ . - . _ _ _ . _ _ _
NARRATIVE
SUMMARY
FOSAVEX - 87 v The exercise will be based upon events leading to core damage and later release of the activity. The initial conditions are:
- 1. Reactor power, 100 percent
- 2. Four circulators in operation .
- 3. 342 MW electrical I
- 4. Both boilers are out of service for a common line repair
- 5. Cooling water systems are normal
- 6. Helium purification systems are normal !
- 7. Electrical distribution system is normal reactor ' operator adjusts At 06:00 the the core orifice valves to redistribute flow, one region is decreasing in temperature slowly. His V actions continue until it is noticed that the thermocouple reading at the outlet of the low region has decreased to almost average core inlet i
temperature. Radiation monitor 9301 indicates an increasing coolant activity. The operator returns the orifice valves to t*,.eir original positions suspecting that ' the low temperature indication was due to a failing thermocouple. Coolant activity continues to increase until it is greater than 25 percent above the initial reading. He informs the Shift Foreman. The time is nov 07:00. The coolant activity level causes a declaration of Unusual Event (NOUE) to be declared. Management requests that a coolant sample be obtained for analysis by the incoming chemists. The on-shift health physics person is directed to obtain the sample. The H.P. enters the building at 07:30 to do this. l
At 08:00 a cold reheat line ruptures at the inlet to the Loop 2 circulator bypass isolation causing a "High Reactor Building Temperature" initiation of SLRDIS (Steam Line Rupture Detection / Isolation System) with the resultant LOFC and loss of secondary cooling capability. This should result in an " ALERT" declared per Table 4, items 8 and 17. (At this point in the scenario the H.P. taking the coolant sample becomes injured.) The electric feed pump is damaged by the high discharge pressure and the turbine driven feed pumps have no steam due to the boiler outage and are unavailable. The main condenser rupture disks are broken when vacuum is lost and the condensate system will require greater than six hours to It is decided to reestablish cooling become available for heat removal. via fire water. The reactor building atmosphere in the area of the cold reheat line break will be approximately 300*F for a significant time with the average building temperature slightly greater than 150*F until 14:00. At 09:45 cooling and forced circulation is recovered using the "A" circulator, driven by boosted firewater and cooling via the Loop 1 ESS section of the steam generator. The reestablishment of flow results in greatly increased primary coolant activity caused by fission products released during the LOFC. At 10:00 the reactor building activity rises with indication that there is primary to secondary leakage in the failed reheat section. A SAE is declared per Table 5, item 2. The release of activity from the building is monitored through the normal reactor building stack monitor but indications are that the filters are not working, flow is 110 percent of normal with no AP across the filters. These conditions indicate the filters are being bypassed and therefore ineffective. The conditions will continue for two hours to allow monitoring teams to be I f observed. AT 12:00 the Loop 2 reheat section will fail depressurizing the RCS through the break in about 20 minutes. The resultant release will be O cause for a declaration of " GENERAL EMERGENCY" per Table 6, item lb. l % ,5 l I l l
At 14:40 the operator attempts to close the circulator bypass and is N successful. The leak is isolated. (O . A review of plant conditions indicates that the plant is no longer presenting a threat to the public and a recommendation that " deescalation be considered" is made. Prior to 16:00 the exercise should be completed. Between 14:40 and 16:00 the steps and conditions for deescalation will be based on plant conditions. m A. l 1 i O l
POSAVEX 87 FOR: snIFT supervisor MESSAGE NO. I
.s
.h LOCATION: CONTROL ROOM TIME: 0600 XX)OOOOOOOOOC XXXXxXXXXXxXXXX THIS IS A DRILL
.D0 NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS MESSAGE:
The initial conditions are:
- 1. Reactor power, 100 percent
- 2. Four circulators in operation
- 3. 342 MW electrical
- 4. Both boilers are out of service for a common line repair
- 5. Cooling water systems are normal
- 6. Helium purification systems are normal
- 7. Electrical distribution system'is normal E
a d o l THIS .lS A DRILL O xxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxx
FOSAVEI '87 p7 Scenario time C OVERALL PLANT PARAMETERS Clock time reno . \4] Rx Power /00 # 4 Turbine Generator Load ._T46 MW PRIMARY COOLANT PRESSURE 4 94 PSIA TEMPERATURE Circulator Inlet #4 deg F Core Outlet /#s r/ des F HELIUM FLOW Loop 1 A7t# 0lbs/hr Loop 2 /. 7x/Fa lbs/hr TOTAL 3 v//0*1bs/hr CIRCULATOR SPEED Circulator A @/5f RPM Circulator B 42/O RPM Circulator C 9/FfRPM Circulator D 9/90 RPM , MOISTURE (DEW POINT) . ME-9306 < :s'I deg F ME-9307 <-57 deg F f_f' SECONDARY C00LAN't FEEDWATER FLOW Loop 1 ////D0lbs/hr Loop 2 / Pay /061bs/hr TOTAL ..p.xx # 1bs/hr MAIN STEAM Loop 1 Pressure - asad PSIG -- Temperature 99F deg F Loop 2 Pressure JSa? PSIG Temperature J g deg F HOT REHEAT Loop 1 Pressure dof PSIG Temperature /OOR_d e s F Loop 2 Pressure 403 PSIG Temperature / OOR d eg F COLD REHEAT Loop 1 Pressure 4/7 PSIG Temperature t,7f d eg F Loop 2 Pressure 4/r1 PSIG Temperature /,7 F d e g F
4 RADIATIM M MIT M S SCENARIO TIME 00'00 PROCESS MWIITMS CLOCE TIME O(o 00 MBIBER SENSITIVITY VALUE ALARMING 1 (Y/N) RT-4801 2.6E-10 ** l.O E +l CPM M RT-4802~ 1.2E-10 ** 1, o E + f CPM M RT-4803 2.5E-8 l.O E e i CPM A. RT-6212 2.2E-8 _ l.o E +f CPM - M RT-6213 2.2E-8 f.o E ,e CPM M RT-7312 2.3E-8 *(PCRV) 3.0 E +1 CPM' M RT-7324-1 _ 2.8E-8 4.o E CPM' u - RT-7324-2 8.9E-7 _ r. o E + # CPM N 1 RT-7325-1 003 003 00S I RT-7325-2 003 OOS 003 RT-73437-1 4.6E-10 ** f. o E + l CPM N RT-73437-2 003 003 003 RT-9301 2.3E-8 ___, S,o E +5 CPM N RT-93252-12 N/A 1.o E + 0 er/hr M AREA MONITORS NUMBER VALUE ALARMING (ar/hr) (Y/N) RT-93250-1 o.I d RT-93250-2 o. I M RT-93250-3 s.o 11 RT-93250--4 c.I J
/ RT-93250 O.I M RT-93250-8 c.I M RT-93250-13 0./ d RT-93250-14 osL M RT-93251-1 05L M RT-93251-3 50.O d RT-93251-4 o, I d RT-93251-5 o.I M RT-93251-6 o.I M RT-93251-7 o.I d RT-93251-8 0.1 d RT-93251-9 o. I d RT-93252-1 OI M RT-93252-2 c.I J RT-93252-4 0.1 M RT-93252-6 o.I d RT-93252-7 ot V RIA-79511 0.t V METER 0RLOGICAL DATA WIND SPEED 5. O _MPE .
WIND DIRECTION FRW 2*70 DEGREES PLUME DEVIATION / SIGNA THETA 2. O DEGREES DIFFERENTIAL TEMPERATURE ' + 4.0 DEGREES T LO
- Value corresponds to the PCRV area channel. Other four channels are 30 cym.
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
l l PRIMARY AUXILIARIES gym Q) BOARD I-01 GAS WASTE SY' STEM 63 Normal LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal BOARD I-02 HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /9 PSIG High Pressure Bottles /of/f PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow 4/SP GPM BUBW Header Pressure JMr PSIG HELIUM CIRCULATORS SYSTEM 21 Normal BOARD I-03_ b REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position //6' INCHES Runback group positions , 2A, rod #2 /fo INCHES l rod #4 /90 INCHES rod #6 /9o INCHES 4F, rod #25 _ /fo INCHES rod #31 /fo INCHES rod #37 /90 INCHES Flux Controller position +/- o % Reserve Shutdown Material 7/oe/md STATUS
BOARD I-05 l HYDRAULIC OIL SYSTEM 91 Normal STEAM WATER. DUMP TANE SYSTEM 22 Loop Selected 3 1.or 2 Pressure. O PSIG.
' Temperature //E deg F l'
l Level 23 INCHES Radiation Jo-#4ar/hr . HELIUM CIRCULATORS SYSTEM 21 Normal NOTE l LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO , l "0" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal , BOARD I-06 EMERGENCY FEE'DWATER PRESSURE 3 M4 PSIG
~
BOILER' FEED PUMPS
- A Speed 45dd RPM A Flow '/A /o3 lbs/hr B Status aA> on/off
- B. Flow 8.5'r /F ib s/hr C Speed 6F W RPM C Flow -
7Sr#5lbs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Tank 480 PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal
. FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal
.O SERVICE iIR SYSTEM 82 N-mai
BOARD I-10 PLANT PROTECTIVE SYSTEM gp RI BUILDING TEMPERATURE-HIGH BAY 100 /09 deg F BAY 200 /gR_deg F BAY 300 /0V_ des F REHEAT ACTIVITY MONITORS Loop 1 Bay.1200 // mr/hr Bay 1100 e/ mr/hr Bay 1000 4/ mr/hr Loop 2 Bay 600 4/ ar/hr Bay 500 . / mr/hr Bay 400 /S mr/hr MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-13 PENETRATION INTERSPACE dP I PSID RX BUILDING SUMP DISCHARGE FLOW .4/O GPM ' (; BOARD I-15 j RI STACK. FLOW M ACFM RX BUILDING / AMBIENT dP -asf PSID BOARD I-7507X' CONTROL ROOM TEMPERATURE 4 deg F 480V ROOM TEMPERATURE N deg F l O
L (. . DETAILED SCENARIO FOSAVEX 87 e h.- tgency Event Time Classification
- 1. Decreasing core region outlet temperature. 0600
- 2. Atempt to equalize core outlet temperatures 0610
- 3. Region outlet temperature approaches average 0630 inlet temperature and the operator recognizes a failed instrument.
- 4. Initiates returning the region orifice valve 0635 to its initial position.
- 5. ~ Coolant activity levels rise as flow increases 0640 in the effected region.
- 6. Coolant activity levels exceed 25 percent of 0645 NOUE tormal. (Tb1 3, item 3)
- 7. Start notifications and declaration. 0700 t
- 8. Complete notifications.
- 9. On shift H.P. enters the reactor building 0745 for primary coolant sample.
O
4 1
' Emergency Event Time Classification {
- 10. - Cold reheat line, loop 2, ruptures and 0800 ALERT 1 circulator bypass and isolation fail to (Tb1 4, items 8 close. Feed and condensate systems are lost. and 17)
NOTE Auxiliary boilers are not available for feed pump turbines and electric feed pump is damaged. Main condenser rupute. discs are blown and condensate system is lost, at least six hours to affect repairs.
'The plant recovery will be with firewater after a 1 1/2 hour delay.
- 11. The H.P. exits the reactor building on the 0804 north side at grade.
NOTE Injured / Contaminated Man Drill
- 12. Reactor building exhaust flow increases by 0805 10 percent and the radiation monitor indicates i that the release if any is unfiltered.
NOTE Indications are that there is some filter damage allowing any release to be monitored but unfiltered. o _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ -
s. Emergency
. Event Time Classification
- 13.: SLRDIS recovery completed using fire water. 0945 Circulation is returned using "A" circulator, primary coolant radioactivity levels increase significantly. Indicating large fission product release during the LOFC.
- 14. Radiation levels in the reactor building 1000 SAE indicat'e some leakage out of the RCS. (Tb1 5, item 2)
Indications of temperature and radiation indicate the. leak is in the Loop 2 reheater and is not isoable from the cold reheat break. NOTE Any attempt to depressurize is not successful at this time.
- 15. Reactor coolant system pressure starts 1145 decreasing rapidly. Reactor building radiation levels increase. Reactor building monitors increase on all channels.
- 16. Reactor coolant pressure is about atmospheric. 1200 General The primary system has depressurized to the Emergency reactor building through loop 2 reheater and (Tb1 6, item Ib) pipe rupture. The activity has been released unfiltered through the venti 11ation system and l
this is confirmed by local EAB readings.
- 17. After depressurization radiation levels begin 1440 SAE based on on-to fall off and eventually are low enough to site conditions downgrade to SAE onsite.
O l1 l Emergency J i t r^ Event Time Classification ! b l
- 18. Cold reheat bypass isolation is closed and 1520 Alert based on i i
EAB radiation levels are low enough to down- onsite condition i grade to Alert.
- 19. End 1600 I i
O O _4 1
O SCENARIO TIME LINE ; V FOSAVEX 1987 l 0600 Distribute initial conditions packages. 0700 Complete discussion of plant conditions and all observers on station. Declare NOUE based on 25% increase in primary coolant activity.
^ Cold reheat line rupture, loop 2.
0800 Loop 2 circulator bypass & isolation fail open. Totalloss of feed and condensate systems. HP that was taking the primary coolant sample is injured and contaminated. 0945 SLRDIS recovery complete on firewater. Primary coolant activity levels increase. i 1000 SAE Coolant leakage becomes evident in the failed reheat section (smallleak). GENERAL
" Gross failure of tubes in the failed reheater, 1200 RCS depressurizes in 20 minutes.
1330 Radiation levels at the EAB and plant conditions no longer justify the General Emergency Classification on site. 1440 Loop 2 circulator bypass is closed, accomplishing system isolation. 1500 Radiation levels at the EAB and plant conditions no longer justify a Site Area Emergency Classification on site, 1600 q Exercise is terminated. C/ M0687111
FOSAVEX 87 FOR: SHIFT SUPERVISOR MESSAGE NO, b i
)
LOCATION: CONTROL ROOM TIME: 0600 l XXXXXXXXXXXXXXXXXX l THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS l XXXXX MESSAGE: The initial conditions are:
- 1. Reactor power, 100 percent
- 2. Four circulators in operation
- 3. 342 MW electrical
- 4. Both boilers are out of service for a common line repair rm Cooling water systems are normal 5.
- 6. Helium purification systems are normal
- 7. Electrical distribution system is normal m
THis .is A DRILL XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX
FOSAVEI '87 p OVERALL PLAJIT PARAMETERS Scenario time d y Clock time r&ro Rx Power /00 # 4 Turbine Generator Load 346 MW PRIMARY COOLANT PRESSURE 4 94 PSIA TEMPERATURE Circulator Inlet #4 deg F Core Outlet /#s ? deg F HELIUM FLOW Loop 1 A 7t/O bibs /hr Loop 2 /. 71/06 lb s /hr TOTAL 3 vX/B* 1b s /h r CIRCULATOR SPEED Circulator A @/fi" R PM Circulator B oa/O RPM : Circulator C 9/rf RPM Circulator D 9/90 RPM , MOISTURE (DEW POINT) ME-9306 - <-s7 des F g ME-9307 6 57 deg F SECONDARY COOLANT FEEDWATER FLOW Loop 1 ////DS1bs/hr Loop 2 /ary/061bs/hr TOTAL g Tre*1bs/hr MAIN STEAM Loop 1 Pressure asad,PSIG Temperature 9!PF deg F Loop 2 Pressure adn2 PSIG Temperature /om deg F HOT REHEAT Loop 1 Pressure dof PSIG Temperature / Coa deg F Loop 2 Pressure 403 PSIG Temperature / OOA de8 F COLD REHEAT Loop 1 Pressure 4/7 PSIG Temperature t,78 deh F Loop 2 Pressure 4/9 PSIG Temperature /,7 8' d e g F O
RADIATION M(BIITt3t3 SCENARIO TIME 00toO PROCESS M(BlITORS CLOCE TIME O (o; o O 2RBtBER SENSITIVITY VALUE ALARMING l (Y/N) RT-4801 2.65-10 **- 1.0 E +l CPM M j
-RT-4802 1.25-10 ** l. a E
- I CPM M 1 RT-4803 2.5E-8 1. 0 E ,. t CPM M RT-6212 2.2E-8 f.o E .( CPM sl RT-6213 2.2E-8 f.o E ,# CPM hl RT-7312. _ 2.3E-8 *(PCRV) 3.o E ,a CPM M RT-7324-1. 2.8E-8 4.o E CPM M RT-7324-2 8.9E-7 1. o E + # CPM N RT-7325-1 005 008 OOS RT-7325-2 008 003 _ _ _
008 RT-73437-1 4.6E-10 ** l.a E cl CPM N
.RT-73437-2 003 003 OOS RT-9303 2.3E-8 F,o E +5 CPM N RT-93252-12 N/A l.O E +O mr/hr M AREA MONITORS NUMBER VALUE ALARMING (ar/hr) (Y/N)
RT-93250-1 c.f J RT-93250-2 o.i # RT-93250-3 s.O d
'RT-93250-4 c.I d RT-93250-5 O.f O- RT-93250-8 o.I Al hl RT-93250-13 0.I J RT-93250-14 o st. M RT-93251-1 05L M RT-93251-3 50.O d RT-93251-4 o. I d RT-93251-5 o.# M RT-93251-6 c.I M RT-93251-7 o.I d RT-93251-8 0l J RT-93251-9 o. I d I RT-93252-1 OI M !
RT-93252-2 o.I d l RT-93252-4 oJ M RT-93252-6 6I V RT-937.52-7 o# V RIA-79511 0.# A/ METER 0RLOGICAL DATA WIND SPEED 5. O MPH . WIND DIRECTI(Mt FR(38 270 DEGREES PLIDtB DEVIATI(Bl/ SIGMA TIETA 2. O DEGREES DIFFERENTIAL TEMPERATURE ' + 4. 0 DEGREES F I O
- Value corresponds to the PCRV area chann=1. Other four channels are 30 cym.
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
PRIMARY AUXILIARIES BOARD I-01 GAS WASTE SYSTEM 63 Normal LIQUID WASTE . SYSTEM 62 Norma.t REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal BOARD I-02_ HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /9 PSIG High Pressure Bottles /os/r PSIG EMERGENCY-FEEDWATER SYSTEM 31
. Emergency Feed Flow e/SP GPM BUBW Header Pressure Nr PSIG HELIUM CIRCULATORS SYSTEM 21 Normal BOARD I-03 \
REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position //f INCHES Runback group p'ositions 2A, rod #2 /fo INCHES rod #4 /90 INCHES rod #6 /96 INCHES 4F, rod #25 /to INCHES rod #31 /fo INCHES rod #37 /90 INCHES Flux Controller position +/- O % Reserve Shutdown Material '7/osona/ STATUS I O V l
BOARD I-05 HYDRAULIC OIL SYSTEM 91 Normal STEAM WATER DUMP TANK SYSTEM 22 Loop Selected 4 1 or 2 Pressure O PSIG Temperature // S deg F Level 23 INCHES Radiation Jo-40 mr /h r HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06 EMERGENCY FEEDWATER PRESSURE 30/4PSIG O O BOILER. FEED PUMPS
- A Speed A5227 RPM A Flow '// /os 1bs/hr B Status aA> on/off B Flow B.fr/F lb s / hr C Speed 4795 RPM C Flow 75xe5lbs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Tank 480 PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE VATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRIMENT AIR SYSTEM 82 Normal SERVICE AIR SYSTEM 82 Normal
BOARD I-10 PLANT PROTECTIVE SYSTEM RI BUILDING TEMPERATURE-HIGH BAY 100 /09 des F BAY 200 40R deg F BAY 300 /06/ deg F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 4/ mr/hr Bay 1100 ac / mr/hr Bay 1000 4/ mr/hr Loop 2 Bay 600 at / mr/hr Bay 500 / mr/hr Bay 400 Af ar/hr MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-13 PENETRATION INTERSPACE dP f #PSID RI BUILDING SUMP DISCHARGE FLOW d/O GPM BOARD I-15 ( RX STACK FLOW m3bMP ACFM RX BUILDING / AMBIENT dP -0 46~ PS I D BOARD I-7507X CONTROL ROOM TEMPERATURE 487deg F c 480V ROOM TEMPERATURE 8E deg F l l l l 1 O
4 FOSAVEI '87 p . Scenario time. /r ( OVERALL PLANT PARAMETERS Clock time 04/f Rx Power /00% Turbine Generator Load Mo MW i PRIMARY COOLANT PRESSURE , 690 PSIA TEMPERATURE Circulator Inlet r/ML des F Core Outlet /ve7 des F HELIUM FLOW Loop 1 47X4 0 lbs/hr Loop 2 A7xm8'lbs/hr TOTAL .r#x/061bs/hr CIRCULATOR SPEED Circulator A 9x5T~ RPM Circulator B 94 /o RPM Circulator C 9/tf" RPM Circulator D 9/fo RPM MOISTURE (DEW POINT) ME-9306 4-F/ d e s F ME-9307 e 47 dog-F SECONDARY COOLANT FEEDWATER FLOW Loop 1 //rb'1bs/hr Loop 2 Los2461bs/hr TOTAL oP.3r/061bs/hr MAIN STEAM Loop 1 Pressure Jsro PSIG Temperature 991 deg F Loop 2 Pressure assa. PSIG Temperature /cos des F HOT REHEAT Loop 1 Pressure 4M" PSIG Temperature /oos deg F Loop 2 Pressure roo3 PSIG Temperature /oos des F COLD REHEAT Loop 1 Pressure //7 PSIG Temperature 47T des F Loop 2 Pressure 4/9 PSIG Temperature 47f deg F O
RADIATIM M ITM S SCENARIO TIME 001 i G PROCESS HCBlITORS CLOCE TIME O (, : is NUMBER SENSITIVITY VALUE ALARMING (Y/N) i RT-4801 2.6E-10 _ ** 1. 0 E +1 CPM M RT-4802 1.2E-10 ** f.o E +e CPM h./ RT-4803 2.5E-8 __, l.o E + t CPM N RT-6212 2.2E-8 I.0 E +( CPM ._ Al RT-6213 2.2E-8 f.o E +1 CPM At RT-7312 ___,2.3E-8 *(PCRV) J.o E er CPM M RT-7324-1 2.8E-8 _ 4.o E + t CPM M - RT-7324-2 ___8.9E-7 1. o E 41 - CPM M RT-7325-1 ._005 OOS 005 RT-7325-2 -OOS 005 OOS RT-73437-1 4.6E-10___ ** 1. o E + I CPM M RT-73437-2 005 008 003 RT-9301 2.3E-6 S.o E + F CPM M RT-93252-12 N/A 1.o E +o ar/hr u A'EA m MONITtMLS NUMBER VALUE ALARMING (ar/hr) (Y/N) RT-93250-1 c. I d RT-93250-2 o. I Al RT-93250-3 5o u RT-93250-4 o.I J O RT-93250-5 RT-93250-8 O.I o./ Al Al RT-93250-13 h O./ d RT-93250-14 o st. V RT-93251-1 05L '
- M RT-93251-3 50.O _ d RT-93251-4 , o, I d RT-93251-5 . ? o.I V RT-93251-6 1 M
RT-93251-7 '('j- c.I-of_ .,_' .,,,,3I RT-93251-8 (g_ . _,,__,,3(,, ii RT-93251-9 6e <
- 7. hl RT-93252-1 i OI V RT-93252-2 o. f J RT-93252-4 0.1 ___ V ,.s RT-93252-4 . o.t V RT-93252-7 !
a# '
< 4 d
RIA-79511 , J 0.# A/ METER 0RLOGICAL DATA WIND SPEED , i *S/d MPE . ; WIND DIREC:' ION .., G81_,,210 , DEGREES PLUME DEVIATIW / 'G - SIGNA TEETA 4 i 2. O 'AX3REES s DIFFERENTIALTEMPEhTORE >
+.. T 6 ~ DEGREES F 'i' O L'
* ? 4 Value corresponds tri;the. PC'tV area channede Kher four channels arc s1
'\ l 30 cys.' Ii t d
** Value correspJDdi[to a 15 minute build-up of M: tin, ty. Build-up starta at the spec!fid scenario / clock time,. .
. _ _ _ _- -_ _- __- _ -__- __--_N
_ El
PRIMARY AUXILIARIES n () BOARD I-01 GAS WASTE SYSTEM 63 Normal LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HEL1UM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal BOARD I-02 HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /f PSIG High Pressure Bottles AstT~ PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow (/4D GPM BUDW Header Pressure acMRC PSIG HELIUM CIRCULATORS SYSTEM 21 Normal g- BOARD I-03 - (> REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position /AF~ INCHES Runback group positions 2A, rod #2 /9o INCHES rod #4 /99 INCHES rod #6 /FO- INCHES 4F, rod #25 / 90 INCHES rod #31 / 90 INCHES i rod #37 /90 INCHES i Flux Controller position +/- O % Reserve Shutdown Material A/O'ran4/ ST ATUS
\ , ,
,4
( o e. f i y _sms I^ 4
BOARD I-05 ('
-} HYDRAULIC OIL STEAM WATER DUMP TANK SYSTEM 91 SYSTEM 22 Normal Loop Selected 42 1 or 2
. Pressure o PSIG Temperature //5 d eg F Level 23 INCHES Radiation 20-vo mr/hr HELIUM CIRCULATORS SYSTEM 21 Normaz NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR.
THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06 EMERGENCY FEEDWATER PRESSURE cyar$ PSIG () BOILER FEED PUMPS A Speed 4530 RPM l A Flow 20pr lbs/hr ' B Status at on/off B Flow r.sx# lbs/hr C Speed 6( W RPM C Flow t75ber ibs/hr l CONDENSATE SYSTEM 31 Normal MISCELLANEOUS } Bypass Flash Tank tro PSIG . t HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal () SERVICE AIR SYSTEM 82 Normal
i BOARD I-10 PLANT PROTECTIVE SYSTEM RI BUILDING TEMPERATURE-HIGh BAY 100 Ag9 des F BAY 200 /02 deg F BAY 300 /09/deg F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 </ mr/hr Bay 1100 </ mr/hr Bay 1000 e/ mr/hr Loop 2 Bay 600 e/ mr/hr Bay 500 / mr/hr Bay 400 /.6~ ar/hr MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-13 PENETRATION INTERSPACE dP _i PSID RX BUILDING SUMP DISCHARGE FLOW ;(A2 GPM BOARD I-15 RI STACK FLOW 158dDACFM RX BUILDING / AMBIENT dP -0.J6~ P S I D BOARD I-7507X CONTROL ROOM TEMPERATURE 4%7 deg F 480V ROOM TEMPERATURE 8f deg F
FOSAVEI '87 Q
- b. OVERALL PLA.NT PARAMETERS Scenario time Ma Clock time _ 043o Rx Power /'do*/I Turbine Generator Load No MW PRIMARY COOLANT PRESSURE 490 PSIA TEMPERATURE !
Circulator Inlet 9%t des F Core Outlet /vsy des F HELIUM FLOW Loop 1 Afr/o' lb s /h r , Loop 2 /, 7 t a
- l b s / h r '
TOTAL usM* lbs/hr CIRCULATOR SPEED Circulator A 9/SS RPM Circulator B 94/o RPM Circulator C 9/11 RPM Circulator D 9/fo RPM MOISTURE (DEW POINT) ME-9306 /-r> deg F
, ME-9307 _ <--51 deg F SECONDARY COOLANT FEEDWATER FLOW Loop 1 4/r/s'1bs/hr Loop 2 /.p2x461bs/hr TOTAL ragm61bs/hr MAIN STEAM Loop 1 Pressure .PJGo PSIG Temperature 9Y des F Loop 2 Pressure enz PSIG Temperature /o% deg F HOT REHEAT Loop 1 Pressure 44r PSIG q Temperature /ooa des F Loop 2 Pressure 403 PSIG Temperature /00s. deg F COLD REHEAT !
Loop 1 Pressure //'I PSIG Temperature 47r deg F Loop 2 Pressure &7 PSIG Temperature 67T deg F O
RADIATION MONITURS SCENARIO TIME oo. A o PROCESS MWITTELS . CLOCE TIME o(,:So NUMBER SENSITIVITY VALUE ALARMING (Y/N) RT-4801 2.6E-10 ** Io E+l CPM M RT-4802 1.2E-10 _ ** I.O E +i CPM N RT-4803 2.5E-8 1. o E +1 CPM- Al RT-6212 2.2E-8 _ I.o E +f _ CPM -
,J .
RT-6213 2.2E-8 f.o E +4 , CPM N l RT-7312 - 2.3E- 8 *(PGV) 3.o E +1 CPM M l RT-7324-1 2.8E-8 4. o E t.I CPM Al RT-7324-2 8.9E-7 1.0 EI CPM Al RT-7325-1 00S 008 OOS RT-7325-2 003 003 005 RT-73437-1 4.6E-10 ** l.o E +f CPM Al RT-73437-2 005 008 005 l RT-9301 2.3E-8 S. 5 E +f CPt4 M RT-93252-12 N/A f. O E +0 mr/hr AI AREA MONITURS NUMBER VALUE ALARMING (ar/hr) (Y/N) RT-93250-1 c. I n/ RT-93250-2 c.I Al RT-93230-3 5o il RT-93250-4 c.I J O RT-93250-5 RT-93250-8 RT-93250-13 O.I o.I 0./ ___ Al d M RT-93250-14 0 SL. V RT-93251-1 05L Al RT-93251-3 S0. O d RT-93251-4 o, I d RT-93251-5 . o.1 _ Al RT-93251-6 c.i M RT-93251-7 o.I u RT-93251-8 0l ~ A/ RT-93251-9 0i d RT-93252-1 Of V RT-93252-2 o.I d RT-93252-4 0.1 M RT-93252-6 oi V RT-93252-7 o# V RIA-79511 0.# A/ METEROLOGICAL DATA WIND SPEED 5.0 MPE . WIND DIRECTI M ' FRW 270 DEGREES PLUME DEVIATIW/ SIGMA TIETA 2. O DEGREES DIFFERENTIAL TEMPERATURE + 4.0 DEGREES T O
- Value corresponds to the PCRV area channel. Other four channels are 30 cys.
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
PRIMARY AUXILIARIES BOARD I-01 l GAS WASTE S Y-S T E M 6 3 Normal l LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal BOARD I-02_ HELIUM STORAGE SYSTEM 24 Low Pressure Bcttles /F PSIG High Pressure Bottles /o+dF PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow e/.ro GPM BUBW Header Pressure _ sons- PSIG HELIUM CIRCULATORS SYSTEM 21 Normal BOARD I-03 REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position //dF INCHES { Runback group positions 2A, rod #2 / Fa INCHES rod #4 /pa INCHES rod #6 /fe INCHES 4F, rod #25 /90 INCHES rod #31 /fd INCHES rod #37 /70 INCHES Flux Controller position +/- O % Reserve Shutdown Material Atwassf STATUS O
BOARD I-05 l {) HYDRAULIC 0IL SYSTEM 91 Normal STEAM WATER DUMP TANK SYSTEM 22 l Loop Selected A ,L or 2 L Pressure o PSIG Temperature //Jr deg F Level. a3 INCHES j Radiation 40-W6 mr/hr j 1 HELIUM CIRCULATORS SYSTEM :21 Normal ) NOTE LOW RANGE dP INDICATIONS WILL BE , OFF SCALE DURING OPERATION AND LOW TO l "0" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO L EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06 EMERGENCY'FEEDWATER PRESSURE 309'O PSIG () BOILER FEED PUMPS A Speed 4dasRPM A Flow 7/ gar Ibs/hr B Status ens on/off B Flow Asx/a51bs/hr C Speed 449r- RPM C Flcw <2sx # 1bs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS. Bypass Flash Tank 4 80 PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal () SERVICE AIR SYSTEM 82 Normal
i l BOARD I-10 PLANT PROTECTIVE SYSTEM [) RX BUILDING TEMPERATURE-HIGH BAY 100 s69 deg F BAY 200 se;t d eg F BAY 300 ./ # deg F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 z/ ar/hr Bay 1100 e/ mr/hr Bay 1000 t/ mr/hr Loop 2 Bay 600 ac/ mr/hr Bay 500 / mr/hr Bay 400 e5' mr/hr MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-13 PENETRATION INTERSPACE dP 4/ PSID RX BUILDING SUMP DISCHARGE FLOW 4/o GPM BOARD I-15 RX STACK-FLOW .3Zec0 ACFM RX EUILDING/ AMBIENT dP -aed PSID BOARD I-7507X CONTROL ROOM TEMPERATURE 47 deg F 480V ROOM TEMPERATURE 8I deg F l O
4 FOSAVEI '87 A Scenario time M d OVERALL PLANT PARAMETERS Clock time O.W T
- Rx Power Alf%
Turbine Generator-Load Mo MW PRIMARY COOLANT PRESSURE ?>o PSIA TEMPERATURE
. Circulator Inlet W# des F Core Outlet N#7 des F HELIUM FLOW Loop 1 Mx4' lbs/hr Loop 2 /,7x/o 6 lbs/hr TOTAL ,?.vx/ab lbs/hr CIRCULATOR. SPEED Circulator A 9/r7 RPM-Circulator B 92/o RPM Circulator C 1/Af RPM Circulator D 9/90 RPM
- MOISTURE'(DEW POINT)
ME-9306 Z-s*/ des F ME-9307. <-s7 des F SECONDARY COOLANT FEEDWATER FLOW Loop 1 1/x/0 6 lbs/hr Loop 2 / 224/06lbs/hr TOTAL 3,3x/o4 lbs/hr MAIN STEAM Loop 1 Pressure #S20 PSIG Temperature 99ff _d e g F Loop 2 Pressure som PSIG Temperature /non , des F HOT REHEAT Loop 1 Pressure 4 # PSIG
. Temperature een des F Loop 2 Pressure 6ol PSIG Temperature /oor des F COLD REHEAT Loop 1 Pressure 4/7 PSIG Temperature F/8 des F Loop 2 Pressure 6/7 PSIG Temperature LOA deg F LO
RADIATION MONITORS SCENARIO TIME OO/4 f PROCESS MONITORS CLOCE TIME o t_ r y r NUMBER SENSITIVITY VAIM ALARMING (Y/N) RT-4401 2.6E-10 ** l.O E +f CPM M RT-4802 1'.2E-10 ** f . O E +. t - CPM AJ RT-4803 2.5E-8 1.0 E +l CPM N RT-6212 _ 2.2E-8 I.o E +i CPM _ N RT-6213 2.2E-8 f.o E ,1 CPM Al RT-7312 _,_,2.3E-8 *(PCRV/ 3. O E +.1 CPM 4 RT-7324-1 2.8E-8 4 o E et CPM U - RT-7324-2 ___8.9E-7 f, o E ,.I CPM Al- ! RT-7325-1 003 008 003 RT-7325-2 008 008 ,,_ 003 . RT-73437-1 4.6E-10 ** f.o E al CPM Al i RT-73437-2 OOS 008 005 RT-9301 2.3E-6 (,. 6 - E + S CPM - Al RT-93252-12 -N/A l.0 E+0 ar/hr A/ i AREA M WITMS NUMBER VALUE ALARMING (ar/hr) (Y/N) RT-93250-1 o. I d RT-93250-2 o.1 # RT-93250-3 5o il RT-93250-4 o.I J RT-93250-5 O.I M O- RT-93250-8 o.I d j RT-93250-13 0./ d i RT-93250-14 o st. V RT-93251-1 o5L M RT-93251-3 50.o d RT-93251-4 o, I d RT-93251-5 o.I M ; RT-93251-6 _,, o.I M RT-93251-7 af u i RT-93251-8 0.1 d RT-93251-9 o1 J RT-93252-1 Of ~ M RT-93252-2 o.I d - RT-93252-4 _ o .1 V I RT-93252-6 al V RT-93252-7 o# V ' RIA-79511 0.# A/ METER 0RLOGICAL DATA i' WIND SPEED 5,0 MPH , WIND DIRECTION FROM 270 DEGREES PLUME DEVIATIW/ SIGMA TEETA 2. O DEGREES DIFFERENTIAL TEMPERATURE +. 4 . 0 DEGREES T O
- Value corresponds to the PCRV area channel. Other four channels are 30 cpm.
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
j
.i
4
~
PRIMARY AUXILIARIES L BOARD I-01 GAS WASTE SYSTEM 63 Normal LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM. SYSTEM 23 Normal i LN-2 SYSTEM 25 Normal BOARD I-02 i HELIUM STORAGE SYSTEM 24 Low Pressure Bottles
. /9 PSIG High Pressure Bottles / der PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow e/fo GPM BUBW Header Pressure ,go &C PSIG HELIUM-CIRCULATORS SYSTEM 21 Normal
.f- BOARD I-03_
REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position /V5' INCHES Runback group positions 2A, rod #2 /90 INCHES rod #4 /90 INCHES rod #6 /90 INCHES 4F, rod #25 /91 INCHES rod #31 /9b INCHES rod #37 /90 INCHES Flux Controller position +/- O % Reserve Shutdown Material 7dbwa/ STATUS \ (' h v
BOARD I-05 (} HYDRAULIC OIL STEAM WATER DUMP TANK SYSTEM 91 SYSTEM 22 Normal Loop Selected 42 1 or 2 Pressure o PSIG Temperature //5' deg F Level 473 INCHES Radiation Ji-v>mr/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFOP.MATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06 EMERGENCY FEEDWATER PRESSURE .7665' PSIG l BOILER FEED PUMPS A Speed 4aw/v RPM A Flow 9mf lbs/hr B Status oro on/off B Flow 95s/orlbs/hr ! C Speed 699_f RPM ; C Flow 4/o37 lbs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Tank 4fD PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal ; () SERVICE AIR SYSTEM 82 Normal i { 1
._- _____-______ U
I BOARD I-10 PLANT PROTECTIVE SYSTEM
\ RX BUILDING TEMPERATURE-HIGH l'
BAY 100 49 des F l BAY 200 .c deg F BAY 300 j, v des F REHEAT ACTIVITY MONITORS L~oop 1 Bay 1200 e / mr/hr 2 Bay 1100 4/ mr/hr Bay 1000 e/ mr/hr Loop.2. Bay 600 c/ mr/hr 1 Bay 500 e ar/hr Bay 400 4JP ar/hr i MOISTURE MONITORS (DEW POINT) Normal : MAIN STEAM LOOP dP- Normal BUFF SEAL MALFUNCTION Normal BOARD I-13 , PENETRATION INTERSPACE dP 4' PSID RX BUILDING SUMP DISCHARGE FLOW </9 GPM ( BOARD I-15 RX STACK FLOW Jo,WOACFM RX BUILDING / AMBIENT dP -4.2TPSID BOARD.I-7507X CONTROL ROOM TEMPERATURE 49 deg F 480V ROOM TEMPERATURE 87 deg F O
FOSAVEI '87 Scenario time /_ q F N-C/ OVERALL PLANT PARAMETERS Clock time c9ao Rx Power /d C Turbine Generator Load c wo MW PRIMARY COOLANT PRESSURE /a90 PSIA TEMPERATURE Circulator Inlet 'KO deg F Core Outlet N W deg F HELIUM FLOW Loop 1 />x/db ibs/hr Loop 2 /,5x/o k Ib s /hr TOTAL C3.'A/9# 1 b s / h r CIRCULATOR SPEED Circulator A 9/55 RPM Circulator B @/O RPM Circulator C 9/Ef RPM Circulator D 9/90 RPM MOISTURE (DEW POINT) ME-9306 <-s> degF ME-9307 <-57 deg F SECONDARY COOLANT FEEDWATER FLOW Loop 1 //x/ok1bs/hr Loop 2 /.12x/00lbs/hr TOTAL p. 3 X /d kib s / h r MAIN STEAM Loop 1 Pressure M.2 0 PSIG Temperature 998 deg F Loop 2 Pressure .,711d PSIG Temperature /002 deg F HOT REHEAT Loop 1 Pressure 4df PSIG Temperature /002degF Loop 2 Pressure /, 03 PSIG Temperature /o0% deg F COLD REHEAT Loop 1 Pressure 6/7 PSIG Temperature 60g deg F Loop 2 Pressure 4/7 / PSIG Temperature 69 7 deg F O
i RADIATION MONITORS SCENARIO TIME _ 01:00 PROCESS MWIITORS CLOCE TIME _ 07 oo NUMBER- SENSITIVITY VALUE ALARMING I (Y/N) RT-4801 2.6E-10 **- f.O E +f CPM M-RT-4802 1.2E-10 ** l. o E +i CPM M RT-4803 2.5E-8 l. O E eI CPM M RT-6212 2.2E-8 I, o E 4 CPM M I RT-6213 2.2E-8 f.o E +4 CPM M RT-7312 2.3E-8 *(PCRV) 3, O E + f CPM M RT-7324-1 2.8E-8 _,__ 4.o E +1 CPM M ' RT-7324 8.9E-7 __ . l.O E M , CPM rJ RT-7325-1 OOS 008 003 RT-7325-2 OOS 005 003 RT-73437-1 4.6E-10 ** I, O E + l CPM M RT-73437-2 OOS 003 005 RT-9301 _2.3E-8 __, 7. o E + 5 CPM kJ RT-93252-12 N/A 1. 0 E + o ar/hr AJ AREA MONITORS NUMBER VALUE ALARMING (ar/hr) (Y/N) RT-93250-1 o. I V RT-93250-2 o. I - M RT-93250-3 5. o . d RT-93250-4 c.i J RT-93250-5 O.I M \' - RT-93250-4 c.I Al RT-93250-13 C./ J RT-93250-14 o st. V RT-93251 o5L M RT-93251-3 50.O V RT-93251-4 o. I J RT-93251-5 o.8 V RT-93251-6 o.I ~-- RT-93251-7 o.I d RT-93251-8 O1 J RT-93251-9 o1 J RT-93252-1 oI V RT-93252-2 o.I kl RT-93252-4 0.1 V RT-93252-6 oI V RT-93252-7 oi V RIA-79511 0.# A/ METER 0RLOGICAL DATA WIND SPEED 5.0 MPE . WIND DIRECTIGf 19 08 270 DEGREES PLUME DIVIATI3f/ SIGMA TETA 2. O DEGREES DIFFERENTIAL TEMPERATURE + 4.0 DEGREES T O
- Value corresponds to the PCRV area channel.
