ML20237B767
| ML20237B767 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/19/1998 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20237B765 | List: |
| References | |
| NUDOCS 9808190241 | |
| Download: ML20237B767 (200) | |
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1 l l 1 l EXERCISE RULES l l 1 4 i I
EXERCISE RULES To define the " extent of play" of the participants and to meet the objectives, the following guidelines have been established:
- 1. The scenario will be conducted without suspension until terminated. Since participants will not be informed of the scenario start time or initiating events, all personnel should follow their normal routines until notified.
- 2. The scenario will commence with postulated conditions requiring the declaration of appropriate emergency classes.
- 3. Four groups of personnel will be in attendance and will function as described below:
A. PARTICIPANTS nre personnel who have been assigned an " acting" role during the scenario. These people serve to take necessary actions to mitigate, terminate, correct, and recover from the simulated emergency. B. CONTROLLERS are personnel who serve an active role in the scenario by providing data to participants. CONTROLLERS may also serve to prompt or initiate certain actions in order to assure continuity of the events described in the scenario. Such prompts can be issued only on the authority of the Lead Controller and solely for the purpose of preserving the scenario timeline and objectives. CONTROLLERS are the only personnel who will provide information to the PARTICIPANTS; other information from personnel not designated as CONTROLLERS or PARTICIPANTS will be disregarded by the participants. CONTROLLERS may also serve as EVALUATORS. C. EVALUATORS are personnel predesignated by ANO and the NRC to provide documentation and assessment of the Emergency Response Organization. They serve a passive function and will only note actions taken by PARTICIPANTS. These personnel have received specific instructions on what areas to cons'ider in their evaluation. EVALUATORS may ask questions of participants to clarify actions taken or procedural concerns but should .ngt interfere with the flow of events. l D. OBSERVERS are personnel who serve no evaluation, control, or participatory function in the scenario. They are allowed to observe in order j to gather information for various purposes. OBSERVERS shall not interfere I with EVALUATORS or PARTICIPANTS. Questions from OBSERVERS should be directed to a CONTROLLER. Identification of personnel: A. Evaluators - Evaluator Badges l
' B. Controllers - Controller Badges C. Observsrs -Observer Badges 1
EXERCISE RULES
- 4. Personnel will be assigned as Controllers at key functional areas to monitor and control the scenario. They will also accompany repair / damage control and survey teams as they re-enter the plant.
- 5. Message forms and the Plant Simulator will be the mechanisms used to initiate, modify and complete the events comprising the overall scenario. Controllers will use the message forms to place the scenario events in effect and to trigger responses from the involved personnel.
- 6. Some participants may insist that certain parts of the scenario are unrealistic.
The Controllers have the authority, with approval from the Lead Controller, to clarify any questions regarding scenario content. In some cases, it may be necessary to use " controller's prerogative" and countermand participant actions to preserve the continuity and objectives of the scenario. Inappropriate actions can delay or speed up the entire scenario and impact the objectives of other groups,
- 7. Note that scenario events are hypothetical. Any portions of the scenario depicting plant system operations transients are simulated events. NQ Control Room actions, or reactions involving operation of plant systems, or affecting generation capability shall be initiated. All scenario messages shall contain the phrase:
"THIS IS A DRILL".
- 8. Postulated accident conditions may result in a simulated radiological release which results in the consideration of protective actions for the general public, and will provide the mechanism for offsite authorities to implement their respective emergency response plans.
- 9. All onsite and offsite emergency response facilities may be manned to perform their prescribed functions as appropriate to the development of the scenario.
- 10. The offsite Early Waming System may be activated by the State.
- 11. Key Participant Guidelines A. Participation by ANO personnel directly involved in responding to an emergency shall be carried out to the fullest extent possible.
All actions are to be performed in accordance with the Emergency Plan and L Procedures as if it were a real emergency. Actions of participants should be identified to the Controller and Evaluator if not evident. B. Participants should respond to questions from Controllers or Evaluators. 2 i
EXERCISE RULES C. Plant / Monitoring Data: Participants should request from the Controllers any data which they feel is necessary for the performance of their function. Data will be provided to any emergency teams by a Controller after the participants have performed the actions necessary to obtain that data. Plant Simulator, SPDS, and RDACS data will most likely be automatic; however, if system failures occur, each Controller will have the time-related plant and radiological parameters of the scenario. This information will be provided to the appropriate participants. D. Participants must act as if radiation levels actually are present, in l accordance with the information provided by a Controller.