30 cym. Other four channels are
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
PRIMARY AUXILIARIES q Q BOARD I-01 GAS WASTE SYSTEM 63 Normal LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal BOARD I-02 HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /9 PSIG High Pressure Bottles M 5' PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow NSo GPM BUBW Header Pressure cm45' PSIG HELIUM CIRCULATORS SYSTEM 21 Normal BOARD I-03_ (3 REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position /4~ INCHES Runback group positions 2A, rod #2 / 90 INCHES rod #4 /90 INCHES rod #6 /90 INCHES 4F, rod #25 Mo INCHES rod #31 190 INCHES rod #37 /90 INCHES Flux Controller position +/- O % Reserve Shutdown Material >f % f STATUS O
BOARD I-05 (G,) HYDRAULIC OIL SYSTEM 91 Normal STEAM WATER DUMP TANK SYSTEM 22 Loop Selected 47 1 or 2 Pressure C PSIG Temperature //5" deg F 4 Level a23 INCHES Radiation j20-Mo mr/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06 EMERGENCY FEEDWATER PRESSURE entVbPSIG BOILER FEED PUMPS A Speed (,500 RPM A Flow 7xayr lbs/hr B Status eML on/off B Flow R.S(m8r1bs/hr C Speed '656M RPM C Flow 75(e5 lbs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Tank _4fd PSIG < HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal i MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal c:) SERV 1cE A1R SYSTEM e2 No,ma1 J
BOARD I-10 PLANT PROTECTIVE SYSTEM ('3' RI BUILDING TEMPERATURE-HIGH BAY 100 /t6rdeg F BAY 200 /cp d eg F BAY 300 /o5/deg F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 4/ mr/hr Bay 1100 </ mr/hr Bay 1000 </ mr/hr Loop 2 Bay 600 </ mr/hr Bay 500 / mr/hr , Bay 400 e r mr/hr MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION -Normal BOARD I-13 PENETRATION INTERSPACE dP </' PS I D RX BUILDING SUMP DISCHARGE FLOW <n/d GPM ( BOARD I-15 RX STACK FLOW C3dd%KCFM RX BUILDING / AMBIENT dP -o,25 PSID BOARD I-7507X CONTROL ROOM TEMPERATURE 407 deg F 480V ROOM TEMPERATURE 88 deg F
FOSAVEI '87
.e Scenario time 75
(, . OVERALL PLANT PARAMETERS Clock time 07/( Rx Power /00 Turbine Generator Load 3Yo MW PRIMARY COOLANT PRESSURE /p9d PSIA TEMPERATURE Circulator Inlet 970 deg F Core Outlet /WC deg F HELIUM FLOW Loop 1 A 9x/d 0 lbs/hr Loop 2 /,W /d* lbs/hr TOTAL 3,vx /o* lbs/hr CIRCULATOR SPEED Circulator A 9/sT RPM Circulator B 9s/0 RPM Circulator C 9/Ps RPM Circulator D 9/90 RPM MOISTURE (DEW POINT) ME-9306 <-57 deg F ME-9307 <-57 deg F k SECONDARY COOLANT FEEDWATER FLOW Loop 1 A/x/o G lbs/hr ! Loop 2 /2rxee 1bs/hr l TOTAL 3 ._2 x / W l b s / h r l MAIN STEAM Loop 1 Pressure .X20 PSIG q Temperature 999 deg F J Loop 2 Pressure > s t ?- PSIG Temperature /otra d eg F HOT REHEAT Loop 1 Pressure L f PSIG
. Temperature / vo s- d e s F ;
Loop 2' Pressure soA PSIG Temperature /vo v- deg F COLD REHEAT Loop 1 Pressure 4/7 PSIG Temperature G?Y deg F Loop 2 Pressure 4/7 PSIG , Temperature F/ deg F l O l _ _ - _ _ - - _ _ _ _ _ _ 1
RADIATION MONITORS SCENARIO TIME OI! I ST PROCESS MONI'IURS CLOCK TIME ovirr NUMBER SENSITIVITY VALUE ALARMING (Y/N) RT-4801 2.6E-10 ** l.o E ei CPM M - RT-4802 ** M 1.2E-10 _ 1. o E *t CPM RT-4803 2.5E-8 1. o E 4. I CPM N RT-6212 2.2E-8 I.0 E +( CPM N RT-6213 2.2E-8 f.o E +1 CPM M RT-7312 2.3E-8 *(PCRV) 3. O E + 1 CPM _ M RT-7324-1 2.8E-8 4. o E W CPM M - RT-7324-2 8.9E-7 f. o E +.1 CPM M RT-7325-1 OOS 00S OOS RT-7325-2 OOS OOS 00S RT-73437-1 4.6E-10 _ ** f. O E +1 CPM bl RT-73437-2 OOS 005 005 RT-9301 2.3E-8 7. 6 E +5 CPM hl RT-93252-12 N/A 1. O E
- O mr/hr M AREA MONITORS NUMBER VALUE ALARMING (mr/hr) (Y/N)
RT-93250-1 c. I d RT-93250-2 o .1 # RT-93250-3 5o d RT-93250-4 0.1 d O RT-93250-5 RT-93250-4 O.I o.I Al Al RT-93250-13 0./ J RT-93250-14 o 5L. V RT-93251-1 05L M RT-93251-3 So. O d RT-93251-4 o, I J RT-93251-5 o.I M RT-93251-6 c.I M RT-93251-7 o.I J RT-93251-8 0. I J RT-93251-9 o. I d RT-93252-1 Ol V RT-93252-2 O.f J RT-93252-4 0.1 M l RT-93252-6 o.I d RT-93252-7 o# V RIA-79511 0.# A/ METER 0RLOGICAL DATA WIND SPEED 5. 0 _ MPH . WIND DIRECTION FROM 270 DEGREES PLUME DEVIATION / SIGNA THETA 2. O DEGREES DIFFERENTIAL TEMPERATURE + 4.0 DEGREES F O
- Value corresponds to the PCRV area channel. Other four channels are 30 cpa.
** Value corresponds to a 15 minute build-up of activity. Build-up starts at t.be specified scenario / clock time.
r PRIMARY AUXILIARIES 7 BOARD I-01 i GAS WASTE SYSTEM 63 Normal LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal ! LN-2 SYSTEM 25 Normal BOARD I-02 HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /7 PSIG High Pressure Bottles A> <6 PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow s/r0 GPM BUBW Header Pressure Joar PSIG J HELIUM CIRCULATORS SYSTEM 21 Normal BOARD I-03_ REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position // f' INCHES Runback group positions 2A, rod #2 /90 INCHES rod #4 /h/ INCHES rod #6 /90 INCHES 4F, rod #25 /10 INCHES rod #31 / 90 INCHES rod #37 /90 INCHES Flux Controller position +/- O % Reserve Shutdown Material 7[uya;f STATUS O V
1 i BOARD I-05 I rN is ) HYDRAULIC.0IL SYSTEM 91 Normal STEAM WATER DUMP TANK SYSTEM zi I Loop Selected ef 1 or 2 Pressure o PSIG Temperature //f deg F j Level 43 INCHES l Radiation - So-vb mr/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO ! EVALUATE FOR OPEN CIRCUALTOR DISCHARGE l VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06
,s EMERGENCY FEEDWATER PRESSURE $3MI PSIG 4
BOILER FEED PUMPS A Speed 4rav RPM A Flow 9,rr lbs/hr B Status r- on/off B Flow P. f r ior Ibs/hr C Speed 49f RPM C Flow 2 Tx orlbs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypasa Flash Tank 47V PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal l
) SERVICE AIR SYSTEM 82 Normal
BOARD I-10 () PLANT PROTECTIVE SYSTEM RI BUILDING TEMPERATURE-HIGH BAT 100 /d9 des F BAY 200 m2 des F BAY 300 /0V des F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 4/ mr/hr Bay 1100 c/ mr/hr Bay 1000 4/ mr/hr Loop 2 Bay 600 z/ mr/hr Bay 500 / mr/hr Bay 400 ei ar/hr MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-13 PENETRATION INTERSPACE dP 5/ PSID
- RI BUILDING SUMP DISCHARGE FLOW </o GPM i
BOARD I-15 RX STACK FLOW 31000 ACFM RX BUILDING / AMBIENT dP -o25 PSID BOARD I-7507X CONTROL ROOM TEMPERATURE G7 deg F 480V ROOM TEMPERATURE 67 deg F
4-FOSAVEI '87 Scenario time fd OVERALL PLANT PARAMETERS Clock time 0?30 Rx Power /00 % Turbine Generator Load avo MW PRIMARY COOLANT PRESSURE #fo PSIA 3 TEMPERATURE i Circulator Inlet Pvt deg F j Core Outlet /W5 des F HELIUM FLOW Loop 1 A7"0' 1b s /h r ' Loop 2 /7x/o*1bs/hr TOTAL 3.(x/oO lbs/hr 5 CIRCULATOR SPEED Circulator A 9/S( RPM Circulator B *p/ a RPM Circulator C 9M RPM Circulator D 4/9a RPM MOISTURE (DEW POINT) ME-9306 e-57 deg F ME-9307 c- 57 deg F SECONDARY COOLANT FEEDWATER FLOW Loop 1 /. / nob lbs/hr Loop 2 /.ssa ro6 lbs/hr TOTAL p.3 x a v lbs/hr MAIN STEAM Loop 1 Pressure asso PSIG Temperature 997 deg F Loop 2 Pressure eStt PSIG Temperature Aron deg F HOT REHEAT Loop 1 Pressure 6df PSIG
, Temperature /cre a des F Loop 2' Pressure 40) PSIG Temperature na2 deg F COLD REHEAT Loop 1 Pressure 4/7 PSIG Temperature G77 des F Loop 2 Pressure 6/7 PSIG Temperature 67V deg F O
_J
RADIATION MC3tITtRS SCENARIO TIME oi! 30 PROCESS MONITORS CLOCE TIME o 1: 30 NUMBEE*M~ SENSITIVITY VALUE ALARMING (Y/N) RT-4801 2.6E-10 ** 1. O E +l CPM M l RT-4802 ___1.2E-10 ** s. o E +l CPM el RT-4803 ___2.5E-8 1. O E + i CPM N RT-6212 2.2E-8 ,___ I.o E +i CPM M RT-6213 2.2E-8 f.o E +1 CPM M RT-7312 2.3E-8 *(PCRV) 3.o E +1 CPM M RT-7324-1 2.8E-8 4.o E +1 CPM Al RT-7324-2 8.9E-7 f.o E +i CPM N RT-7325-1 OOS 00S OOS RT-7325-2 OOS OOS 003 RT-73437-1 _,__4.6E-10 ** t.o E +l CPM M RT-73437-2 003 00s 00s RT-9301 2.3E-8 8.o E +.5 CPM M RT-93252-12 N/A b o E +o ar/hr M AREA MONITORS NUMBER VALUE ALARMING (ar/hr) (Y/N)- RT-93250-1 o. f kl RT-93250-2 o.I Al RT-93250-3 so Al RT-93250-4 c.I d 9 RT-93250-5 RT-93250-8 RT-93250-13 O.I o.t M M 0.I d RT-93250-14 o 5L. V RT-93251-1 05l. Al RT-93251-3 50.O d RT-93251-4 o, I d RT-93251-5 o.# Al RT-93251-6 c.I Al RT-93251-7 o.I J RT-93251-8 0.( J RT-93251-9 o. I d RT-93252-1 oI V RT-93252-2 _ O.I J RT-93252 o./ V RT-93252-6 o.I V RT-93252-7 ot V RIA-79511 0.s d METER 0RLOGICAL DATA WIND SPEED F. 0 MPH , WIND DIRECTION FRQt 270 DEGREES PLUME DEVIATICBl/ SIGMA TFETA 2. O DEGREES DIFFERENTIAL TEMPERATURE + 4. 0 DEGREES T O
- Value corresponds to the PCRV area channel. Other four channels are 30 cpe.
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
i PRIMARY AUXILIARIES l BOARD I-01 GAS WASTE SYSTEM 63 Normal l LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Norms 1 PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal BOARD I-02 HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /f PSIG High Pressure Bottles /o+s' PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow e/r0 GPM BUBW Header Pressure Joas" PSIG HELIUM CIRCULATORS SYSTEM 21 Normal BOARD I-03_
-O REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position //5' INCHES Runback group positions 2A, rod #2 /90 INCHES -
rod #4 /90 INCHES rod #6 /?s INCHES 4F, rod #25 / 99 INCHES rod #31 /90 INCHES rod #37 /90 INCHES Flux Controller position +/- O % Reserve Shutdown Material 7/cuuof __ STATUS O
o BOARD I-05 () HYDRAULIC OIL STEAM WATER DUMP TANK SYSTEM 91 SYSTEM 22 Normal Loop Selected S 1 or 2 Pressure o PSIG Temperature //6 deg F Level >> INCHES Radiation ag:Et_ar/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. , MAIN TURBINE SYSTEM 51 Normal BOARD I-06 EMERGENCY FEEDWATER PRESSURE Jof'o PSIG () LOILER FEED PUMPS A Speed 46#O RPM A Flow 74 /or lbs/hr 3 Status ons on/off 3 Flow Esper ibs /hr C Speed _6, Q RPM C Flow 7fx M 1bs/hr CONDEN!iATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Tank 4go PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal I I FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal () SERVICE AIR SYSTEM 82 Normal l
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"" j PLANT PROTECTIVE SYSTEM CG .
' t. ** 'e 6g R1 BUILDING TEMPERATURE-HIGH J BAY 100 4 Mf deg F , [
" BAY 200 ,
' ' l,
, , a 2- deg F * '
, BAY 300 . 's j _,/ov de g I'/ (Zy REKEA*ACTIVITYidNITORS
'/'
Loop 1 Bay 1100 *' <s
,,, 4 / O;/hr l j
l' Bay 1100 c/ mr/hr g 3 7 Tay 1000 ' 4/ er/hr 7x l ,'
' Loop 2 Bay 600 '
z/ 'ar/hr V '
/ Bay 500 / mr/hr <
D4; 400 *
'I _41_mr/hr ,\ -
u M0'ISTUREMONIT0dS(DEWPOINT) y ?f Ne'aal r j1 3 l t . + ! Ntirmal (s MAIN STL%M LOOF' dP '
! / ,
l s ..I 3.' % fi BUFF SE AL MALWYCTI0'.( , Normal *
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' ' ' , 'e BOARD I- d'. i #
~~. , j ?T q PENETRATION INTERSPACE dP ,? T,' PS10.. t
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- v .* t RI BUILDING SUMP DISCHARGE FLOW ( 's y _G PM / <- i I
14 6
'l BOARD I-15 r x, 9 RX W.fACK FLOW '
3d E ACFM , 1
. I.
RX 3 GILDING / AMBIENT dP -o.af PSID I 1 .' BOARD I-7507X # CC!1 TROL ROOM,TEMPERAT.URE 47 deg F ; N 1 l 480f ROOM TEMPERATURE *j - s W_d e g F ' \ 1
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- I y , ,. FOSAVEI '87 Q
- Scenario time /o f
. b ,,,
. OVERALL PLANT PARAMETERS Clock time or/w 4
Rx Power /oo#/ c Turbine Generator Load Mo MW PRIMARY COOLANT PRESSURE G90 PSIA TEMPERATURE Circulator Inlet N2, des F
! Core Outlet /W( des F
.,l HELIUM FLOW I Loop 1 A ?i/db ibs/hr
\ f'N
, Loop 2 /, % /061bs/hr
, s. l.I TOTAL 1 Fx/vtibs/hr
;\.
CIRCULATOR SPEED
., Circulator A 9/60 RPM
.'. , Circulator B 92 /0 RPM
! 9;cro RPM Circulator C Circulator D 9/90 RPM MOISTURE (DEW POINT)
ME-9306 4-s? deg F /,; ME-9307 e-c r 7 deg F
% SECONDARY COOLANT
.t I FEEDWATER FLOW Loop 1 / / </0fibs/hr i7 1 Loop 2 / m /s5 lbs/hr i TOTAL 43 </oT lbs/hr MAIN STEAM Loop 1 Pressure .4500 PSIG Temperature 999 deg F Loop 2 Pressure E s/ PSIG Temperature /voa deg F HOT REHEAT Loop 1 Pressure 40f PSIG
, Temperature n02 deg F Loop 2 Pressure /+1 PSIG T'emperature /oon deg F COLD REHEAT Loop 1 Pressure 6 /'7 PSIG !
Temperature c?7 deg F , Loop 2 Pressure C/'7 PSIG l Temperature 697 deg F n ;
p-RADIATION M(EtITtRS SCENARIO TIME oI:(iT PROCESS M(El! TORS C14CR TIME 07:us-NtBIBER SENSITIVITY -VALUE ALARMING (Y/N) RT-4801 2.6E-10 ** l.o E +4 CPM AJ RT-4802 1.28-10 ** I.O E +f CPM U RT-4803 2.5E-8 1 0 E #. I CPM. M RT-6212- 2.25-8 __,, I.o E +f CPM - M RT-6213 2.2E-4 __, l.o E +1 _, CPM U RT-7312 2.35-8 __, *(PCRV) 3. O E + f CPM u RT-7324 2.8E-8 4.O E +1 CPM L RT-7324-2 _ 4.9E-7 1. o E + l CPM N RT-7325-1 008 008 008 RT-7325-2 ~~~ 008 003 008 RT-734I7-1 4.6E-10 ** f.OE 41 CPM V RT-73437-2 008 003 003 RT-9301 2.3E-8 s . 5 E +.5 CPM d RT-93252-12 N/A 1. O E +0 ar/hr V AREA MONITORS NONBER VALUE ALARMING (ar/hr) (Y/N) RT-93250-1 c. I d RT-93250-2 o. i # RT-93250-3 . 5o d RT-93250-4 0. I J O RT-93250-5 RT-93250-4 RT-93250-13 o.I oI 0./ M d 4 RT-93250-14 o 50 M RT-93251-1 05L M RT-93251-3 50.o d RT-93251-4 o. I d RT-93251-5 o.I M RT-93251-6 c.I M RT-93251-7 ai d RT-93251-8 C. I d RT-93251-9 o. I J RT-93252-1 ol M RT-93252-2 c. I d RT-93252-4 o .1 __ M RT-93252-6 aI d RT-93252-7 o# V RIA-79511 0.s d METER (BLLOGICAL DATA WIND SPEED 5.0 MPE . WIND DIRECTI(Et 11ttat 2'70 DEGREES PLUME DEVIATION / SI(Bla TIETA 2.O Derruru DIFFERENTIAL TEMPERATURE + 4.0 DEGREES T O * ;'alue corresponds to the PCRV area channel. Other four channels are 30 cpe.
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
PRIMARY AUXILIARIES () BOARD I-01 GAS WASTE SY' STEM 63 Normal LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSYEM 23 Normal LN-2 SYSTEM 25 Normal BOARD I-02 HELIUM STORAGE SYSTEM 24 Low Pressure Bottles __ /9 PSIG High Pressure Bottles /oyf PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow 4/ro GPM BUBW Header Pressure 404r PSIG HELIUM CIRCULATORS SYSTEM 21 Normal BOARD I-03_' REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position //f INCHES Runback group positions 1 2A, rod #2 /90 INCHES rod #4 /90 INCHES rod #6 /90 INCHES 4F, rod #25 /90 ~~ INCHES ; rod #31 /90 INCHES rod #37 /90 INCHES Flux Controllar position +/- O % ' Reserve Shutdown Material 74ai, e1/ STATUS
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- _ _ l
BOARD I-05 () HYDRAULIC OIL SYSTEM 91 Normal STEAM WATER DUMP TANK SYSTEM 22 Loop Selected .7 1 or 2 Pressure a PSIG Temperature //f deg F Level ,73 INCHES Radiation E- 70 mr/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE JP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "O" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISLHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-05
, EMERGENCY FEEDWATER PRESSURE 20Vo PSIG /
(_/ BOILER FEED PUMPS A Speed CS&c RPM A Flow 9 10 s lbs/hr B Status es on/eff B Flow 3;x ,o r lbs/Tr C Speed 6v75 RFM C Flow ?sxio 5' lbs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Tank _ 4fD PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal
) SERVICE AIR SYSTEM 82 Normal 4
L I
BOARD I-10 g3 PLAHT PROTECTIVE SYSTEM
\j RI BUILDING TEMPERATURE-HIGH l
j BAT.100 /d? deg F ! BAY 200 /02 des F BAY 300 /or des F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 z/ mr/hr Bay 1100 4/ mr/hr Bay 1000 </ ~~ar/hr Loop 2 Bay 600 </ sr/hr Bay 500 / ar/hr Bay 400 zr ar/hr MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-13 PENETRATION INTERSPACE dP 9' PSID RI BUILDING SUMP DISCHARGE FLOW #/# GPH (-)
\_/ - BOARD I-15 i
RX STACK FLOW Jd.d5 ACFM RX BUILDING / AMBIENT dP -0 25'PSID BOARD I-7507X CONTROL ROOM TEMPERATURE 67 deg F 480V ROOM TEMPERATURE ?P deg F I O.
POSAVEX 87 FOR: REACTOR OPERATOR MESSAGE NO. n TIME: nann LOCATION: costnot Room i i XXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS MESSAGE: There is a loud noise that persists for about 4 minutes. The reactor trips and SLRDIS actuates. SLRDIS indicates a Loop 2 failure. Loop 2 circulator bypass valve, PV-2244, and its isolation, HV-2242, will not close. (j'i \ Both cold reheat lines and the Loop 2 hot reheat iniicate atmospheric pressure. i l 1 { XXXXXXXXXXX)' XXXXXXXXXXXXXXXXXXXX THIS .lS A DRILL XXXXXXXXXXXXXXXXXXXXXXXXX)O(XXXXXXXXXXXXXXXXXXXXXXXXXX i 1
1 *'g FOSAVEI '87
/~ ' Scenario time #n OVERALL PLA.NT PARAMETERS Clock time ce m Rx Power <#COdAf Turbina Generator Load O MW PRIMARY COOLANT PRESSURE '790 PSIA TEMPERATURE Circulator Inlet W O des F Core Outlet / M c deg F HELIUM FLOW Loop i O lbc/hr ,
Loop 2 O lbs/hr i TOTAL O lbs/hr CIRCULATOR SPEED Circulator A 4300 RPM Circulator B <20c RPM Circulator C <300 RPM Circulator D <300 RPM MOISTURE (DEW POINT) ME-9306 4-57 deg F q ME-9307 _4-57 deg F SECONDARY COOLANT FEEDWATER FLOW Loop 1 O lbs/hr Loop 2 O lbs/hr TOTAL O lbs/hr MAIN STEAM Loop 1 Pressure Mo PSIG Temperature /o vodeg F Loop 2 Pressure J M:n PSIG Temperature /4tso deg F HOT REHEAT Loop 1 Pressure r1co PSIG
, Temperature MVO deg F Loop 2 Pressure o PSIG Temperature /03o d6g F COLD REHEAT Loop 1 Pressure o PSIG Temperature 4 76~ des F Loop 2 Pressure o PSIG Temperature 47f deg F O
RADIATION MONITORS SCENARIO TIME o 2:0o PROCESS M(BfITGtS CLOCK TIME 08:o0 NtBIBER" SENSITIVITY VALUE ALARMING (Y/N). RT-4801 2.6E-10 ** 1. O E +1 CPM M l
!AT 4802 1.2E-10 ** 1. o E +1 CPM Al RT-4803 2.5E-8 4. o E +.1 CPM M RT-6212 2.2E-8 I.o E +f CPM -
M RT-6213 ' _ 2.2E-8 __ l.o E +f CPM d-RT-7312 2.3E-8 *(PCRV) 3. 0 E + 1 CPM N RT-7324-1 2.8E-8 4t o E +. I CPM M RT-7324-2 ,,,_,,,8. 9 E-7 t. o E 4.1 CPM . O RT-7325-1 008 , , , , , _ 005 00S . RT-7325-2 003 008 005 RT-73437-1 4. 6E-10,_,,,, ** l.0 E 4. I CPM N RT-73437-2 00S 005 OOS RT-93H 2.3E-8 9.o E + 5 CPM M RT-93252-12 N/A 1. o E + 0 ar/hr d ARIA MCBf! TORS NUMBER VALUE ALARMING. (ar/hr) (Y/N) RT-93250-1 0. f hl RT-93250-2 -Ql M RT-93250-3 5o d RT-93250-4 c.I d RT-93250-5 O.( M RT-93250-8 c.r hl RT-93250-13 0./ J ,, RT-93250-14 O st. V i RT-93251-1 05L M ! RT-93251-3 50.o _ d i RT-93251-4 o. f d RT-93251-5 o.8 ___ V RT-93251-6 0 I- N RT-93251-7 d.I u RT-93251-8 0.1 V RT-93251-9 ~~ oI d RT-93252-1 0.I M RT-93252-2 O.f J RT-93252-4 o.f M RT-93252-6 oI A/ RT-93252-7 ol -
-- V RIA-79511 0.1 A/
METER 0RLOGICAL DATA WIND SPEED 5.0 MPE , WIND DIRECTI M FROM _,. 2 70 DEGREES PLUME DEVIATIW/ SIGNA TIETA 2. O DEGREES DIFFERENTIAL TEMPERATURE +. 4. 0 DEGREES F O
- Value correds to the PCRV area channel. Other fore channels are 30 cym.
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
l
PRIMARY AUXILIARIES BOARD I-01 l GAS WASTE SYSTEM 63 Normal ] LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal-PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal
.._ ROARD I-02 HELIUM STORAGE. SYSTEM 24 Low Pressure Bottles /9 PSIG High Pressure Bottles /o w PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow e/ro GPM s BUBW Header Pressure _Sm e PSIG 3
HELIUM CIRCULATORS SYSTEM 21 Normal BOARD I-03_ REACTOR CONTROL SYSTEM 12 Regulating Rod'(1) position O INCHES Runback group positions 2A, rod #2 0 ' INCHES rod #4 c) INCHES-rod #6 0 INCHES 4F, rod #25 o INCHES rod #31 O INCHES rod #37 O INCHES Flux Controller position +/- "/4 % Reserve Shutdown Material 7f%ed STATUS
BOARD I-05 (). HYDRAULIC OIL SYSTEM 91 Normal STEAM WATER DUMP TANK SYSTEM 22 Loop Selected / 1 or 2 Pressure /949 PSIG Temperature _3Af des F Level 75 INCHES Radiation Jo-vo ar/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "O" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06 EMERGENCY FEEDWATER PRESSURE O PSIG () BOILER FEED PUMPS A Speed c/ RPM A Flow O lbs/hr B Status orp on/of f B Flow o lbs/hr C Speed a RPM C Flow o lbs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Tank C) PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Wormal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Noraal () SERVICE AIR SYSTEM 82 Normal
l l BOARD I-10 PLANT PROTECTIVE SYSTEM l V RX BUILDING TEMPERATURE-HIGH BAT 100 > #0 des F BAT 200 wro deg F BAY 300 7/50 deg F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 4/ mr/hr Bay 1100 c/ mr/hr Bay 1000 4/ mr/hr Loop 2 Bay 600 // mr/hr Bay 500 / ar/hr Bay 400 Af ar/hr MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-13 PENETRATION INTERSPACE dP # PSID RX BUILDING SUMP DISCHARGE FLOW f' GPM BOARD I-15 RX STACK FLOW .3 M' ACFM RX BUILDING / AMBIENT dP -0,3 PSID BOARD I-7507X CONTROL ROOM TEMPERATURE M deg F 480V ROOM TEMPERATURE E'f .d eg F I
POSAVEX 87 i FOR: CONTROL ROOM OPERATOR _ MESSAGE NO. 8 O v LOCATION: CONTROL ROOM TIME: 0805 t i i XXXXXXXXXXXXXXXXXXX THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS XXXXXXXXXXXXXXXXXXXXXXY MESSAGE: Report to the Control Room that the electric feedpump discharge flange is blowing feedwater everywhere. The turbine driven feed pumps have no supply steam pressure. : (3
%)
e THIS .lS A DRILL XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX
POSAVEX 87 FOR: SUIFT SUPERVISOR MESSAGE NO. o LOCATION: couTRoL ROOM TIME: 0805 XXXXXXXXXXXXXXXXXX I THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS MESSAGE: i Inform the controller of actions you would have performed to recover from SLRDIS. The actual recovery will be simulated by the controller. He will inform you when SLRDIS recovery is complete. n v XXXXXXXXxxXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXxXXXXXXXXXX THis .ts A DRILL O V XXxxXXxxxXxxxxxxxxxxxxxxxxxxxxxxxxxxXxxxxxxxxxxxXxXxx
POSAVEX 87 FOR: couTuon Room OPERAToa MESSAGE NO. LOCATION: CONTROL ROOM TIME: 0807 XXXXXXXXXXXXXXXXXX THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS XXXXXXXXXXXXXXXXXXXXKXX, X 1 MESSAGE: 1 A guard reports that a man has been found on the north side of the reactor building and he is unconscious.
\
i XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX 1 THIS .lS A DRILL O XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX V I
- ____- D
FOSAVEX 87 FOR: CONTROL ROOM OPERATOR MESSAGE NO. O LOCATION: CONTROL ROOM TIME: 0810 _ XXXXXXXXXXXXXXXXX THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS XXXXXXXXXXXXX MESSAGE: The operator in the turbine building reports the rupture disc on the south-east for the main condenser is leaking steam out. All the operating condensate pumps are vibrating severely and may be damaged. s i 1 . I 1 h XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS .lS A DRILL l XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX
FOSAVEX 87 l FOR: EMERGENCY TEAM LEADER MESSAGE NO. k LOCATION: AT THE SCENE OF INJURY TIME: APPROX. 0810 XXXXXXXXXXXxXXXXXX l THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS JCXXX MESSAGE: The individual was in the containment building and exposed to the steam. He. injured his head when exiting the building using the crash bar. He has a knot on his forehead, there is no bleeding, and has the following vital signs: Respiration 12 O - BP 90/60 l Strong Pulse (2+) Pupils are both equal and reactive to light He has third degree burns on his hands and lower arms, he ! is contaminated (see attached). There are no open cuts, he is semi-conscious (i.e., delirium, does not recall exact details of what happened, time, de,te). NOTE: ALL ACTIVITIES ASSOCIATED WITH ST. LUKES (NOTIFICATION, TRANSPORTATION, CARE) ARE TO BE SIMULATED! xxxxxxxxxXXxxxxxXxxxxXxXxXXxxxxxxxxxXxxXxxxxxxxxxxXXX THIS .lS A DRILL (D xxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxx v
t FOSAVEI '87 I l Scenario time /35' l l s OVERALL PLANT PARAMETERS Clock time ofr/5 l Rx Power ///Ldf4 Turbine Generator Load _ _ , ,
) MW PRIMARY COOLANT , _
PRESSURE ,, 6 9 5' PS I A TEMPERATURE Circulator Inlet , 9'/o des F l Core Outlet //So des F HELIUM FLOW 4 Loop 1 o lbs/hr ) Loop 2 lbs/hr O TOTAL O lbs/hr CIRCULATOR SPEED Circulator A 4300 RPM Circulator B c.3on RPM Circulat'ro C 430o RPM Circulator D <'20 RPM MOISTURE (DEW POINT) ME-9306 4-59 deg F ME-9307 e- R deg F SECONDARY COOLANT FEEDWATER FLOW Loop 1 0 lbs/hr Loop 2 d _1bs/hr TOTAL o lbs/hr MAIN STEAM Loop 1 Pressure o PSIG Temperature #6r deg F Loop 2 Pressure as9r PSIG Temperature 99o deg F HOT REHEAT Loop 1 Pressure 44( PSIG
. Temperature 'No deg F Loop 2 Pressure o PSIG Temperature f'/o deg F COLD REHEAT Loop 1 Pressure } PSIG Temperature ,
K) deg F Loop 2 Pressure o PSIG Temperature Cr> _ des F O
i RADIATION M(Ef!T M S SCDIARIO TIME o 2.: Is PROCESS MONITORS CLOCE TIME o8: 1S-NUMBER SENSITIVITY VALUE ALARMING (Y/N) RT-4801 2.6E-10___ ** l. O E +1 CPM M RT-4802 1.2E-10 ** 1. o E +.4 CPM AJ RT-4803 2.5E-8 1. 0 E + 1 CPM N RT-6212 2.2E-8 __,_ I.o E +f CPM - M RT-6213 2.2E-8 f.o E +1 CPM M RT-7312 2.3E-8 _ *(PCRV) 1o E + 1 CPM M RT-7324-1 2.8E-8 4.0 E + c CPM M - RT-7324-2 8.9E-7 ,,_,_ 1, o E W CPM V RT-7325-1 005 003 003 RT-7325-2 003 003 OOS RT-73437-1 4.6E-10___ ** 1. o E + i CPM N l RT-73437-2 .__,_,,005 003 005 RT-9301 2.3E-8 9. 5 E + 5 CPM N ] RT-93252-12 N/A 1. O E + 0 ar/hr d AREA MONITORS NUMBER VALUE ALARMING l (ar/hr) (Y/N) RT-93250-1 c. I d RT-93250-2 o. i # RT-93250-3 5o Al RT-93250-4 o.t J O, RT-93250-5 RT-93250-8 O.I d.I Al d : RT-93250-13 0./ J ! RT-93250-14 o st. M RT-93251-1 05L M RT-93251-3 50.O d -l RT-93251-4 oI d RT-93251-5 o.I M i RT-93251-6 c.I M . RT-93251-7 o.I J RT-93251-8 01 d RT-93251-9 o. I J RT-93252-1 OI W Rf-93252-2 d. f J RT-93252 4 0.1 M RT-93252-6 al V RT-93252-7 aI d )' RIA-79511 0.s V
~
METERMIDGICAL DATA WIND SPEED F.0 MPE , WIND DIRECTION FROM 2*70 DEGREES
)
PLUME DIVIATICBI/ l SIGMA TIITA 2. O DEGREES DIFFERENTIAL TEMPERATURE +.4.0 DEGREES F O
- Value corresponds to the PCRV area channel. Other four channels are j 30 cym.
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
PRIMARY AUXILIARIES BOARD I-01 GAS WASTE. SYSTEM 63 Normal LIQUID WASTE -SYSTEM 62 Normal REACTOR PLANT. COOLING WATER SYSTEM 46- Normal PURIFIED HELIUM SfSTEM 23 Normal LN-2 SYSTEM 25 Normal BOARD I-02 HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /f PSIG High Pressure Bottles MS PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency-Feed Flow e/r0 GPM BUBW Header Pressure 30/,5 PSIG HELIUM CIRCULATORS SYSTEM 21 Normal BOARD I-03_ REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position 0 INCHES Runback group positions 2A, rod #2 O INCHES rod #4 o INCHES rod #6 o INCHES 4F, rod #25 0 INCHES rod #31 0 INCHES rod #37 . o INCHES Flux Controller position +/- ///4 % Reserve Shutdown Material 7 wal STATUS O
'\
BGARD I-05 HYDRAULIC OIL SYSTEM 91 Normal STEAM WATER DUMP TANK SYSTEM 22 Loop Selected / 1 or 2 Pressure /96 PSIG - ' Temperature ;frA- deg F Level ?f INCHES Radiation /o-% mr/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW L.'NGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0* PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE - SYSTEM 51 Formal BOARD I-06 _, EMERGENCY FEEDWATER PRESSURE 9 PSIG BOI.LER FEED PUMPS A Speed O RPM A Flow 0 lbs/hr B Status o# on/off B Flow 0 lbs/hr
'C Speed 0 RPM C Flow a lbs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Tank 0 PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER - SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal ? SERVICE AIR SYSTEM 82 Normal
BOARD I-10 PLANT PROTECTIVE SiSTEM , D() RI BUILDING TEMPERATURE-HIGH BAY 100 >/r3 deg F BAY 200 >/ro des F BAY 300 >/ rd deg F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 </ ar/hr Bay 1100 </ mr/hr Bay 1000 </ mr/hr Loop 2 Bay 600 4/ mr/hr Bay 500 /. 0 ar/hr Bay 400 Af ar/hr MOISTURE MONITORS (DEW POINT) Norsal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-13 PENETRATION INTERSPACE dP , M PSID RX BUILDING SUMP DISCHARGE FLOW T/ GPM BOARD I-15 RX STACK FLOW .J.loce ACFM RX BUILDING / AMBIENT dP -0.cdPS ID BOARD I-7507% CONTROL ROOM TEMPERATURE 69 des F 480V ROOM TEMPERATURE PP deg F O
4 FOSAVEI '87 g %g Scenario time /3~0 as ,)- OVERALL PLLRT PARAMETERS Clock time 0130 Rx Power #6d/5 Turbine Generator Load O MW PRIMARY COOLANT ~ PRESSURE 69f PSIA TEMPERATURE Circulator Inlet 290 deg F Core Outlet //ry) des F HELIUM FLOW Loop 1 0 lbs/hr Loop 2 O lbs/hr TOTAL 0 lbs/hr CIRCULATOR SPEED Circulator A 4300 RPM Circulator B 430L PM R Circulator C <3&o RPM Circulator D cs&o RPM MOISTURE (DEW POINT) ME-9306 Z-57 deg F ME-9307 z-s7 deg F SECONDARY COOLANT FEEDWATER FLOW Loop 1 5 lbs/hr Loop 2 o lbs/hr TOTAL u lbs/hr MAIN STEAM Loop 1 Pressure o PSIG Temperature &5D deg F Loop 2 Pressure 4350 PSIG Temperature 9h3 deg F HOT REHEAT Loop 1 Pressure O PSIG
, Temperature 9 65 deg F Loop 2 Pressure o PSIG Tempe ra tu re ?a deg F COLD REHEAT Loop 1 Pressure o PSIG Temperature J #0 deg F Loop 2 Pressure o PSIG Temperature 4d deg F
RADIATIW MWntst8 SCENARIO TIME O2!3o PROCESS M MITORS CLOCE TIME 08:So O. NOMBER SENSITIVITY VALUE ALARMING (Y/N) RT-4801 2.6E-10 ** l.o E e-l CPM N RT-4802 1.2E-10 _ ** l.0 E +1 CPM N RT-4803 2.5E-8 ___, l.o E +1 CPM V RT-6212 2.2E-8 I.o E +i CPM M , RT-6213 2.2E-8 f.o E ,1 CPM M { RT-7312 2.3E-8 *(PCRV) 3. o E .61 CPM u I RT-7324-1 2.8E-8 4, o E + l CPM Li
- I RT-7324-2 8.9E-7 1.o E ei CPM U RT-7325-1 008 003 003 RT-7325-2 003 003 005 RT-73437-1 4.6E-10 ** 1.o E +1 CPM M RT-73437-2 008 003 008 RT-9301 2.3E-8 l. o E 4(, CPM M RT-93252-12 N/A 1. o E + 0 mr/hr M AREA MONITORS NOMBER VALUR ALARMING (ar/hr) (Y/N)
RT-93250-1 o. I J RT-93250-2. o. I M i RT-93250-3 5o d I RT-93250-4 0.1 d RT-93250-5 M
')'
} . o.I RT-93250-8 o.I J RT-93250-13 0./ J RT-93250-14 o st. V RT-93251-1 05L M RT-93251-3 So. O d RT-93251-4 oI d RT-93251-5 o.# M RT-93251-6 c.I M RT-93251-7 ~
o.I u RT-93251-4 0.1 A/ RT-93251-9 o. I d RT-93252-1 Ol M RT-93252-2 o.I J RT-93252-4 o/ M RT-93252-6 oi V RT-93252-7 oi V RIA-79511 0.1 V METER 3 LOGICAL DATA WIND SPEED 5. 0 MPE , WIND DIRECTION FRW 2'70 DEGREES PLIBM DEVIATIW/ SIGNA THETA 2. O DEGREES DIFFERENTIAL TFMPERATORE + 4.0 DEGREES F O
- Value corresponds to the PCRV area channel. Other four channels are l 30 cym.
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
-PRIMARY AUXI!IARIES
,rn ( ,), BOARD I-01 GAS WASTE SYSTEM 63 Normal LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal BOARD I HELIUM STORAGE SYSTEM 24 , Low Pressure Bottles /9 PSIG High Pressure Bottles /0$'r PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency. Feed Flow e/ro GPM BUBW Header Pressure s%c PSIG HELIUM CIRCULATORS SYSTEM 21 Normal BOARD I-03_ iO REACTOR CONTROL SYSTEM 12 i Regulating Rod (1) position O INCHES Runback group positions 2A, rod #2 /> INCHES rod #4 J INCHES rod #6 J INCHES 4F, rod #25 o INCHES rod #31 ) INCHES rod #37 ,1 INCHES ; Flux Controller position +/- ///v % Reserve Shutdown Material _Tocer/hd( STATUS ()
BOARD I-05 HYDRAULIC OIL SYSTEM 91 Normal STEAM WATER DUMP TANK SYSTEM 22 Loop Selected / 1 or 2 Pressure /99 PSIG Temperature JPG deg F Level 9f INCHES Radiation SS-Fo mr/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06 EMERGENCY FEEDWATER PRESSURE C PSIG BOILER FEED PUMPS A Speed O RPM A Flow 17 lbs/hr B Status C# on /o f f B Flow U lbs/hr C Speed o RPM C Flow 3 lbs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Tank O PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal SERVICE AIR SYSTEM 82 Normal
l BOARD I-10 r^ PLANT PROTECTIVE SYSTEM RI BUILDING TEMPERATURE-HIGH BAT 100 >/fD d e g F BAT 200 >/TV deg F i BAT 300 7 /ro deg F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 4 / mr/hr Bay 1100 c/ mr/hr Bay 1000 er ar/hr Loop 2 Bay 600 4/ mr/hr Bay 500 / ar/hr Bay 400 /. ( mr/hr MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-13 PENETRATION INTERSPACE dP 9V'PSID RI BUILDING SUMP DISCHARGE FLOW <:7 GPM BOARD I-15 RI STACK FLOW J05000 ACFM RI BUILDING / AMBIENT dP ~ 207 PSID BOARD I-7507% CONTROL ROOM TEMPERATURE 67 deg F 480V ROOM TEMPERATURE f? deg F A U
l FOSAVEI '87 r~ Scenario time /45F i_)' s . OVERALL PLANT PARAMETERS Clock time egys" Rx Power- 90 d/S Turbine Generator Load a MW PRIMARY COOLANT PRESSURE 695 PSIA TEMPERATURE Circulator Inlet 9St2 deg F Core Outlet /ypr" deg F 1 I HELIUM FLOW j Loop 1 O lbs/hr j Loop 2 O lbs/hr j TOTAL o lbs/hr q CIRCULATOR SPEED Circulator A e sco RPM Circulator B z 3cm> RPM Circulator C 22&o RPM Circulator D , <329 RPM MOISTURE (DEW POINT) ME-9306 4-57 des F ME-9307 .e-r? deg F SECONDARY COOLANT FEEDWATER FLOW Loop 1 C3 lbs/hr Loop 2 c) lbs/hr TOTAL c) lbs/hr MAIN STEAM Loop 1 Pressure /f PSIG Temperature 4 50 deg F Loop 2 Press.ure 473< PSIG Temperature 97o des F HOT REHEAT Loop 1 Pressure
- O PSIG
. Temperature no deg F Loop 2 Pressure O PSIG Temperature 990 deg F COLD REHEAT Loop 1 Pressure A PSIG Temperature S50 deg F Loop 2 Pressure d PSIG Temperature ffa deg F
RADIATION N(3tI M 'SCINARIO TIME oZN7 ! PROCESS N(3112tELS CLOCK TIME og: (45 ,_ NDNBER SENSITIVITY . VAIDE ALARMING (Y/N) RT-4801 2.65-10 **- f.0 E +1,_CPN y RT-4402 1.2E-10 ** i.o E + l _ CPM. M RT-4803 2.5E-6 1. o E + l CPM rJ RT-6212. 2.2E-8 1.o E ,( CPM + u RT-6213 2.2E-8 f.o E ,4 CPM M RT-7312 2.3E-8 *(PCRV) Ao E&4 CPN M RT-7324-1 2.8E-9 4,o E +1 CPM M - RT-7324-2 8.9E-7 I, o E +. I CPM w RT-7325-1 003 003 OOS RT-7325-2 003 003 003 __ RT-73437-1. 4.6E-10 _ ** l. o E + l CPM M RT-73437-2 . 00S_ _ , 003 005 RT-9301 2.3E-6 f , 5 E +(. CPM U _ _ _ _ RT-9325?.-12 N/A _ _, I, o E + o ar/hr M ARIA M(Ef! M S NOMBER VALUE ALAltMING (ar/hr) (Y/N) RT-93250-1 c. I d RT-93250-2 o.i At RT-93250-3 5o Al n RT-93250-4 c.I d J' RT-93250-5 O.f ., Al RT-93250-4 c.I J RT-93250-13 d./ J RT-93250-14 o 50 W RT-93251-1 05L Al RT-93251-3 50.O d RT-93251-4 o. I d RT-93251-5 o.I M _ RT-93251-6 c.I M ,_ RT-93251-7 oI d RT-93251-4 0. I J RT-93251-9 c. I ,__ d RT-93252-1 Ol W RT-93252-2 c.I d RT-93252-4 oJ A/ l RT-93252-4 ai d RT-93252-7 ai _ V
'RIA-79511 o.I d METERCRIDGICAL DATA !
WDID SPEED s.O MPI . I WIND DIRECTION FRI3t 210 DEGREES i PLUME DEVIATION / ' SIGN & TERTA 2. O DEGREES 5 DIFFERENTIAL TEMPERA 2URE + 4.0 DEGREES F l 0 t falue corresponds to the PCRV area channel. Other four channels are
!0 cym.
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the w ified scenario / clock time.
_ - _ - _ _ _ _ - _ _ .-_D
PRIMARY AU:ILIARIES () BOARD I-01 GAS WASTE SYSTEM 63 Normal LIQUID WASTE SYSTF" 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal BOARD I-02 HELIUM STORAGE SYSTEM 24 Low Pressure Bottles ___ff PSIG High Pressure Bottles _ /vem? PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow 2/f GPM BUBW Header Pressure 1g9r PSIG HELIUM CIRCULATORS SYSTEM 21 Normal B0/,RD I-03_ O REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position O INCHES Runback group positions 2A, rod #2 O INCHES rod #4 __ _ u INCHES rod #6 o INCHES 4F, rod #25 0 _ INCHES rod f?? 9 INCHES rod #i< 0 INCHES Flux Controller position +/- N/4 % Reserve Shutdown Material laserfd STATUS O
BOARD I-05 , (} HYDRAULIC OIL STEAM WATER DUMP TANK SYSTEM 91 SYSTEM 22 Normal Loop Selected / 1 or 2 Pressure /90 PSIG Temperature r?V deg F Level 77 INCHES Radiation Jo-vo ar/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE D'JRING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06 _ EMERGENCY FEEDWATER PRESSURE /T' PSIG (I BOILER FEED PUMPS A Speed o RPM A Flow O lbs/hr B Status <# on/off B Flow o lbs/hr C Speed 0 RPM C Flow o lbs/hr CONDENSATE SYSTEM $1 Normal MISCELLANEOUS Bypass Flash Tank 0 PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal (} SERVICE AIR SYSTEM 82 Normal
l BOARD I-10 PLANT PROTECTIVE SYSTEM RI BUILDING TEMPERATURE-HIGH BAT 100 2/5D ,deg F BAT 200 >/ro d e g F BAY 300 >/r0 deg F l REHEAT ACTIVITY MONITORS l Loop 1-Bay 1200 4/ mr/hr l Bay 1100 e/ mr/hr l Bay 1000 c/ mr/hr Loop 2 Bay 600 4/ mr/hr Bay 500 / mr/hr Bay 400 /d ar/hr MOISTURE M0!!ITORS (DEW POINT) Nornst MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-23 PENETRATION INTERSPACE dP 9' PSID RI BUILDING SUMP DISCHARGE FLOW < /d G PM f BOARD I-15 RI STACK FLOW JUtoro ACFM RI BUILDING / AMBIENT dP - ct, P3ID BOARD I-7507I CONTROL ROOM TEMPERATURE &? deg F 480V ROOM TEMPERATURE 77 deg F i
FOSAVEI '87
.n Scenario time 4D OVERALL PLD T PARAMETERS Clock time Cyc (d
Rx Power h Turbine Generator Load O MW PRIMARY COOLAMT~ PRESSURE __ Otro PSIA TEMPERATURE Circulator Inlet 900 d eg F Core Outlet _22frfadeg F HELIUM FLOW Loop 1 o lbs/hr Loop 2 a lbs/hr TOTAL _, O lbs/hr CIRCULATOR SPEED Circulator A s%T RPM Cir::ulator B _,d oo RPM ; Circulator C Mg_R PM l Circulator D A.1 RPM ! MOIS*rURE (DEW POINT) ; ME-9306 s -5') deg F ! ME-9307 <-r7 deg F {,,) (/ SECONDARY COOLANT FEEDWATER FLOW Loop 1 C) ._1bs/hr Loop 2 v lbs/hr TOTAL O _1bs/hr MAIN STEAM Loop 1 Pressure Jo PSIG Temperature , 4@ deg F Loop 2 Pressure >30,5 PSIG Temperature 96 o des F HOT REHEAT Loop 1 Pressure o PSIG Temperature 9M des F Loop 2 Preseure _ o PSIG Temperature 960 deg F i COLD REHZAT Loop 1 Pressure O PSIG Temperature _ - 71 deg F Loop 2 Pressure O PSIG Temperature 7A deg F , O
RADIATION M TORS SCENARIO TIME o3:oo PROCESS M TORE CLOC% TIME o4,oo Nt1MBER SENSITIVITY VALUE ARJOGING (Y/N) RT-4801 2.6E-10 ** l.O E +1 CPN u _ RT-4402 1.2E-10 ** l. o - E +1 CPM AJ
~
RT-4803 2.5E-8 10 E +. i CPM U RT-6212 2.2E-8 I. o E 4 - CPN M
~
RT-6213 2.2E-8 1.o E gj _ CPN N 2T-7312 2.3E-8 _ *(PCRV) In E +f CPM M RT-7324-1 2.8E-3 4. o E + 1 CPM , d - RT-7324-2 8.9E-7 I.o E +1 CPN M RT-7325-1 003 008 003 RT-7325-2 OOS 005 008 i RT-73437-1 4.6E-10 ** l.0 E +1 CPM Al RT-73437-2 , 008 003 000 { RT-9301 2.3E-8 to E SG-CPM A. 1 RT-93252-12 N/A s,o E to ar/hr M ARIA NONITCES i NUMBER VALUE ALARNING (arthr) (Y/N) RT-93250-1 o. I J RT-93250-2 o. I M RT-93250-3 5o u RT-93250-4 c.f .,_ d _ RT-93250-5 o.I M .,_. RT-93250-8 c. I M RT-93250-13 d.I d RT-93250-14 0 SL. M RT-93251-1 0$L M RT-93251-3 50.O d l RT-93251-4 o, i d RT-93251-5 o.I M RT-93251-6 c.1 # 1 RT-93251-7 o.I u l RT-93251-8 O. I d RT-93251-9 o. I d RT-93252-1 oi M l RT-93252-2 o.I J l RT-93252-4 0.1 M I RT-93252-6 oI V RT-93252-7 oi V RIA-79511 0.s d METEROLOGICAL DATA WIND SPEED .
' 5',0 MPE .
WIND DIRECTI M FRW __ E 0 DEGREES 1 PLUME DEVIATIW/ I SIGNA TEETA 2. O _ DEGREES DIFFERENTIAL TEMPERATURE l
+ 4. 0 DEGREES F O
- Value corresponds to the PCRV area channel. Other four channels are 30 cym.
** Value corresponds te a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
i
4 PRIMARY AUXILIARIES O) . (, BOARD I-01 GAS WASTE SY-STEM 63 Normal LIQUID WASTE SYSTEM 62 Normal 4 REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal _ . BOARD I-02 HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /f PSIG High Pressure Bottles drvr PSIG l 1 EMERGENCY FEEDWATER SYSTEM 31 j Emergency Feed Flow </TD GPM EUBW Header Pressure vaar PSIG HELIUM CIRCULATORS SYSTEM 21 Normal j i BOARD I-03_ ' i . REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position O INCHES Runback group positions 2A, rod #2 ,J INCHES rod #4 v INCHES 3 1 rod #6 o INCHES I 4F, rod #25 o " INCHES rod #31 -~ o INCHES rod #37 O INCHES Flux Controller position +/- N/A % Reserve Shutdown Material fy5er/ec(. STATUS 1 l O
BOARD I-05 l I () HYDRAULIC-0,IL STEAM WATER DUMP TANK SYSTEM 91 SYSTEM 22 Normal Loop Selected / 1 or 2 4 Pressure /90 PSIG l Temperature < W deg F j Level 75 INCHES 1 Rad ia r. ion ,4U - St> m r / h r HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. 1 THIS INFORMATION IS REQUIRED TO i EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. ' MAIN TURBIME . SYSTEM 51 Normal BOARD I-06 EMERGENCY FEEDWATER PRESSURE 1 30 PSIG ; f) BOILER FEED PUMPS-A Speed C RPM A Flow v' lbs/hr B. Status v4' on/off B Flow. C lbs/hr C Speed - o RPM C Flow a los/hr
' CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Tank d PSIG HOT REHEAT BYPASS VALVE POSITIONS Norma'.
PLANT ELEdTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal y() SERVICE AIR SYSTEM 82 Normal
t BOARD I-10 ~ PLANT PROTECTIVE SYSTEM L x_/ l () RIBUILDIhtTEMPERATURE-HIGH
. BAY 100' >/57) deg F BAY 200 yyJ31., des F BAY 300 7/no deg F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 4 /' ar/hr Bay 1100 </ mr/hr Bay 1000 </ mr/hr Loop 2 Bay 600 4/ sr/hr Bay 500 / mr/hr Bay 400 /, 5i er/hr MOISTURE NLNITORS (dew POINT) Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal I
BOARD I-13 PENETRATION INTERSPACE dP 1' PSID RI BUILDING SUMP DISCHARGE FLOW R' _GPM BOARD I-15 RX STACK FLOW ??e ACFM RI BUILDING / AMBIENT dP d PSID BOARD I-7507X CONTROL ROOM TEMPERATURE 67 deg F 480V ROOM TEMPERATURE 77 deg F ( ' _-_-______-_-_________D
.s i
FOSAVEI '87 i (~} Scenario t'ine /6 L/ OVERALL PLANT PARAMETERS Clock time o9/5 Rx Power 4?d45 Turbine Generator Load a MW PRIMARY. COOLANT PRESSURE J PO PSIA i TEMPERATURE I Circulator Inlet _fvo deg F l Core Outlet 4 4Q__ des F HELIUM FLGW Loop 1 O lbs/hr Loop 2 o lbs/hr TOTAL O lbs/hr CIRCULATOR SPEED l Circulator A 2300 RPM Circulator B < 200 RPM Circulator C 4300 RPM Circulator D <bo RPM MOISTURE (DEW POINT) ME-9306 4-59 deg F ME-9307 <-59 deg F SECONDARY COOLANT FEEDWATER FLOW Loop 1 o lbs/hr Loop 2 o lbs/hr TOTAL _ 0 lbs/hr MAIN STEAM Loop 1 Pressure & PSIG Temperature A35 deg F Loop 2 Pressure 0275 PSIG Temperature 950 deg F HOT REHEAT Loop 1 Pressure O' PSIG
. Temperature ao deg F Loop 2 Pressure O PSIG Tempwratare 950 deg F COLD REHEAT Loop 1 Pressure S PSIG Temperature M3 des F ,
Loop 2 Pressure O PSIG Temperature 475 deg F O i
)
l l RADIATION HONITMS SCENARIO TIME o3:i5 PROCESS MONITORS CLOCE TIME og:i5
\ NtBIBEE SENSITIVITY VALUE ALARHING (Y/N)
RT- 4801 2.6E-10__, ** l.o E St CPM d RT-4802 1.2E-10__,_ ** 1. O E +.1 CPM M _ RT-4803 2.5E-8 1. o E +1 CPM N i RT-6212 2.2E-8 I.0 E ,i CPM 4 I RT-6213 2.2E-8 f.o E +1 CPM M l RT-7312 RT-7324-1 2.3E-4 2.8E-8
*(PCRV)~ ? o E +1 4.o E41 CPM CPM M
Al - [ l _ { RT-7324-2 8.9E-7 1. O E +1 CPM M l RT-7325-1 OOS 003 OOS -l RT-7325-2 005 003 OOS l RT-73437-1 4.6E-10___ ** f.O E +1 CPM M RT-73437-2 005 003 003 RT-9301 ,__2.3E-8 2.5 E 4 CPM M RT-93252-12 N/A 1.o E e ar/hr A/ AREA MCBtIT W S NUMBER VALUE ALARMING (ar/hr) (Y/N) RT-93250-1 o. I d RT-93250-2 o .1 # RT-93250-3 5o u RT-93250-4 0.1 d O RT-93250-5 RT-93250-8 O.I c.I Al al RT-93250-13 C./ d RT-93250-14 o sL. M RT-93251-1 05L Al RT-93251-3 50.o d RT-93251-4 oI d RT-93251-5 o.I d RT-93251-6 c.I M RT-93251-7 d.I d RT-93251-8 0. I - d RT-93251-9 o. I J RT-93252-1 af M RT-93252-2 c.I J
'ET-93252-4 0.1 V l RT-93252-6 oI d l RT-93252-7 o# d !
RIA-79511 0.t A/ ) METER 0RLOGICAL DATA l WIND SPED M0 MPH .
~{
WIND DIRECTION FRON 270 DEGREES j PLUME DEVIATIW/ SIGMA TEETA 2. O DEGREES DIFFERENTIAL TEMPERATURE + 4.0 DEGREES F O
- Value corresponds to the *CRV area channel. Other four chacnels are 30 cys.
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
PRIMARY AUXILIARIES () BOARD I-01 GAS WASTE SYSTEM 63 Normal LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal ; I LN-2 SYSTEM 25 Normal I BOARD I-02__ HELIUM STORAGE - SYSTEM 24 I Low Pressure Bottles /C PSIG High Pressure Bottles 99< PSIG EMERGENCY FEEDWATER SYSTEM 31
' argency Feed Flow Ammo GPM EJBW Header-Pressure ~x# PSIG HELIUM CIRCULATORS SYSTEM 21 Normal BOARD I-03
'- REACTOR CONTROL SYSTEM 12 { Regulating Rod (1) position O INCHES Runback group positions l 2A, rod #2 ___ C) INCHES rod #4 o INCHES rod #6 O INCHES 1 4F, rod #25 o INCHES j rod #31 c) INCHES ) rod #37 INCHES Flux Controller position +/- N/M % Reserve Shutdown Material JC uchd STATUS O l
]
BOARD I-05__ (~') HYDRAULIC OIL SYSTEM 91 Normal V STEAM WATER DUMP TANK SYSTEM 22 Loop Selected / 1 or 2 Pressure /90 PSIG Temperature .3?T' deg F Level 97 INCHES Radiation _20 -M-> mr/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE' VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06 EMERGENCY FEEDWATER PRESSURE 49' PSIG () BOILER FEED PUMPS A. Speed M RPM A Flow 0 lbs/hr B Status dl on/off B Flow o lbs/hr C Speed O RPM C Flow 1 lbs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Tank O PSIG 1 1 HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WA' UR TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal (} SERVICE AIR SYSTEM 82 Normal
BOARD I-10 l PLANT PROTECTIVE SYSTEM ( ( R1 BUILDINGtTEMPERATU9.E-HIGH 1 BAY 100: >/s U d e s F BAY 200 f
>/ r0 d es F 1 BAY 300 >fr; des F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 e/ mr/hr Bay 1100 c/ mr/hr -
Bay 1000 c/ mr/hr Loop 2 Bay 600 </ mr/hr I Bay 500 / mr/hr Bay 400 /,r ar/hr MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal _ BOARD I-13 PENETRATION INTERSPACE dP 1' PSID RX BUILDING SUMP DISCHARGE FLOW s/) GPM () BOARD I-15 RX STACK FLOW , _Livv0 ACFM RX BUILDING / AMBIENT dP -e/I PSID BOARD I-7507X C0hfROL ROOM TEMPERATURE 67 deg F 480V ROOM TEMPERATURE R/ deg F i O
l i b FOSAVEX '87 Scenario time d'A0 (~~)' (_ OVERALL PLANT PARAMETERS Clock time 04&O Rx Power /Od6 Turbine Generator Load O MW PRIMARY COOLANT PRESSURE dcPO PSIA TEMPERATURE Circulator Inlet a?/,9 deg F Core Outlet *xha deg F HELIUM FLOW Loop 1 of4coolbs/hr Loop 2 a lbs/hr TOTAL #0 m ibs/hr CIRCULATOR SPEED Circulator A //ev RPM Circulator B e3ov RPM Circulator C z2&o RPM Circulator D e too RPM MOISTURE (DEW POINT) ME-9306 /-S7 des F ME-9307 <-57 deg.F SECONDARY COOLANT ~~ FEEDWATER FLOW Loop 1 C) lbs/hr Loop 2 c) lbs/hr
. TOTAL n 1bs/hr MAIN STEAM Loop 1 Pressure 2,v' PSIG Temperature _JSr deg F Loop 2 Pressure >> 5a PSIG Temperature 9vo deg F HOT REHEAT Loop 1 Pressure O PSIG
. Temperature 9</o des F Loop 2 Pressure o PSIG Temperature 9yo deg F COLD REHEAT Loop 1 Pressure o PSIG Temperature 970 des F Loop 2 Pressure n PSIG Temperature /A9 deg F O>
\-
RADIATION M(BIITtRS SCENARIO TIME -03/3o PROCESS MONITORS CLOCE TIME _ 09: 3o NtBIBER SENSITIVITY VALUE ALARMING (Y/N) RT-4801 2.6E-10 ** 1.0 E +1 CPM M RT-4802 1.2E-10,__ ** 10 E el ,_, CPM e RT-4803- 2.5E-8 1.0 E +1 CPM y RT-6212 2.2E-8 I,o E +1 _, CPM - y RT-6213 2.2E-8 1.o E ,i CPM y RT-7312 2.3E-8 *(PCRV) 1.oEI CPM -u RT-7324-1 7.8E-8 4.0 E41 CPM d - RT-7324-2 8.9E-7 I,O E &I CPM N RT-7325-1 003 OOS 005 RT-7325-2 003 003 005 RT-73437-1 4.6E-10 _ ** I.o E +1 CPM V RT-73437-2 005 003 005 RT-9301 2.3E-6 84.0 E +b CPM M RT-93252-12 :/A 1.o E +o ar/hr V AREA MONITORS NUMBER VALUE ALARMING (ar/hr) (Y/N) RT-93250-1 c. I __ d RT-93250-2 o.I M RT-93250 so d RT-93250-4 o.I J RT-93250-5 O.I M RT-93250-4 - c. I M _O_ RT-93250-13 0./ J RT-93250-14 osL ~ W RT-93251-1 ost M _ RT-93251-3 50.o d RT-93251-4 o. I d . RT-93251-5 o.# M RT-93251-6 o.I M RT-93251-7 o.I d RT-93251-8 0. I u RT-93251-9 oi d RT-93252-1 Oi V RT-93252-2 o.f J i RT-93252-4 0.1 M l RT-93252-6 o. I d f RT-93252-7 oi V 1 RIA-79511' O.# d ) METFRNN'ICAL DATA WIND SPEED 5" O MPB . ; WIND DIRECTIM FROM 2'70 DEGREES I PLUME DEVIATIW/ SIGMA TIETA 2. O DEGREES DIFFERENTIAL TEMPERATURE +.4.0 DEGREES F ,
- Value corresponds to the PCRV area channel. Other four channels are 30 cym.
**. Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
PRIMARY AUXILIARIES _ BOARD I-01 l 1 GAS WASTE SYSTEM 63 Normal f LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal j PURIFIED HELIUM SYSTEM 23 Normal I LN-2 SYSTEM 25 Normal BOARD I-02 HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /9 PSIG High Pressure Bottles 90 4 PSIG EMERGENCY FEEDWATER SYSTEM 31 { Emergency Feed Flow /ar# GPM BUBW Header Pressure S&G PSIG HELIUM CIRCULATORS SYSTEM 21 Normal _ BOARD I-03 REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position o INCHES Runback group positions 2A, rod #2 O INCHES rod #4 ~ O INCHES rod #6 o INCHES 4F, rod #25 d INCHES rod #31 o INCHES r o d. #37 o INCHES Flux Controller position +/- N4/ % Reserve Shutdown Material h,te/e/ STATUS 4 O
BOARD I-05 () HYDRAULIC. 0IL SYSTEM 91 Normal STEAM WATER DUMP TANK SYSTEM 22 Loop Selected / 1 or 2 Pressure /90 PSIG-Temperature 1&M deg F Level 96 INCHES Radiation 30-9'0 ar/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06 EMERGENCY FEEDWATER PRESSURE 49' PSIG () BOILER FEED PUMPS A Speed C7 RPM A Flow o 1bs/hr ' B Status oN on/off B Flow o lbs/hr C Speed a RPM C Flow 0 lbs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS ! Bypass Flash Tank O PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal 4 MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal i INSTRUMENT AIR SYSTEM 82 Normal SERVICE AIR -( ) SYSTEM 82 Normal
. 1 I ~
BOARD I-10 PLANT PROTECTIVE SYSTEM RI BUILDING TEMPERATURE-HIGH BA7> 100: > /D des F BAY 200 J/rv deg F BAY 300 7/ro deg F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 4/ ar/hr Bay 1100 <-/ ar/hr Bay 1000 </ ar/hr l Loop 2 Bay 600 e/ ar/hr l Bay 500 / mr/hr l Bay 400 /,< ar/hr MOISTURE MONITORS (DEW POINT) Normal ! MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-13_ PENETRATION INTERSPACE dP +# PSID RX BUILDING SUMP DISCHARGE FLOW s'A9 GPM O s_ ,/ BOARD I-15 RX STACK FLOW _.17cro ACFM RX BUILDING / AMBIENT dP -0,sf PSID BOARD I-7507X CONTROL ROOM TEMPERATURE. 6f deg F 480V ROOM TEMPERATURE fi des F O
FOSAVEX 87 FOR: CONTROL ROOM OPERATOR MESSAGE NO. b (O v e LOCATION: CONTROL ROOM TIME: 0945 l l XXXXXXXXXXXXXXXXXX l THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS MESSAGE: Inform the Shift Foreman that the SLRDIS recovery is. complete using fire water and you have circulation using "A" Circulator. XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS .ls A DRILL XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX
FOSAVEI '87 f) Scenario time 22f
\_/ OVERALL PLANT PARAMETERS Clock time 09v5 i Rx Power 9M Turbine Generator Load d MW PRIMARY COOLANT PRESSURE Md PSIA TEMPERATURE Circuintor Inlet A /e 9 d e g F Core Oetlet /5'/i' des F HELIUM FLOW Loop 1 <3?oc lbs/hr Loop 2 o lbs/hr TOTAL 3700 lbs/hr CIRCULATOR SPEED Circulator A /Jac> RPM Circulator B 436o RPM Circulator C 4300 RPM Circulator D /3oo RPM MOISTURE (DEW POINT)
ME-9306 4 -$? deg F ME-9307 <- 5 7 dea F SECONDARY C00LisNT FEEDWATER FLOW Loop 1 a lbs/hr Loop 2 O lbs/hr TOTAL 4 lbs/hr MAIN STEAM Loop 1 Prercure # PSIG Temperature JSr deg F Loop 2 Pressure 3227 PSIG Temperature 9'/0 deg F HOT REHEAT Loop 1 Pressure d PSIG
. Temperature 9.2r deg F '
Loop 2 Pressure o PSIG T'emperature 440 deg F COLD REHEAT Loop 1 Pressure ? PSIG Temperature s ed deg F Loop 2 Pressure n PSIG Temperature 9") deg F 1 O
RADIATION M(3fITURS SCENARIO TIME 05 45 PROCESS M(BlITW S CLOCE TIME o4:4s NUMBER SENSITIVITY VALUE ALARMING (Y/N) RT-4801 2.6E-10 **- f.0 E +1 CPM M RT-4802 1.2E-10__, ** l.o E 4.I CPM y RT-4803 2.5E-4 l.o E +1 CPM N RT-6212 2.2E-8 _ I.o E +f CPM - N RT-6213 2.2E-8 f.o E +1 CPM at RT-7312 2.3E-6 *(PCRV) 3. o E + l CPM al RT-7324-1 2.8E-8 __, 4. O E +.1 - CPM M RT-7326-2 8.9E-7 l. O E +1 CPM M RT-7325-1 003 003 008 RT-7325-2 005 005 008 RT-73437-1 4. 6E-10,,_,, ** l.o .E +1 CPM N RT-73437-2 005 008 OOS RT-9301 2.3E-8 L., o E e 7 CPM Y RT-93252-12 N/A 10 E +o ar/hr N ARIA MONITORS NUMBER VALUE ALARMING (ar/hr) (Y/N) RT-93250-1 C. I d RT-93250-2 o. I M RT-93250-3 5o d RT-93250-4 c. I d RT-93250-5 O.I M O- RTa93250-4 RT-93250-13 o.I d O./ d RT-93250-14 o st. . V RT-93251-1 05L M RT-93251-3 50.O d RT-93251-4 o. f M RT-93251-5 o.I M RT-93251-4 c.I M RT-93251-7 d.f. LI RT-93251-8 0I J RT-93251-9 o. I kl RT-93252-1 Of M RT-93252-2 0.I J RT-93252-4 0.1 V RT-93252-6 a1 d RT-93252-7 oI W RIA-79511 0.1 d METER 0RLOGICAL DATA WIND SPEED F,0 MPR . WIND DIRECTI M FRW 270 DEGREES PLUME DEFIATIW/ SIGNA TEETA 2. O DEGREES DIFFERENTIAL TEMPERATURE + 4. 0 DEGREES F
- Value corresponds to the PCRV area charmal. Other four channels are 30 cym.
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
1
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PRIMARY AUXILIARIES
/ ~')
\_ ,/ BOARD I-01 l 1
GAS WASTE SYSTEM 63 Normal LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal BOARD I-02 HELIUM STORAGE SYSTEM 24 Lev Pressure Bottles /9 PSIG High Pressure Bottles 00 9' PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow A970 GPM BUBW Header Pressure 20/ 5 PSIG HELIUM CIRCULATORS SYSTEM 21 Normal BOARD I-03 REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position O INCHES Runback group positions 2A, rod #2 O INCHES rod #4 0 INCHES rod #6 d INCHES 4F, rad #25 0 INCHES rod #31 O INCHES rod #37 0 INCHES Flux Controller position +/- //4; % Reserve Shutdown Material # JUcer/tc[ STATUS O _- __ - -________a
~
BOARD I-05 () HYDRAULIC OIL SYSTEM 91 Normal STEAM WATER DUMP TANK SYSTEM 22 Loop Selected / 1 or 2 Pressure /&d PSIG Temperature !&O deg F Level X INCHES i Radiation 5a- +3 mr/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. s THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06 EMERGENCY FEEDWATER PRESSURE 4+/ PSIG BOILER FEED PUMPS A Speed O RPM A Flow v lbs/hr B Status d4 on/off B Flow o lbs/hr C Speed 6 RPM C Flow 0 lbs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Tank C PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal ' () SERVICE AIR SYSTEM 82 Normal 1
- - _ - - - _Y
E l l
, BOARD I-10 PLANT PROTECTIVE SYSTEM f
O RX BUILDING TEMPERATURE-HIGH l BAY 104 //50 des F BAY 200 >/rd des F BAY 300 >rro deg F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 & mr/hr ) Bay 1100 c/ mr/hr Bay 1000 </ mr/hr , Loop 2 Bay 600 / mr/hr i Bay 500 / mr/hr f Bay 400 /, 5 mr/hr MOISTURE MONITORS (DEW POINT) Normal ) MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal j BOARD I-13 PENETRATION INTERSPACE dP ( PSID , RX BUILDING SUMP DISCHARGE FLOW 4/o GPM r BOARD I-15 RX STACK FLOW JJ@oACFM RX BUILDING / AMBIENT dP -0,K PSID BOARD I-7507X CONTROL ROOM TEMPERATURE 47 deg F 480V ROOM TEMPERATURE 8 deg F l l l O
FOSAVEX 87 FOR. OPERATOR MESSAGE NO. (
' LOCATION: FSV SWITCHBOARD TIME: 1000 XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS IS A DRILL DO NOT INITlATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX MESSAGE:
This is from Radio Station KBCO in Boulder. . I would like to speak with your Station Manager, I believe his name in Chuck Fuller. I'm trying to get some information on the accident. J- l so i XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX ) THIS IS A DRILL XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX
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FOSAVEI '87 Scenario time Mo O OVERALL PLANT PARAMETERS Clock time /ooo Rx Power /d M Turbine Generator Load O MW PRIMARY COOLANT PRESSURE '700 PSIA TEMPERATURE Circulator Inlet /G# deg F Core Outlet /600 deg F HELIUM FLOW Loop 1 J700 lbs/hr Loop 2 0 lbs/hr TOTAL 3990 lbs/hr CIRCULATOR SPEED Circulator A XJ00 RPM Circulator B , <3Or> RPM Circulator C <Joo RPM Circulator D <rar; RPM HOISTURE (DEW POINT) ME-9306 2-S7 deg F ME-9307 s- s'7 deg F SECONDARY COOLANT FEEDWATER FLOW Loop 1 O lbs/hr Loop 2 c> lbs/hr TOTAL O lbs/hr MAIN STEAM Loop 1 Pressure # PSIG Temperature se deg F j Loop 2 Pressure GMo PSIG Temperature 920 deg F HOT REHEAT Loop 1 Pressure o PSIG
, Temperature G30 deg F Loop 2 Pressure o PSIG Temperature /m deg F COLD REHEAT Loop 1 Pressure o PSIG ]
Temperature /, 71" des F Loop 2 Pressure o _PGIG Temperature /4Y deg F
.i (
RADIATIM IEBIITORS SCENARIO TIME 0i4!O0 PROCESS MONI'IVRS CLOCE TIME tof co .D h NtBIBEE ' SENSITIVITY VALUE' ALARMING
-(Y/N)
RT-4801_ , 2.6E-10___ ** 1, o E 41 CPM hl RT-4402 ** l. a E + f CPM Al 1.2E-10___
'RT-4403 2.5E-4 f.o E et CPM M, RT-6212 2.2E-4 f.o E +i,,,, CPM kJ RT-6213 2.28-4 -
f.o E +4 CPM Al RT-7312 2.3E-8 *(PCRV) 2.0 E +4 CPM Y RT-7324-1 2.8E-8 _ _,,, -3.3 E +4 _ CPM M - RT-7324-2 __,_8.9E-7 1.1 E +4__CPH M RT-7325-1 00S 005 __;_ 005 RT-7325-2 003 003 _ 008 RT-73437-1 4.6E-10_,,_ ** 1. o E + 1 CPM- Al ,, RT-73437-2 , 003 003 003 RT-9301 2.3E-4 L.o E,3,L,_ CPM Y RT-93252-12 N/A S. O E +n ar/hr Y ARIA MCBIITMS . l lEBIBER VAI,UE ALARMING (ar/hr) (Y/N) RT-93250-1 200.0 Y RT-93250-2 2 oo.0 Y RT-93250-3 s0 V RT-93250 2.00.0 Y s M O RT-93250-5
- n. f RT-93250-4 = loo. o Y RT-93250-13 d.t M RT-93250-14 o $ t. - -
U RT-93251-1 RT-93251-3 _d st. 50.o- [_ MAl RT-93251-4 o.5- M RT-93251-5 2 oo. O Y- i RT-93251-6 f.oo. o ( RT-93251-7 2 oo. o Y RT-93251-4 2 oo. o 'Y RT-93251-9 f 2 oo. o ' Y RT-93252 I oo. o Y RT-93252-2 1 co.o -Y RT-93252 2.o ( , M RT-93252.-6 2 00.0 V RT-93252-7 eoo. c V RIA-79511 c. 6 M i U' l MRN20RLOGICAL DATA _ WIND SPEED KO MPR, '. WIND DIRECTIM FRW 270 DEGREES l PLUME DEVIATION / SIM A TERTA 2. O DEGWLCES . DIFFERENTIAL TEMPERATURE +.4.0 DEGREES F I
- Value corresponds to the PCRV area channel. Other four channels are 30 cym.
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time, i
l
f. PRIMARY AUXILIARIES j ... BOARD I-01 GAS WASTE SY-STEM 63 Normal LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal BOARD I-02 HELIUM STORAGE SY5T2M 24 Low Pressure Bottles /P ~PSIG nigh Pressure Bottles P9s ?SIG EMERGENf3 FEEDWATER SYSTEM 31 ' Emergency Feed Flow /007, GPM BUBW Header Pressure .300 6 FSIG HELIUM CIRCULATORS SYSTEM 21 Nermal BOARD I-03 f~ I, REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position o INCHES Runback group positions 2A, r*.d #2 O INCHES - rod #4 o INCHES rod #6 o INCHES 4F, rod #25 o INCHES rod #31 o ~ INCHES ' rod #37 0 INCHES Flux Controller position +/- to'e % Reserve Shutdown Material _rus eh d STATUS k.s
BOARD I-0$ h HYDRAULIC OIL SYSTEM 91 Normal STEAM WATER Dt?NP TANI SYSTEM 22 Loop Sele,cted / 1 or 2 l Pressure /90 PSIG l Temperature ?SO deg F ! Level 75 INCHES Radiation <#0-90 mr/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES, MAIN TURBINE SYSTEM 51 Normal
, BOARD I-06 c
EMERGENCY FEEDWATER PRESSURE 49'PSIG BOILER FEED PUMPS A Speed O KPM A Flow o lbs/hr " B Status de 'on/off B Flow 0 lbs/hr C Speed o RPM C Flow A lbs/hr CONDENSATE SYSTEM 31' Normal MISCELLANEOUS Bypass Flash Tank 6 PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal h SERVICE AIR SYSTEM 82 Normal
BOARD I-10 1 PLANT PROTECTIVE SYSTEM h RXBUILDINhTEMPERATURE-HIGH BAY 10a >/5) deg F BAT 200 >/ -o d e g F i BAT 300 5/ro deg F j REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 </ mr/hr Bay 1100 </ mr/hr Bay 1000 _;e / mr/hr Loop 2 Bay 600 / mr/hr Bay 500 / mr/hr Bay 400 / mr/hr 4 MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-13 PENETRATION INTERSPACE dP SI PSID RX BUILDING SUMP DISCHARGE FLOW O GPM lh , BOARD I-15 RX STACK FLOW y der 0 ACFN T RX BUILDING / AMBIENT dP ; et$fSID BOARD I-7507X _ CONTROL ROOM TEMPERATURE 49 deg F 480V ROOM TEMPERATURE PP deg F O
POSAVEX 87
- FOR: CONTROL ROOM OPERWtOR MESSAGE NO. '/O O LOCATION: - gguTROL ROOM TIME: 10os .J XXXXXX XXXXXXXXXXXXXXXXXX THIS IS A DRILL ,
1 i DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS XxXXxXXXXXxXXX I MESSAGE: Both cold reheat temperatures are increasing. O G 4 l 1 Xx^xxxxxXXxXX)OOO(xXXxXxxxXxXxxxXXXxXxxxxXxxxXXxxxXxxX ! THIS .lS A DRILL lv)' l f' xxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxXxxxxxxxxxxxxxxxxx 1 { !
1 i 4 FOSAVEI '87 r-s Scanscio time ORS $' ' l y ) OVERALL PLANT PARAMETERS ' Clock time /0/ r ; Rx Power Aadas Turbine Genarator Load n' MW PRIMARY COOLANT FRESSURE 6c f PSIA TEMPERATURE Circulator Inlet /94 deg F Core Outlet s^rso des F HELIUM FLOW Loop 1 ,7790 lbs/hr Loop 2 o lbs/hr TOTAL J Oo* lbs/hr CIRCULATOR SPEED
'irculator A XJ#v RPM Circulator B e300 RPM Circulator C cago RPM Circulator D 47/mo_ RPM MOISTURE (DEW POINT)
ME-9306 /-57_d e g F ME-9307 <-57 deg F SECONDARY COOLANT FEEDWATER FLOW Loop 1 o Ibs/hr Loop 2 o __1bs/hr TOTAL __ o _1bs/hr MAIN STEAM L;:; ' Pressure tv9' PSIG Temperature Jtf deg F Loop 2 Pressure 3/50 PSIG Temperature . 700 des F HOT REHEAT Loop 1 Pressure o PSIG '
. Temperature om des F Loop 2 Pressure _
r, PSIG Temperature /r -o deg F COLD REHEAT Loop 1 Pressure o PSIG l Temperature /? v> des F Loop 2 Pressure o PSIG ; Temperature /gro deg F l l i
e ', RADIATION MWITIES SCENARIO TIME aq: Is . PROCESS M(Ef!TM S CLOCE TIME io:is IEBIBER SENSITIVITY VALUE ALtJtNING (Y/N) RT-4801 ,,,,2. 6E-10 ** 1.O E +1 CPM M a RT-4802 1. 2E-10_,,,,_ **,_,,,_ l . o E +l CPM M RT-4803 2.5E-S t,o E *l CFM N RT-6212 2.2E-8 I.o E .4 CPM N RT-6213 _,,,,,2. 2E-8 -f.o E +1 'CPN N RT-7312 ,,_,,,2. 35-8 ___ *(PCRV) . , , 2.0 E A -CPH Y _ RT-7324-1 2.GE-8 3. 3 E + 4 CPM N - RT-7324-2 8. 9E-7 ,_,,_ l.I E +3 CPN Al l RT-7325-1 OOS_,_ 005 _ 008 RT-7325-2. 00S_, , 003 00S_ RT-73437 4.6E-10 ** t.o E +1 CPM M RT-73437-2 OCS- 008 ,,- 008 RT-9301' 2.3E 8 L.S E 4 CPN Y-RT-93252-12 _ _,,N/A 5. O E + 0 mr/hr- Y AREA M(E N NUMBER VALUR ALARMING (ar/hr) (Y/N) RT-93250-1 700.0 . Y RT-93250-2 2o00 Y RT-93250-3 so V RT-932504 ~ 2.co.o Y l
/^ RT-93250-5 n. 5" O
- RT-93250 _
lo o. o Y RT-93250-13 0./ Al RT-93250-14 o% M RT-93251-1 dSL M RT-93251-3 S0.0 V RT-93251-4 oS Al RT-93251-5 2 oo. o Y RT-93251-6 2oo. o _._ V RT-93251-7 2 oo. o Y RT-93251-8 E co. o Y RT-93251-9 2 oo. o Y i RT-93252-1 Ioo. o Y RT-93252-2 2.oo.o Y-t RT-932524 Jr.o O RT-93252-4 2 00.0 V RT-93252-7 __ Eoo. O V RIA-79511 c. 6 M
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NETER MLOGICAL DATA WIND SPEED 5.0 MPH , WIND DIRECTIM FR(3t 270 DEGREES PLUME DE7IATIW/
- l. SIGNA TIETA 2.O DEGREES DIFFERENTIAL TEMPERATURE + 4.0 DEGREES T O
- Value corresponds to the - PCRV area channel. Other four channels are '
30 cym.
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
' PRIMARY AUXILIARIES
_ _ _ , , ., BOARD I-01 GAS WASTE SYSTEM 63 Normal LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal BOARD I-02 i HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /f PSIG High Pressure Bottles # 90 PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow x@v GPM BUBW Header Pressure roGs PSIG HELIUM CIRCULATORS SYSTEM 21 Normal BOARD I-03_
/~' 's )\ REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position O INCHES Runback group positions 2A, rod #2 O INCHES rod #4 0 INCHES rod #6 O INCHES 4F, .od #25 0 INCHES rod #31 0 INCHES rod #37 d INCHES Flux Controller position 4/- N/4 %
Reserve Shutdown Mat.erial h r/re/ _ STATUS 4 u>
BOARD I-05 .I HYDRAULIC OIL SYSTEM 91 Normal
}
STEAM WATER DUMP TANI SYSTEM 22 Loop Selected / 1 or 2 Pressure /fd PSIG Temperature JS5 deg F Level 96 INCHES Radiation fd-(d ar/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD a-06 EMERGENCY FEEDWATER PRESSURE 41/ PSIG () BOILER FEED PUMPS A Speed O RPM A Flow o lbs/hr B Status - 63 on/off B Flow o lbs/hr C Speed 0 RPM C Flow 0 lbs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Tank M PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal SERVICE AIR SYSTEM 82 Normal __________________J
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BOARD I-10 PLANT PROTECTIVE SYSTEM V RI BUILDI N TEMPERATURE-HIGH BAY.104 BAT 200
> (P des F' y /50 deg F BAY 300 y /So deg F l REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 Z/ mr/hr Bay 1100 e/ mr/hr Bay 1000 </ mr/hr Loop 2 Bay 300 / mr/hr Bay 500 / mr/hr Bay 400 /, f ar/hr MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-13 j PENETRATION INTERSPACE dP / PSID RI BUILDING SUMP DISCHARGE FLOW 0 GPM BOARD I-15 RX STACK FLOW d!,000 ACFM RX BUILDING / AMBIENT dP -o M PSID
_ BOARD I-7507X CONTROL ROOM TEMPERATURE 47 deg F 480V ROOM TEMPERATURE E deg F
-FOSAVEX 87 FOR: .. OPERATOR. MESSAGE NO. // /
LOCATION: FSV SWITCHBOARD TIME: 1030 l XXXXXXXXXXXXXXXXXXXXXXXXXXXX;;XXXXXXXXXXXXXXXXXXXXXXXX THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX MESSAGE: - I represent Accident Cleanup Inc. I heard about your accident on television. Sounds like you are going to need some help. I can send three HP Technicians and two .! Chemists to your site tomorrow. What time should they be j there, and how many more HP's will you need next week?