- E. If entering normal station radiation areas, observe all rules and procedures.
l No one (including Controllers, Evaluators, and Observers) is exempt from l normal station radiological practices and procedures. NOTE: DO NOT ENTER HIGH RADIATION AREAS IN THE PLANT. FOLLOW ALARA PRINCIPLES. F. If in doubt, ask a Controller for clarification. The Controller will not prompt or coach participants. They will not provide information to participants regarding scenario development or _ resolution of problem aress encountered. Participants are expected to obtain information thrauch their own organizations and exercise their own itwhment in determining l response actions and resolvina problems.
- 12. Simulated Events: Certain events / activities will be simulated rather than utilize the actual employment of resources. Any ouestions as to the simulation of actions should be directed to a Controller for aooroval.
Example: The use of fire extinguishing agents would not be performed but simulated. Teams would respond but only perform a " walk-thru" of fire fighting actions. NOTE: if an equipment failure or malfunction unrelated to the scenario is I encountered, participants are expected to report these problems and initiate actions to correct the failure / malfunction. This will better enable us to demonstrate our capability in handling these problems in an actual emergency.
- 13. Provisions for Actual Emeroency- Participants, controllers, evaluators, and f- visitors should not take any actions which would preclude maintaining emergency l readiness of the organization and community. If an actual emergency occurs requiring a group to terminate its participation in the scenario, they should notify the Lead Controller. All messages concerning actual emergency events should be proceded with "THIS IS NOT. REPEAT, NOT A DRILL".
- s. 3
EXERCISE RULES
- 14. Communications: Communications between participants shall occur in accordance with all applicable emergency response procedures. All communications, including initial telephone conversations, radio transmissions, public address announcements, etc., should begin with "This is a drill" or contain the phrase in the message.
- 15. Compliance With All Laws: Intentional violation of any laws is not permitted.
Participants, controllers, evaluators, and observers must comply with all Federal, State and locallaws.
- 16. A_ void Property Endangerment: Participants, controllers, evaluators, and observers must avoid endangering property (public or private), members of the general public or the environment.
- 17. Minimize Public Inconvenience: it is not the intent to arouse or inconvenience the public. All communications should be prefaced with 'This is a drill".
- 18. Termination of Scenario e The Lead Controller will notify and release all controllers and participants whenever the scenario is terminated.
. The Lead Controller will notify all offsite points of contact to advise that the scenario is being terminated.
NOTE: All simulated events will be initiated under the direction of the Lead Controller, individuals are prohibited from creating real or simulated situations that have not been provided for in the scenario and approved by the Lead Controller. l i e
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EXERCISE ~ RULES INSTRUCTIONS FOR VISITORS
- 1. Scenario events and timing sre confidential. Do not discuss them with I participants.
- 2. Do not interfere with the actions taken by the participants, controllers, and evaluators.
- 3. Visitors must stay with their assigned escort and follow their escort's instructions.
4 Visitors must display their ANO visitor badge and other assigned maar:c of identification, j 5. Within emergency response facilities, visitors must position themselves such that access to status boards, charts, equipment, etc. is not hindered. If congestion becomes a problem, visitors may be asked to leave temporarily by a controller.
- 6. Visitors should direct questions to their escort or a controller. Direct questions to
! players only after scenario termination. ! 7. Visitor safety responsibilities:
- Safety takes precedence over all other requirements.
1 e in cases of accidents or injury, report promptly to your escort or a controller, and assist as required. ! Report any hazardous condition to your escort or a controller.
. Cooperate in every respect with the plant safety program so that operations may be conducted in a way that ensures safety.
i e Follow all safety rules, take no unnecessary chances, use all safeguards and ( safety equipment provided, and make safety a part of your responsibility.
. in the case of fire or en actual emergency, follow the instructions of your escort or a controller.
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1 f I t l l l CONTROLLER INSTRUCTIONS AND - EVALUATION CHECKLISTS L
INSTRUCTIONS FOR CONTROf I FRS/ EVALUATORS
- 1. Personnel are assigned as controllers and/or evaluators at au key functional areas to monitor and control the scenario. They will accompany repair / damage control and survey teams as they re-tsnter the plant.
- 2. The controllers wiu be coordinated by a Lead Facility Contmiler iri each ERO facility. The Exercise Lead Controlier will be responsible for the overaH conduct of the scenario.
- 3. Message forms and simulated data will be issued to initiate, modify and complete the events compnsing the overall scenario. Seleded controllers will use message forms to start scenario events and trigger responses from the involved emergency response organizations. Each controller will have copies of the messages controlhng the portion of the scenario for which he/she is responsible.
- 4. Conaolhng messages will be prose.1ted to the designated participant at the time specified in the event schedule. The controller should follow up with an explanation of the message and answer questions to ensure that the partopant understands the message.