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XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS IS A DRILL - XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX J
.u e
FOSAVEI '87 (q Scenario time Md
/ OVERALL PLMIT PARAMETERS Clock time /sso l
Rx Power 995 Turbine Generator Load O MW PRIMARY COOLANT PRESSURE 4 10 PSIA TEMPERATURE Circulator Inlet MO deg F Core Outlet M 7o des F HELIUM FLOW Loop 1 J700 lbs/hr Loop 2 /> lbs/hr TOTAL __J '7 vo lbs/hr CIRCULATOR SPEED Circulator A /#0 RPM Circulator B e3ao RPM Circulator C < 300 RPM Circulator D < 300 RPM MOISTURE (DEW POINT) ME-9306 4-57 deg F ME-9307 <-S? deg.F O' SECONDARY COOLANT FEEDWATER FLOW Loop 1 r> lbs/hr Loop 2 O lbs/hr ' TOTAL 0 lbs/hr MAIN STEAM , Loop 1 Pressure 4</ PSit? Temperature 45T deg F Loop 2 Pressure 1/dC PSIG Temperature Rd deg F HOT REHEAT Loop 1 Pressure o PSIG Temperature fico des F Loop 2 Pressure o PSIG Temperature neo deg F COLD REHEAT Loop 1 Pressure O PSIG Temperature /Mo dag F Loop 2 Pressure .
> PSIG Temperature # % _deg F
RADIATIM M(BIITtMt3 SCENARIO TIME 04.3o
. . . . PROCESS MONITtRS CLOCK TIME 1o: 30 SENSITIVITY NUMBER" VALUE ALARMING (Y/N)
F G W1 2.68-10___, ** l. O E <-l CPM M
's* 4802 1.2E-10__ ** p.O E +1 CPM N RT-4803 2.5E-8 ~
I, o E 4-1 CPM N RT-6212 2.2E-4. I.0 E +f CPM W RT-6213 2.2E-8 f.o E ,1 CPM M RT-7312 2.38-8 *(PCRV) 2.0 E +4 CPM y RT-7324-1 2.8E-4 3 ,'3 E + 4 CPM M RT-7324-2 8.9E-7 1. I E + 3 CPM -M RT-7325-1 008 008 008 RT-7325-2 005 _ 003 008 RT-73437-1 4.6E-10,_, **- 1. O E + 1 CPM N RT-73437-2 005 ,_, 003 005 RT-9301 2.3E-8 G,. S E + 7 CPM Y RT-93252-12 N/A F. 0 E + O ar/hr Y ARIA MONITORS NUMBER VALUE ALARMING (ar/hr) (Y/N) RT-93250-1 200.0 Y RT-93250-2 2 oc.o Y RT-93250-3 50 V RT-93250-4 2.0o.0 Y-O RT-93250-5 RT-93250-4 RT-93250-13 a, f to o. o M Y-0.I Al RT-93250-14 o $t. . Al RT-93251-1 Ost. M RT-93251-3 So.o M RT-93251-4 o.5- Al RT-93251- 5 ~ 2 oo. o Y RT-33251-6 Zoo.o Y __ RT-93251-7 2 o o. o Y ~ RT-93251-4 2 oo. o Y RT-93251-9 2 oo. o Y RT-93252-1 Ioo. o Y ! RT-93252-2 f- oo.o Y RT-93252-4 f.o V RT-93252-6 2 00.O V - I l RT-93252-7 Loo. O V l RIA-79511 c. S M KETF8M W ICAL DATA i WIND SPEED F. 0 MPE . j WIND DIRECTIM FRW . . , 2'70 DEGREES PLUME DEVIATIN/ 2.O SIGNA TERTA DEGREES DIFFERENTIAL TEMPERATURE +. 4. 0 DEGREES F O
- Value corresponds to the PCRV area channel. Other four channels are j l
30 cym. '
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
PRIMARY AUXILIARIES l
-( BOARD I-01 l!
GAS WASTE SYSTEM 63 Normal LIQUID WASTE SYSTEM 62 Normal I RZACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal BOARD I-02 HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /f PSIG i High Pressure Bottles 9*3 PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow A?co GPM BUBW Header Pressure l dos si PSIG l l HSLIUM CIRCULATORS SYSTEM 21 Normal O k-BOARD I-03_ l REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position ;, INCHES Runback group positions 2A, rod #2 __ o INCHES rod #4 o INCHES rod #6 _ o INCHES > 4F, rod #25 0 INCHES rod #31 O INCHES rod #37 o . INCHES Flux Controller position +/- N/d % Reserve Shutdown Material fave/WI STATUS l
BOARD I-05 l O i]8 HYDRAULIC OIL SYSTEM 91 Normal STEAM WATER DUMP TANK SYSTEM 22 Loop Selected / 1 or 2 Prescure Md PSIG Temperature M52 deg F Level 27 INCHES Radiation Jo-w mr/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE D!! RING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06 - EMERGENCY FEEDWATER PRESSURE [ PSIG
/
BOILER FEED PUMPS j A Speed O RPM l A Flow // lbs/hr B Status 4/ on/off { B Flow O lbs/hr C Speed 0 RPM l j C Flow 0 _lbs/hr l CONDENSATE SYSTEM 31 Normal l l MISCELLANEOUS Bypass Flash Tank o PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TO.IR SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal j l FIREWATER SYSTEM 45 Normal
]
INSTRUMENT AIR SYSTEM 82 Normal SERVICE AIR SYSTEM 82 Normal 4 1 l _ -J
BOARD I-10 ~ PLANT PROTECTIVE SYSTEM RX BUILDING TEMPERATURE-HIGH BAT 100 >/r0 des F BAY 200 >KO deg F BAY 300 >ra deg F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 4/ mr/hr Bay 1100 4/ ar/hr Bay 1000 </ mr/hr Loop 2 Bay 600 Bay 500
/ _ar/hr
/ mr/hr Bay 400 /. 5 mr/hr MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-13 PENETRATION INTERSPACE dP '/ PSID RX BUILDING SUMP DISCHARGE FLOW -0.or GPM BOARD I-15 Fr. STACK FLOW E ar) ACFM RX BUILDING / AMBIENT dP -0.;r PSID BOARD I-7507X CONTROL ROOM TEMPERATURE 67 deg F 480V ROOM TEMPERATURE hi" deg F l
l O i l l
a FOSAVEX '87 API' () OVERALL PLANT PARAMETERS Scenario time Clock time /#+'j[-~ Rx Power f//6 Turbine Generator Load 0 _MW PRIMARY COOLANT 1 PRESSURE &c0 _ PSIA TEMPERATURE Circulator Inlet /12 deg F Core Outlet 22+'d des F HELIUM FLOW Loop 1 +44s> lbs/hr Loop 2 _ o lbs/hr TOTAL </44r> lbs/hr CIRCULATOR SPEED Circulator A /9TN RPM Circulator B <200 RPM Circulator C <tm RPM . Circulator D /300 RPM l MOISTURE (DEW POINT) - ME-9306 2-5? des F- ! ME-9307 <-s9 deg F I SECONDARY COOLANT FEEDWATER FLOW Loop 1 6 lbs/hr ) Loop 2- m lbs/hr TOTAL 0, lbs/hr - MAIN STEAM Loop 1 Pressure 49' PS1G Temperature otrf des F Loop 2 Pressure J L PSIG Temperature 0'ed deg F HOT REHEAT Loop 1 Pressure o PSIG Temperature EGO des F Loop 2 Pressure 9 PSIG - Temperature // -a deg F
' COLD REHEAT Loop 1 Pressure O PSIG Temperature /no des F Loop 2 Pressure a PSIG Temperature /nD deg F .
lO
RADIATION HMITORS SCENARIO TIME o4: 45 PROCESS MONITORS CLOCK TIME 10: 4 5 NUMBER SENSITIVITY VAIRE ALARMING (Y/N) ' RT-4401 2.6E-10 ** I, o E + l CPM N
~
RT-4402 1.2E-10 ** 1. O E 4- 1 CPM M RT-4803 2.5E-8 f.o E +1 CPM Aj RT-6212 2.2E-8 I.o E +( CPM y RT-6213 _ 2.2E-8 f.o E ,1 CPM M RT-7312 2.3E-8 ___ *(PCRV) 2. o E + 4 CPM Y RT-7324-1 2.8E-8 3. 3 E + 4 CPM N - i
- RT-7324-2 8.92-7 l.I E +3 CPM M RT-7325-1 OOS _
00S 005 RT-7325-2 ,____003 OOS 00S RT-73437-1 ** l. o E 4- 1 CPM N 4.6E-10___ RT-73437-2 OOS_ OOS 005 KI-9301 2.3E-8 %oE +.'7 CPM Y RT-93252-12 N/A 5. O E + 0 mr/hr Y ' AREA MONITORS l NUMBER VALUE ALARMING l (ar/hr) (Y/N) l RT-93250-1 200.o Y I RT-93250-2 2oo.o Y ' RT-93250-3 s0 O RT-93250-4 2.co.o Y S RT-93250-5 RT-93250-8 RT-93250-13
- n. f 2.o o. o 0./
M Y Al RT-93250-14 0$L Al RT-93251-1 _ ost. Al RT-93251-3 50.0 A/ RT-93251-4 o.5 Al RT-93251-5 2 oo. o Y RT-93251-6 2 oo. o V RT-93251-7 2 ao. o Y RT-93251-8 2 oo. o Y RT-93251-9 2 ao. o Y RT-93252-1 I o'o. o Y RT-93252-2 Z. co. o Y RT-93252-4 2.o O RT-93252-4 2 00.0 V RT-93252-7 4co. O _ V RIA-79511 c. 6 M METER 0RLOGICAL DATA WIND SPEED 5: 0 MPH , WIND DIRECTION FROM 270 DEGREES PLUME DEVIATION / SIGMA THETA 2. O DEGREES DIFFERENTIAL TEMPERATURE + 4. 0 DEGREES F O
- Value corresponds to the PCRV area channel. Other four channels are 30 cym.
** .Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
PRIMARY AUXILIARIES l () _ BOARD I-01 GAS WASTE SYSTEM 63 Normal LIQUID WASTE SYSTEM 62 Normal 4 REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal ROARD I-02 { l HELIUM STORAGE SYSTEM 24 I Low Pressure Bottles /9 PSIG High Pressure Bottles C40 PSIG l EMERGENCY FEEDWATER SYSTEM 31 < Emergency Feed Flow / ens GPM BUBW Header Pressure Ster PSIG HELIUM CIRCULATORS SYSTEM 21 Normal BOARD I-03_ REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position O INCHES Runback group positions 2A, rod #2 o INCHES
- rod #4 6 INCHES rod #6 a INCHES 4F, rod #25 b INCHES rod #31 6 INCHES rod #37 .
6 INCHES Flux Controller position +/- ///4 % Reserve Shutdown Material JLo<rlec[ STATUS i i l I ([3) i l
L
- l .
BOARD I-05 () HYDRAULIC OIL SYSTEM 91 Normal l STEAM WATER DUMP TANK SYSTEM 22 l Loop Selected ' 1 or 2 Pressure /VO PSIG Temperature J r0 deg F Level or INCHES Radiation Jt-vo ar/hr ' HELIUM CIRCULATORS SYSTEM 21 Normal NOTE , LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO i "0" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06
' EMERGENCY FEEDWATER PRESSURE 4+/'PSIG BOILER FEED PUMPS 1 A Speed O RPM A Flow o lbs/hr
~
B Status o on/off B Flow a lbs/hr C Speed o RPM C Flow d Ibs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypasa Flash Tank O PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal () SERVICE AIR SYSTEM 82 Normal
e BOARD I-10 PLANT-PROTECTIVE SYSTEM RX BUILDINGrTEMPERATURE-HIGH BAT 100 >/rv. des F BAY.200 3, co deg F
. BAY 300 p/fd des F REHEAT .CTIVITY MONITORS Loop 1 Bay 1200 4/ ar/hr Bay 1100 e/ ar/hr Bay 1000 er ar/hr Loop 2 Bay 600 e/ ar/hr Bay 500 / ar/hr-Bay 400 /, ( ar/hr MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-13 PENETRATION INTERSPACE dP Y' PSID RX BUILDING SUMP DISCHARGE FLOW 0 GPM U BOARD I-15 RX STACK FLOW JJsar> ACFM RX BUILDING / AMBIENT dP -0Jf PSID BOARD I-7507X CONTROL ROOM TEMPERATURE. 67 deg F 480V ROOM TEMPERATURE ?? des F )
i O [ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . . . _ _ _ _ _ _
FOSAVEI '87 Scenario time _t5 e h' t OVERALL PLANT PARAMETERS Clock time /mo Rx Power Pd/S Turbine Generator Load o MW PRIMARY COOLANT PRESSURE 6,75 PSI A TEMPERATURE Circulator Inlet /7f deg F Core Outlet /os o deg F HELIUM FLOW Loop 1 SSDd Ibs/hr Loop 2 o lbs/hr TOTAL _Jrvo lbs/hr CIRCULATOR SPEED Circulator A /65D RPM Circulator B s2go RPM Circul:2 tor C z w RPM Circulator D < t cro RPM MOISTURE (DEW POINT) ME-9306 4-59 deg F ME-9307 <-s7 deg F SECONDARY COOLANT 3 FEEDWATER FLOW I Loop 1 o lbs/hr 2 Loop 2 C/ lbs/hr TOTAL 0 lbs/hr MAIN STEAM Loop 1 Pressure # PSIG Temperature d?ST deg F Loop 2 Pressure Accc PSIG Temperature 840 deg F HOT REHEAT Loop 1 Pressure 'O PSIG
. Temperature MO des F Loop 2 Pressure _ PSIG Temperature #m deg F COLD REHEAT !
Loop 1 Pressure O PSIG I Temperature RJ deg F ! Loop 2 Pressure O PSIG Temperature /000 deg F I _m_ _________m___ _ _ _ - _ _ _ - . _ _ - _ - _ _ _ -
RADIATION MINITtRS SCENARIO TIME oS1oo PROCESS NINITORS CLOCK TIME 1i:oo __ NOMBER SENSITIVITY VALUE AIwUtMING (Y/N) RT-4801 2. 6E-10_,,,,,, ** l.O E + f _ CPM U RT-4802 1.2E-10 ** l,O E +i CPM Al RT-4803 ,,,,,,,,,2. 5 E-8 f.o E +1 CPN O , RT-6212 2.2E-4 _ -I.o E ,i CPM - N j RT-6213 2.2E-8 f.o E +1 CPN V RT-7312 2.3E-4 _ *(PCRV) 2.0 E e4 CPM V RT-7324-1 2.82-8 3. 3 E + 6- CPN M - RT-7324-2 8.9E-7 f. I E e 3 CPN W RT-7325-1 003 00S 003 RT-7325-2 003 008 008 RT-73437-1 4.6E-10___ ** I. O E +1 CPM M RT-73437-2 008 003 003 RT-9301 2.3E-4 7.o E c 1 CPM Y RT-93252-12 N/A' __ S.O E eO ar/hr V ARIA MONITURS NUMBER VALUE ALARMING ) (ar/hr) (Y/N) RT-93250-1 2o0.0 Y RT-93250-2 2 oo.o Y RT-93250-3' s0 0 RT-93250-4 1 00.0 Y O RT-93250-5 RT-93250-8 RT-93250-13
- n. f to o. o d./
M Y M RT-93250-14 o$L - M RT-93251-1 dSL Al RT-93251-3 S0.0 V RT-93251-4 o. 5" M RT-93251-5 2 oo. o Y RT-93251-6 Eoo. o V RT-93251-7 2 oo. o Y RT-93251-8 2 co. o Y RT-93251-9 2 oo. o Y RT-93252-1 I oo. o Y RT-93252-2 1 oo.o Y RT-93252-4 E.o O RT-93252 2 00.0 V RT 93252-T Ioo. O V RIA-79511' O. 6 U METER (RLOGICAL DATA WIND SPEED F.0 MPH , WIND DIREC120N FR(3( 2*70 DEGREES FLIRfE DE9'If2IL9/ SIGMA M ETA 2. O DEGREES DIFFERENTIA!. TEMPERATURE + 4.0 DEGREES F
- Value corresponds to the PCRV area channel.
~ Other four channels are 30 cym.
** Value corresponds to a 15 minute build-up of actavity. Build-up starts at the specified scenario / clock time.
l^ PRIMARY AUXILIARIES I BOARD I-01 GAS WASTE SYSTEM 63 Normal LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal ! PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal ROARD I-02 HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /9 PSIG High Pressure Bottles PV/- PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow /W GPM BUBW Header Pressure 106f PSIG HELIUM CIRCULATORS SYSTEM 21 Normal BOARD I-03_ REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position o INCHES Runback group positions 2A, rod #2 o INCHES rod #4 o INCHES rod #6 c) INCHES 4F, rod #25 o INCHES rod #31 o INCHES cod #37 0 INCHES Flux Controller position +/- /v/4 % Reserve Shutdewn Material @ w &ci STATUS O
l BOARD I-05 () HYDRAULIC' OIL SYSTEM 91 Normal STEAM WATER DUMP TANK SYSTEM 22 Loop Selected / 1 or 2 Pressure ./40 PSIG Temperature J51 deg F Level 75' INCHES Radiation c#o vd ar/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE I LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. ; THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06 EMERGENCY FEEDWATER PRESSURE 6/ PSIG BOILER FEED PUMPS A Speed O RPM A Flow o lbs/hr B Status ofF on/off B Flow o lbs/hr C Speed o RPM C Flow o lbs/hr ' CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypasa Flash Tank o PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal () SERVICE AIR SYSTEM 82 Normal
BOARD I-10 PLANT PROTECTIVE SYSTEM r (3) RI BUILDINF TEM:REATURE-HIGH BAY 100 p/59 des F BAY 200 y/so des F BAY 300 > /r> d e s F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 c/ mr/hr Bay 1100 </ mr/hr Bay 1000 , </ ar/hr Loop 2 Bay 600 / ar/hr Bay 500 / mr/hr Bay 400 /,5 mr/hr MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal _ BOARD I-13 PENETRATION INTERSPACE dP / PSID RX BUILDING SUMP DISCHARGE FLOW d GPM
! BOARD I-15 RX STACK FLOW JK ACFM RX BUILDING / AMBIENT dP -d,/ PSID ,
i BOARD I-7507X J CONTROL ROOM TEMPERATURE 57 deg F 480V ROOM TEMPERATURE PT deg F i O
- wa+
t FOSAVEI '87 Scenario time 3/ f l O OVERALL PL&NT PARAMETERS Clock time ///3-Rx Power 76 Turbine Generator Load o MW PRIMARY COOLANT PRESSURE 4 70 PSIA TEMPERATURE Circulator Inlet /?( deg F Core Outlet 900 deg F HELIUM FLOW Loop 1 67&o lbs/hr Loop 2 o lbs/hr ; TOTAL 69&o lbs/hr CIRCULATOR SPEED
. Circulator A , /0/o RPM Circulator B (TUD RPM Circulator C 2:0e RPM Circulator D <.200 RPM MOISTURE (DEW POINT)
ME-9306 en deg F
- c. ME-9307 < - 53 deg.F SECONDARY COOLANT _ _ _
FEEDWATER FLOW - Loop 1 o lbs/hr Loop 2 o lbs/hr TOTAL 0 lbs/hr MAIN STEAM Loop 1 Pressure 54/ PSIG Temperature o rms deg F Loop 2 Pressure /950 PSIG Temperature (so deg F HOT REHEAT Loop 1 Pressure o PSIG
. Temperature 22 0 deg F Loop 2 Pressure o PSIG Temperature / ran d eg F COLD REHEAT Loop 1 Pressure o PSIG Temperature Sn9 deg F Loop 2 Pressure o PSIG Temperature /tro d eg F
RADIATI M M ITORS SCENARIO TIME O 6: I5 130CE88 MtRf!20R8 CLOCR TIE 2 i I: 1T O - -= = - (Y/N) RT-4401 2.65-10 ** 1. O E + l CPM M RT-4802 1.2E-10 ** 4.O E +1 CPM M RT-6403 2.5E-8 1. o E + 1 CPM d RT-6212 2.2E-8 I.o E +i CPM M RT-6213 ___2.2E-4 f.o E +d CPN M RT-7312 2.3E-8 *(PCRV) _ 2. o E + 84 CPM Y RT-7324-1 2.8E-8 3. 3 E +4 CPM M - i RT-7326-2 8.98-7 s. I E +3 CPM' W RT-7325-1 005 008 005 RT-7325-2 005 003 008 RT-73437-1 4.6E-10__,, ** 1. 0 E + 1 CPM ,,_, PJ RT-73437-2 003 005 008 AT-9301 2.3E-8 7. 0 E +7 CPM Y RT-93252-12 !!/A__ S.o E co ar/hr _ Y ARIA N NONRER VALUR ALARMING ! (ar/hr) (Y/N) RT-93250-1 RT-93250-2 2o0.0 2oo.0 { ! RT-93250-3 ao O RT-93250-4 2. o.o Y l
% RT~93250-5 ~ a. f M RT-93250-8 1.o o. o .Y RT-93250-13 d./ Al RT-93250-14 o $t -
Al RT-93251-1 ost Al RT-93251-3 S0.0 __ hl RT-93251-4 o.r M RT-93251-5 200,o Y RT-93251-6 ~~' f.oo. o Y RT-93251-7 2 oo. o Y RT-93251-8 2 co. o Y - RT-93231-9 2 oo. o Y RT-93252-1 Ioo.o Y RT-93252-2 L oo.0 Y RT-93252-4 2.o O RT-93252-6 2 00.0 Y RT-93252-7 Loo. O Y RIA-79511 c. 5 M METER 0RLOGICAL DATA Eo
~
WIND SPEFD MPE . WIND DIRICTION FRW 270 DEGREES PLUME DEVIATION / SIGNA TIETA 2. O DIGREE5 DIFFERENTIAL TEMPERATURE + 4.0 DEGREES T O
- Value corresponds to the PCRV area channel. Other four channels are 30 cym.
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
PRIMARY AUXILIARIES BOARD I-01 GAS WASTE SYSTEM 63 Normal LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal i PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal BOARD l-02 HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /9 PSIG High Pressure Bottles iVS PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow Avtd GPM BUBW Header Pressure SOM PSIG HELIUM CIRCULATORS SYSTEM 21 Normal 1
~
BOARD I-03 REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position O INCHES Runback group positions 2A, rod #2 d INCHES rod #4 0 INCHES rod #6 __ 0 INCHES 4F, rod #25 0 INCHES rod #31 0 INCHES rod #37 o INCHES Flux Controller position +/- N/# % Reserve Shutdown Material JGard'ed STATUS 2 c::> l
l BOARD I-05 i HYDRAULIC 0IL SYSTEM 91 flormal .} STEAM WATER ~ DUMP TANK SYSTEM 22 Loop Selected / 1 or 2 Pressure _ 7t; PSIG Temperature 357 deg F Level 95 INCHES Radiation Jo -+'d mr/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE - LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. ( MAIN TURBINE SYSTEM 51 Normal BOARD I-06 _ EMERGENCY FEEDWATER PRESSURE 64/ PSIG () E0ILER FEED PUMPS A Speed o RPM A Flow 0 lbs/hr B Status J# on/off B Flow o lbs/hr C Speed 0 RPM C Flow 0 lbs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Tank O PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal SERVICE AIR SYSTEM 82 Normal {
BOARD I-10
,_s PLANT PROTECTIVE SYSTEM N RI BUILDINGLTIMPERATURE-HIGH BAY IOS 7/r0 deg F BAY 200 pfry deg F BAY 300 y,r0 deg F l REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 2/ mr/hr Bay 1100 e/ mr/hr
' day 1000 e/ ar/hr Loop 2 Bay 600 e/ mr/hr Bay 500 /
mr/hr Bay 400 /.5 mr/hr MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-13 PENETRATION INTERSPACE dP 4' PSID RI BUILDING SUMP DISCHARGE FLOW -oar GPM BOARD I-15 RI STACK FLOW .% d00 ACFM RI BUILDING / AMBIENT dP -0.3 7 PSID BOARD I-7507I, CONTROL ROOM TEMPERATURE di deg F 480V ROOM TEMPERATURE II deg F O i m_________________------_.--- -
FOSAVEX 87 , j FOR: OPERATOR _ MESSAGE NO. /2
~ .
l LOCATION: HDQTS SWITCHBOARD TIME: 1130 l I XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS IS A DRILL l DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX MESSAGE: - Two Ebasco maintenance workers have arrived at University Hospital - Denver, claiming they were exposed to high levels of radiation. They were doing maintenance at the Met Tower and said they did not hear the evacuation alarm.
-O .
O s 4 4e XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS IS A DRILL XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX I
e FOSAVEI '87 Scenario time 330 O OVERALL PEAAT PARAMETERS Clock time //30 { Rx Power 9t /6 \- Turbine Generator Lcad o MW PRIMARY COOLANT PRESSURE bhi PSIA TEMPERATURE Circulator Inlet af deg F Core Outlet 70er d eg F HELIUM FLOW Loop 1 9ffo lbs/hr Loop 2 o lbs/hr TOTAL 99&o ibs/hr CIRCULATOR SPEED Circulator A /8/o RPM Circulator B z 'co RPM Circulator C e 200 RPM Circulator D < 3 00 RPM MOISTURE (DEW POINT) ME-9306 /-r? deg F ME-9307 4 - S*> deg F SECONDARY COOLANT FEEDWATER FLOW Loop 1 O lbs/hr Loop 2 lbs/hr TOTAL 0 lbs/hr l MAIN STEAM l Loop 1 Pressure CV PSIG Temperature str deg F Loop 2 Pressure /<f00 PSIG Temperature fr00 deg F HOT REHEAT Loop 1 Pressure o PSIG
. Temperature Re deg F Loop 2 Pressure 9 PSIG Temperature /m deg F COLD REHEAT Loop 1 Pressure J PSIG Temperature 9'/0 deg F Loop 2 Pressure a PSIG Temperature 9fo deg F O
4 RADIAT!W N(BOI M SCENARIO TIME ost30 PROCESS NtalITURS CIACE TIME i I .* 3 0 j NtBIBERs SDISITIVITY VALUE ALARNING-(Y/N) RT-4801 2.6E-10 ** I, o E + 1 CPN. M RT-4802 1.2E-10 ** I,o E el CPN M RT-4803 2.5E-8 1. o E + l CPN N , RT-6212 2.2E-4 I. o E W CPM . O RT-6213 2.2E-8 f.o E +1 CPN u 1 RT-7312 ___2.3E-8 *(PCRV) 2.o E # CPN Y ! RT-7326-1 2.88-4 3.3 E +9 CPN M - RT-7324-2 8.9E-7 i, i E +3 CPM M RT-7325-1 003 008 008 ' RT-7325-2 008 003 008 RT-73437-1 4.6E-10 ** l.0 E +1 CPM M RT-73437-2 003 008 008 RT-9301 2.3E-4 _
- v. 5 E +7 CPN Y RT-93252-12 N/A 5 0 E + 0 ar/hr Y AREA NCBffTtXS NUMBER VALUE ALARNING (nr/hr) (Y/N) !
RT-93250-1 200.O Y a RT-93250-2 2 oo.0 V , RT-93250-3
- sO V 1 RT-93250-4 2.co.o Y f RT-93250-5 M O RT-93250-8 RT-93250-13
- n. f to o. o d./
Y M . , _ _ , j i RT-93250-14 o%- Al __ RT-93251-1 ost. Al RT-93251-3 S0.0 M RT-93251-4 o "I Al RT-93251-5 2 oo. o V l RT-93251-6 f.oo. o V l RT-93251-7 2 oo. o Y l RT-93251-8 ~ 2 co. o -Y RT-93251-9 2 oo. o Y RT-93252-1 I oo. o Y RT-93252-2 L oo.0 Y RT-93252-4 E.o V RT-93252-6 2co0 V I RT-93252-7 Loo. O V RIA-79511' O. 6 M NETER MLOGICAL DATA WIND SPEED 50 MPR . WIND DIRECTION FRW 2 70 ___ DEGREES PLUME DEVIATIW/ SIGNA TEETA 2.O DEGREE 8 DIFFERENTIAL TEMPERATURE _
+ 4.0 DEGREE 8 F O
- Value cosi Ws to the PCRV area channel. Other four channels are
)
30 ep.
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
PRIMARY AUXILIARIES () BOARD I-01 GAS WASTE SYSTEM 63. Normal LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal ROARD I-02_- HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /9 PSIG High Pressure Bottles ;'9 FSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow #xso GPM BUBW Header Pressure 2005 PSIG HELIUM CIRCULATORS SYSTEM 21 Normal BOARD I-03_ A-) REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position 0 INCHES { Runback group positions 2A, rod #2 o INCHES rod #4 ./ INCHES rod #6 0 INCHES 4F, rod #25 0 INCHES rod #31 n INCHES rod #37 u INCHES Flux Controller position +/- r/4) % Reserve Shutdown Material L e hrd STATUS O I
i' BOARD I-05 HYDRAULIC OIL: SYSTEM 91- Normal ) STRAM WATER DUMP TANK SYSTEM 22 Loop Selected / 1-or 2-Pressure /tJ PSIG Temperature 3cr des F-Level or INCHES Radiation- Jo-t'o ar/hr
~
HELIUM CIRCULATORS SYSTEM 21- ' Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. i
'THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES.
MAIN TURBINE SYSTEM 51 Normal BOARD'I-06 EMERGENCY FEEDWATER PRESSURE 49I PSIG BOILER FEED PUMPS A Speed o RPM A Flow o lbs/hr B Status o A7 on/off B Flow o lbs/hr C Speed a RPM C Flow o lbs/hr , CONDENSATE SYSTEM 31 Normal MISCELLANEOUS J Bypass Flash Tank O PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal SERVICE AIR SYSTEM 82 Normal
~
BOARD I-10 PLANT PROTECTIVE SYSTEM l
/~~ i 'A -
RI BUILDING-TEMPERATURE-HIGH BAT 100 ><3ns deg F Bf7 200 >/ro deg F BAY 300- >en; deg F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 4/ mr/hr Bay 1100 e/ mr/hr Bay 1000 c/ ar/hr Loop 2 Bay 600 er ar/hr Bay 500 / mr/hr Bay 400 /r er/hr MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-13 PENETRATION INTERSPACE dP 9/ PSID RI BUILDING SUMP DISCHARGE FLOW O GPM i
\
(,)\ _ BOARD I-15 RI STACK FLOW -?LCA9ACFM RX BUILDING / AMBIENT dP -0,2r PSID BOARD I-7507% CONTROL ROOM TEMPERATURE G47degF 480V ROOM TEMPERATURE Rf deg F i I l
)>
FOSAVEI '87 7- Scenario time T+5F OVERALL PLABT PARAMETERS Clock time /4s" Rx Power f&S Turbine Generator Load a MW PRIMARY COOLANT PRESSURE G7T PSIA TEMPERATURE Circulator Inlet /ZT deg F Core Outlet sve- deg F HELIUM FLOW Loop 1 //dav lbs/hr Loop 2 o lbs/hr TOTAL Nm lbs/hr CIRCULATOR SPEED Circulator A /900 RPM Circulator B 23oo RPM Circulator C e f cro ., RPM Circulator D 43co RPM MOISTURE (DEW POINT) ME-9306 2-57 deg F ; ME-9307 <-s? deg F ( SECONDARY COOLANT FEEDWATER FLOW Loop 1 o lbs/hr Loop 2 O lbs/hr ' TOTAL o lbs/hr !
. MAIN STEAM Loop 1 Pressure 4V PSIG Temperature c o rr' deg F !
Loop 2 Pressure /PSD PSIG ; Temperature 7YO deg F HOT REHEAT , Loop 1 Pressure o PSIG
. Temperature 9Po deg F Loop 2 Pressure o PSIG Temperature um deg F COLD REHEAT Loop 1 Pressure 0 ,PSIG Temperature rz n deg F Loop 2 Pressure o PSIG Temperature 9+9 (eg F
'i RADIATION MONITORS SCDIARIO TIME 05:45 PROCESS MONITORS - CLOCK TIME I1.'45 NtBIBER SENSITIVITY VALUE ALARMING (Y/N)
RT-4401 2.6E-10 ** l. O E +- l CPM M
-RT-4402 1.2E-10 ** I,O E + I . CPM M RT-4803 2.5E-8 10E+l CPM A RT-6212 2.2E-8 I.0 E +i CPM M RT-6213 2.2E-8 f.o E +1 CPM M RT-7312 2.3E-8 *(PCRV) 2,2. E + 4 CPM Y RT-7324-1 ___,2.8E-8 l.4 E +5 CPM Y RT-7324-2 8.9E-7 _,_, 4.6 E + 3 CPM Y RT-7325-1 005 005 OOS RT-7325-2 00S 008 005 RT-73437-1 4.6E-10 ** 1. 0 E 4 l CPM M RT-73437-2 OOS 005 OOS RT-9301 2.3E-8 7. 5 E +7 CPM Y RT-93252-12 N/A 7 o E +0 ar/hr Y AREA MONITORS NUMBER VALUE ALARMING (ar/hr) (Y/N)
RT-93250-1 Ano.o N RT-93250-2 800.0 M RT-93250-3 5.0 M ' RT-93250-4' Boo.O Y RT-93250-5 2. 0 Y tO . RT-93250-8 RT-93250-13 Boo.o d./ Y M
- RT-93250-14 O5L M .__
RT-93251-1 05L M RT-93251-3 50.O M RT-93251-4 2.0 Y RT-93251-5 Aco. O Y RT-93251-6 Boo. O V RT-93251-7 Foo O f RT-93251-8 80o.0 ,, V RT-93251-9 Boo.o V l RT-93252-1 Boo.O Y i RT-93252-2 Boo. O Y RT-93252-4 8.o Y RT-93252-6 Boa o Y RT-93252-7 A co.o Y RIA-79511 2. O N METEROLOGICAL DATA WIND SPEED ?.0 MPH . WIND DIRECf A FROM 270 DEGREES FLUME DEV1.dION/ SIGNA THETA 2. O DEGREES DIFFERENTIAL TEMPERATURE + 4.0 DEGREES F
- Value corresponds to the PCRV area channel. Other four channels are 30 cym. l
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
1 PRIMARY AUXILIARIES I ( BOARD I-01 GAS WASTE SYSTEM 63 Normal LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal 1 LN-2 SYSTEM 25 Normal BOARD I-02 HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /9 PSIG High Pressure Bottles 9 90 PSIG i EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow /apo GPM BUBW Header Pressure 306s PSIG HELIUM CIRCULATORS SYSTEM 21 Normal BOARD I-03_ ,
\- REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position O INCHES Runback group positions l
2A, rod #2 d INCHES rod #4 O INCHES rod #6 o INCHES 4F, rod #25 n INCHES rod #31 O INCHES rod #37 0 INCHES Flux Controller position +/- N/A % Reserve Shutdown Material Efustekc/ STATUS l
BOARD I-05 el) HYDRAULIC OIL SYSTEM 91 Normal STEAM-WATER DUMP TANK SYSTEM 22 Loop Selected / 1 or 2 1 Pressure /9/s PSIG Temperature lid deg F Level 7C INCHES Radiation Jo - t'o ar/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO ,
"0" PSI FOR A SHUTDOWN CIRCULATOR.
THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06 EMERGENCY FEEDWATER PRESSURE 45/'PSIG BOILER FEE'D PUMPS A Speed O RPM A Flow o lbs/hr B Status 04: on/off B Flow o lbs/hr C Speed o RPM C Flow 0 lbs/hr CONDENSATE SYSTEM 31 Normal a MISCELLANEOUS Bypass Flash Tank o PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal I PLANT ELECTRICAL Normal MAIN TOWER , SYSTEM 41 Normal ! I SERVICE WATER TOWER SYSTEM 42 Normal I FIREWATER SYSTEM 45 Normal ! INSTRUMENT AIR SYSTEM 82 Normal () SERVICE AIR SYSTEM 82 Normal 1
~
BOARD I-10 PLANT PR01'ECTIVE SYSTEM j .Y
- L' RI BUILDING TEMPERATURE HIGH BAT 100 >/r0 deg F BAT 200 >/ro deg F BAY 300 >/ ro deg F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 /___mr/hr Bay 1100 / mr/hr Bay 1000 / mr/hr Loop 2 Bay 600 / mr/hr Bay 500 Ar ar/hr Bay 400 J,r ar/hr MOISTURE MONITORS (DEW POINT).-p Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-13 PENETRATION INTERSPACE dP PSID RX BUILDING SUMP DISCHARGE FLOW O GPM BOARD I-15 RX STACK FLOW 33,000 ACFM RX BUILDING / AMBIENT dP -0.8f PSID BOARD I-7507X CONTROL ROOM TEMPERATURE 49 deg F 480V ROOM TEMPERATURE _fE deg F t
'FOSAVEX 87 FOR:' OPERATOR MESSAGE NO. N l k -
TIME: 1200 LOCATION: HDQTS SWITCHBOARD XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX ! 1 THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX MESSAGE: Due to unusually warm weather, which is creating high system demand,_and the fact that the Pawnee and Zuni Stations are down for unexpected maintenance, a news release was issued yesterday calling for PSCC customers to curtail electrical use. You have received a call from Ken Headrick, Manager Northern Division, Fort Collins Office. He has received a number of calls from local hospitals and nursing homes. The callers were aware of yesterdays news release, and the accident at FSV. The hospitals were to be advised of the situation relative to potential power failures. This is particularly true of Fort Collins Community Hospital since its backiup electrical system'is down for maintenance. I i XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS IS A DRILL XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX U -
i
. .. k l
, \
FOSAVEI '87 r- Scenario time 36 0 l
; Q) OVERALL PLANT PARAMETERS Clock time non )
l Rx Power /ddAS j Turbine Generator Load a MW PRIMARY COOLANT ) PRESSURE 500 PSIA )' TEMPERATURE Circulator Inlet /05 des F Core Outlet 350 des F HELIUM FLOW Loop 1 A h lbs/hr Loop 2 n 1bs/hr TOTAL /Vrm lbs/hr CIRCULATOR SPEED Circulator A /9dC RPM Circulator B sJoo RPM Circulator C 43 eo RPM Circulator D 4 3eo RPM MOISTURE (DEW POINT) ME-9306 2-59 deg F ME-9307 <-c? deg F SECONDARY COOLANT FEEDWATER FLOW Loop 1 9 lbs/hr Loop 2 > lbs/hr
. TOTAL j lbs/hr MAIN STEAM Loop 1 Pressure 6V PSIG Temperature c/W des F Loop 2 Pressure 4 00 PSIG Temperature % des F HOT REHEAT Loop 1 Pressure O PSIG
, T6mperature ?',o des F Loop 2 Pressure C PSIG Temperature m) deg F UJ COLD REHEAT l Loop 1 Pressure 9 PSIG ero des FML Temperature Loop 2 Pressure a PSIG Temperature Svo deg F(U O
RADIATION HONI20RS SCENARIO TIME O(,.*0 0 PROCESS HONI'IORS CLOCE TIME l 2 .* O O q C/ NUMBER SENSITIVITY VALUE ALARMING (Y/N) RT-4801 2.6E-10 ** 954 CPM Y RT-4802 1.2E-10 ** OSW CPM Y RT-4803 2.5E-8 SSH ,, CPM Y RT-6212 2.2E-8 l. o E d CPM v RT-6213 2.2E-8 to E W CPM M RT-7312 2.3E-8 *(PCRV) OsW CPM Y , RT-7324-1 2.8E-8 45H CPM V RT-7324-2 8.9E-7 85E4 CPM Y RT-7325-1 OOS Cos 00S RT-7325-2 OOS OOS OOS RT-73437-1 4.6E-10 ** 3. 3 E+4 CPM Y RT-73437-2 OOS 005 OOS RT-9301 2.3E-8 A Y E #t. CPM M RT-93252-12 N/A 1. 2 E +2 mr/hr V AREA MONI20RS NUMBER VALUE ALARMING (ar/hr) (T/N) RT-93250-1 osu Y RT-93250-2 ooM ~ V RT-93250-3 2. o (+ 3 Y RT-93250-4 os4 Y RT-93250-5 2 o0. O Y O RT-93250-8 RT-93250-13 054 O./ M Y RT-93250-14 2. o 6 + 5 V RT-93251-1 2. o E + 3 Y RT-93251-3 2.o 6 *3 Y RT-93251-4 Loo.o Y RT-93251-5 osu Y RT-93251-6 05 4 V RT-93251-7 05 N- V RT-93251-8 05#4 Y RT-93251-9 05(4 V RT-93252-1 03 4 Y RT-93252-2 as H. Y RT-93252-4 2. o E+ 3 Y RT-93252-6 0.54 Y RT-93252-7 0.54 Y RIA-79511 T oo. o Y METER 0RLOGICAL DATA WIND SPEED 2. .O _ MPH , WIND DIRECTION FROM 270 DEGREES PLUME DL'VIATION/ SIGMA TEETA 2. O DEGREES DIFFERENTIAL IIMPERATURE +.4.0 DEGREES F 1
- Value corresponds to the PCRV area channel. Other four channels are 30 cpm.
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
PRIMARY AUXILIARIES ). BOARD I-01_ GAS WASTE SYSTEM 63 Normal LIQUID WASTE SYGTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal i LN-2 SYSTEM 25 Normal l BOARD I-02 HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /9 PSIG High Pressure Bottles 6s0 PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow /dut GPM BUBW Header Pressure Sogf PSIG HELIUM CIRCULATORS SYSTEM 21 Normal BOARD I-03, REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position O INCHES Runback group positions 2A, rod #2 o INCHES rod #4 o '~ INCHES rod #6 o INCHES 4F, rod #25 o INCHES i rod #31 o INCHES rod #37 o _ INCHES Flux Controller position +/- 4%o % Reserve Shutdown Material Imer/ecL STATUS e
i BOARD I-05 HYDRAULIC OIL SYSTEM 91 Normal (( ) STEAM WATER DUMP TANK SYSTEM 22 Loop Selected / 1 or 2 l Pressure /90 PSIG l Temperature a p3' deg F Level ?s" INCHES Radiation, Jo 'rd ar/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal ! BOARD I-06 _ EMERGENCY FEEDWATER PRESSURE 4s/'PSIG () BOILER FEED PUMPS A Speed O RPM A Flow d Ibs/hr B Status 46 on/off B Flow o lbs/hr C Speed a RPM C Flow n 1bs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Tank O PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal la \IN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal (} SERVICE AIR SYSTEM 82 Normal
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BOARD I-10
,-. PLANT PROTECTIVE SYSTEM
! ~
RX BUILDING TEMPERATURE-HIGH BAT 100 r/f0 des F BAY 200 pga deg F BAY 300 y'ro des F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 /ov ar/hr Bay 1100 zev ar/hr Bay 1000 A70 ar/hr Loop 2 Bay 600 /ou ar/hr Bay 500 eso ar/hr Bay 400 /vo ar/hr MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-13 PENETRATION INTERSPACE dP 9/ PSID RX BUILDING SUMP DISCHARGE FLOW d GPM r ( BOARD I-15 RX STACK FLOW jrr,.o&o ACFM RX BUILDING / AMBIENT dP f. 43 PSID BOARD I-7507X CONTROL ROOM TEMPERATURE G7 deg F 480V ROOM TEMPERATURE 2P deg F \ l
9 FOSAVEI '87 r- Scenario time 393,; l OVERALL PELRT PARAMETERS Clock time /2/r Rx Power 965 Turbine Generator Load O MW PRIMARY COOLANT PRESSURE /5 PSIA TEMPERATURE Circulator Inlet /4r deg F Core Outlet J (gp__ des F i HELIUM FLOW l Loop 1 _S EXJt>lbs/hr Loop 2 o lbs/hr ] TOTAL 4/ctn? lbs/hr CIRCULATOR SPEED Circulator A 'rocm3 RPM Circulator B +to RPM Circulator C 47# RPM Circulator D 4'4a RPM MOISTURE (DEW POINT) ME-9306 Z-57 deg F ME-9307 _;i;5'7 des F SECONDARY COOLANT FEEDWATER FLOW Loop 1 O lbs/hr Loop 2 o lbs/hr TOTAL 0 lbs/hr MAIN STEAM Loop 1 Pressure 6 v' PSIG Temperature ;2 rf _deg F Loop 2 Pressure /75n ,PSIG Temperature 94a _deg F HOT REHEAT Loop 1 Pressure v__PSIG
. Temperature ?vo deg F Loop 2 Pressure a PSIG Temperature m deg F COLD REHEAT Loop 1 Pressure O PSIG Temperature ;co deg F Loop 2 Pressure o PSIG Temperature c -:> deg F
RADIATION MONITORS SCENARIO TIME OG: I 5" PROCESS MONITORS CLOCE TIME I2: I5 l SENSITIVITY O' NUMBER VALUE ALARMING (Y/N) RT-4801 __2.6E-10 SSH CPM Y RT-4802 1.2E-10 **, O5W CPM V RT-4803 2.5E-8 _ _ OSH CPM Y RT-6212 _,_2.2E-8 I.o E +d CPM M RT-6213 2.2E-8 f.o E +1 CPM M RT-7312 2.3E-8 *(PCRV) eS4 CPM Y RT-7324-1 2.SE-8 95H CPM Y J RT-7324-2 8.9E-7 __ ').I E t 6 CPM ( RT-7325-1 005 005 OOS RT-7325-2 00S OOS 00S RT-73437-1 4.6E-10 ** G. 'T E +(, CPM Y RT-73437-2 OOS 005 OOS RT-9301 2.3E-8 3. 0 E + 6 CPM AJ RT-93252-12 N/A t. I E +2 ar/hr Y AREA MONIIORS NUMBER VALUE ALARMING (mr/hr) (Y/N) RT-93250-1 o54 Y ' RT-93250-2 OS4 Y ! RT-93250-3 7. O E-+-3 Y l RT-91250-4 os4 V RT-93250-5 2 o0. O Y
/ RT-93250-8 0514 Y RT-93250-13 C./ M RT-93250-14 2.OE+y V RT-93251-1 z. o E e3 Y RT-93251-3 2. o E + 3 Y RT-93251-4 zoo. O V RT-93251-5 054 V RT-93251-6 05 4 Y RT-93251-7 o54 V RT-93251-8 054 f RT-93251-9 0.54 Y RT-93252-1 054 Y RT-93252-2 ns4 Y RT-93252-4 2. o F +3 Y RT-93252-6 ASM Y RT-93252-7 054 V RIA-79511 200, O Y METER 0RLOGICAL DATA WIND SPEED 2.0 MPH .
WIND DIRECTION FROM 270 DEGREES PLUME DEVIATION / SIGMA THETA 2. O DEGREES DITTERENTIAL TEMPERATURE + 4.0 DEGREES T l A Value corresponds to the PCRV area channel. Other four chtnnels are A 30 cpm.
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
PRIMARY AUXILIARIES i /~T s,) , BOARD I-01 CAS WASTE SYSTEM 63 Normal LIQUID WASTT SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal BOARD I HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /9 PSIG High Pressure Bottles ?#o PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow /99D GPM BUBW Header Pressure Oro PSIG HELIUM CIRCULATORS SYSTEM 21 Normal BOARD I-03_ REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position O INCHES Runback group positions 2A, rod #2 o INCHES rod #4 o INCHES rod #6 O INCHES 4F, rod #25 0 INCHES rod #31 O INCHES rod #37 o INCHES Flux Controller position +/- N/A % Reserve Shutdown Material .L o/ecl STATUS l
BOARD I-05 {} HYDRAULIC OIL STEAM WATER DUMP TANK SYSTEM 91 SYSTEM 22 Normal Loop Selected / 1 or 2 Pressure //2 PSIG Temperature _TP0 des F Level </5 INCHES Radiation 50-40 ar/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06 EMERGENCY FEEDWATER PRESSURE 6 9' PSIG () BOILER FEED PUMPS A Speed O RPM A Flow v lbs/hr B Status :- on/off B Flow a lbs/hr C Speed a RPM C Flow 0 lbs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Tank S PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal SERVICE AIR SYSTEM 82 Normal t -- -
BOARD I-10 PLANT PROTECTIVE SYSTEM RI BUILDING TEMPERATURE-HIGH BAT 100 >/53 des F BAT 200 S /ro des F BAY 300 3/ rt de s F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 /.'A2 mr/hr Bay 1100 90 mr/hr Bay 1000 /av ar/hr Loop 2 Bay 600 /vo ar/hr Bay 500 Ato ar/hr Bay 400 /oo ar/hr MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-13 PENETRATION INTERSPACE dP _ 4/'PSID RI BUILDING SUMP DISCHARGE FLOW 0 GPM () BOARD I-15
- RX STACK FLOW JUE.O*D ACFM RI BUILDING / AMBIENT dP f, C PSID BOARD I-7507%
CONTROL ROOM TEMPERATURE 47 deg F 480V ROOM TEMPERATURE 27 deg F O
FOSAVEI '87 f- Scenario time 6 90 (g) OVERALL PLANT PARAMETERS Clock time x030 Rx Power 2/90s Turbine Generator Load o MW PRIMARY COOLANT PRESSURE /r PSIA I TEMPERATURE l Circulator Inlet /45" -deg F , Core Outlet SMU deg F { HELIUM FLOW
';j Loop 1 J/Ocq1bs/hr Loop 2 o 1bs/hr ;
TOTAL; m2/Ovv lbs/hr CIRCULATOR SPEED Circulator A /GOT1 RPM . Circulator B _ 6 50 RPM Circulator C oro RPM Circulator D 470 RPM MOISTURE (DEW POINT) ME-9306 4-SR_ des F ME-9307 4-39 deg F SECONDARY COOLANT FEEDWATER FLOW Loop 1 O lbs/hr s Loop 2 o lbs/hr ! TOTAL O lbs/hr I MAIN STEAM ! Loop 1 Pressure 69' PSIG Temperature Orr deg F Loop 2 Pressure /?Oo PSIG Temperature 920 deg F , HOT REHEAT Loop 1 Pressure o PSIG Temperature 9pd deg F Loop 2 Pressure O PSIG Temperature mv ra deg F COLD REHEAT Loop 1 Pressure 6 PSIG Temperature 2/r> _deg F Loop 2 Pressure 9 PSIG Temperature 4^r0 _d e g F
1 RADIATION MONI'IURS SCENARIO TIME %'30 PROCESS MONI'IORS CLOCE TIME t2:3o NUMBER SENSITIVITY VALUE ALARMING (Y/N) RT-4801 2.6E-10 ** SSN CPM f RT-4802 1.2E-10 ** 65N CPM y RT-4803 2.5E-8 __ 954 CPM Y l RT-6212 2.2E-8 I. 0 E W CPM _ h/ J RT-6213 - 2.2E-8 ~ f.o E +1 CPM M RT-7312 2.2E-8 *(PCRV) B. 7 E 4 CPM Y RT-7324-1 2.8E-8 __ 95W CPM Y RT-7324-2 8.9E-7 4.9 E ,. S CPM Y RT-7325-1 OOS OOS 00S RT-7325-2 OOS OOS 005 RT-73437-1 4.6E-10__, ** 7.3 E % CPM Y RT-73437-2 OOS 00s 00S RT-9301 2.3E-8 3.c7 E +4 CPM N RT-93252-12 N/A ~7,7 E +-[mr/hr Y AREA MONI'IORS NUMBER VALITE ALARMING (mr/hr) (Y/N) RT-93250-1 - 654 Y RT-93250-2 osW V RT-93250-3 7 o E+.2 V RT-93250-4 oS4 V rw RT-93250-5 76.O V i RT-93250-8 o54 Y RT-93250-13 O./ M RT-93250-14 7.0EM Y RT-93251-1 03L N RT-93251-3 7.o 6+2. Y RT-93251-4 -7 o. O Y RT-93251-5 n3M Y RT-93251-6 05W V RT-93251-7 n5W Y RT-93251-8 os4 Y RT-93251-9 654 ( RT-93252-1 n54 V RT-93252-2 nsW Y RT-93252-4 7. O E' + 2. Y l RT-93252-6 03W Y ! RT-93252-7 o54 Y RIA-79511 . 70.O Y METElwRLOGICAL DATA ,,_ l WIND SPEED 2.0 MPH . WIND DIRECTION FROM 270 DEGREES ( PLUME DEVIATION / SIGMA THETA 2. O DEGREES DITTERENTIAL TEMPERATURE + 4. 0 DEGREES T
- Value corresponds to the PCRV area channel. Other four channels are 30 cpe.
** Value corresponds to a 15 minute build-up of activity. Build-up starts 4 at the specified scenario / clock time.
b
i PRIMARY AUXILIARIES ,\ . ( ,/ BOAkb I-01 GAS WASTE SYSTEM 63 Normal LIQUID WASTE . SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal BOARD I-02 HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /9 PSIG High Pressure Bottles ISD PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow /d01 _GPM BUBW Header Pressure 970 PSIG HELIUM CIRCULATORS SYSTEM 21 Normal 7 .s BOARD I-03_ REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position C) INCHES Runback group positions 2A, rod #2 o INCHES rod #4 > INCHES rod #6 o INCHES 4F, rod #25 o INCHES rod #31 o INCHES rod #37 9 INCHES Flux Controller position +/- //dd % Reserve Shutdown Material 25ced/d. STATUS O V
BOARD I-05 k.,) HYDRAULIC OIL SYSTEM 91 Normal STEAM WATER DUMP TANK SYSTEM 22 Loop Selected / 1 or 2 Pressure //o PSIG Temperature ?hs des F Level 97 INCHES Radiation Jo-yo mr/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERAiION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06__ EMERGENCY FEEDWATER PRESSURE 49' PSIG BOILER FEED PUMPS A Speed O RPM A Flow 1 lbs/hr B Status wv on/off B Flow o lbs/hr C Speed o RPM C Flow 0 lbs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Tank 6 PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal () SERVICE AIR SYSTEM 82 Normal _._________.__________J
BOARD I-10 (~~ PLANT PROTECTIVE SYSTEM RI BUILDING TEMPERATURE-HIGH BAT 100 >/ 5') deg F BAY 200 >/r0 deg F BAY 300- 7/c0 des F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 Na ar/hr Bay 1100 /m ar/hr Bay 1000 /s ar/hr Loop 2 Bay 600 /so ar/hr Bay 500 No ar/hr Bay 400 /ov ar/hr MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-13 PENETRATION INTERSPACE dP V PSID RX BUILDING SUMP DISCHARGE FLOW b GPM BOARD I-15 RX STACK FLOW 31 M ACFM RX BUILDING / AMBIENT dP 0.4/ PSID BOARD I-7507 CONTROL ROOM TEMPERATURE 47' deg F 480V ROOM TEMPERATURE f6 deg F l i i O
j . . l- FOSAVEX '87 Scenario time _,f/O f ( OVERALL PLANT PARAMETERS Clock time _,j m Rx Power 965 o Turbine Generator Load MW PRIMARY C00LAhf PRESSURE /S-~ PSIA TEMPERATURE Circulator Inlet af deg F Core Outlet WO des F HELIUM FLOW ~ Loop 1 ,f/dev lbs/hr Loop 2 o lbs/hr TOTAL S/vero lbs/hr CIRCULATOR SPEED . l Circulator A 9 600 RPM , Circulator B __ 9ao RPM Circulator C 490 RPM Circulator D 9eo RPM MOISTURE (DEW POINT) ME-9306 e T/deg F ME-9307 <-s? deg F SECONDARY COOLANT FEEDWATER FLOW Loop 1 9 lbs/hr Loop 2 n 1bs/hr TOTAL o lbs/hr NAIN STEAM Loop 1 Pressure 4 [ PSIG Temperature JST deg F Loop 2 Pressure M r4 PSIG Temperature mm deg F HOT REHEAT - Loop 1 Pressure o PSIG
. Temperature '700 des F Loop 2 Pressure D PSIG Temperature +> deg F COLD REHEAT Loop 1 Pressure O PSIG Temperature ##d deg F l Loop 2 Pressure o PSIG Temperature WJ deg F
RADIATION MONITORS SCENARIO TIME OG: 45 ' l PROCESS MONITtNt3 CLOCE TIME I 2. : 4 s- ) NUMBER SENSITIVITY- VALUE ALARMING (Y/N) ' RT-4801 2.6E-10 ** _. 9 514 CPM Y RT-4802 1.2E **_ GSM CPM V RT-4803 2.5E-8 83W CPM Y RT-6212 2.2E-8 !.o E +i CPM M l l RT-6213 - 2.2E-8 f.o E +1 CPM V i RT-7312 2.3E-8 _ *(PCRV) k o E +(, CPM Y l RT-7324-1 2.8E-8 , SSW CPM Y - RT-7324-2 8.9E-7 J. 3 E +-5 CPM Y : RT-7325-1 005 003 OOS RT-7325-2 005 005 OOS 3 RT-73437-1 4.6E-10 ** 8. 5 E + 4 CPM Y I RT-73437-2 OOS 003 00S i RT-9301 2.3E-8 3. 4 E + 6 CPM M RT-93252-12 N/A (. 4 E +1 mr/hr Y AREA NONITG18 NUMBER VALUE ALARMING (ar/hr) (Y/N) RT-93250-1 OSW Y RT-93250-2 05W Y RT-93250-3 7.o E +'2. ,, Y RT-93250-4 05W V RT-93250-5 70 . o Y RT-93250-8 oS4 V
\ RT-93250-13 d./ U RT-93250-14 7. O E + 4- Y RT-93251-1 0.5 L M RT-93251-3 't. O E +- Z Y RT-93251-4 7o. o Y RT-93251-5 054 Y RT-93251-6 ash Y RT-93251-7 os4 Y RT-93251-8 o54 Y RT-93251-9 o54 Y RT-93252-1 osu Y RT-93252-2 osW Y RT-93252-4 '
- 7. o E + 2 Y RT-93252-6 05N Y RT-93252-7 05 4 Y RIA-79511 70, O Y METER 0RLOGICAL DATA WIND SPEED /.0 MPH , ,
WIND DIRECTION 1%0M 270 DEGREES j PLUME DEVIATION / SIGMA THETA 2.O DEGREES DIFFERElfTIAL TEMPERATURE + 4.0 DEGREES F
- Value corresponds to the PCRV area channel. Other four channels are
-O 30 cpm.
** Value corresponds to a 15 minute build-up, of activity. Build-up starts ;
at the specified scenario / clock time. N
L 1 r PRIMARY AUXILIARIES ( BOARD I-01 l GAS WASTE SYSTEM 63 Normal LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal ROARD I-02 HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /9 PSIG High Pressure Bottles 5vf PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow / -ve ' GPM < BUBW Header Pressure 00-0 PSIG HF.LIUM CIRCULATORS SYSTEM 21 Normal t i BOARD I-03_ REACTOR CONTROL SYSTEM 12 i Regulating Rod (1) position 6 INCHES Runback group positions 2A, rod #2 d INCHES ) rod #4 a INCHES } rod #6 o INCHES 4F, rod #25 0 INCHES rod #31 0 INCHES rod #37 o INCHES Flux Controller position +/- 76d/ % Reserve Shutdown Material j c/d d STATUS L i
* .J
4 l BOARD I-05 () HYDRAULIC OIL SYSTEM 91 Normal STEAM' WATER DUMP TANK SYSTEM 22 Loop Selected / 1 or 2 Pressure /*>r PSIG Temperature. <797 deg F Level- 75 INCHES Radiation S0-40 mr/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06 EMERGENCY FEEDWATER PRESSURE 4V PSIG BOILER FEED PUMPS A Speed O RPM A Flow o lbs/hr B Status oW on/off B Flow o lbs/hr C Speed o RPM C Flow o lbs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Trnk O PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal () SERVICE AIR SYSTEM 82 Normal L
- l. .
I BOARD I-10
,-~ PLANT PROTECTIVE SYSTEM RI BUILDING TEMPERATURE-HIGH BAT 100 2/f6 des F BAY 200 7/n deg F BAY 300 fven deg F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 </'d mr/hr Bay 1100 <e? mr/hr Bay 1000 an? ar/hr Loop 2 Bay 600 499 mr/hr i Bay 500 <w; mr/hr i Bay 400 9'O mr/hr MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal BUFF CEAL MALFUNCTION Normal BOARD I-13 PENETRATION INTERSPACE dP </'PSID RX BUILDING SUtd DISCHARGE FLOW O GPM BOARD l-15 RX STACK FLOW 84 T76 ACFM RX BUILDING / AMBIENT dP -0.0/ PSID BOARD I-7507X CONTROL ROOM TEMPERATURE 67 deg F 480V ROOM TEMPERATURE fi deg F i
O.
FOSAVEX 87
--j FOR: OPERATOR MESSAGE NO. !
O LOCATION: FSV SWITCHBOARD TIME: 1300 1
- XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS
~
XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX MESSAGE: I live north of Platteville, and heard on my radio that I should evmcuate. I lost my emergency booklet and I am not sure where to'go. The wind seems to be coming from the
~
east so I was gr ng to go to Greeley but my neighbors say they are evacuating Greeley too. e O XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS IS A DRILL
>'XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX
~
FOSAVEI '87
- Scenario time 4/.:f d OVERALL PLANT PARAMETERS Clock time ned Rx Power PdA5 Turbine Generator Load 4 MW PRIMARY COOLANT PRESSURE C PSIA TEMPERATURE Circulator Inlet /c,( deg F Core Outlet 1/d deg F HELIUM FLOW Loop 1 J//r/r/ lbs/hr Loop 2 _
o lbs/hr TOTAL J/or# lb s /hr CIRCULATOR SPEED Circulator A f6UO RPM Circulator B wo RPM Circulator C cro RPM Circulator D .. z,o o R P M MOISTURE (DEW POINT) ME-9306 e- Q deg F ME-9307 2-r? deg F SECONDARY COOLANT FEEDWATER FLOW Loop 1 O lbs/hr Loop 2 O lbs/hr TOTAL 0 lbs/hr MAIN STEAM Loop 1 Pressure 6V PSIG i Temperature > sT deg F Loop 2 Pressure /S'90 PSIG Temperature 6frd deg F HOT PEHEAT Loop 1 Pressure o PSIG Temperature 6 c/o d eg F Loop 2 Pressure o PSIG i I Temperature ',Jo deg F COLD REHEAT Loop 1 Pressure F PSIG Temperature -94' 0 deg F Loop 2 Pressure o PSIG Temperature 1AO deg F O
RADIATION M(Nf! TORS SCENARIO TIME o r i00 PROCESS MONITORS CLOCE TIME i3:oo NtBIBEK SENSITIVITY VALUE ALARMING (Y/N) RT-4801- 2.6E-10 ** 9564 CPM Y RT-4802 1.2E-10,__ ** 85le CPM Y RT-4403 _ 2.5E-8 8544 CPM V RT-6212 2.2E-8 I.o E +i CPM M RT-6213 - 2.2E-8 f.o E +1 CPM V RT-7312 2.3E-8 ,___ *(PCRV) 2. 9 E +(o CPM Y RT-7324-1 ___2.8E-8 6.I E +(e CPM Y RT-7324-2 8.9E-7 ___ l . (o E + 5 CPM Y RT-7325-1 005 008 003 RT-7325-2 OOS 00S 005 _ RT-73437-l' 4.6E-10___ ** 9. 3 E + (, CPM Y RT-73437-2 -OOS 00S 005 RT-9301- 2.35-8 3. it E +J CPM M RT-93252-12 N/A' 44. F E+1 mr/hr Y AREA MONITtBS NUMBER VALUE ALARMING (ar/hr) (Y/N).' RT-93250-1 05M Y RT-93250-2 osN Y RT-93250-3 2.O r +2. Y RT-93250-4 05d Y RT-93250-5 '20.0 Y RT-93250-4 osM Y M RT-93250-13 0./ RT-93250-14 2.o E + 4 Y RT-93251-1 06L -M RT-93251-3 2.o r + 2 Y RT-93251-4 20.O Y RT-93251-5 O$4 Y RT-93251-6 ds4 Y RT-93251-7 - OW Y RT-93251-8 05F Y RT-93251-9 d56- Y RT-93252-1 05 F V RT-93252-2 05R Y RT-93252-4 Z.o E+ 2 Y RT-93252-6 c5 H V RT-93252-7 05M V RIA-79511 20.o Y METER 0RLOGICAL DATA WIND SPEED /,0 MPR . WIND DIRECTION FROM ' 270 DEGREES PLUME DEVIATION / SIGMA THETA 2. O DEGREES DIFFERENTIAL TEMPERATURE + 4. 0 DEGREES F
- Value corresponds to the PCRV area channel. Other four channels are 30 cym. t
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
L. PRIMARY AUXILIARIES BOARD I-01 GAS WASTE SYSTEM 63' Normal LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal BOARD I-02
. HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /9 PSIG l High Pressure Bottles 550 PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow #tro GPM .!
BUBW Header Pressure 'wo PSIG HELIUM CIRCULATORS SYSTEM 21 Normal BOARD I-03_
-REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position a INCHES Runback group positions 2A, rod #2 0 INCHES rod #4 o INCHES rod #6 o INCHES 4F, rod #25 o INCHES rod #31 o INCHES rod #37 0 INCHES Flux Controller position +/- w //> %
Reserve Shutdown Material Zuw hcl STATUS O
BOARD I-05 () HYDRAULIC OIL SYSTEM 91 Normal STEAM WATER DUMP TANK SYSTEM 22 Loop Selected / 1 or 2 Pressure /90 PSIG Temperature 367 deg F Level +<F INCHES Radiation Jo-vo ar/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO '
"0" PSI FOR A SHUTDOWN CIRCULATOR.
THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06 EMERGENCY FEEDWATER PRESSURE GV PSIG BOILER FEED PUMPS A Speed O RPM A Flow o lbs/hr B Status 94 on/off B Flow 0 lbs/hr j C Speed a RPM i C Flow a lbs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Tank O PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal SERVICE AIR Normal (( ) SYSTEM 82 l a
BOARD I-10 PLANT PROTECTIVE SYSTEM
. y ,. .
( RI BUILDI S TEMPERATURE-HIGH BAY 100 >/st deg F BAY 200 >/ca des F BAY 300- y/en deg F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 /> mr/hr Bay 1100 /0 ar/hr Bay 1000 /0 mr/hr Loop 2 Bay 600 /o ar/hr Bay 500 /0 ar/hr Bay 400 /0 mr/hr MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-13 PENETRATION INTERSPACE dP / PSID RX BUILDING SUMP DISCHARGE FLOW _d GPM BOARD I-15 RX STACK FLOW J' oco ACFM RX BUILDING / AMBIENT dP -o, / PSID BOARD I-7507X CONTROL ROOM TEMPERATURE /, ') deg F 480V ROOM TEMPERATURE W deg F l O
FOSAVEX 87 FOR: MEDIA REPS MESSAGE NO. ![ n U ' LOCATION: SEOC - TIME: 1315 XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX MESSAGE: The line of questioning, by the " reporters" is as.follows:
'l. Background on FSV
- 2. " Technical" discussion of what went wrong
- 3. System vs. human error
- 4. Relationships to Chernobyl/TMI
- 5. In-House-Shelter / Evacuation
- 6. PSCC/ State / Local Interface
( 7. Electrical Supply; Cost Impacts
- 8. Annual Graded Exercise Requirements O
XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS IS A DRILL XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX
FOSAVEI '87 Scenario time #/f5 Qq OVERALL PLANT PARAMETERS Clock tiae_ 436 Rx Power 7/M Turbine Generator Load a MW PRIMARY COOLANT PRESSURE /s" PSIA TEMPERATURE Circulator Inlet /6( deg F Core Outlet #co deg F HELIUM FLOW Loop 1 g_p g lbs/hr Loop 2 n its/hr TOTAL Jo rcro lbs/hr CIRCULATOR SPEED Circulator A 79cD RPM Circulator B 9eo RPM Circulator C '> rs RPM Circulator D /,PO RPM MOISTURE (DEW POINT) ME-9306 e-57 dog F ME-9307 /-co deg F SECONDARY COOLANT FEEDWATER FLOW Loop 1 m lbs/hr Loop 2 6 lbs/hr TOTAL O lbs/hr MAIN STEAM Loop 1 Pressure 6V PSIG Temperature e rf deg F Loop 2 Pressure /Wo PSIG Temperature /,ro deg F HOT REHEAT-Loop 1 Pressure o PSIG
. Temperature & #) deg F Loop 2 Pressure n PSIG Temperature wro deg F COLD REHEAT Loop 1 Pressure a PSIG Temperature -490 deg F Loop 2 Pressure o PSIG Temperature W90 deg F O
i RADIATION MONITORS SCENARIO TIME O 7;I5" PROCESS MONITORS. CLOCE TIME 1 "E i 15 NUMBER SENSITIVITY VALUE ALARMING (Y/N) RT 4401 2.6E-10 ** SSM CPM Y ' RT-4802 __,1.2E-10 ** 9% CPM , Y RT-4803 2.5E-8 45H CPM y RT-6212 2.2E-8 I. o E 4 CPM U RT-6213 2.2E-8 f.o E W CPM A/ RT-7312 _ 2.3E-8 *(PCRV) I.3 E4 CPit Y-RT-7324-1 2. 8E-8 __, 7. L E + (. CPM Y ! RT-7324-2 __,8.9E-7 7. o E & 4 CPM - Y ' RT-7325-1 003 OOS 00S RT-7325-2 OOS 00S 00S RT-73437-1 4.6E-10 ** 4.9 E &L CPM Y RT-73437-2 OOS 00s 005 RT-9301 2.3E 3. 3 E * (, CPM U RT-93252-12 N/A 1 n E + 1 mr/hr Y AREA MONITORS NUMBER VALUE ALARMING-(ar/hr) (Y/N) RT-93250-1 o5H 'r' RT-93250-2 o34 V RT-93250-3 Z o E y 2. Y RT-93250-4 034 V-RT-93250-5 2.a. O V RT-93250-8 C.54 V RT-93250-13 0./ Al RT-93250-14 2. O E + 4 Y RT-93251-1 ost U RT-93251-3 Z.o E + 2. V RT-93251-4 20.0 V __ RT-93251-5 034 Y RT-93251-6 os4 Y RT-93251-7 AS4 Y RT-93251-8 03M V RT-93251-9 ("O M Y . RT-93252-1 O3M V l RT-93252-2 oSN Y RT-93252-4 2. o E +2. Y RT-93252-6 054 Y i RT-93252-7 0.54 V RIA-79511 - 40.O Y l METEROLOGICAL DATA Y WIND SPEED /. O MPH . WIND DIRECTION FROM 270 DEGREES PLUME DEVIATION / SIGMA THETA 2. O DEGREES DIFFERENTIAL TEMPERATURE + 4.0 DEGREES T
- Value corresponds to the PCRV area channel. Other four channels are
. 30 cym.
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
t-
PRIMARY AUXILIARIES () BOARD I-01 GAS WASTE SYSTE!! 63 Normal LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal BOARD I-02 HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /9 PSIG High Pressure Bottles T+<' PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow A2E7 GPM BUBW Header Pressure 9m9 PSIG HELIUM CIRCULATORS SYSTEM 21 Normal BOARD I-03 REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position O INCHES Runback group positions 2A, rod #2 O INCHES - rod #4 0 INCHES rod #6 o INCHES 4F, rod #25 d INCHES rod #31 0 INCHES rod #37 0 INCHES Flux Controller position +/- #dv % Reserve Shutdown Material 3v3eMod STATUS O
BOARD I-05 () HYDRAULIC OIL SYSTEM 91 Normal STEAM WATER DUMP TANK SYSTEM 22 Loop Selected / 1 or 2 Pressure /47 PSIG Temperature 3 &5' deg F Level Of INCHES Radiation 30 -+'0 mr/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06 EMERGENCY FEEDWATER PRESSURE 44' PSIG BOILER FEED PUMPS A Speed o RPM A Flow a lbs/hr B Status . c4 on/off B Flow d lbs/hr C Speed d RPM C Flow a lbs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Taak 6 PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal () SERVICE AIR SYSTEM 82 Normal
j BOARD I-10 (
., ~x . ,
.e PLANT PROTECTIVE SYSTEM 1 RI BUILDIES TEMPERATURE-HIGH BAY 100 >/p des F BAY 200 >/SO des F BAT 300 7/fd des F '
1 REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 +/ ar/hr Bay 1100 y ar/hr Bay 1000 y ar/hr Loop 2 Bay 600 4^ ar/hr Bay 500 9 ar/hr Bay 400 </ ar/hr MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD ?.-13 1 PENETRATION INTERSPACE dP 9' PSID
- RI BUILDING SUMP DISCHARGE FLOW O GPM b BOARD I-15 RI STACK FLOW _$$ T/d ACFM RX BUILDING / AMBIENT dP -o.2f PSID BOARD I-7507X CONTROL ROOM TEMPERATURE. 49 deg F 480V ROOM TEMPERATURE 29 des F O
FOSAVEI '87 f3 Scenario time #4f V OVERALL PLANT PARAMETERS Clock time a rr Rx Power fl>5 Turbine Generator Load d MW PRIMARY COOLANT PRESSURE /6 PSIA TEMPERATURE Circulator Inlet /46 deg F Core Outlet 3 r s' deg F HELIUM FLOW Loop 1 J/. 00lbs/hr Loop 2 o lbs/hr TOTAL 2 ,/ 4/u91b a / hr CIRCULATOR SPEED Circulator A 8/60 RPM Circulator B /3r0 RPM Circulator C (Igv RPM Circulator D 2 300 RPM MOISTURE (DEW POINT) ME-9306 447 deg F ME-9307 /-s'7 d e g F SECONDARY COOLANT FEEDWATER FLOW Loop 1 3 lbs/hr Loop 2 O lbs/hr TOTAL O lbs/hr MAIN STEAM Loop 1 Pressure 4V PSIG Temperature ><< deg F Loop 2 Pressure /WO PSIG Temperature Goo deg F HOT REHEAT-Loop- L Pressure o PSIG Y Temperature Mr deg F Loop"1 Pressure 5 PSIG
, T'e'ap e ra t u re ??C deg F COLD REHEAT Loop 1 Pressure ? PSIG Temperature ?x deg F Loop 2 Fressure o PSIG Temperature '"N deg F
RADIATION MONITORS. SCENARIO TIME 67147 i 1 PROCESS MONITORS CLOCE TIME 13.ySi NUMBEK SENSITIVITY VALUE ALARMING l (Y/N) RT-4801 2.62-10 ** 354 CPM Y RT-4802 ___,1.2E-10 ** 8 564 CPM Y-RT-4803 2.5E-8 8 564 _ CPM V RT-6212 2.2E-8 _,_,, I.o E +f CPM U RT-6213' 2.2E-8' l.o E +i CPM Al RT-7312 ___2.3E-8 *(PCRV) k7 E+5 CPM Y RT-7324-1 2.8E-8.__, I. I E Ho CPM Y RT-7324-2 8.9E-7 J, to E + 4 CPM Y RT-7325-1 005 ._ 003 005 RT-7325-2 008 005 005 RT-73437-1 4.6E-10 ** 7A E c5' CPM _ Y ; RT-73437 OOS OOS 005 , RT-9301 2.3E-8 3.0 E +6 CPM M RT-93252-12 N/A 2. I E +1 ar/hr Y , AREA MONITORS NUMBER- VALUE ALARMING (ar/hr) (Y/N) RT-93250-1 A,o E + 3 Y RT-93250-2. EoEe3 Y RT-93250-3 Bo. o 6 e O Y RT-93250-4 an sy3 V RT-93250 B. O E +.0 V RT-93250-8 B. O E+ 3 Y L RT-93250-13 0.I Al RT-93250-14 05L U j RT-93251-1 OsL (f RT-93251-3 #o.O Em M RT-93251-4 S. O E +O , Y RT-93251-5 3. O E + 3 Y RT-93251-6 8. o Ee3 Y RT-93251-7 E.O E + 1 Y _ RT-93251-8 S.O E + 3 Y RT-93251-9 8 0 E + ~6 _,_ V RT-93252-1 8.o EA Y RT-93252-2 8. O E+3 Y RT-93252-4 80.o G +O Y RT-93252-6 8. O E +3 Y RT-93252-7 B. O s #3 Y RIA-79511 8. O Ge O Y METER 0RLOGICAL DATA WIND SPEED 2.,0 MPri . WIND DIRECTION FROM 270 DEGREES PLUME DEVIATION / SIGMA THETA 2. O DW3REES DIFFERENTIAL TEMPERATURE + 4.0 DEGREES T
- Value corresponds to the PCRV area channel. Other four channels are O 30 cym.
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
I .
PRIMARY AUXILIARIES () BOARD I-01 GAS WASTE SYSTEM 63 Normal LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal BOARD I-02 HELIUM STORAGE SYSTEM 24 i Low Pressure Bottles /9 PSIG High Pressure Bottles tsf PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Faed Flow A2&O GPM BUBW Header Pressure 900 PSIG HELIUM CIRCULATORS SYSTEM 21 Normal _ BOARD I-03 k-) REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position O INCHES Runback group positions 2A, rod #2 O INCHES l rod #4 6 INCHES rod #6 O INCHES 4F, rod #25 A INCHES rod #31 6 INCHES rod #37 0 INCHES Flux Controller position +/- M/4 % Reserve Shutdown Material 2Tente/td STATUS
4
~
BOARD I-05 () HYDRAULIC'0IL. STEAM WATER DUMP TANE SYSTEM 91 SYSTEM 22 Normal Loop Selected / 1 or 2 Pressure /57 PSIG Temperature JG/ des F Level 97 INCHES Radiation ;d-ro ar/hr HELIUM CIRCULATORS SYSTEM 21 Normal-NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06 EMERGENCY FEEDWATER PRESSURE 64/ PSIG () BOILER FEED PUMPS A Speed C7 RPM A Flow o iba/hr B Status cv on/off B Flow o lbs/hr .' C Speed o RPM C Flow 0 lbs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Tank o PSIG HOT REHEAP BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal () SERVICE AIR SYSTEM 82 Normal
B0 RD I-10
,es ....._er. PLANT PROTECTIVE SYSTEM t <
RI BUIL -TEMPERATURE-HIGH BAY 100i )VG) des F BAT 200 PC des F BAT 300 T/c) deg F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 4/ mr/hr Bay 1100 v ar/hr Bay 1000 9 mr/hr Loop 2 Bay 600 W ar/hr Bay 500 4/ ar/hr Bay 400 4 mr/hr MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-13 PENETRATION INTERSPACE dP 4' PSID RX BUILDING SUMP DISCHARGE FLOW 0 GPM BOARD I-15 RX STACK FLOW 31000 ACFM RX BUILDING / AMBIENT dP -0 Sf'PSID BOARD I-7507% CONTROL ROOM TEMPERATURE f'/ deg F 480V ROOM TEMPERATURE MV deg F 4 s t_- l
I FOSAVEI '87 Scenario time f'fd () OVERALL PLANT PARAMETERS 6d6 Clock time /350 Rx Power i Turbine Generator Load a MW PRIMARY COOLANT ; PRESSURE /r PSIA I TEMPERATURE Circulator Inlet E _,,deg F Core Outlet 394 deg F HELIUM FLOW Loop 1 JWtVU9 lbs/hr l Loop 2 0 lbs/hr TOTAL A7Aero lbs/hr ; CIRCULATOR SPEED Circulator A hWU) RPM Circulator B z 's ]o RPM Circulator C 4tn RPM Circulator D L3vs RPM MOISTURE (DEW POINT) ME-9306 /-9) _deg F-ME-9307 c-59 deg F SECONDARY COOLANT 1 FEEDWATER FLOW Loop 1 O lbs/hr Loop 2 o lbs/hr TOTAL o lbs/hr r' MAIN STEAM H Loop 1 Pressure e, V PSIG Temperature 355 deg F Loop 2 Pressure /49B PSIG Temperature Gv'd deg F HOT REHEAT Loop 1 Pressure O PSIG -
, Temperature 610 deg F Loop 2 Pressure O PSIG
, Temperature ~43 des F COLD REHEAT Loop 1 Pressure O PSIG Temperature ??0 deg F Loop 2 Pressure A PSIG Temperature 34o deg F
RADIATION NONITORS SCENARIO TIME 0 7 1 'L o i I PROCESS NCMfITORS CLOCE TIME , t 313 O _
' NUMBER SENSITIVITY VALUE ALARMING (Y/N) -
RT-4801 __,_2.6E-10 ** OSU CPM Y ,,,,_ RT 4802 ** 93W CPM V 1.2E-10___ _,_ RT-4803 2.5E-8 95H CPM Y __ RT-6212 2.2E-8 I. o E 4 CPM M RT-6213 _,__2.2E-8 1.0 E +1 CPM u RT-7312 2.3E-8 *(PCRV) 4.9 E F5' CPM _ _ _ _ V RT-7324-1 _,,,,,,2. 8E-8 I ,7 E ,. G CPM Y __ l RT-7324-2 _,,,_,8 . 9 E-7 5. 2, E + 4 CPM __,. Y ! RT-7325-1 OOS 00s _,_ 00s RT-7325-2 OOS OOS _,_ OOS , RT-73437-1 _,_,,4. 6 E-10 (1) ** 4.7 E +- S CPM __, Y RT-73437-2 OOS 008 OOS RT-9301 2.3E-8 ___ 3 . 2. E +G CPM M RT-93252-12 N/A 2. G E e-1 mr/hr Y AREA MONITORS NUMBER VALUE ALARMING (mr/hr) (7/N) RT-93250-1 A.n44 Y RT-93250-2 8.o e +3 Y Bo.OE+O_ RT-93250-3 Y RT-93250-4 B. O E+ 3 Y RT-93250-5 8. O E -* o Y
.O RT-93250-8 R. O 6+3 Y RT-93250-13 O.I __
M RT-93250-14 05 L M RT-93251-1 O$L , , Al RT-93251-3 B0.0 6 + d_ % Al RT-93251-4 8. O G's )_,, Y RT-93251-5 _
- 9. O E r_p,,_,,,, , Y RT-93251-6 A o E e 3 _,,_, Y RT-93251- F;oE+3 Y RT-93251-5 5.o E+ 3 Y RT-93251-9 5 O E + 2, y RT-93252-1 8. O G + 3 Y RT-93252-2 roe +3 Y RT-93252-4 40. O C + 0 Y RT-93252-6 B. o E + 3 Y RT-93252~7 8.0 E eJ Y RIA-79511 7.OE+O V METER 0RLOGICAL DATA ~
WIND SPEED /, O MPH , WIND DIRECTION FROM 270 DEGREES PLUME DEVIATION / SIGMA THETA 2. O ,__ DEGREES DITTEREFIIAL T1!MPERATURE + 4.0 DEGREES T
- Value corresponds to the PCRV area channel. Other four channels are
\
30 cpm.
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
(d A nw cade:) e n% fs+ i*h SU'6CL 0 && $h b0
PRIMARY AUXILIARIES j( f BOARD I-01 GAS WASTE SYSTEM 63 Normal LIQUID WASTE SYSTEM'62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal BOARD I-02__ HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /9 PSIG High Pressure Bottles- 5+a PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow 10079 GPM BUBW Header Pressure ?ct) PSIG HELIUM CIRCULATORS - SYSTEM 21 Normal BOARD I-03_ REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position f) INCHES Runback group positions 2A, rod #2 (2 INCHES rod #4 '1 INCHES rod #6 r? INCHES 4F, rod #25 0 INCHES rod #31 n INCHES rod #37 O INCHES Flux Controller position +/- N/A % Reserve Shutdown Material ._Ir/MMCdSTATUS , i I I i O I I _ _ ._ ._______________ _ ____ - _ - O
BOARD I-05
/~'g HYDRAULIC OIL SYSTEM 91 Normal 1 %.)
l STEAM WATER DUMP TANK SYSTEM 22 Loop. Selected / 1 or 2 Pressure AGS PSIG Temperature JG/ deg F Level 9E INCHES Radiation Jb -vo ar/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO ! EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06 EMERGENCY FEEDWATER PRESSURE 45/ PSIG () BOILER FEED PUMPS A Speed 0 ,_ RPM A Flow 0 lbs/hr B Status n (Z on/off B Flow o lbs/hr C Speed O RPM C Flow d 1bs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Tank O PSIG
, HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal SERVICE AIR SYSTEM 82 Normal
~
BOARD I-10 PLANT PROTECTIVE SYSTEM k-f) V RI BUILDI M TEMPERATURE-HIGH BAT 10E ;vr0 des F BAY 200 y7eo deg F BAY 300 ps0 des F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 W mr/hr Bay 1100 y ar/hr Bay 1000
- mr/hr Loop 2 Eay 600 Y mr/hr Bay 500 v ar/hr Bay 400 9 mr/hr MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-13 PENETRATION INTERSPACE dP [ PSID j RI BUILDING SUMP DISCHARGE FLOW O GPM BOARD I-15 RX STACK FLOW J.Ijf.DC ACFM RX BUILDING / AMBIENT dP - 0.BT PSID BOARD I-7507X CONTROL ROOM TEMPERATURE 67 deg F 480V ROOM TEMPERATURE 7/ deg F
. g. - t i
O
. FOR:, OPERATOR MESSAGE NO.
, LOCATtGN: FSV SWITCHBOARD TIME: iann XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX MESSAGE: - Several hotels in the area have called stating that residents of the evacuated area have arrived at their facilities. They stated that the bills should be forwarded to PSCC for payment. The_ hotel operators want to know if this is accurate, and if so, what is the correct billing procedure? e 4 XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX THIS IS A DRILL XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX
. l
FOSAVEI '87 l p Scenario time 4fd - U OVERALL PLANT PARAMETERS Clock time e Rx Power #M Turbine Generator Load o MW i PRIMARY COOLANT PRESSURE / 5' PSIA TEMPERATURE Circulator Inlet /4f deg F Core Outlet Yr0 deg F HELIUM FLOW Loop 1 ,4/4tr)1b s/hr Loop 2 O lbs/hr TOTAL R/coe 1b s /hr CIRCULATOR SPEED Circulator A 7900 RPM Circulator B 9 6ac RPM Circulator C 2 Acer) RPM Circulator D - c6M RPM MOISTURE (DEW POINT) ME-9306 < -5 7 deg F ME-9307 4-s? deg F l SECONDARY COOLANT FEEDWATER FLOW Loop 1 C lbs/hr Loop 2 d Ibs/ht TOTAL O lbs/hr MAIN STEAM Loop 1 Pressure 4f PSIG Temperature AST _deg F Loop 2 Pressure /390 PSIG Temperature 600 deg F l HOT REHEAT Loop 1 Pressure o PSIG
. Temperature 490 deg F l Loop 2 Pressure o PSIG Temperature la deg F COLD REHEAT Loop 1 Pressure O PSIG i Temperature rn deg F Loop 2 Pressure o PSIG Temperature no deg F 1
l ----- _
i 1 l RADIATION MONITORS SCENARIO TIME 08:00 l PROCESS MONITORS CLOCE TIME i4:oo 1 r ! NUMBER SENSITIVITY VALUE ALARMING i (Y/N) ! RT-4401 2.6E-10 ** 9 S 14 CPM Y RT-4402 1.2E-10 ** 8 W CPM V RT-4803 2.5E-8 _ G4E+5 CPM Y ) 2.2E-8 RT-6212 1. o E H CPM AJ RT-6213 2.2E-8 f.o E +1 CPM M RT-7312 2.3E-8 _,_,_ *(PCRV) J. 4 .E +5 CPM Y RT-7324-1 2.8E-8 5.7 E+5 CPM Y RT-7324-2 _ 8.9E-7 l. 5 E +t4 CPM Y RT-7325-1 OOS 00S 005 RT-7325-2 OOS 00S 005 RT-73437-1 4. 6 E-10__,_, ** 45E+5 CPM Y RT-73437-2 OOS 00S 005 RT-9301 __,_2.3E-8 2.9 E +f, CPM M RT-93252-12 N/A I. S E +1 mr/hr Y ! AREA MONITORS NUMBER VALUE ALARMING (mr/hr) (Y/N) RT-93250-1 3. o F + 3 _ Y RT-93250-2 3. O E +.3 Y RT-93250-3 3o.O6+0 Y RT-93250-4 3.o 6et Y RT-93250-5 3. O E c0 Y
,p RT-93250-8 3. O E t- 3 Y RT-93250-13 O./ AJ RT-93250-14 OsL M RT-93251-1 05L M RT-93251-3 50.0 E+ 0 AJ RT-93251-4 3. O E 4 O Y RT-93251-5 '% o E t. 3 Y RT-93251-6 3. o ee S Y RT-93251-7 3 o E , 2, y RT-93251-8 3 o E + '2, Y RT-93251-9 in E+3 V RT-93252-1 S.O E + 3 Y RT-93252-2 ~4 n E + 3 Y ~
RT-93252-4 300Eeo Y RT-93252-6 3. O E + 3 Y RT-93252-7 J. o E + 3 Y RIA-79511 3. O E
- O Y METEROLOGICAL DATA WIND SPEED 2. 0 MPH .
WIND DIREL*fION FROM 2'70 DEGREES PLUME DEVIATION / SIGMA THETA 8. O DEGREES DIFFERENTIAL TEMPERATURE +.4.0 DEGREES T (
- Value corresponds to the PCRV area channel. Other four channels are 30 cpm.
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
i i PRIMARY AUXILIARIES () BOARD I-01 GAS WASTE SYSTEM 63 Normal i 4 LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal ROARD I-02_ 1 HELIUM STORAGE SYSTEM 24 { Low Pressure Bottles /9 PSIG 1 High Pressure Bottles var PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow /mro GPM BUBW Header Pressure ?co PSIG HELIUM CIRCULATORS SYSTEM 21 Normal I BOARD I-03_ REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position o INCHES Runback group positions 2A, rod #2 o INCHES rod #4 ] INCHES rod #6 a INCHES 4F, rod #25 o INCHES rod #31 0 INCHES rod #37 6 INCHES Flux Controller position +/- N/A % Reserve Shutdown Material :Derr/ed STATUS O
BOARD I-05 () HYDRAULIC OIL SYSTEM 91 Normal STEAM WATER DUMP TANK SYSTEM 22 Loop Selected / 1 or 2 Pressure /Ts' PSIG Temperature T66 deg F Level Of INCHES Radiation Jo-VJ mr/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06 EMERGENCY FEEDWATER PRESSURE 69 PSIG p (,) BOILER FEED PUMPS A Speed a F.PM A Flow o lbs/hr B Status S#- on/off B Flow 0 lbs/hr C Speed n RPM C Flow O lbs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Tank O PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal () SERVICE AIR SYSTEM 82 Normal
l BOARD I-10
,f s PLANT PROTECTIVE SYSTEM RI BUILDING TEMPERATURE-HIGH i BAT 106 >/f6 des F l BAY 200 y / ro deg F BAY 300 7/50 des F !
REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 3 mr/hr Bay 1100 y ur/hr Bay 1000 t ar/hr I Loop 2 Bay 600 3 mr/hr Bay 500 s ar/hr Bay 400 5 mr/hr 1 MOISTURE MONITORS (DEW POINT) Normal 1 MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-13 I PENETRATION INTERSPACE dP 9# PSID RX BUILDING SUMP DISCHARGE FLOW O GPM BOARD I-15 RX STACK FLOW _[Lcop ACFM RX BUILDING / AMBIENT dP -GL / PSID BOARD I-7507X CONTROL ROOM TEMPERATURE 67 deg F ! 480V ROOM TEMPERATURE EP deg F O
i A Scen'ario time ff[ 's-) OVERALL PLANY PARAMETERS Clock time Avr( Rx Power SMS Turbine Generator Load o MW PRIMARY COOLANT PRESSURE /r PSIA TEMPERATURE Circulator Inlet /Go deg F Core Outlet 19f deg F HELIUM FLOW Loop 1 M Sdolbs/hr Loop 2 O lbs/hr . TOTAL ARRfva lbs/hr CIRCULATOR SPEED Circulator A ffdPO RPM Circulator B 9r0 RPM ~ Circulator C 9ro RPM Circulator D 970 RPM MOISTURE (DEW POINT) ME-9306 4-57 deg F ' ME-9307 4.-s'? d eg F SECONDARY COOLANT FEEDWATER FLOW Loop 1 a lbs/hr Loop 2 O lbs/hr TOTAL 0 lbs/hr MAIN STEAM Loop 1 Pressure 59' PSIG Temperature ,# deg F Loop 2 Pressure A ?v'd PSIG Temperature 5%o deg F HOT REHEAT I Loop i Pressure O PSIG t
. Temperature 44f deg F Loop 2 Pressure o PSIG T'emperature m< deg F COLD REHEAT Loop 1 Pressure O PSIG Temperature 79C deg F Loop 2 Pressure 6 PSIG Temperature 37s deg F
RADIA kON MTURS SCENARIO TIME o9 Is PROCESS M TORS CLOCE TIME t 4 '. t 5" NtMBER SENSITIVITY VALUE ALARMING (Y/N) RT-4801- 2.6E-10 **' 9584 CPM Y ! RT-4802 ,___1.2E-10___ ** 95H CPH Y RT-4803 _ 2.5E-8 4, b E +5 CPM V RT-6212 2.2E-8.__,_ ,_, l.0 E + L CPM M ! RT-6213 2.2E-8 f.o E +1 CPM M RT-7312 2.3E-4 *(PCRV) 2. 3 E +5 CPM V-RT-7324-1 2.8E-8 3. 7 E + 5 CPM Y j RT-7324-2 8.9E-7 _ 1. 2. E + 4 CPM V ; RT-7325-1 008 008 003 l RT-7325-2 008 003 003 RT-73437-1' 4.6E-10 ** I .1 E +.( , CPM Y
- RT-73437-2 005 003 008 RT-9301 2.3E-8 2. 8 E +(, CPM M
, RT-93252-12 N/A t. 7 E +1 ar/hr V AREA MTtBS NUMBER VALUE ALARMING (ar/hr) (Y/N) i RT-93250-1 S. O E e 3 Y I RT-93250-2 3.oEe3 Y RT-93250-3 So. O E+ 0 Y RT-93250-4 3.o E+3 Y RT-93250-5 3 . o c +- 0 V
'RT-93250-8 3. O E + 3 Y
.O-RT-93250-13 0./ U-RT-93250-14 05L M ,
RT-93251-1 0$L M ! RT-93251-3 50.0 E + 0 0 RT-93251-4 3. O E + O Y RT-93251-5 J. O E cA Y RT-93251-6 3.0 6+B Y RT-93251-7 AoG+3 V RT-93251-8 3.OEt3 V RT-93251-9 &O s-e 3 Y RT-93252-1 3. o E e S Y
'RT-93252-2 3. 0 6 v3 Y RT-93252-4 3n.o 6+0 Y
'RT-93252-6 30e+3 Y RT- 93252-7 3.oEr3 Y-RIA-79511 3.O E eO V METER 0RIAGICAL DATA WIND SPEED 7. 0 MPE .
WIND DIRECTION FRON 270 DEGREES PLUME DEVIATION /
-SIGNA THETA 2. O DEGREES DIFFERENTIAL TEMPERATURE + 4.0 DEGREES F O
- Value corresponds to the PCRV area channel.
30 cym.
** Value corresponds to a 15 minute build-up of activity.
Other four channels are Build-up starts
)
at the specified scenario / clock time.
.1
PRIMARY AUXILIARIES fm t
) BOARD I-01 l GAS WASTE SYSTEM 63 Normal LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal ROARD I-02 HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /9 PSIG High Pressure Bottles 5Ad PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow /## GPM BUBW Header Pressure 9mp PSIG HELIUM CIRCULATORS SYSTEM 21 Normal BOARD I-03 REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position O INCHES Runback group positions 2A, rod #2 o INCNES rod #4 0 INCHES rod #6 0 INCHES 4F, rod #25 0 INCHES rod #31 o INCHES rod #37 0 INCHES Flux Controller position +/- h// %
Reserve Shutdown Material h v M d STATUS
1
~
BOARD I-05 [e
% )'
HYDRAULIC OIL SYSTEM 91 Normal STEAM WATIR DUMP TANK SYSTEM 22 Loop Selected / 1 or 2 Pressure /S0 PSIG Temperature t?Go deg F Level 95 INCHES Radiation 2-vo ar/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06 EMERGENCY FEEDWATER PRESSURE 6 [ PSIG e ( BOILER FEED PUMPS A Speed O RPM A Flow c) lbs/hr l B Status 03 on/off B Flow o 1bs/hr C Speed 0 RPM i C Flow U lbs/hr CONDENSATE SYSTEM 31 Normal I MISCELLANEOUS I Bypasa Flash Tank () PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal ! l SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal SERVICE AIR SYSTEM 82 Normal
}
BOARD I-10
. PLANT PROTECTIVE SYSTEM RI BUILDING TEMPERATURE-HIGH BAY.100 /r0 deg F BAY 200 /ro deg F BAY 300 /r> deg F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 / mr/hr Bay 1100 / mr/hr Bay 1000 / mr/hr Loop 2 Bay 600 /,C ar/hr Bay 500 / mr/hr Bay 400 /, 5 mr/hr MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal ,
BUFF SEAL MALFUNCTION Normal BOARD I-13 PENETRATION INTERSPACE dP 9! PSID RI BUILDING SUMP DISCHARGE FLOW d GPM () BOARD I-15 RX STACK FLOW JU,oco ACFM RX BUILDING / AMBIENT dP -0J5'PSID BOARD I-7507X CONTROL ROOM TEMPERATURE /9 deg F 480V ROOM TEMPERATURE 2E deg F O
FOSAVEI '87 p Scenario time F/d V OVERALL PLANT PARAMETERS Clock time /'r30 Rx Power M Turbine Generator Load O MW PRIMARY COOLANT PRESSURE N PSIA TEMPERATURE Circulator Inlet Ned des F Core Outlet 3 70 des F HELIUM FLOW Loop 1 JGSPO lbs/hr Loop 2 0 lbs/hr TOTAL #prao lbs/hr CIRCULATOR SPEED Circulator A Mvo RPM Circulator B 90v RPM Circulator C 9cro RPM Circulator D 700 RPM MOISTURE (DEW POINT) ME-9306 4 -57 d e g F
, ME-9307 es? deg F k SECONDARY COOLANT FEEDWATER FLOW Loop 1 O lbs/hr Loop 2 O lbs/hr TOTAL 0 lbs/hr MAIN STEAM Loop 1 Pressure 4/ PSIG Temperature >K deg F Loop 2 Pressure //90 _PSIG Temperature SGo deg F HOT REHEAT L Loop 1 Pressure o PSIG l
Temperature 4ST des F 1 Loop 2 Pressure O PSIG Temperature 3M deg F COLD REHEAT Loop 1 Pressure O PSIG Temperature 3?o des F ' Loop 2 Pressure o PSIG Temperature 3 70 deg F l l
' RADIATION MONITtRS SCENARIO TIME- O R l-3 0 -
PROCESS MONITtRS CLOCE TIME i4:30 NONBER SENSITIVITY VALUE : ALARMING' (Y/N) RT-4801 _,__2.6E ** 8 514 CPM Y RT-4802. 1.2E-10___, ** 854 CPM Y RT-4803 2.5E-8 ___, 2. I E e 5' CPM Y RT-6212 2.2E-8 I.o E +i CPM M ~ RT-6213- 2.2E-8 _,__ l.o E +1 _ CPM U RT-7312 2.3E-8 *(PCRV) 1. 1 E +.5" CPM Y RT-7324-1 . _ 2.SE-8. f. 9 E +- 5" CPM Y RT-7324-2 ___.8.9E-7 6 0 E A CPM V RT-7325-1 005 008 008-RT-7325-2 008 008 008 RT-73437-1 4.6E-10_,,_ ** f.1 E 4.(, CPM Y RT-73437-2 OOS 008 003 RT-9301 2.38-8 - 2 7 E H, CPM M RT-93252-12: __ _ __N/ A A.5 E +C ar/hr Y AREA MONITtRS NUMBER- VALUE ALAPMI!r, (ar/hr) (Y/N)
.RT-93250-1 9. o 6 + 'Z. Y-RT-93250-2 9. o E +- 7_ ' Y -RT-93250-3 9.0 6 e O M RT-93250-4 9 06e2 V RT-93250-5 0.9 Al RT-93250-8 4.0 6 +2 Y RT-93250-13 0./ A/ i RT-93250-14 05L M -RT-93251 osL Al RT-93251-3 SO. O E+ O b>
RT-93251-4 a.4 M ! RT-93251-5' 9.OE+2 Y RT-93251-6 9. 0 E eZ Y , RT-93251-7 4.0 f" c2 V , RT-93251-8 0, o 6 +2. V i RT-93251-9 4.0 En V RT-93252-1 9. o E +2. Y RT-93252-2 9 0 E + 2. Y RT-93252-4 4. O G +-0 V RT-93252-6 4. o G e 2. Y RT-93252-7 9. O E +- 2. Y RIA-79511 O .9 A)
~
METER 0RLOGICAL DATA WIND SPEED S.O MPH . WIND DIRECTION FROM 2 '7 O DEGREES PLUME DEVIATION / SIGMA THETA 2. O DEGREES DIFFERENTIAL TEMPERATURE + 4. 0 DECREES F
'* Value corresponds to the PCRV area channel. Other four channels are 30 cym. ** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
<- PRIMARY AUXILIARIES k,,N) .
BOARD I-01_ GAS WASTE SYSTEM 63 Normal LIQUID WASTE SYSTEM 62 Normal l REACTOR PLANT COOLING WATER SYSTEM 46 Normal l PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal BOARD I-02 HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /9 PSIG High Pressure Bottles 54' PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow /ard GPM BUBW Header. Pressure 700 PSIG HELIUM CIRCULATORS SYSTEM 21 Normal BOARD I-03_ REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position O INCHES Runback group positions 2A, rod #2 O INCHES - rod #4 0 INCHES rod #6 0 INCHES 4F, rod #25 0 INCHES rod #31 O INCHES rod #37 0 INCHES Flux Controller position +/- N/(A % Reserve Shutdown Material 1%krsthdL STATUS ! i
I BOARD I-05 HYDRAULIC OIL SYSTEM 91 Normal (~')T STEAM WATER DUMP TANK SYSTEM 22 Loop Selected / 1 or 2 Pressure /97 PSIG Temperature urso deg F Level 97 INCHES Radiation Jo a mr/hr HELIUM CIRCULATORS SYSTEM 21 Normal I NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06 EMERGENCY FEEDWATER PRESSURE 4 G/ PSIG () BOILER FEED PUMPS A Speed O RPM A Flow o lbs/hr B Status 04F on/off B Flow o lbs/hr C Speed a RPM C Flow 0 lbs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Tank 0 PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal l FIREWATER SYSTEM 45 Normal . l' INSTRUMENT AIR SYSTEM 82 Normal (} SERVICE AIR SYSTEM 82 Normal a
BOARD I-10 PLANT PROTECTIVE SYSTEM O. RX BUILDING' TEMPERATURE-HIGH BAY 100 /ro deg F BAY 200 /co des F j BAY 300 Ma deg F j i REHEAT ACTIVITY MONITORS i Loop 1 Bay 1200 / mr/hr I Bay 1100 / mr/hr l Bay 1000 // mr/hr Loop 2 Bay 600 / mr/hr ' Bay 500 / mr/hr Bay 400 / mr/hr , l MOISTURE MONITORS'(DEW POINT) Normal . MAIN STEAM LOOP dP Normal , BUFF SEAL MALFUNCTION Normal BOARD I-13 PENETRATION INTERSPACE dP f PSID RX BUILDING SUMP DISCHARGE FLOW O GPM BOARD I-15 RX STACK FLOW 34 M ACFM RX BUILDING / AMBIENT dP -0,6 PSID BOARD I-7507X CONTROL ROOM TEMPERATURE / G deg F 480V ROOM TEMPERATURE 77 deg F l i O
FOSAVEX 87 FOR: CONTROL' ROOM OPERATOR MESSAGE No. ! LOCATIOil: CONTROL ROOM TIME: 1440 XXXXXXXXXXXXXXXXXX THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS XXX MESSAGE: You again attempted to close the Loop 2 circulator bypass isolation, HV- 2 2 4~2 , and it has closed. Notify the Shift Foreman. I m V 4 e THIS .IS A DRILL XXXXXXXXX.XXXXXXXXXXXXXXXXXXXX>CKXXXXXXXXXXXXXXXXXXXXXX
FOSAVEI '87 rw Scenario time 525' (_) OVERALL PLANT PARAMETERS Clock time /vys' Rx Power fMI Turbine Generator Load o MW. PRIMARY COOLANT PRESSURE PSIA TEMPERATURE Circulator Inlet / 58 deg F Core Outlet 34 s deg F HELIUM FLOW j Loop 1 c#/dc* lbs/hr Loop 2 o lbs/hr TOTAL o2/Ochs1bs/hr CIRCULdTOR SPEED - Circulator A P90U RPM Circulator B Ovo RPM Circulator C 9m RPM Circulator D 100 RPM MOISTURE (DEW POINT) ME-9306 2 -S"/ d e g F ME-9307 _ 4-57 deg F SECONDARY COOLANT FEEDWATER FLOW Loop 1 d lbs/hr Loop 2 o lbs/hr TOTAL d Ibs/hr MAIN STEAM Loop 1 Pressure 49' PSIG Temperature JW deg F Loop 2 Pressure /ono PSIG Temperature 5+'o d e g F HOT REHEAT Loop 1 Pressure o PSIG
. Temperature 4ser deg F Loop 2 Pressure o PSIG Temperature s2G f deg F COLD REHEAT Loop 1 Pressure o PSIG Temperature 76 f deg F Loop 2 Pressure o PSIG Temperature 36 CE deg F O
o
RADIATION MONI'IORS SCENARIO TIME ry g 4 5 PROCESS MONI'IORS CLOCE TIME 4.45 O NUMBER SENSITIVITY VALUE ALARMING (Y/N) RT-4801 2.6E-10 ** Dol 4 CPM V RT-4802 1.2E-10 ** 9514 CPM V RT-4803 2.5E-8 1,4 E +5 CPM Y RT-6212 2.2E-8 f.0 E +( CPM M RT-6213 2.2E-8 f.o E +1 CPM~ U RT-7312 2.3E-8 *(PCRV) 9.0 E 4-4 CPM Y RT-7324-1 ~~ 2.8E-8 l.3 E +-5 CPM ~ Y RT-7324-2 8.9E-7 4.0 E c3 CPM Y RT-7325-1 OOS 00S ~ 00S RT-7325-2 005 005 OOS RT-73437-1 4.6E-10 ** I,3 E 4 CPM ~ V RT-73437-2 OOS 00S OOS RT-9301 _ 2.3E-8 2. r E c(, CPM M RT-93252-12 N/A 7.O E r0 mr/hr Y AREA MONI'IORS I NUMBER VALUE ALARMING (mr/hr) (Y/N) RT-93250-1 4.0 6 + 2. V
, RT-93250-2 Q.0 E c2. V '
RT-93250-3 4. O E +- O AI RT-93250-4 'toEr2 Y RT-93250-5 o,9 A) , RT-93250-8 9.o E r 2. Y RT-93250-13 ' O./ Al i RT-93250-14 O.S f_ Al i RT-93251-1 0$L A/ RT-93251-3 S'O. O E t-O Al RT-93251-4 o.9 U ! RT-93251-5 9. o e c 2. Y ! RT-93251-6 9. o 6 c2. Y i RT-93251-7 4o Ee2 Y RT-93251-8 9.O E r2 Y ., RT-93251-9 9. o E
- 2. y RT-93252-1 9. o 6 + 7- V RT-93252-2 9. 0 6 e "F. Y RT-93252-4 4.o Ero Y ,
RT-93252-6 9. O Et-2. V RT-93252-7 9.O G*2 Y RIA-79511 O4 V METER 0RLOGICAL DATA WIND SPEED F.0 MPH . WIND DIRECTION FROM 270 DEGREES PLUME DEVIATION / SIGMA THETA 2. O DEGREES DIFFERENTIAL TEMPERATURE + 4.0 DEGREES F
- Value corresponds to the PCRV area channel. Other four channels , are 30 cps.
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenaric/ clock time.
4 PRIMARY AUXILIARIES h BOARD I-01 GAS WASTE SYSTEM 63 Normal LIQUID WASTE SYSTEM 62 Normal l REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal BOARD I-02 HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /9 PSIG High Pressure Bottles S/o PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow Az70 GPM BUBW Header Pressure G90 PSIG HELIUM CIRCULATORS SYSTEM 21 Normal BOARD I-03_ REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position _ O INCHES Runback group positions 2A, rod #2 O INCHES rod #4 0 INCHES rod #6 o INCHES 4F, rod #25 3 INCHES rod #31 C INCHES rod #37 o INCHES Flux Controller position +/- N/A % Reserve Shutdown Material jfugehd STATUS O
BOARD I-05
-( ) HYDRAULIC OIL SYSTEM 91 Normal STEAM WATER DUMP TANK SYSTEM 22 Loop Selected / 1 or 2 l Pressure /35 PSIG Temperature tre deg F Level ?' INCHES :
Radiation 2n-v0 mr/hr ) HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO < EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. j MAIN TURBINE SYSTEM 51 Normal BOARD I-06 EMERGENCY FEEDWATER PRESSURE /, G/ PSIG BOILER FEED PUMPS i A Speed 6 RPM A Flow a lbs/hr B Status oF on/off B Flow o lbs/hr C Speed o RPM C Flow v lbs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Tank 5 PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal l INSTRUMENT AIR SYSTEM 82 Normal () SERVICE AIR SYSTEM 82 Normal
BOARD I-10 PLANT PROTECTIVE SYSTEM RI BUILDING TEMPERATURE-HIGH BAY 100 BAT 200 fff des F
/-79 deg F BAY 300 /6 des F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 4/ mr/hr Bay 1100 e/ mr/hr Bay 1000 er ar/hr Loop 2 Bay 600 e/ mr/hr Bay 500 / mr/hr Bay 400 Af ar/hr MOISTURE MONITORS (DEW POINT) Normal l MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-13 PENETRATION INTERSPACE dP # PSID RI BUILDING SUMP DISCHARGE FLOW 6 GPM BOARD I-15 RX STACK FLOW O,no ACFM RX BUILDING / AMBIENT dP -0. 6 PSID BOARD I-7507X CONTROL ROOM TEMPERATURE 66 deg F 480V ROOM TEMPEP.ATURE 7') deg F O
FOSAVEI '87 Scenario time S~147 l Or OVERALL PLANT PARAMETERS Clock time / s2v> l Rx Power J-4dfS , Turbine Generator Load o MW 1 PRIMARY COOLANT I PRESSURE () PSIA TEMPERATURE Circulator Inlet /40 deg F Core Outlet 350 des F HELIUM FLOW Loop 1 . vat >r>1bs/hr ' Loop 2 o lbs/hr TOTAL 4 /or>o lb s /h r CIRCULATOR SPEED Circulator A P(/trv RPM Circulator B 60e RPM Circulator C Goo RPM Circulator D Jeoo RPM MOISTURE-(DEW POINT) ME-9306 2-57 deg F ME-9307 z-s? deg F SECONDARY COOLANT FEEDWATER FLOW Loop 1 6 lbs/hr ; lbs/hr Loop 2 o TOTAL O lbs/hr MAIN STEAM Loop 1 Pressure 49# PSIG Temperature #JCF deg F Loop 2 Pressure FGo PSIG Temperature r;o deg F HOT REHEAT Loop 1 Pressure o PSIG
. Temperature 6+1r deg F Loop 2 Pressure o PSIG Temperature 360 deg F COLD REHEAT Loop 1 Pressure 6 PSIG Temperature _? G o des F Loop 2 Pressure o PSIG Temperature 20 0 deg F O
I RADIATION MONITORS SCENARIO TIME 04:00 ' PROCESS MONITORS CLOCE TIME _ _ 1si 6 ~~~~[~ , nU NONRER SENSITIVITY VALUE ALARMING (Y/N) RT-4801 2.6E-10 ** $5t4 CPM Y
~
RT-4802 1.2E-10 ** 5~5II[ CPM Y RT-4803 2.5E-8 7. I E d , CPM Y RT-6212 2.2E-8 f.o E +i CPM PJ RT-6213 2.2E-8 1. 0 E +f CPM M RT-7312 _,_,2.3E-8 *(PCRV) 4.0 E +H CPM Y RT-7324-1 2.8E-8 (M E + 4 CPM V RT-7324-2 ___8.9E-7 2.o E +.3 CPM V RT-7325-1 00S 00s ,_ 00S RT-7325-2 OOS OOS 00S ~ RT-73437-1 __,4.6E-10 _ (l)**__,,,,si2 E e 4 CPM _,,y_ RT-73437-2 00S 007 _ 008 RT-9301 2.3E-8 2. (, E + (a CPM M RT-93252-12 N/A ja.O E + o ar/hr V AREA MONITORS NUMBER VALUE ALARMING (ar/hr) (Y/N) RT-93250-1 1,.p,f + 2. j RT-93250-2 _,,,,gE e 2. Y j RT-93250-3 ,
~ ~ ~ ~
s.OEto U RT-93250-4 _ ,1. o 6 + 2 , Y _ q RT-93250-5 . ,,fic I M V RT-93250-8 RT-93250-13 i .c e"> + 2 0.I V Al RT-93250-14 03 L '~ M RT-93251-1 ,_,J $l_ lLJ RT-93251-3 50. o E + O _,_, _ AJ RT-93251-4 O.I _ _ _ _ , N RT-93251-5 1. O E + 2. Y RT-93251-6 I, o E r2 Y RT-93251-7 o E t 7._ Y RT-93251-8 i o s t- 2 Y RT-93251-9 1. O E e2_ V RT-93252-1 1. o E e 2. _, Y RT-93252-2 t. o F e L V RT-93252-4 1. o FdO M RT-93252-6 8. o E. t2, Y RT-93252-7 1.0 64-2 Y RIA-79511 0.I M METEROLOGICAL DATA ,,___ WIND SPEED .5*. O MPH , WIND DIRECTION FRCH ,,,,,,,J 7 0 DEGREES PLUME DEVIATION / SIGNA THETA _ 8.O DEGREES DIFFERENTIAL TEMPERATURE + 4.0 DEGREES T
- Value corresponds to the PCRV area channel. Other four channels are 30 eps.
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
(I) A nr.a cadd}3 C isfd ik un'c t O NL l9 00
j l l PRIMARY AUXILIARIES ,
) BOARD I-01 GAS WASTE SYSTEM;63 Normal LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER STSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Norme.1 l LN-2 SYSTEM 25 Normal i MOARD I HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /P PSIG High Fressure Bottles 500 PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow //21 GPM BUBW Header Pressure 370 PSIG HELIUM CIRCULATORS SYSTEM 21 Normal BOARD I-03__ - \ REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position O INCHES l Runback group positions i
2A, rod #2 o INCHES rod #4 0 INCHES rod #6 o INCHES 4F, rod #25 o INCHES rod #31 o INCHES roJ #37 o INCHES Flux Controller position +/- N/n % Reserve Shutdown Materitl I"5 dfedL ,ST ATUS I L
9 BOARD I-05 fm 's,) HYDRAULIC OIL SYSTEM 91 Normal STEAM WATER DUMP TANK SYSTEM 22 Loop Selected / 1 or 2 Pressure /31 PSIG Temperature _cr,r deg F Level Or INCHES Radiation so. v3 mr/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. < THIS INFORMATION IS REQUIRED TO l EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06 I EMERGENCY FEEDWATER PRESSURE 6f/ PSIG ( BOILER FEED PUMPS A Speed n RPM A Flow o lbs/hr B Status o cf on/off B Flow 6 lbs/hr C Speed o RPM C Flow C lbs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Tank o PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal j SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal SERVICE AIR SYSTEM 82 Normal
BOARD I-10 PLANT PROTECTIVE SYSTEM
.{'- RX BUILDING TEMPERATURE-HIGH BAY 100' N/A des F BAY 200 / var d eg F BAY 300 /v/ deg F i
REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 z/ mr/hr Bay 1100. e/ mr/hr ! Bay 1000- e./ ar/hr Loop 2 Bay 600 -c / mr/hr Bay 500 ac / mr/hr Bay 400 /, f ar/hr MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-13 PENETRATION INTERSPACE dP 9#PSID RX BUILDING SUMP DISCHARGE FLOW O GPM () BOARD I-15,__ RX STACK FLOW 3360* ACFM RX BUILDING / AMBIENT dP -0,2f PSID BOARD I-7507X CONTROL ROOM TEMPERATURE 69 deg F 480V ROOM TEMPERATURE 79 deg F 0
FOSAVEI '87 r
~
Scenario time vsv ( OVERALL PLAET PARAMETERS Clock time /Ss Rx Power #- (/$ Turbine Generator Load d 'MW PRIMARY COOLANT PRESSURE /f PSIA TEMPERATURE Circulator Inlet /GO deg F Core Outlet 2 55 .deg F HELIUM FLOW Loop 1 JNeo 1bs/hr Loop 2 O lbs/hr TOTAL 37tg2n_1bs /hr CIRCULATOR SPEED Circulator A 9(FT) RPM Circulator B Gro RPM Circulator C M1 RPM Circulator D %70 RPM MAISTURE (DEW POINT) ME-9306 4-57 d e g F ME-9307 ,
<-57 d e g . F SECONDARY COOLANT FEEDWATER FLOW Loop 1 6 lbs/hr Loop 2 o 1bs/hr TOTAL a lbs/hr MAIN STEAM Loop 1 Pressure M PSIG Temperature > Sr deg F Loop 2 Pressure 7oo PSIG Temperature S~oo deg F HOT REHEAT Loop 1 Pressure a PSIG
. Temperature 335' deg F Loop 2 Pressure o PSIG Temperature c;rs deg F COLD REHEAT Loop 1 Pressure 6 PSIG Temperature r deg F Loop 2 Pressure a PSIG Temperature NC deg F O
v
RADIATION MONITORS SCENARIO TIME 04 t5 PROCESS HONITORS CLOCK TIME 1S: is OV NUMBER SENSITIVITY VALUE ALARMING (Y/N) RT-4801 2.6E-10__, ** SSH CPM Y RT-4802 1.2E-10__ ** 85H CPM Y RT-4803 2.5E-8 46 E +LI CPM Y RT-6212 2.2E-8 I.o E +f CPM N RT-6213 2.2E-8 f.o E +1 CPM M RT-7312 2.3E-8 *(PCRV) 2. 6 E +'4 CPM Y RT-7324-1 2.8E-8 4.I E + 4 CPM V RT-7324-2 ,___8.9E-7 I,3 E +3 CPM Y RT-7325-1 OOS 005 OOS RT-7325-2 005 ,__ 00S 00S RT-73437- 1 _ 4.6E-10 ** 9.I E +4 CPM Y RT-73437-2 OOS 005 OOS RT-9301 2.3E-8 2 0 E +-(o CPM M RT-93252-12 N/A 5.0 E c0 mr/hr V AREA MONITORS NUMBER VALUE ALARMING (mr/hr) (Y/N) RT-93250-1 I. O s'+ 2. Y RT-93250-2 i, o &+7- S' RT-93250-3 6. O G +- 0 0 RT-93250-4 i . o E + 2. Y r RT-93250-5 O.I M
+
RT-93250-8 l. O Cr2 Y RT-93250-13 O./ N RT-93250-14 05L U RT-93251-1 05L AJ RT-93251-3 50. O e t O V RT-93251-4 O.I AJ RT-93251-5 1. O E + 2. Y RT-93251-6 I. O EE t- 2. Y RT-93251-7 1.0 G +- 2 V RT-93251-8 1. 0 6 + 2 V RT-93251-9 t. O E e 2_ V RT-93252-1 I . O G +- 2. Y RT-93252-2 1OEt2 f RT-93252-4 i . O E +- 0 0 RT-93252-6 1, o G 4-2_ Y RT-93252-7 1. o E + 2. y RIA-79511 O. I U METER 0RLOGICAL DATA WIND SPEED EO MPH . WIND DIRECTION FROM 270 DEGREES PLUME DEVIATION / SIGNA THETA 2.O DEGREES DIPPERENTIAL TD(PERATURE + 4.0 DEGREES P l l
- Velue corresponds to the PCRV area channel. Other four channels are
,4 30 cpm.
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
d
4 PRIMARY AUXILIARIES ) BOARD I-01 GAS WASTE - SYSTEM 63 Normal LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal LN-2 . SYSTEM 25 Normal ROARD I HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /9 PSIG High Pressure Bottles -(2d PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow /dTO GPM BUBW Header Pressure 4 76 PSIG HELIUM CIRCULATORS SYSTEM 21 Nornal BOARD I-03_ REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position d INCHES Runback group positions 2A, rod #2 6 INCHES rod #4 D INCHES rod #6 o INCHES 4F, rod #25 A INCHES rod #31 8 INCHES rod #37 </ INCHES Flux Controller position +/- X//s % Reserve Shutdown Material I 29f/rdhd STATUS i
~
BOARD I-05 HYDRAULIC OIL SYSTEM 91 Normal (J) STEAM WATER DUMP TANK SYSTEM 22
-Loop Selected __. / 1 or 2 Pressure /;ur PSIG Temperature 7 322 dog F Level 95 INCHES Radiation gro-99 mr/hr HELIUM CIRCULATORS SYSTEM 21 Normal NOTE LOW RANGE dP INDICATIONS WILL BE OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR.
THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06 EMERGENCY FEEDWATER PRESSURE 6 9 PSIG BOILER FEED PUMPS A Speed , m RPM A Flow 6 lbs/hr B Status oF on/off B Flov o 1bs/hr C Speed 6 RPM C Flow 0 lbs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Tank d PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal () SERVICE AIR SYSTEM 82 Normal
BOARD I-10 PLANT PROTECTIVE SYSTEM ( ') RI BUILDING TEMPERATURE-HIGH BAY 100 /ro deg F BAY 200 m deg F BAY 300 /-ro d es F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 // mr/hr
-Bay 1100 4/ mr/hr Bay 1000 e/ mr/hr Loop 2 Bay 600 </ mr/hr Bay 500 / mr/hr Bay 400 /, r ar/hr MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-13 PENETRATION INTERSPACE dP +/ PSID
<~ RX BUILDING SUMP DISCHARGE FLOW 0 GPM (_) BOARD I-15 RX STACK FLOW JJ 000 ACFM RX BUILDING / AMBIENT dP -J.cf PSID BOARD I-7507X CONTROL ROOM TEMPERATURE (7 deg F 480V ROOM TEMPERATURE 27 deg F 1 1 O
FOSAVEI '87 (~T Scenario time 570 ( s) OVERALL PLANT PARAMETERS Clock time /53o Rx Power Turbine Generator Load J'd6 NMW PRIMARY COOLANT PRESSUPE /C PSIA TEMPERATURE Circulator Inlet /(f deg F Core Outlet J TO deg F HELIUM FLOW Loop 1 J9', 000 lbs/hr Loop 2 o lbs/hr TOTAL / / 000 lbs/hr CIRCULATOR SPEED Circulater A P'/06 RPM Circulator B 4(a RPM Circulator C 4 50 RPM Circulator D Aro RPM MOISTURE (DEW POINT) ME-9306 2 -59 deg F ME-9307 /-57 deg F (' SECONDARY COOLANT FEEDWATER FLOW Loop 1 o lbs/hr Loop 2 o lbs/hr TOTAL 0 lbs/hr MAIN STEAM Loop 1 Pressure 6V PSIG Temperature AST deg F Loop 2 Pressure too PSIG Temperature +'P o deg F HOT REHEAT Loop 1 Pressure r3 PSIG
. Temperature 62r deg F Loop 2 Pressure o PSIG Temperature 3To deg F COLD REHEAT Loop 1 Pressure o PSIG Temperature 30) deg F Loop 2 Pressure o PSIG Temperature JTd deg F O
1 RADIATION MONI20RS SCENARIO TIME 09: 30 PROCESS MONITORS CLOCK TIME I5'.'30 NUMBER SENSITIVITY VALUE ALARMING I (Y/N) i j RT-4801 2.6E-10___ ** B S(4 CPM Y RT-4802 1.2E-10 D54 CPM Y RT-4803 2.5E-8 2.,4 E t.4 CPM Y RT-6212 __,2.2E-8 1.o E +l__ CPM U RT-6213 2.2E-8 ___ l.o E +4 CPM Al RT-7312 2.3E-8 *(PCRV) I, 3 E +.4 CPM Y RT-7324-1 2.8E-8 2.I E+4 CPM AJ RT-7324-2 8.9E-7 (, M E +1 CPM A/ I 00S RT-7325-1 OOS 00S RT-7325-2 OOS OOS 00S RT-73437-1 4.6E-10 ** f. 2 E +6 CPM Y RT-73437-2 OOS 005 OOS RT-9301 2.3E-8 Z,4 E e7 CPM N RT-93252-12 N/A 3. (, E e O mr/hr Y AREA MONI20RS NUMBER VALUE ALARMING (mr/hr) (Y/N) RT-93250-1 i,o E t 2. Y RT-93250-2 l , o A + 2. V RT-93250-3 5 o G+ O U RT-93250-4 1,0 E v2 V RT-93250-5 O.I Al RT-93250-8 i . O E + '2. Y RT-93250-13 0./ Al _ RT-93250-14 O$L M RT-93251-1 0$L A) RT-93251-3 Jn.OE+0 Al RT-93251-4 c.I Al RT-93251-5 i , o G + 2. Y RT-93251-6 I.o G + 2 Y RT-93251-7 l.o Gt-2 Y RT-93251-8 i .O E +-2. V RT-93251-9 1. O G t 2. Y RT-93252-1 1. o Gr2. V RT-93252-2 1. 0 E v2. Y RT-93252-4 f.n M en U RT-93252-6 10 6 t 2 Y RT-93252-7 i , o ErL Y RIA-79511 O.I AJ METER 0RLOGICAL DATA WIND SPEED 5,0 MPH , WIND DIRECTION FROM 2'70 DEGREES PLUME DEVIATION /
. SIGMA THETA 2. O DEGREES DITTERENTIAL TEMPERATURE + 4.0 DEGREES T
- Value corresponds to the PCRV area channel. Other four channels are 30 cpm.
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time.
PRIMARY AUXILIARIES BOARD I-01 GAS WASTE SYSTEM 63 Normal LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal BOARD I-02 HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /9 PSIG High Pressure Bottles w en PSIG i EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow Am GPM BUBW Header Pressure 695 PSIG HELIUM CIRCULATORS SYSTEM 21 Normal BOARD I-03_ G REACTOR CONTROL SYSTEM 12 Regulating Rod (1) position O INCHES Runback group positions 2A, rod #2 o INCHES rod #4 > INCHES rod #6 ? INCHES 4F, rod #25 o INCHES rod #31 5 INCHES rod #37 o INCHES Flux Controller position +/- ///A % Reserve Shutdown Material _Ts<ve/ed STATUS O
BOARD I-05 () HYDRAULIC OIL STEAM WATER DUMP TANK SYSTEM 91 SYSTEM 22 Normal Loop Selected / 1 or 2 Pressure /03 PSIG Temperature c FO deg F Level 77 INCHES Radiation ;0-va mr/hr HELIUM CIRCULATORS SYSTEM 21 Normal : NOTE LOW RANGE dP INDICATIONS WILL BE 0FF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN CIRCULATOR. THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06 EMERGENCY FEEDWATER PRESSURE # 49'PSIG BOILER FEED PUMPS A Speed O RPM A Flow e7 lbs/hr B Status a# on/off B Flow o lbs/hr C Speed a RPM C Flow n 1bs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Tank C) PSIG { HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal INSTRUMENT AIR SYSTEM 82 Normal () SERVICE AIR SYSTEM 82 Normal
9 l __ BOARD I-10 PLANT PROTECTIVE SYSTEM , RI BUILDING TEMPERATURE-HIGH BAT 1@E /pSrdeg F BAY 200 /'2r d eg F BAY 300 /ag, d eg F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 4/ mr/hr Bay 1100 4/ mr/hr Bay 1000 4/ mr/hr Loop 2 Bay 600 4/ mr/hr Bay 500
/ mr/hr '
Bay 400 /,f ar/hr MOISTURE MONITORS (DEW POINT) Normal MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNCTION Normal BOARD I-13 PENETRATION INTERSPACE dP 9 PSID'
~
RX BUILDING SUMP DISCHARGE FLOW d GPM () BOARD I-15 __ l RX STACK FLOW jl' CP1
< ACFM RX BUILDING / AMBIENT dP -- d, 9 f'P S I D BOARD I-7507X !
CONTROL ROOM ' TEMPERATURE 67 deg F 480V ROOM TEMPERATURE FI deg F O i 1
. _ j FOSAVEI '87
,G Scenario time STrf V OVERALL PLANT PARAMETERS Clock time /rw Rx Power 1-8 N Turbine Generator Load a MW PRIMARY COOLANT PRESSURE /r PSIA TEMPERATURE Circulator Inlet /Co deg F Core Outlet 3<< deg F HELIUM FLOW Loop 1 W OOO lbs/hr Loop 2 o lbs/hr .
TOTAL m ovo 1bs/hr CIRCULATOR SPEED Circulator A WOO RPM Circulator B 4ro RPM Circulator C bro RPM Circulator D G7o RPM MOISTURE (DEW POINT) ME-9306 <-37 deg F ME-9307 <-57 deg F SECONDARY COOLANT l FEEDWATER FLOW Loop 1 D lbs/hr Loop 2 a lbs/hr i TOTAL c) lbs/hr l MAIN STEAM ' Loop 1 Pressure # PSIG Temperature ASC deg F Loop 2 Pressure <ur PSIG Temperature vGo des F HOT REHEAT Loop 1 Pressure e, PSIG
, Temperature soo deg F Loop 2 Pressure o PSIG
, Temperature .Tra deg F COLD REHEAT Loop 1 Pressure o PSIG Temperature 2s a deg F Loop 2 Pressure a PSIG i Temperature __3 r0 deg F l
l 1
RADIATION MONITORS SCENARIO TIME 09:45 i PROCESS MONITORS ~ CLOCK TIME f 6:4y
.l -O NUMBER SENSITIVITY VALUE ALARMING (Y/N)
RT-4401 2.6E-10 ** 8364 CPM V RT-4802 _ 1.2E-10_,_ ** 8 081 CPM Y RT-4803 2.5E-8 _ l . G E +.4 CPM A) RT-6212 2.2E-8 I.o E +( CPM A) , RT-6213 ,__,2.2E-8 f.o E ,1 CPM Al l
'RT-7312 2 . 3 E-8 ' _,,_,, *(PCRV) gM E +3 CPM Y RT-7324 ,_,,_2. 8E-8 1. 44 E + 4 CPM AJ l
RT-7324-2 8.9E-7 4. 5 E + 2. CPM Al RT-7325-1 005 003 005 RT-7325-2 OOS 003 005 RT-73437-1 4.6E-10 ** 1.4 E + 5' CPM Y RT-73437-2 OOS 008 005 RT-9301 2.3E-8 2 3 E + (, CPM AJ RT-93252-12 N/A 3 0 E +O ar/hr Y AREA MONITORS NUMBER VALUE ALARMING (ar/hr) (Y/N) RT-93250 f. O E+2. V RT-93250-2 f. O G c 2. Y , RT-93250-3 5 o 6+ O Li RT-93250-4 I. O E c2. Y RT-93250-5 0,t U RT-93250-8 i,o E + 2 Y RT-93250-13 0./ U RT-93250-14 05L A1 ! RT-93251-1 03L Al RT-93251-3 So, OE+ 0 Al RT-93251-4 o. I Al RT-93251-5 f .o E c 2. Y RT-93251-6 1. O E e 2. V RT-93251-7 l. o E c 2. V i RT-93251-8 f.O E + 2 Y RT-93251-9 I. O E t 2. V RT-93252-1 i.O E c2 Y _,, RT-93252-2 1. O E v 2.- Y RT-93252-4 l. O E+O Al I RT-93252-6 f. 0 E & 7. Y RT-93252-7 I . o a c2 Y RIA-79511 0. I M METER 0RLOGICAL DATA i WIND SPEED s.0 MPH . WIND DIRECTION FROM 270 DEGREES PLUME DEVIATIGt SIGNA THETA 2.O DEGREES ; DIFFERENTIAL TEMPERATURE +. 4. 0 DEGREES F ' (D 30 cps.
** Value corresponds to a 15 minute build-up of activity. Build-up starts at the specified scenario / clock time. !
. PRIMARY AUXILIARIES
( BOARD I-01 GAS WASTE SYSTEM 63 Normal LIQUID WASTE SYSTEM 62 Normal REACTOR PLANT COOLING WATER SYSTEM 46 Normal PURIFIED HELIUM SYSTEM 23 Normal LN-2 SYSTEM 25 Normal BOARD I-02 i HELIUM STORAGE SYSTEM 24 Low Pressure Bottles /V PSIG 3 i High Pressure Bottles 3 90 PSIG EMERGENCY FEEDWATER SYSTEM 31 Emergency Feed Flow Mrm GPM BUBW Header Pressure GPO PSIG HELIUM CIRCULATORS SYSTEM 21 Normal 7 BOARD I-03 REACTOR CONTROL SYSTEM 12 Regulating Rod (1). position O INCHES Runback group positions 2A, rod #2 o INCHES rod #4 o INCHES rod #6 O INCHES 4F, rod #25 o INCHES rod #31 O INCHES rod #37 n INCHES Flux Controller position +/- /Vdv % Reserve Shutdown Material .25cerfec/ STATUS O
L i l. I BOARD I-05 ()I HYDRAULIC OIL SYSTEM 91 Normal STEAM WATER DUMP TANK SYSTEM 22 Loop Selected / 1 or 2 Pressure of PSIG Temperature ?.on deg F Level of INCHES , Radiation jo-Vo mr/hr l HELIUM CIRCULATORS SYSTEM 21 Normal NOTE 1 i LOW RANGE dP INDICATIONS WILL BE l OFF SCALE DURING OPERATION AND LOW TO "0" PSI FOR A SHUTDOWN. CIRCULATOR. THIS INFORMATION IS REQUIRED TO EVALUATE FOR OPEN CIRCUALTOR DISCHARGE VALVES. MAIN TURBINE SYSTEM 51 Normal BOARD I-06 EMERGENCY FEEDWATER PRESSURE SY PSIG (~} (_- BOILER FEED PUMPS l A Speed O RPM A Flow - 0 lbs/hr B Status 04 on/off B Flow o lbs/hr C Speed 0 RPM C Flow 0 lbs/hr CONDENSATE SYSTEM 31 Normal MISCELLANEOUS Bypass Flash Tank C PSIG HOT REHEAT BYPASS VALVE POSITIONS Normal PLANT ELECTRICAL Normal MAIN TOWER SYSTEM 41 Normal SERVICE WATER TOWER SYSTEM 42 Normal FIREWATER SYSTEM 45 Normal ! INSTRUMENT AIR SYSTEM 82 Normal () SERVICE AIR SYSTEM 82 Normal
BOARD I-10
-~ PLANT PROTECTIVE SYSTEM ~#
RI BUILDI C TEMPERATURE-HIGH BAY IOS //5' deg F BAY 200 af deg F BAY 300 //7 deg F REHEAT ACTIVITY MONITORS Loop 1 Bay 1200 af / mr/hr Bay 1100 Z/ mr/hr i Bay 1000 err ar/hr Loop 2 Bay 600 _64__ar/hr Bay 500 4/ mr/hr Bay 400 /,f ar/hr l 1 MOISTURE MONITORS (DEW POINT) Normal j MAIN STEAM LOOP dP Normal BUFF SEAL MALFUNC" TION Normal l BOARD I-13 i PENETRATION INTERSPACE dP '/ PSID RX BUILDING SUMP DISCHARGE FLOW d GPM r (, BOARD I-15 RX STACK FLOW Jj a79 ACFM RX BUILDING / AMBIENT dP -. 6L 3 PSID BOARD I-7507X CONTROL ROOM TEMPERATURE C7 deg F 480V ROOM TEMPERATURE P4[deg F l 1 1
FOSAVEX 87_ FOR: cRD MESSAGE NO. LOCATION: FCP TIME: XXXXXXXXXXXXXXXXXX THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS X MESSAGE: i' j When you believe you have achieved the exercise objectives, conclude FOSAVEX 87. 1
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t i uO 7.0-1 l' SECTION 7.0 ONSITE RADIOLOGICAL DATA Section Page 7.1 Plant Monitoring Data '7.1-1 7.2 Radiation / Chemistry Data 7.2-1. 7.3 Plant Area Radiation Levels. 7.3-1
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In t) Rome ( d/h ; l Channel Location RT-93250-1 Refueling Machine Control Room - Rx (fl.4fil') /0~' h 10' RT-93252-1 Refueling Floor Northeast - Rx (fl. 4rts') /0-' f 10Y RT-93251-1* Reactor Plant Exhaust Filter Room - Tb (El.4?64') /o 5 f, /o? RT-93250-2 East Walkway Outside HSF - Rx (El. Vf41') /o-' f, /0 4 RT-93252-2 South Stairwell - Rx (El. 4T44') 10-' 4. 10 ' RT-93250-3 Hot Service Facility Platform - Rx(El. 4141') lo 4. lo" RT-93251-3 Hot Service Facility Blower Suction - Rx(El.ytyt') lo-' f. f o* RT-93250-4 East Walkway HSF Entrance - Rx (El. 4t31') s o-' f, fo M RT-93251-4 General Office Area - Tb (El. 4til') Ib" f. 'lo" RT-93252-4 Analytic Intrument Room - Rx (El. 4tW) lo*' f. lo" 4 RT-93250-5 Main Control Room - Tb (El. 4fM') lo ' t. 10
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* = High range monitor
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. i L SECTION 8.2:. ] RELEASE RATE / DOSE ASSESSMENT ~
,. FOSAVEX - 87
-I* :
PLUME SEGMENT:- TIME: From dd!OO To OTIST j
- RELEASE RATE:
l Noble Gas. O Ci/sec *
~ Iodine (Total) O ci/sec !
PROJECTED DOSES: e O l l o 3,1 - 4 ' I __-____________________________-_O
SECTION 8.2 RELEASE RATE / DOSE ASSESSMENT-FOSAVEX -'87' O-
. PLUME SEGMENT: $ TIME: From ,/ /Od_ To /Ol/V RELEASE RATE:
Noble Gas / 6 b CUsec Iodine (Total) O Ci/see PROJECTED DOSES: DIST- DILUTION WHOLE BODY THYROID ANCE FACTOR 00SE RATE DOSE RATE (MILES) (SEC/M3) (REM /HR) ( RE M/ HR ) EAB 3.362E- 4 4.357E- 3 0.000E+ 0 . 0.5 2.037E- 4 2.640E- 3 0.000E+ 0 1.0 1.071E- 4 1.388E- 3 0.000E+ 0 1.5 7.380E- 5 9.565E- 4 0.000E+ 0 2.0 5.662E- 5 7.336E- 4 0.000E+ 0 3.0 3.d54E- 5 4.996E- 4 0 000E+ 0 4.0 2.905E- 5 3.765E- 4 0.000E+ 0 5.0 2.331E- 5 3.022E- 4 0.000E+ 0 7.5 1.577E- 5 2.045E- 4 0.000E+ 0 10.0 1.196E- 5 1.553E- 4 0.000E+ 0 O u-r i ___.-___-_-______--A
SECTION 8.2 RELEASE RATE / DOSE ASSESSMENT FOSAVEX - 87 PLUME SEGMENT: b TIME: From /dMI To /d'6k RELEASE RATE: Noble Gas /. E E Ci/sec Iodine (Total) O Ci/sec PROJECTED DOSES: DIST- DILUTION WHOLE BODY THYROID ANCE FACTOR DDSE RATE DOS E R ATE (MILES) (SEC/M3) (REM /HR) (REM /HR) EAB 3.362E- 4 4.357E- 3 0.000E+ 0 , 0.5 2 037E- 4 2.640E- 3 0.000E+ 0 1.0 1.071E- 4 1.388E- 3 0.000E+ 0 1.5 7.380E- 5 9.565E- 4 0.000E+ 0 2.0 5 662E- 5 7.338E- 4 0.000E+ 0 3.0 3.d54E- 5 4.996E- 4 0.000E+ 0 l l 4.0 2.905E- 5 3.765E- 4 0.000E+ 0
- 5.0 2.331E- 5 3.022E- 4 0.000E+ 0 1
7.5 1.577E- 5 2.045E- 4 0.'000E+ 0 10.0 1.198E- 5 1 553E- 4 0.000E+ 0 l l O u-a
SECTION 8.2 RELEASE RATE / DOSE ASSESSMENT FOSAVEX - 87 PLUME SEGMENT: C TIME: From j d O To /heYk RELEASE RATE: Noble Gas /. 6 E Ci/sec . Iodine (Total) O Ci/sec PROJECTED DOSES: . DIST- 3ILUTION WHOLE BODY THYROID ANCE FACTOR DOSE RATE DOS E R ATE (MILES) (SEC/M3) (REM /HR) (REM /HR) EAB 3.362E- 4 4.357E- 3 0.000E+ 0 0.5 2.037E- 4 2.640E -3 0.000E+ 0 1.0 1.071E- 4 1.388E- 3 0.000E+ 0 l '. 5 7.380E- 5 9.565E- 4 0.000E+ 0 2.0 5.662E- 5 7.338E- 4 0.000E+ 0 3.0 3.854E- 5 4.996E- 4 0.000E+ 0 4.0 2.905E- 5 3.765E- 4 0.000E+ 0 5.0 2.331E- 5 3.022E- 4 0.000E+ 0 7.5 1.577E- 5 2.045E- 4 0.000E+ 0 10.0 1.198E- 5 1.553E- 4 0.000E+ 0 5.1-7
. _ - _ . - - _ _ _ _ - - _ - _ - _ _ J
SECTION'8.2 RELEASE RATE / DOSE. ASSESSMENT FOSAVEX - 87 g y .. i PLUME SEGMENT: h < TIME: From[N1( To_ job _f
. RELEASE RATE:
Noble Gas /. 5'2 - A
,__Ci/sec -
Iodine (Total). O 4,_Ci/sec-PROJECTED DOSES: DIST- 3ILUTICN WHOLE BODY THYROID
'ANCE FACTOR DOSE RATE DOS E R AYE (MILES) (SEC/M3) (REM /HR) (REM /HR)
EAB 3.362E- 4 4.357E- 3 0.000E+ 0 0.5 2.037E- 4 2.640E- 3 0.000E+ 0 1.0 1.071E- 4 1.388E- 3 0.000E+ 0 1.5 7.380E- 5 9.565E- 4 0.000E+ 0 { 20 5.662E- 5 7.338E- 4 0.000E+ 0 3.0 3.854E- 5 4.996E- 4 0.000E+ 0 4.0 2.905E- 5 3.765E- 4 0.000E+ 0 5.0 2.331E- 5 3.022E- 4 0.000E+ 0 7.5 1.577E- 5 2.045E- 4 0.000E+ 0 10.0 1.198E- 5 1.553E- 4 0.000E+ 0 i l 0 l J
l SECTION 8.2 RELEASE RATE / DOSE ASSESSMENT FOSAVEX - 87 PLUME SEGMENT: b- HME: From //l00 To ////4 RELEASE RATE: Noble Gas /, 6 6 - Ci/sec - Iodine (Total) O Ci/sec PROJECTED DOSES: DIST- JILUTION WHOLE BODY THYROID ANCE FACTOR DOSE RATE DOS E R ATE (MILES) (SEC/M3) (REM /HR) (REM /HR) EAB 3.362E- 4 4.357E- 3 0.000E+ 0 0.5 2.037E- 4 2.640E- 3 0.000E+ 0 1.0 1.071E- 4 1.388E- 3 0.000E+ 0 1.5 7.380E- 5 9.565E- 4 0.000E+ 0 20 5.662E- 5 7.338E- 4 0.000E+ 0 3.0 3.d54E- 5 4.996E- 4 0.000E+ 0 4.0 2.905E- 5 3.765E- 4 0.000E+ 0 5.0 2.331E- 5 3.022E- 4 0.000E+ 0 ; 7.5 1.577E- 5 2.045E- 4 0.000E+ 0 10.0 1.198E- 5 1 553E- 4 0.000E+ 0 1 .' o l F.2-9
SECTION 8.2 RELEASE RATE / DOSE ASSESSMENT FOSAVEX - 87
. PLUME SEGMENT: k TIME: From //!/$ To //;N RELEASE RATE:
Noble Gas /. 5 b CUsec Iodine (Total) 'O Ci/sec PROJECIED DOSES: OIST- DILUTION WHOLE BODY THYROID ANCE FACTOR 00SE RATE 00SE RATE
'(MILES) (SEC/M3) (REM /HR) (REM /HR)
GAB 3.362E- 4 4.357E- 3 0.000E+ 0 1
-1 0.5 2.037E- 4 2.640E- 3 0.000E+ 0 1.0 1.071E- 4 1.388E- 3 0.000E+ 0 1.5 7.380E- 5 9.565E- 4 0.000E+ 0 2.0 5.662E- 5 7.338E 0.0GOE+ 0 l
30 3.d54E- 5 4.996E- 4 0.000E+ 0
'4.0 2.905E- 5 3.765E- 4 0.000E+ 0 5.0 2.331E- 5 3.022E- 4 0.000E+ 0 7.5 1.577E- 5 2.045E- 4 0.000E+ 0 10.0 1.198E- 5 1.553E- 4 0.000E+ 0 l
l 1 O 4 l 3.t-10 t
- - _ - - - - - - - - - - - --- a
E
.. SECTION 8.2 RELEASE RATE / DOSE ASSESSMENT FOSAVEX - 87
- PLUME SEGMENT: b TIME: From //!30 To //lN RELEASE RATE:
Noble Gas /. E E -2 Ci/sec - Iodine (Total) O- Ci/sec . PROJECTED DOSES: DIST- 3ILUTION WHOLE BODY THYROID ANCE FACTOR DOSE RATE DOS E R ATE (MILES) (SEC/M3) (REM /HR) (REM /HR) EA8 3.362E- 4 4.357E- 3 0.000E+ 0 0.5 2.037E 4 2.640E- 3 0.000E+ 0 1.0 1.071E- 4 1.388E- 3 0.000E+ 0 1.5 7.380E- 5 9.565E- 4 0.000E+ 0 2.0 5.662E- 5 7.338E- 4 0.000E+ 0 3.0 3.d54E- 5 4.996E- 4 0.000E+ 0 4.0 2.905E- 5 3.765E 4 0.000E+ 0 50 2.331E- 5 3.022E- 4 0.000E+.0 7.5 1.577E- 5 2.045E- 4 0.000E+ 0 10.0 1.198E- 5 1.553E- 4' O.000E+ 0 O g.1-ll ' c _ -_ .__ _- __ _-_---_ _ _ -
n ( l SECTION 8.2 RELEASE RATE / DOSE ASSESSMENT FOSAVEX - 87 i :(-) PLUME SEGMENT: _ TIME: From //W_I To //!69
. RELEASE RATE:
Noble Gas d,2.E-2 Ci/see Iodine (Total) O Ci/see PROJECTED DOSES: i OIST-- DILUTION WHOLE BODY THYROID ') ANCE FACTOR DOSE RATE DOSE RATE (FILES) (SEC/e3) (REN/HR)' (REM /HR) EAB 7.012E 3.718E- 2 0.000E+ 0 - 0.5 4.249E- 4 2.253E- 2 0.000E+ 0-
. - 1.0 2.290E- 4 1.214E- 2 0.000E+ 0 1.5 1.607E- 4 8.523E- 3 0.000E+ 0 2.0 1.251E- 4 6.632E- 3 0.000E+ 0 3.0 8.693E- 5 4.609E- 3 0.000E+ 0 4.0 6.645E- 5 ~ 3.523E- 3 0.000E+ 0 0.0 5.388E- 5 2.857E- 3 0.000E+ 0 7.5 3.707E- 5 1.966E- 3 0.000E+ 0 10.0 2.645E- 5 1.508E- 3 0.000E+ 0 O
T, '2.- / 2.
SECIION 8.2 RELEASE RATE / DOSE ASSESSMENT 4 FOSAVEX - 87 O PLUME SEGMENT: [- TIME: From /2/00 To /7,' / @ RELEASE RATE: Noble Gas 2., f b -f I Ci/sec ' Iodine (Total) /, / b - [ Ci/sec PROJECTED DOSES: DIST- OlLUTION WHOLE BODY THYROID ANCE FACTOR DOSE RATE DOSE RATE (MILES) (SEC/P3) (REM /HR) ( RE M/ HR )
~
EAB 7.012E- 4 1.239E+ 1 9.165E+ 0 0.5 4.249E- 4 7.511E+ 0 5.554E+ 0 1, ') 2.290E- 4 4.047E+ 0 2.993E+ 0 k 1.5 1.6C7E- 4 2.841E+ 0 2.101E+ 0 2.0 1.251E- 4 2.211E+ 0 1.635E+ 0 3.0 8.693E- 5 1.536E+ 0 1.136E+ 0 4.0 6.645E- 5 1.174E+ 0 8.685E- 1 5.0 5.388E- 5 9.523E- 1 7.043E- 1 7.5 3.707E- 5 6.553E- 1 4.846E- 1 10.0 2.845E- 5 5.028E- 1 3.718E- 1 O T, 2 -13
SECTION 8.'2 RELEASE RATE / DOSE ASSESSMENT FOSAVEX - 87 i O PLUME SEGMEIC: [- TIME: From /2,'/I To / M'/ T j RELEASE RATE: Noble Gas /,4 6 + / Ci/sec - Iodine (Total) /, / b ' f Ci/sec l PROJECTED DOSES: O I S T -- DILUTION WHOLE BODY THYROID l At4 CE FACTOR DOSE RATE 00SE RATE (MILES) (SEC/P3) (REM /HR) (REM /HR) EA8 7.012E- 4- 8 097E+ 0 9.165E+ 0 - 0.5 4.249E- 4 4.907E+ 0 5.554E+ 0 1.0 2.290E- 4 2.644E+ 0 2.993E+ 0 l.5 1.607E- 4 1.856E+ 0 2.101E+ 0 2.0 1.251E- 4 1.444E+ 0 1.635E+ 0 3.0 8.693E- 5 1.004E+ 0 1.136E+ 0 4.0 6.645E- 5 7.673E- 1 8.685E- 1 5.0 5.388E- 5 6.222E- 1 7.043E- 1 7.5 3.707E- 5 4.281E- 1 4.846E- 1 i 10.0 2.845E- 5 3.285E- 1 3.718E- 1 0
%.2.-14
l SECTION 8.2 RELEASE RATE / DOSE ASSESSMENT FOSAVEX - 87 PLUME' SEGMENT: k TIME: From /hOO Tolh!l/Y RELEASE RATE: Noble Gas b,7 E4 O Ci/sec Iodine (Total) 7 i E Cusec PROJECTED DOSES: DIST- DILUTION WHOLE BODY THYROID ANCE FACTOR DOSE RATE DOSE RATE (MILES) (SEC/M3) (REM /HR) (REM /HR) EAB 7.012E- 4 3.966E+ 0 6.665E+ 0 - 0.5 4.249E 2.403E+ 0 4.039E+ 0 l- 1.0 2.290E- 4 1.295E+ 0 2.176E+ 0 1.5 1.607E- 4 9.091E- 1 1.528E+ 0 1 2.0 1.251E- 4 7.074E- 1 1.189E+ 0 3.0 8.693E- 5 4.917E- 1 8 263E- 1 4.0 6.645E- 5 3.758E- 1 6.316E- 1 5.0 5.388E- 5 3.047E- 1 5.122E- 1 7.5 3.707E- 5 2.097E- 1 3.524E- 1 10.0 2 845E- 5 1.609E- 1 2.704E- 1 l l 4
%. 2.-I5
.,(_ SECTION 8.2 ' RELEASE RATE / DOSE ASSESSMENT FOSAVEX - 87 f. To/7,189 PLUME SEGMENT: . TIME: From /$!M[ RELEASE RATE:' Noble Gas 9,' [a 5+O 'Ci/sec ' Iodine (Total) I,Y b -"21 -Ci/sec PROJECTED DOSES: DIST- DILUTION WHOLE BODY THYROIO ANCE FACTOR DOSE RATE- DOSE RATE (MILES) ( SE C / P. 3 ) (REM /HR) (REN/HR) EAB l'.402E -3 5.453E+ 0 9.165E+ 0 . 0.5 o.499E- 4 3.305E+ 0 5.554E+ 0 1.0 4.579E- 4 1.781E+ 0 2.993E+ 0 1.5 3.215E- 4 1.250E+ 0 2.101E+ 0 2.0 2.5C2E- 4 9. 72 7E- 1 1.635E+ 0 3.0 1.739E- 4 6.760E- 1 1.136E+ 0 4.0 1.329E- 4 5.168E- 1 8.685E- 1 5.0 1.078E- 4 4.190E- 1 7.043E- 1 7.5 7.415E- 5 2.883E- 1 4.846E- 1 10.0 5.689E- 5 2.212E- 1 3.718E- 1
%. 2.- M
___._____________.___w
SECTION 8.2
' RELEASE RATE / DOSE ASSESSMENT FOSAVEX - 87
,r y 6
M PLUME SEGMENT: TIME: From /3 IOC To /3!/V RELEASE RATE: Noble Gac 2,2.(i+0 c1isee Iodine (Total) h,O$~b Ci/sec PROJECTED DOSES: DIST- DILUTION WHOLE BODY THYROID ANCE FACTOR DOSE RATE 00SE RATE (NILLS) (SEC/N3) (REN/HR) (REM /HR) EAB 1.402E- 3 2.644E+ 0 6.665E+ 0 , 0.5 8 499E- 4 1.602E+ 0 4.039E+ 0 1.0 4.579E- 4 8.633E- 1 2.176E+ 0 1.5 3.215 E- 4 6. 061E- 1 l'.528E+ 0 2.0 2.5C2E- 4 4.716E- 1 1.189E+ 0 3.0 1.739E- 4 3.278E- 1 8.263E- 1 4.0 1.329E- 4 2.506E- 1 6.316E- 1 5.0 1.078E- 4 2.032E- 1 5.122E- 1 7.5 7.415E- 5 1.398E- 1 3.524E- 1 10.0. 5.689E- 5 1.073E- 1 2.704E- 1
.(w )
$.1-17
l L , SECTION 8.2 [ RELEASE RATE / DOSE ASSESSMENT FOSAVEX - 87 t . l
..M From /3!/I PLUME SEGMENT: TIME: To _/3.'2 7 RELEASE RATE:
Noble Gas k, 7 2 -- / Ci/sec -
. Iodine (Total) . N. d b " b - Ci,3ec-l PROJECTED DOSES:
s
'DIST- '0ILUTION WHOLE BODY THYROIO ANCE FACTOR DOSE RATE DOSE RATE (MILES) ( S E C'/ M 3 ) (REM /HR) (REM /HR)
EAB 1.4C2E- 3 1.157E+ 0- 4.416E+ 0 .- 0.5 d.499E- 4 7.010E- 1 2.676E+ 0
'1.0 4.579E- 4 3.777E-'1 1.442E+ 0 1.5 3.215E- 4 2.652E- 1 1. 012 E + 0 l
2.0 2.502E- 4. 2.063E- 1 7.877E- 1 1 1 1 3.0 1.739E- 4 1.434E- 1 5.474E- 1 4.0 1.329E- 4 1.096E- 1 4.185E- 1 5.0 1.078E- 4 8 888E- 2 3.393E- 1 l 7.5 7.415E- 5 6.116E- 2 2.335E- 1 1 J 10.0 5.689E- 5 4.693E- 2 1.791E- 1 l O
%. 2.-l 5
SECTION 8.2 RELEASE RATE / DOSE ASSESSMENT FOSAVEX - 87 i l PLUME SEGMENT: O. T1xE: rrom /3:30 To /.3. 4y RELEASE RATE:' Noble Gas 7, 3 b - [ Ci/sec Iodine (Total) f, Y b ~2 Ci/see t PROJECTED DOSES: , DIST- . DILUTION WHOLE 800Y THYROID ANCE FACTOR DOSE RATE DOSE RATE iMILtS) (SEC/M3) (REM /HR) (REM /HR) EAB 1.402E- 3 8 758E- 1 2.333E+ 0 _ 0.5 8.499E- 4 5.307E- 1 1.414E+ 0 1.0 4.5T9E- 4 2.860E- 1 7.617E- 1 l' . 5 3.215E- 4 2.008E- 1 '.348E- 1 2.0 2.502E- 4 1 562E- 1 4.161E- 1 3.0 1.739E- 4 1.086E- 1 2.892E- 1 1 4.0 1.329E- 4 8.300E- 2 2.211E- 1 5.0 1.076E- 4 6.730E- 2 1.793E- 1 7.5 7.415E- 5 4.631E- 2 1.233E- 1 10.0 5.689E- 5 3.553E- 2 9.464E- 2 1 0 -
%,2.-19
SECTIGN 8.2 RELEASE RATE / DOSE ASSESSMENT FOSAVEX - 87 O PLUME SEGMENT: P 1:ME: rrom /3! # To /3:M RELEASE RATE: Noble Gas 3O b- / Ci/sec Iodine (Total) 1, 4 E - 2. Ci/sec PROJECTED DOSES: DIST- DILUTION WHOLE BOCY THYROIO ANCE FACTOR DOSE RATE DOSE RATE (MILES) (SEC/P3) (REM /HR) (REM /HR) EA8 7.012E- 4 2.974E- 1 1.166E+ 0 - 0.5 4.249E- 4 1.803E- 1 7.069E- 1 1.0 2.290E- 4 9.712E- 2 3.809E- 1 1
,- 1.5 1.607E- 4 6.818E- 2 2 674E- 1 2.0 1.251E- 4 5 306E- 2 2.081E- 1 3.0 d.o93E- 5 3.687E- 2 1.446E- 1 4.0 6.645E- 5 2.819E- 2 1.105E- 1 5.0 5.36eE- 5 2.286E- 2 8.963E- 2 7.5 3.707E- 5 1.573E- 2 6.167E- 2 10.0 2.845E- 5 1.207E- 2 4.732E- 2 O
3.2-20
SECTION 8.2-RELEASE RATE / DOSE ASSESSMENT FOSAVEX - 87 f h To , h k PLUME SEGMENT: TIME: From_f$00
~
RE LEASE RATE: Noble Gas 2,6 6 -/ Ci/sec Iodine (Total) /,0 E - 1 Ci/sec PROJECTED DOSES: k DIST- DILUTION WHOLE BODY THYROIO Al4 CE FACTOR DOSE RATE DOSE RATE (MILES) (SEC/M3) (REN/HR) (REM /HR) l EAB 7.012E- 4 1.487E- 1 8.748E- 1 - 0.5 4.249E- 4 9.013E- 2 5.302E- 1 1.0 2.290E- 4 4.856E- 2 2.856E- L' 1.5 1.607E- 4 3.409E- 2 2.005E- 1 2.0 1 251E- 4 2.653E- 2 1.561E- 1 3.0 d.693E- 5 1.844E- 2 1.085E- 1 4.0 6.645E- 5 1.409E- 2 8.290E- 2 , 5.0 5.388E- 5 1.143E- 2 6.722E- 2 7.5 3.707E- 5 7.863E- 3 4.626E- 2 10.0 2.845E- 5 6.033E- 3 3.549E- 2 l 4
. I i
1 i O ) E 2- 2. I L - -___- --- ------ - -_---- _ -
SECIION 8.2 RELEASE RATE / DOSE ASSESSMENT FOSAVEX - 87 PLUME SEGMENT: TIME: From /kI/h To fk [k RELEASE RATE: l Noble Gas' f,]$"f CUsec ' Iodine (Total)- [3,i b-3 Ci/sec , PROJECTED DOSES: DIST- DILUTION WHOLE B00Y THYROID ANCE FACTOR 00SE RATE 00S E . R A T E-(MILES)-(SEC/M3) (REM /HR) (REM /HR) ! EAB 7.012E- 4 9.914E- 2 5.832E- 1 - 0.5 4.249E- 4 6.006E- 2 3.534E- 1 1.0 2.290E- 4 3.237E- 2 1.904E- 1 1.5 1.607E- 4 2.273E- 2 1.337E- 1 2.0 1.251E- 4 1.769E- 2 1.040E- 1 30 8.693E- 5 1.229E- 2 7.230E- 2 4.0 6.645E- 5 9.396E- 3 5.527E- 2 5.0 5.368E- 5 7 619E- 3 4.482E- 2 7.5 3.707E- 5 5.242E- 3 3.084E-~2 10.0 2.845E- 5 4.022E- 3 2.366E- 2 O ! l 5.2-22. , (
SECTION 8.2 RELEASE RATE / DOSE ASSESSMENT FOSAVEX - 87
. r~s l4!30 To /4://t/
PLUME SEGMENT: TIME: From RELEASE RATE: Noble Gas $. 3 E - 2. ci/sec - Iodine (Total) 50 E-3 ci/sec PROJECTED DOSES: DIST- DILUTION WHOLE BODY THYROID ANCe FACTOR DOSE RATE 00SE RATE (MILES) (SEC/M3) (REM 6HR) d (REM /HR)
~
EAB 3.362G- 4 2.377E- 2 1.997E- 1 0.5 2.037E- 4 1.440E- 2 1.210E- 1 1.0 1.071E- 4 7.570E- 3 6.361E- 2
- 1.5 7.380E- 5 5.217E- 3 4.384E- 2
?
2.0 5.662E- 5 4.003E- 3 3.364E- 2 i 3.0 3.854E- 5 2.725E- 3 2.290E- 2 4.0 2.905E- 5 2.054E- 3 1.7265- 2 5.0 2.331E- 5 1.648E- 3 1.385E- 2 1 I 7.5 1.577E- 5 1 115E- 3 9.372E- 3 ] 10.0 1.198E- 5 8.470E- 4 7.118E- 3 O T.2-13
't SECTION 8.2 RELEASE RATE / DOSE ASSESSMENT FOSAVEX - 87 T )'
PLUME SEGMENT: TIME: From he To hIhh RELEASE RATE: Noble Gas $I b"b CUsec
. Iodine (Total) N.3 Ed Ci/sec PROJECTED DOSES:
DIST-. DILUTION WHOLE BODY THYROID ANCE FACTOR DOSE RATE DOSE RATE * (MILES) (SEC/M3) (REM /HR) (REM /HR)
~
EA6 3.362E- 4 1.584E- 2 1.338E- 1 0.5 2.037E- 4 9.601E- 3 8.108E- 2 g 1.0 1.071E- 4 5.047E- 3 4.262E- 2 1.5 7.380E- 5 3.478E- 3 2.938E- 2 2.0 5.662E- 5 2.668E- 3 2.254E- 2 3.0 3.954E- 5 1.817E- 3 1.534E- 2 4.0 2.905E 5 1.369E- 3 1.156E- 2 5.0 2.331E- 5 1.099E- 3 9.280E- 3 7.5 1.577E- 5 7.435E- 4 6.279E- 3 10.0 1.198E- 5 5.647E- 4 4.769E- 3 O T. 2. - 2 Y L- - - - _ _ _ _ - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
SECTION 8.2 RELEASE RATE / DOSE ASSESSMENT FOSAVEX - 87 l I PLUME SEGMENT: k TIME: From_6:00 To 6!/V
- l. RELEASE RATE:
Noble Gas 21 E-2 cusec Iodine (Total) /. ? E -3 cosec PROJECTED DOSES: DIST- DILUTION WHOLE BODY THYROID ANCE FACTOR DOSE RATE DOSE RATE (MILES) (SEC/M3). (REM /HR) (REM /HR) EAB 3.362E- 4 7.922E- 3 6.990E- 2 0.5 2.037E- 4 4.800E- 3 4.236E- 2 1.0 1.071E- 4 2.523E- 3 2.226E- 2 1.5 7.380E- 5 1.739E- 3 1.535E- 2 2.0 5.662E- 5 1.334E- 3 1.177E- 2 3.0 3.854E- 5 9.063E- 4 8.015E- 3 4.0 2.905E- 5 6.846E- 4 6.040E- 3 5.0 2.331E- 5 5.494E- 4 4.848E- 3 7.5 1.577E- 5 3.717E- 4 3.280E- 3 10.0 1.198E- 5 2.823E- 4 2.491E- 3 , l O . 3.1-25
7 SECTION 8.2 RELEASE RATE / DOSE ASSESSMENT FOSAVEX - 87 PLUME SEGMENT: Y TIME: From /h'/h To /6/N RELEASE RATE: Noble Gas I. 7 E- & Cu ee Iodine (Total). /,7 b "3 Ci/see PROJECIT.D DOSES: DIST- DILUTION WHOLE BODY THYRDID ANCE FACTOR DOSE RATE DOSE' RATE (MILES) (SEC/M3) (REM /HR) (REN/HR) EAB 3.362E- 4 5.150E- 3 6.990E- 2 0.5 2.037E- 4 3.120E- 3 4 236E- 2 1.0 1.071E- 4 1.640E- 3 2.226E- 2 1.5 7.3 DOE- 5 1.130E 1.535E- 2 2.0 5.662E- 5 8.672E- 4 1.177E- 2 3.0 3.854E- 5 5.904E- 4 8.015E- 3 4.0 2.905E- 5 4.450E- 4 6.040E- 3 5.0 2.331E- 5 3.571E- 4 4.848E- 3 7.5 1.577E- 5 2.416E- 4 3.280E- 3 10 0 1.198E- 5 1.835E- 4 2.491E- 3 O T,1 - M
IL , SECTION 8.2 RELEASE RATE / DOSE ASSESSMENT-FOSAVEX - 87 PLUME SEGMENT: k TIME: From }$!,M To /h!N RELEASE RATE: Noble Gas 9.3Ed ci/sec Iodine (Total) f,3 6 4 ci/sec PROJECTED DOSES: DIST- DILUTION WHOLE 80DY THYROID ANCE FACTCR DOSE RATE DOSE RATE (MILES) (SEC/P3) (REM /HR) (REM /HR) EAo 3.362E- 4 2.654E- 3 5.193E- 2 , 0.5 2.037E- 4 1.608E- 3 3.147E- 2 1.0 1.071E- 4 8.453E- 4 1.654E- 2 1.5 7.380E- 5 5.826E- 4 1.140E- 2 2.0 5.662E- 5 4 470E- 4 8.745E- 3 3.0 3.854E 5 3.043E- 4 5.954E- 3 4.0 2.905E- 5 2.293E- 4 4.487E- 3 5.0 2.331E- 5 1.840E- 4 3.601E- 3 7.5 1.577E- 5 1 245E- 4 2.437E- 3 10.0 1.198E- 5 9.458E- 5 1.851E- 3 5, 2- E 7
SECTION 8.2 RELEASE RATE / DOSE ASSESSMENT FOSAVEX - 87 PLUME SEGMENT: k TIME: From kN To [h'
. RELEASE RATE:
Noble Gas _ [,2 b d Ci/sec j Iodine (Total) .k b-h Ci/sec PROJECTED DOSES: DIST- DILUTION WHOLE BODY THYR 010 ANCE FACTCR DOSE RATE DOSE RATE (MILES) (SEC/N3) (REM /HR) (REM /HR) EAB 3.362E- 4 1.783E- 3 3.795E- 2 0.5 2.037E- 4 1.080E- 3 2.299E- 2 ! 1.0- 1.071E- 4 5.678E- 4 1.209E- 2 1.5 7.380E- 5 3.913E- 4 8.330E- 3 2.0 5.062E- 5 3.002E- 4 6.391E- 3 3.0 3.854E- 5 2.044E- 4 4.351E- 3 4.0 2.905E- 5 1.540E- 4 3 279E- 3 5.0~ 2.331E- 5 1.23bE- 4 2.632E- 3 7.5 1.577E- 5 8.364E- 5 1.781E- 3 10.0 1.198E- 5 o.353E- 5, 1.352E- 3 O T.2-Z?
SECTION 8.3 FIELD MONITORING DATA FOSAVEX - 87 r~M ! ' ~
~ PLUME SEGMENT: RELEASE TIME: From [ LOO To h 6 7 PROJECTED IN-FIELD SAMPLING RESULTS Ambient -
Radiation-
. Levels
- Particulate *I-l31 (mR/hr) Activity Att ivity Concentra- Net Concentra- Net Distance Window Window tion Count Rate tion Count Rate (Miles) Open Closed (,,pCi /ce ) (com) JpC1/ce) (cpm)
EAs SG BG mM o mbA O o.s BG BG mhA o MM o . 1.o BG BG mhA o mhA o 1.s BG BG mbA o mbA 0 ' O 2.o BG bG mM o MM O 2.s 6G' dG fnM o MbA 0 1.0 - BG BG MM o (UA O r.o BG AG mM o MbA 0 s.o eG BG nbA. O MDA 0
,.s AG BG mbA O MDA 0 lo.o' $G $h @f O $MA O
*' Based on a collection volume of 15 ft' (4.2 x lo' cc) 7,3-l
SECTION 8.3 FIELD MONITORING DATA FOSAVEX - 87 PLUME SEGMENT: RELEASE TIME: From /O!OO To /O!/4 i PROJECTED IN-FIELD SAMPLING RESULTS Ambient Radiation Levels
- Particulate *I-131 (mR/hr) Activity Activity Concentra- Net Concentra- Net Distance Window Window tion Count Rate tion Count Rate (Miles) Open Closed _IpCi/cc) (com) JpCi/cc) (cpm)
EAs 8.SNo it. 4 +0 mbA O MDA O o.s 52+O 2A 40 thhA O thbA. O - 1.0 2.t10 INtO MDA o MDA o 1.s I,9+0 9.1- l MbA o MbA O 0 2.0 J.5+O 9,3 -l mbg O mbA . O 2.s 1,2 + 0 4,2 -1 MhA-o MhA 0 i 3.o Lo+0 5, D-1 MbA o MbA o 4.o 76-1 3.9-I mg O mbA O 1 s.o 6.0 -1 3. 0 -1 pgg 0 MDA o 7.s NO't 2,0- 1 m3g o MA o io.o 3.2- / l.6-/ #DA O #UA O ) I 1
- Based on a collection volume of 15 ft' (4.2 x 10' cc) {
8.3 .
'SECTION 8.3 FIELD MONITORING DATA FOSAVEX - 87 PLUME SEGMENT: h RELEASE M E: From [ MI To MM PROJECTED ~<
IN-FIELD SAMPLING RESULTS Ambient ' Radiation Levels .*Particulate *I-131 (mR/hr) Activity Activity Concentra- Net Concentra- Net Distance Window Window tion Count Rate -tion Count Rate (Miles) Open Closed JpCi/cc) (com)' JpCi/cc) (com)- EA8 $INO h,4+0 m04 0 m04 o o.s 5,2 +O 2.4 +0 thbA 0 thhA o 1.0 2.ta INTO MbA o MbA o 1.s I,9 + 0. 9,1- l MbA o MDA O Q 2.o )5+0. 9,5-l mDA O inDA o 2.s I.2 +0 4,2 -1 MhA o MhA O 2.0 Lo+0 5 D-l MbA o MbA o u.o 7,4-/ 3,7-l MM O MM o q s.o 4.0 -1 3.0 -l nbg 0 nbh o 7.s M 0-1 2,0-I M1) O MbA O 1o.0 3.2-l I.6-1 pfbg 0 AlDA o
- Based on a collection volume of is ft' (4.2 x 10' cc) i O
7,a-3
SECTION 8.3 FIELD MONITORING DATA FOSAVEX - 87 f% PLUME SEGMENT: b RELEASE TIME: From [hdO To / <YY PROJECTED IN-FIELD SAMPLING RESULTS Ambient Radiation Levels
- Particulate *I-131 (mR/hr) Activity Activity Concentra- Net Concentra- Net Distance Window Window tion Count Rate tion Count Rate (Miles) Open Closed JpCi/ce) (cpm) JpCi/ce) (cpm)
EAB 8. h o l+. 4 + 0 m0A O m0A O o.s 5 2+O 2.440 MhA O mbA O 1.0 2.710 1,4t0 MDA o MDA o 1.s I,9+0 9.1- l Mb.4 o MbA O ' 9,3-l Q 2.0 }.5+O mDA O MDA o 2.s 1.2 + 0 l2-I mpA O MbA O 2.0 LO+0 5, D-l MbA o MbA o a.o 9.4-l 3.9-I mm O mbA O s.o 6.0 -l 3.0 -I nog C MD4 o 1.s M 0-1 2.0-I m1A . O MhA O to.o' 3.Z- / l.6-/ geg O_ #DA o
- Based on a collection volume of 15 ft' (4.2 x 10' cc)
I
\
l %. l e 1 T.3.4 L
SECTION 8.3 FIELD MONITORING DATA FOSAVEX - 87 PLUME SEGMENT: h RELEASE TIME: From /O!YI To /O'67 PROJECTED IN-FIELD SAMPLING RESULTS Ambient Radiation Levels
- Particulate *I-131 (mR/hr) Activity Activity Concentra- Net Concentra- Net Distance Window Window tion Count Rate tion Count Rate (Miles) Open Closed JpC1/cc) (cpm) JpCi/ce) (com)
EAB 3.b O 4.4+0 m04 0 m04 0 a.s 5. 2 + O 2.440 inhA o mbA o ~ 1.0 2.11 0 int 0 MDA o mhA o l 1.s I,9 + 0 9,1- l MDA o MbA O g 2.o /,5+0 7,3-l mD4 o MDA o 2.s 1,2 + 0 L2-1 mpA o MpA o 2.0 Lo+0 50-I inbA o thbA o a.o 9.4-1 3,9-l mhA O mbA O , s.o 6,0 -/ 3.0-/ M04 C MDA o 7.5 N O'l [,0- { (Y))l O _ (Yihk D 10.o _ 3.2-I l.&-I gpg O MDA o
- Based on a collection volume of 15 ft' (4.2 x 10' cc)
O 7.3-5
SECTION 8.3 FIELD MONITORING DATA FOSAVEX - 87 PLUME SEGMENT: h RELEASE TIME: From //,'00 To [l!/Y PROJECTED IN-FIELD SAMPLING RESULTS Ambient Radiation Levels
- Particulate *I-131 (mR/hr) Activity Activity Concentra- Net Concentra- Net Distance Window Window tion Count Rate tion Count Rate (Miles) Open Closed jpCi/cc) (cpm) jpCi/cc) (cpm)
EAB 8.R + O If,4 +o m0A 0 mD4 o o.s 5. 2 + O 2.440 mbA O mbA O . 1.o 2. t10 INtO mbA o MDA o 1.s 1.9 + 0 9.1- I mbe o MbA O Q 2.0 J.5+O 9,3-l mDA O MDA O 2.s I.2 + 0 d2 -l MhA . O MhA O 3.0 Lo+0 5; D-l MbA o MbA o 1 a.o 9.4-1 3.9-l mba O mbA O s.o G.0 -1 3. 0 -l nng 0 nnh o 7.s M O-l 2.0- l mnA O MhA O to.o 3.2- / l.6-/ #DA O #DA O
- Based on a collection volume of 15 ft' (4.2 x lo' cc)
O r.4-6 _ _ _ _ . _ _ _ _ _ _ _ _ . _ . _ . _ _ _ _ _ _ _ _ . . _ . _ _ _ - - - - - - _ - _ - - _ - _ - _ - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ' - - - - - - - - - - - - - ^ - - - - - - - - - ~ ^ - - - ~ - - - - - - - - - ~ - - -
SECTION 8.3 FIELD MONITORING DATA FOSAVEX - 87 PLUME SEGMENT: RELEASE TIME: From //'/[ To //![7 PROJECTED - IN-FIELD SAMPLING RESULTS Ambient Radiation Levels
- Particulate *I-131 (mR/hr) Activity Activity Concentra- Net Concentra- Net Distance Window Window tion Count Rate tion- Count Rate (Miles) Open Closed _(yCi/cc) (com) _,pci/cc) ( (cpm)
EAB 8.940 4,4+o mD4 0 204 0 a.s 5 2 +O 2.440 thhA _ O (hhA 0 - 1.0 2.810 IN +0 mbA o MDA o 1.s I,9+0 9.1- I mba o inDA O O 2o /s+o 7s-l mon o mod o 2.s I,2 +0 ll,2 -I O inbA O MbA 2.0 Lo+0 5; D-l MbA o MbA o u.o 7,4-/ 3,7-l _mg O (MM O s.o 4.0 -1 3.0 -l n0A. O nbh o 1.s -- M O-l 2.0- I mng O MhA O 10.o 3. 2- / l.6-/ #DA O #DA o ' l
- Based on a collection volume of is ft* (4.2 x los ee)
I 1 O l E 3- 7 i
'. i
_ - _ _ - _ - - ---__--___--__-_A
l SECTION 8.3 FIELD MONITORING DATA FOSAVEX - 87
,r >
k-. PLUME SEGMENT: h RELEASE TIME: From //d C To //lN PROJECTED IN-FIELD SAMPLING RESULTS Ambient Radiation Levels .
- Particulate *T-131 (mR/hr) Activity Activity Concentra- Net Concentra- Net Distance Window Window tion Count Rate tion Count Rate (Miles) Open Closed _1pci/ce) (com) _1pci/ce) (epm)
EAa 8.t+ o l+. 4 + 0 MDA O m0A O o.s 5. 2 + O 2.440 mhA o MbA o 1.0 2. T10 INtO MDA o MbA_ o 1.s I,9 + 0 9.7- l MbA o MbA 0 (} 2.o /,5#0 I,2 +0 7,3-l 4,2 -1 mDA o nfDA o 2.s MhA o mhA _- O a.o Lo+0 5;D-I MbA o MbA o 4.o 7,4-/ 3 ?-l Mg O MhA O s.o 4.0 -I 3.o -l h DA. O MD4 o 7.5 NO'l 2,0- I m)) O MhA O so.o 3.2- / l.4-/ pf0A O diDA o
- Based on a collection volume of 15 ft' (4.2 x 10' cc)
I F.3-y
SECTION 8.3 FIELD MONITORING DATA FOSAVEX - 87
,b .
PLUME SEGMENT: ,k -RELEASE TIME: From f/s'kI To //67-PROJECTED- - IN-FIELD SAMPLING RESULTS-Ambient l Radiation Levels ~
- Particulate *I-131 !
(mR/hr) ' Activity Activity Concentra- Net ~ Eoncentra- Net Distance Window Jindow tion Count Rate tion Count Rate (Miles) Open Closed JpC1/ce) (com) Jpci/cc) (com) EAs 74+l 3.7+1 mM o MDA O l o.s 'U + L L'M I mhn o mhn o 1.0 2.tki .I, 21/ mbA 0 GM_ o 1.s L7+l 8.5+ 0 Mbg. . O mbA O _2 . 0 1,3 + l d.6+0 m0g _ O #bA O_ 2.5 l. H / 5%+0 my o _-- mhn o ; 2.0 9.2+0. 4d +0 mgp O MbA o ! r.o ?.0+0 3. 5 +0 mg O MhA O s.o 5810 2.940 pgg a MhA O r.s 4.0+0 2.040 g O thbA o 1o.0 3. 0+0 1.6+0 g O t)pA O
- Based on a collection volume of 15 ft' (4.2 x 10' cc) 1.
l O ?.3-9 L~ ._ -
SECTION 8.3 FIELD MONITORING DATA FOSAVEX - 87 PLUME SEGMENT: I RELEASE TIME: From /2IOO' To((,'/4 PROJECTED - IN-FIELD SAMPLING RESULTS Ambient Radiation Levels
- Particulate *I-131 (mR/hr) Activity Activity Concentra- Net Concentra- Net Distance Window Window tion Count Rate tion Count Rate (Miles) Open Closed JpCi/ce) (cpml__ JpCi/cc) (cpm)
EAB 2.4 +y 12. + y I,l/6 2. C+ 6 I,l 6 I. Ith' o.s 1,5+ 4 7.93 6,7-4 /,6+6 (>,7- ? U+ 3 1.o 3.0+3 4,0+3 34-4 3.cH 6 3%-7 34+ 3 ' 1.s 5t>13 2.2+3 25-6' 5.9+5 2.5 -7 2.5+ 3 l 2.o y,l/13 2.2tS' 2.0-6 y,7+ 5 2.0 -7 2.013 \ 2.s 3.t+3 f.9+3 1.1-6 4.0 + 5 1,7 - 7 1,7 + 3 3.o 3.o + 3 _/.5+3 /.4-6 S.3+5 /,V-7 /.y+3
. r.o 2.4 th I,2+3 1. 0 - 6 U +5 U-7 /,0 + 3 s.o I.1 + 3 Si+ 2 T. 5- 7 2.0+5 8,5 -5 76 4 1
(;7.s I,3+3 &Z 5.1 -7 /.4+6 57-R E?+Z io.o /,043 50+t 4. 5-7 /. l+5 4.5-8 4.642-l j i l.
- Based on a collection volume of 1s ft' (4.2 x lo' cc) i6 o
L O r. 3 -/ o i y n I
-SECTION'8.3 FIELD MONITORING DATA
-FOSAVEX - 87 PLUME SEGMENT: [ RELEASE TIME: From I1I/h To /[ [ i PROJECTED -
IN-FIELD SAMPLING RESULTS Ambient Radiation Levels
- Particulate *I-131 i- (mR/hr). Activity Activity Concentra- Net Concentra- Net Distance Window Window tion Count Rate tion Count Rate (Miles) Open Closed _{pCi/cc) (cpm) _{pCi/cc) (cpm)
EAn /,6 + 4 K. I 43 /, /- 5 2 C+6 /./-6 /,/+V o.s 99+3 4.9+3 d.2-6 I,446 j.7 -? 6,7+ 3 ' 1.o. ' 5, E +3 2.93 3.6-6 7.94 46-7 3,D 3 1.s 3.9 +3 l, '] + 3 25-6 5.9+6 2.5-7 2.5O
'" 2**3 " ' 3 ~' "'' *~'
O 2.5- 2, v+ 3 /,2 + 3
/,7-6 '/,046 /,7 -7 2.o+ 3
/,7 t3 3.o 2,0-13 1,0+3 /,4-6 .23+5 IN-7 JN13 c.o 25+3 77+Z_ /.0-4 2.446 /O-7 /,043 s.o ),2+3 6,2+ 2 S&9 2.0+6 T.G-1 E S+1-7.5 $,d
- Z 4,3+2 51-7 l.II+5' S.1 -? E7 +2 10.o d,6v2 3.3+2 4,5-? l. l-t 5 4. 5-% 4,5+Z
- Based on a collection volume of 15 ft' (4.2 x 10' cc)
O ?. 3 - // l
l' SECTION 8.3 FIELD MONITORING DATA FOSAVEX - 87 PLUME SEGMENT: K RELEASE TIME: From /h 3 O To / h k k PROJECTED IN-FIELD SAMPLING RESULTS Ambient Radiation Levels
- Particulate *I-131 (mR/hr) Activity Activity Concentra- Net Concentra- Net Distance Window Window tion Count Rate tion Count Rate (Miles) Open Closed JpCi/cc) (cpm) JpCi/cc) (cpm)
EAB 7,0 +3 4.0 +3 v.C-6 /,14 6 9.o - 7 t 043 0.5 4,3+3 2.443 4,9 -6 /,1+6 4,7 - 7 4,9 + 3 1.o 2.6 + 3 /.3+3 Z 4 -4 4. l +5 2.6-7 2.4 + 3 1.5 J,h 5 9.I + 2 L9-6 4,2+5 I,8-7 /, t+ 3 O a 2.o /,4 + 3 71+ Z ly-4 3,3+5 /,y-7 /, y+ 3 2.5 /2+3 6.0+2 /, Z-6 '2.96 /,2 -7 l.24 3 3.o 9.b2 4.bZ /0-4 Z4*5 /O-7 /,043 c.o '26+Z S.842 24-7 /,9+5 24-9 2f+E s.o 6.0 + 2 3.o+2 6. 2- 9 1,56 (.2-t G,2 + Z 7.5 k,3fh 2. l+ E % 3-7 /,0+5' _4 3-f y,3 + 2 _1o.o 3.2 + 2 l.4+ & 3. 3-7 2 %+Y 3.3-8 3.3+2 i
- Based on a collection volume of 15 ft' (4.2 x lo' cc) l (3
G l T. 3 - / 2 h___________
SECTION 8.3 FIELD MONITORING DATA FOSAVEX - 87
. ,f-w PLUME SEGMENT: h RELEASE TIME: From /h,Y[ To /I!h7 PROJECTED IN-FIELD SAMPLING RESULTS Ambient Radiation Levels
- Particulate *I-131 (mR/hr) Activity Activity
~
Concentra- Net Concentra- Net Distance Window Window tion Count Rate tion Count Rate (Miles) Open Closed JpCi/cc) (cpm) _(pCi/cc) (com) Eis /,/4Y 5m3 //-r _2.6 + 6 / l-6 //+y o.s U+3 3.3+3 d.9- d I,4+6 d.9 - 7 d,7+3 1.o 34+3 /,?+3 3.4-6 4 5+5 3.4 -7 3.4+3 1.s 2.4r3 1. 3 +3 2. 5-6 5,9t6 25-7 2.93 t/,7+6 O 2.o /.9+3 9.7 + 2 t.0- 6 2.0-7 2.0+ 3 2.s l.7+3 f.3 +E /. 7- r, 1016 /? 7 /,7+ 3 3.o 1.4+3 4.7+ E /.y- 6 S. 3+6 ly-7 l,w3 u.o /.0+3 5.2 + t /.o-6 f.y+5 /.o -? /,043 s.o 7,4 +1 4, 'l+ E 75-7 2.0 +6 ts-g 85+ 2, 7.s $1b +$ b $+b $s0-l lY+$ $,0 "$ # 5.0+ b h,kf b 2. 2+1 V 5-7 /. I + 6 45-3 4641 lo.o
)
)
- Based on a collection volume of 15 ft' (4.2 x 105 cc)
O ?. 3 -/ 3 i
SECTION 8.3 FIELD MONITORING DATA FOSAVEX - 87
.f PLUME SEGMENT: M RELEASE TIME: From /3'00 To /3*/Y PROJECTED IN-FIELD SAMPLING RESULTS Ambient Radiation Levels
- Particulate *I-131 (mR/hr) Activity Activity Concentra- Net Concentra- Net Distance. Window Window tion Count Rate tion Count Rate (Miles) Open Closed JpCi/cc) (com) JpCi/cc) (com)
EAs 52+3 2.4 +3 %o-6 l.9+(o 7.o~J R0+3 o.5 3.243 /.4 + 3 4,9-6 l,2+6 4.F7 4. 9 r3 - 1.o /,7+ 3 74+Z 2.4-6 6.l + 6 2.6 - 7 Z4+3 1.5 /,2 + 3 4,l eZ /,7-6 4,2 + 6 /,8-7 /,7+ 3 O 2.e 7.v+ t- 4.1+ z l 9'-4 3.s +5 l.4- 7 /,</+3 2.5 %,0+t yo+E /,2-6 2.F6 l.Z-7 /,2/ 3 2.o d.4+ 2 3.3+2 1,0-6 2. W G l.0 - 7 l.0+3 a.o 50+2 25+t 9,L-7 l.9 +6 26-W 7,4+ t s.o 4.o + 1, 2.04 6.2-1 15+5 6,2 -8 6,2+t 7.5 2. h+ [f I.kth Y.3-7 /.046 Q,3 -f 9,3+f 1o.o 2.f+g I.l+ t 3.3-7 7.9+V 134 3. 3 eg l
- Based on a collection volume of 15 ft' (4.2 x lo' cc)
O E 3 -/9
SECTION 8.3 FIELD MONITORING. DATA FOSAVEX - 87 1 7% - PLUME SEGMENT: M RELEASE TIME: From ' /3 '/( To /31[Y PROJECTED
'IN-FIELD SAMPLING RESULTS Ambient Radiation Levels
- Particulate *I-131 (mR/hr) . Activity Activity Concentra- Net Concentra- Net Distance Window Window tion Count Rate tion Count Rate (Miles) Open Closed JpCi/ce) (cpm) __pCi/cc)
( (cpm) EAB 2.44 S /,243 53-4 /, 3+/, E3-7 &3+3 0.5 /N#3 70 4 3,2-6 764E 3. 2- 7 3.24 3 ~ 1.o 7,4rZ. 3.84 Z !. 7 4 4,045 /,'7 - 7 /,7+3 1.s 5.44 2,'lv2 1,2 -d 2.8+5 j,2-7 /,2t3 9,5+ 2 ' n' 2.o 2.s 4.2 + t
- 3. 6 + t
- 2. I + t I,%4 9.5 -7
- 7. I-7 2.2 +5
- f. V5 9.5-%
g,1 -t 8I+t 2.o 2,% t l.4 + t 6.4-7 f.445 6.6-t 4A+t s.o 2. 2 + L l. I + t S.1- 9 1,2+5 5.I- 8 9;lv2 s.o . /.942, 8.9 + l M I-? 9,7+V 4,/-f ll, / +1 7.5 l,'$+b h.lYh $* h ~ h.bk f.$ ~$ bo $f $ 10.0 k.D/ N.7+f 2.2~7 h.$N 2.2-8 2,2
- 7-
- Based on a collection volume of 1s ft' (4.2 x 10' cc)
T. 3-/8
SECTION 8.3 FIELD MONITORING DATA FOSAVEX - 87
.r -
j PLUME SEGMENT: __ b RELEASE TIME: From /3!3 0 To .[3!h [ l i PROJECTED IN-FIELD SAMPLING RESULTS i Ambient Radiation-Levels
- Particulate *I-131 (mR/hr) Activity Activity j Concentra- Net- Concentra- Net Distance Window Window tion-. Count Rate tion- Count Rate (Miles) Open Closed JpCi/cc) (cpm) ._( pCi/ce) (cpm)
EAs I,943 Rbt 2.?-6 4.65 2,2-1 2, %+3 o.5 /,/+ 3 5,3,2 /,7-6 4,046 /, 7- 7 /,743. 1.0 5,8+t 2. 9+ 2 9, 2- ? 2. 2 +5 9,2 -8 9,2 +l 1.s 4.0+& 2.0 +t d5-7 1,5+6 &*,5-% 6,54 0 2.0 3. 2+Z l. 4 + 2
/,4#&
S',0 - 7 4,3-7 la 2 +5
/,046 50-8 5'O + 2 4,3+t 2.5 2.tet 4.3 -8 3.o 2. 2+2 /, /+ 8 3.5 -7 9 3+y 3.5-t 3.sva u.o /,7+Z 7,3+1 f.?- 7 (,4 +4 2.7-T f,7+ E s.o /,3 +Z 6,7+l 2. 2-7 5.1+ Y 2.24 2.2 4Z >
7.s $,b+f N,b + f l*$*$ b5$Y f,$ ~$ f,64b 1o.o '2trl 3.9/ l. l-7 2,444 /,l- f /,l+2.
- Based on a collection volume of 15 ft' (4.2 x lo' ec) i 8.3-/6 1
SECTION 8.3 FIELD MONITORING DATA FOSAVEX - 87' PLUME SEGMENT: k RELEASE TIME: From j3!k I To /1/59 PROJECTED IN-FIELD SAMPLING RESULTS Ambient Radiation Levels
- Particulate *I-131 (mR/hr) Activity Activity Concentra- Net Concentra- Net Distance Window Window tion Count Rate tion Count Rate
-(Miles) Open Closed _1pCi/cc) (cpm) _ipCi/cc) (cpm) eAB d,0+2. 3. 0 +2 l. 4-6 3.5+f I,4-7 ),4+ 3 a.s 3,6 +2 l, X+t %.5 -7 2. 0 +C T,5-t 7.G+L _
1.o /,9 + E 7.7+I V 4-7 /. / + 5 4,4-7 V,4+ Z 1.5- /,4+ E 6,R+/ 3. 2- 7 '7. 4 + 4 12-? 3.'24 vO f.5-7 5,1+ 4 2,5-7 2.o /, I+ Z- 5. 3 +l 2542. 2.s 9,0 t i 4,5+1 2. I ~ 7 50+4 L/-2 2.l+'2-3.o 7.4 +/ 3.7+L /,7- 7 V,0 +V l. ?-8 /,')
- 2 c.o 5,4 + I 2.fs/ /,3-7 3. l+ 4 /. 3-F /,3
- Z ;
5.o _ 4,64/ 23+l /./-7 2.449 /,l-f /,/ * & ! 7.5 bobff f,hN / ].U ,$4 V~$ YY io.o 2.4+l /,1+/ 5.7-8 /,344 6,'7-9 6,7+/ ) { t i i
- Based on a collection volume of 15 ft* (4.2 x 108 cc) l
- 7. 3 -/7 1
l
7 l SECTION 8.3 . FIELD MONITORING DATA FOSAVEX - 87 l 0%
\
PLUME. SEGMENT: b RELEASE TIME: From /4.'00_ To /4'/4 i PROJECTED . IN-FIELD SAMPLING RESULTS Ambient Radiation Levels
- Particulate *I-131 (mR/hr) Activity Activity Concentra- Net Concentra- Net Distance Window Window tion Count Rate tion Count Rate (Miles) Open Closed JpCi/cc) (cpm) JpCi/cc) (com)
EAs lo+t /,P Z //-4' 2.44 /, /-7 /,/43 o.s I,942- 9,0+I L4-1 I. S'+6 & L/-@ (,4+ t 1.o 9.?+1 4,9 + I 3. V-? 8,0 +4 3.4-8 3.4+ t ; 2.5 4R4l S.4 +1 Z4-7 E?+4 2.y-F f.V v 2-Q 2.o 5,4+/ 2.74/ /,9 - 7 4,6+V /.f-f /,9 + 1 2.5 4,44/ 2.3H /.4-7 3. T44 /,4-g /,4 4 3.o 3.44/ /,f+f /,3-7 3.l+ 4 /,3-f /,366 u.o 2.9+/ l.4 +l /.0-7 2.444 /,0-R /,0+t s.o 2,2+l I,I+ ) 8,I 4 /. 9+ y LI-9 7,l.t I 7.5 / hNf ],1 +0 5,b '$ f.b$ S,h~$ $b4f 10.0 b$+/ h.0+0 Nob ~S f.0 NE Y,b ~f 4,bff
- Based on a collection volume of 15 ft' (u.2 x 10' cc) 9 O 7. 3-/ 8
SECTION 8.3 FIELD MONI'IORING DATA l FOSAVEX - 87
/^% .
PLUME SEGMENT: k RELEASE TIME: From fh,/h 'To fk i f PROJECTED IN-FIELD SAMPLING RESULTS
' Ambient Radiation Levels
- Particulate *I-131 (mR/hr) Activity Activity Concentra- Net Concentra- Net Distance Window Window tion Count Rate. tion Count Rate (Miles) Open Closed Jpci/ce) (cpm) Jpci/ce) (cpm)
EAa 2.0+2 9.9 + l 7.0 -7 In+5 10-8 10 4 o.s /2+2 C.01 I 4,3-? 1.0 +5 4,3- 8 4, 3 + L . 1.o G.4+1 12.+1 2.3-7 5v14' 2. 2 -8 23+2 1.s '/.4 / 2.3+/ /,4- 7 3. 8+ V l.4- 8 /,p t 2.o 3.4 H /. f 4 / /,3 - 7 3, H V l. 3 - f /,3 r Z (J~ 2.s 3.o+ 1 15+1 /,l-9 2.41V l.I- 8 f H 2. a.o 2 4+l I. L+ l 894 2.H V 8,7-9 7,7t l u.o /.7+/ 9.WO 6,7-8 /.449 6,7- 7 f,7+/ s.o 15 4l 7,440 E y-8 /.3+y Ey-9 Ey+l 7.s /.0+I E t+0 3.7-7 7,7 +3 3.7-9 3,7+ / io.o 00+0 4,0+o 29-S 4,74 3 f.7-9 2.?f /
- Based on a collection volume of 15 ft' (4.2 x 10' cc)
?. 3-/ f i
- - ~ - _ _ _ - - _ - - - _ _ _ _ _ - - - - - - _ . _ _ _ . _
SECTION 8.3 , FIELD MONITORING DATA FOSAVEX - 87 PLUME SEGMENT: $ RELEASE TIME: From Il/l30 To fh'YY l PROJECTED IN-FIELD SAMPLING RESULTS Ambient Radiation Levels
- Particulate *I-131 (mR/hr) Activity Activity Concentra- Net Concentra- Net Distance Window Window tion Count Rate tion Count Rate (Miles) Open Closed jpci/cc) (cpm) JpCi/ce) (cpm)
EAB h;h4f 2.b f N.k- 7 5,7f k fM"$ f,kt h o.s 2.t+1 1.4 + I _f5-7 3.5+4 I,5-$ 15+L. 1.o I. 5+ l 7.4 + 0 7,? - 8 /, 849' 7?-? 7.74/ 1.5 l. 0 + l 5 2+0 S. 3 -? /.31V 5,3-1 5;3 + I 1,7+3 4, I1I Q 2.o 7.0+ 0 4.0 +0 4. l-$ 4.l- 1 2.3 Q40 3.V40 354 8. 3+3 3.5-9 3.5+ I 3.o 54+0 2.7+0 2. 8-8 L6+3 2.8-9 2.S+l r.o 4.2t0 2.Ir0 2.1- 8 5D+3 2.I- 9 2. l+ l s.o 3. t + 0 i.t:10 f.?- ? 4.0 +3 I,7-9 I,9tI 7.5 babf 0 fo l40 Y. f ~ $ 2 b*b lo f
- 0 tl5 f lo.o /,7+0 7.5-/ F,4-9 2.043 %.6-/0 9.0+0 '
- Based on a collection volume of is ft' (4.2 x lo' cc)
O 8'.3-20
SECTION 8.3 FIELD MONITORING DATA PLUME SEGMENT: I R LEA E TIME: From fk'Th To /hi$( L PROJECTED IN-FIELD SAMPLING RESULTS Ambient a
' Radiation Levels
- Particulate *I-131 (mR/hr) Activity Activity Concentra- Net Concentra- Net Distance Window Window tion Count Rate tion. . Count Rate (Miles) Open Closed _(pCi/cc) (cpm) _(pCi/cc) (cpm)
EAa 3,2+ / /,4+/ /4-7 3.84 V /,4-9 /,642. o.5 /,1+ l 9.6 + 0 7,7-8 2,3 + Y 3,8-9 7.7 + / 1.o /. 0+ l 50+0 9, l ' /, Zf y 5./-9 5/+ / 1.5 70+o 35+o 3.54 7.3 +3 35-9 35+I 2,9- R d,4 + 3 Q 2.o 54+0 y,6+0
- 2. h o 2,3+0 SN13 2.7-9 2.9+ I 2.s 2. 3-% 2.3 - 9 2. 3 + I 3.o 240 /,9+ 0 /,1- T 45+3 /,7-9 l.9tI a.o 2.8+0 l.440 /, t/-? 9.3+3 /,4-9 /N+ l s.o 2.2#0 1. l+0 l. /- 8 2,4 + 3 /,l- 9 /,l+I 7.5 l840 AN~I .b~ _le ((4 b $b-/0 $0f0 10.0 1,1+ 0 56-l 5,%'l I,443 5,8-10 6,0 + 0 i
i
- Based on a collection volume of 15 ft' (4.2 x lo' cc)
O e. 3 2./
l SECTION 8.3 FIELD MONITORING DATA FOSAVEX - 87 f~ PLUME SEGMENT: [1 RELEASE TIME: From /6.'00 To _/6!/// PROJ6CTED IN-FIELD SAMPLING RESULTS Ambient Radiation Levels
- Particulate *I-131 (mR/hr) Activity Activity Concentra- Net Concentra- Net Distance Window Window tion Count Rate tion Count Rate (Miles) Open Closed JpCi/cc) (cpm) JpCi/ce) (cpm)
EAB /,[+[ 7.3 th ff. 4-9 2.0 + 9' 7,y-9 3,y # / o.s 9,640 4.7+0 5', I - 9 l.214 T I-9 5 l+ / - . 1.o 50+0 2540 2.7-8 0+3 f.7-9 2,7+ / 1.5 3.440 l."/+ 0 /.9-4 96+ 3 /. ?- 1 /, ? + / O 2.o z.6+o l.s+o l. 4 - 8 3 +3 l.4-9 l.v+ / 2.5 2,2 r0 /,l40 /,2-7 2.b3 /,2 - 9 /,2+l a.o I,74 0 9, \ -I 1,7-9 2.3 + 3 9,9 -10 I,0+l a.o I,4 +0 6.8-l 73-9 f ?+ 3 1,3-/0 10+0 s.o I, I40 5,5-I 5.1 - 9 I,445 G,9-/0 d,0+0
,.s '7y-l 33-1 4. 0 - 9 9,4+ ?- MM O to.o E4-/ 2.bl 3.0-9 ?l47- mM o
- Based on a collection volume of 15 ft' (4.2 x lo" cc)
,r V) F 3 .
___________________________________U
SECTION 8.3 FIELD MONITORING DATA FOSAVEX - 87 l '!" . PLUME SEGMENT: Y RELEASE TIME: From [6.'/h To _/h/[i PROJECTED - IN-FIELD SAMPLING RESULTS Ambient Radiation Levels
- Particulate *I-131 (mR/hr) Activity Activity Conce ta- Net Concentra- Net Distance Window Window tion Count Rate tion Count Rate (Miles) Open Closed JpCi/cc) (com) JpCi/cc) (cpm)
EAB /,0Il 6,Z+0 T.4-? 2.04 f y-9 9#+l o.s d.2 + 0 1H0 $ I-1 L 2 4 Y. 5 l-9 5, l+ l . 1.o 3.l+D l.b i o 2.7-8 6,y+ 3 2.7-T 2. 7+l 1.3 Z2+0 /,l40 /.7-7 /M+3 1.1-9 /, 9 + l
/,7+0 70-/ 3,343 /,W/
Q 2.o
/,5+ 0 7,3 -/
/. V-8
/,2- 7
/M-9 1,1-9 l,2+ /
2.5 2.7+ 3 3.o _ /,2 + 0 M -l 7,7- 7 f.3+3 1.7-/ 0 /.dt / u.o 9.0 - I 4,5-l ?,3- 9 /.7+ 3 23-/O 7040 s.o 'l2-l 3.fo-l %9-1 /.4+3 5,9-10 (.0 + 0 7.5 Lf,$ ~f fu N"I N0" Nib Whk 0 1o.o 3.&- I l. 2-1 3.0-9 9. l+ 7/ MM o
- Based on a collection volume of 15 ft' (4.2 x 10' cc)
I O r.3-23
SECTION 8.3 FIELD MONITORING DATA FOSAVEX - 87 O PLUME SEGMENT: k4l __ RELEASE TIME: From 16!30 To /h/kk PROJECTED IN-FIELD SAMPLING RESULTS
, Ambient ,
Radiation i Levels
- Particulate *I-131 (mR/hr) Activity Activity Concentra- Net Concentra- Net Distance Window Window tion Count Rate tion Count Rate l (Miles) Open Closed JpCi/cc) (cpm) JpCi/cc) (com)
EAs 5.W0 2.'l+0 d. 3 - V J,5W 6,3- 9 6,S +1 l o.s .12+0 l.6 + 0 3,8- E 9.0 +3 3.8 -9 3.h I 1.o I,71 0 95-1 2. 0 -8 4.7t3 2.0- 9 2.0 + l 1.s /,240 5,g-l /, V- ? 3,3+ 3 /V-9 l,W / Q 2.o 1. 0-1 4.5-l I,I-f? 2.6+3 Il- 9 I,I + 1 1.s 9.d-l St-l 9. l- 9 2.H3 9,l-lO 9.0f 0 3.o 6,0-1 10-l 7. 2-9 /.7#3 72-/0 20#0 a.o 4,4-1 2. 5-1 SM-9 f. 3 +3 53-10 S.0 + 0 s.o 3. 4-1 l. t-l 4. 3-9 A0+3 MM O 7.5 $.N # l l.b'I $o$-0 ho ?4 RIDA O 1o.o I.9-I 9.G-2 2. 2 - 9 524 mM o
- Based on a collection volume of 15 ft' (4.2 x lo' cc)
O T. 3- 2 V
SECTION 8.3 FIELD MONITORING DATA L FOSAVEX - 87
.y~ ,
PLUME SEGMENT: 'Y RELEASE TIME: From /6.' b To /h!N PROJECTED - IN-FIELD SAMPLING RESULTS
')
. Ambient -
Radiation Levels
- Particulate *I-131 (mR/hr) -Activity Activity'-
Concentra- Net Concentra- Net Distance Window Window tion Count Rate tion Count Rate (Miles) Open closed Jpci/cc) (com) Jpci/ce) (cpm) EAn 3.6+0 1.?40 'l. & - 7 1,1+ V 4.g-q L1,6 f( o.5 2.2 + 0 1,l+ 0 2.9- t d.d+ 3 _2. 8-9 2.94 ( . 1.o I,I + 0 5.7-1 I,5-T 3,5+ 3 1.5-9 1,6+l . 1.5 7.t-/ 3.9-l /,0-8 2.4 +3 /. o 'l /,04I JQ 2.o 4.0-1 3.0-) 77~9 /A+3 27-10 ?. 0 + 0 2.5 5,o-1 25-) 6. 5- 9 f.543 6',5-jo 20+0 3.o 4,0-1 f,0-/ 5,3-9 /,3+3 F,3-/0 6,0fo a.o 3.0-1 1. G-l 4.0-9 9,44 mM o s.o 2. 4-( l 2-1 3,2 -9 9.d42 MM 0 7.5 I,7-f I,k-b 2. I' Y 6,2Y b $M O 1o.o I.3-1 CN-L I,6 - 9 3,8+2 MI)L o
- Based on a collection volume of 15 ft' (4.2 x 10 cc) 8 O ?. 3- 2 5~
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c _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ . - ___ _ _____-_ _-_ - _ ____ 9.0-1 SECTION
9.0 REFERENCES
Section Page 9.1 Procedure Index 9,1-1 9.2 Key Documents 9.2-1 O O
9.1-1 SECTION 9.1 PROCEDURE INDEX Tabies 9-1 and 9-2 identify the FSV RERP Implementing Procedures and Supporting Procedures respectively. Controllers / Observers should become familiar with those procedures which directly affect the portion of the emergency organization they are responsible for evaluating. O O
lI 9,1-2 TABLE 9-1 RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURES NO. SUBJECT
-RERP-CLASS. Classification RERP-DOSE Offsite Dose Calculations Methodology RERP-ECP Executive Command Post Procedure RERP-EXP Emergency Exposure Guidelines RERP-FCP Forward Command Post Procedure RERP-FIELD Field Monitoring Procedure RERP-NOTIFICATION Notification RERP-ORG FSV Emergency Organization and Responsibilities RERP-PAR Protective Action Guideline Recommendations
(~ ' RERP-PCC Personnel Control Center Procedure RERP-SE0C State Emergency Operations Center Procedure RERP-SURVEY Inplant/Onsite Radiological Monitoring RERP-THYROID Thyroid Blocking Agent Administration RERP-TSC Technical Support Center Procedure RERP-VC Visitors Center Procedure RERP-MET Meteorological Data Acquisition RERP-CED Corporate Emergency Director RERP-NOUE Notification of Unusual Event Procedure RERP-ALERT Alert Procedure RERP-SAE Site Area Emergency Procedure RERP-GE General Emergency Procedure O
l [ i 9.1-3 O TABLE 9 FSV SUPPORTING P'10CEDURES Implements / Procedure Designation Supplements RERP and Title Section No. FSV Administrative Procedures G-2 FSV Procedure Systems 8 G-3 Action Request - Preparation and Processing 8 G-4 Security, Visitor, and Reactor Building Access Control 6 , h l G-5 Personnel Emergency Response 5,6 G-7 FSV Project Personnel Training
.and Qualification' Programs 5,8 G-9 Controlled Work Procedures 4,7,9 i G-10 Data Management 8 P-1 Plant Operations 5,6,8,9 P-3 Radioactive / Contaminated Waste /
Area Control 6,9 P-7 Work Control - SSR Processing 9 P-8 Fire Fighting and Prevention 5,6 P-10 Safe Work Practices 6 Q-1 FSV Organization and Responsibilities 5 Q-2 Quality Assurance Program 8 Q-3 Design Control System 9 i Q-16 Corrective Action System 8 Q-18 QA Monitoring and Audit Program 8 a
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Procedure Designation- Supplements RERP < and Title Section No. _l l l Health Physics Procedures !
- HPP-1 Intervals of Surveys and s .
Use of Survey Maps 6 HPP-2 Bioassay Program 6 l HPP-8 Radiation Surveys 6,9 '- s; HPP-9. ' Establishing and Posting : ! Controlled Areas L,9."( HPP-10 Area and Equipment Decontamination 6,9 } HPP-11 Personnel Decontamination 6 HPP-12 Portable Air Sample Collection and Analysis 4,6 l HPP-13 Continuous Air Monitors 4 HPP-14 Analytical Instrumentation Room 4,6 HPP-16 Selection and Use of Respiratory l Protection' Equipment 6,7 ' HPP-17 Determining Radioactive Liquid Release Rates 4,6 HPP-18 Radioactive Gas Waste Release Rate Calculations 4,6 : HPP-20 Calibration of Radiation Detection Instruments 7,8 HPP-21 Surface Radioactive Contamination Surveys 6,9 HPP-26 Radioactive Material Control and Handling. 6,9 O
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Procsdure Designation Supplements RERP and' Title' Section No.
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HPP-27 . Personnel Dosimetry 6,9 HPP-30 Shipment of. Radioactive Materials 6,9
, HPP-33 Fast Gas and Iodine Sampling :4,6 HPP-37 RERP Inventory List 6,7 HPP-44 radioactive Material Spill 4 HPP-45. _#
Air Activity Analysis Using the RM 14/15 with HP210 Probe 6 HPP-48 Routine Maintenance, Inspection, and Cleaning of Respiratory Equipment 7,8 HPP-50 Breathing Air System Sampling Procedure 6 (L HPP-51 Changing Particulate Filters and Iodine Collection Cartridges in RT Monitors and Continuous Air Monitors 6 HPP-53 RT 7325 and RT 73437 Emergency Filter and Cartridge Removal 6 x HPP-56 Reactor Building Exhaust Stack Discharge Activity Calculation 6 HPP-63 Quantitative Respirator Fit Testing 6,7,8 HPP-64 Operating the Harshaw TASC-12-A6 Automatic Alpha / Beta Counting System 6 , HPP-66 Operation of Portable Survey Instrumentation 6,7 1. l HPP-67 Calibration and Operation Procedure i for the Eber11ne SAM-2 Stabilized Assay Meter 6,7 HPP-69 Operation and Performance Verification of the NMC PCC-11TC 6 I
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Procedure' Designation Supplements RERP and Title Section No. Radiochemistry Procedures RCP-9' Sample Preparation For Gamma Spectral 1 Analysis 6,9 RCP-24 Analysis of Vent Particulate and Iodine Monitor Filter for Surveillance Requirement (ESR 8.1.lef-W) 6 i RCP-36 Radioactivity Calculations 6 1 RCP-38 Operation and Calibration of Computer
' Based-Beta Gamma Analysis System 6,9 RCP-40 Operation and Calibration of the Whole Body Counting-System 6,9 l .
Procedure Manuals and plant i Training Programs Administrative Manual Situation Response Training, Sections 4.0 - 4.6 8 Fire Suppression and Prevention Manual Sections 1, 2, 8 5,6,7,8 Emergency Procedures Manual (EPs) All Sections 4,5,6 l Station RERP Implementing Procedures All Procedures All Medical Emergency Plan 5,6,7 Safe Shutdown and Cooling with Highly Degraded Plant Conditions and Abnormal Procedures for Shutdown Cooling 4,6
-l' Security Administrative Procedures 4,6 Station Manager's Administrative Procedures 7 x,
.9.1-7
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Procedure Designation Supplements.RERP ano' Title Section No. Technical / Administrative Services' Manager's
-Administrative Procedures 4,6,8 Public Service Company RERP Public Information Plan 5,7,8,9 l
State of Colorado Fort St. Vrain Radiological Emergency Response Plan (State RERP)- 5,6,7,8 Weld County Radiological Emergency
. Response Plan 5,6,7,8 ;
Security Instruction 6.10
.(Personnel Accountability for !
Station Emergencies) 5' 6 Operations Order Book All L l l l I i l i%
9.2-1 ,c~. (_J" SECTION 9.2 KEY DOCUMENTS Provided below is a list of those documents which govern the FSV Emergency Preparedness Program.
- 1. Fort St. Vrain Radiological Emergency Response Plan.
- 2. Fort St. Vrain System Operating Procedures.
- 3. Fort St. Vrain Emergency Procedures.
- 4. Fort St. Vrain Technical Specifications.
- 5. Fort St. Vrain Updated Final Safety Analysis Report.
- 6. Title 10, Code of Federal Regulations Part 50.47 and Appendix E.
7 NUREG - 0654/ FEMA - REP - 1, Revision 1.
-~s 8. NUREG - 0696.
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