Two idnds of messages will be used: Messaaes Messages used as a primary means of implementing scenario events by hypothesizing conditions. These wGl be supported by simulated data where necessary.
- Contingency Messaaes Messages used at the decretion of the Lead Controller in order f.o mainteen the scenano schedule or conhnuity of simulated events. These are not to be issued unlest, absolutely necessary.
- 5. ControNors shaN Dg provide informahon to the partidpants regardsng scenario development or resolution of problem areas enmuntered. The participants are expected to obtain informa: ion through their own organization and use their own judgement in determining responses and problem resolution. If the scenario time Nne will be wwvw'::1 or scenano events wig be invahdated as a result of either inconed or incomplete participant responses or a participant lack of krc M-p of how to proceed, the controller wiu prompt the participant with necessary instructions and wlN note the failure on his/her critique sheets
- 6. Note that scenano events are hypothetical. Any portions of the scenario depichng plant system opershonal transients are simulated events No control room adeons or reactions involvino operation of Diant systems or affectino Generatino capability will be initssted if you are not clear as l'J what actions should be taken by the partopants or why, make sure you ask the Lead Controller. Controllers stahoned at areas vital to maintainmg generating capahiisy should be especially aware and take extra precautions in issuing messages or giving instructions regarding the scenario events.
- 7. Participants are not allowed to introduce items into the scenario Some participants may insist that certain parts of the scenario are unrealistic. The controllers have the authority, with approval from the Lead ControNer, to darify any questions regarding scenario content. In some cases, it may be necessary to exercise "controner's prerogative" to preserve the conhnuity and objechvos of the scenario.
- 8. Controllers will only guide the schons of the partidpents when it is otwoous that unchecked actions wiu I
have a significant imped on the aw-aful complebon of the scenario. Covmot.Last PaoMPts sHoULD aE MEPT TO A MosMuM APm AVOWED F AT ALL PossWLE. ) 1 1
9, Controllers rnd evaluators do not have to follow the radiation exposure control prachoes for the simulated radiation levels frorn the scenario. However, the participants myg follow the raoistion protechon rules. CoNmoLIBIs, EVaLMaTons. AfD PARTEMMrTE sNTWWE Actual afATIoN mm nnras s Y CoNmollaD ansas must assenvu au. Nonnai. namanow coNmoi. pnaences.
- 10. ControNor/ Evaluator asfoty responsiteties:
safety takes precedence over aN other requirements. In case of accident or injury, report promptly to the Lead ControNor and get medical assistance wthout delay. Report any hazardous condition to the Lead Controller.
=
Follow safety rules, take no unnecessary chances, use all safeguards and safety equipment provided, and rnake safety a part of your responsibility. Be sure to have a hard hat and safety glasses with you when entering the plant Know your exed duties in case of fire or an adual emergency; suspend scenario-related achvities.
- 11. wControllers h,ough must not Coni ihe toad issueouer.
",surpnse" messages ws is essent. or -daad fo,ihe of the "surpnse" adions at the participants. The{
- 12. Controllers and Evaluators wul commence their assignments at assembly locahons for the parbeipants they are to observe, or as diremed by the lead controller. Prior to scenario commencement, au communications should be tasted to ensure satistadory communications between the lead controllers and an othercontreuers.
- 13. AH controllers wul syndventze their weldies to ensure that messages are delivered at the proper time.
Times on messages are set relative to the beginning of the scenario.
- 14. The Lead ControllerwlN determine the approprials time for scenario termination and ensure au controllers and participants are advised.
- 15. Upon complebon of the scenario, evaluators should begin preparation of their critiques.
N9MRI De'n
- 1. Know the overall controner/evalustor organization and how to contad the Lead Controller.
- 2. Be sure you understand the scenarlo.
- 3. Be at your post at least 20 minutes before the start of participant action. Pesition yourself to maximize l your effectiveness in issuing messages and observing the participants.
- 4. Identify the phone (or radio for field teams) you wlN use to maintain communications with lead controller.
- 5. Identify yourself at aN times to aN participants. Wear identification provided.
- 6. Identify the participants (by name and function) that you wlN be controlling or evaluating
- 7. Remember that there may be two times: a scenario time and real time.
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- 8. Keep the play on schedule by checking your detailed scenario.
- 9. Stay on the time line when providing information. Contact the Lead Controller if significant delays are encountered, so that scenario event timing can be adjusted accordingly.
- 10. Issue messages on time or as direded by the Lead Controller. Make sure the participants understand it.
- 11. Allow the participants reasonable flexibility to perform their functions and demonstrate their skill, $
knowledge, and initiative. Except during graded Exa.uses, Controllers should perfonn on the spot conechons whenever it becomes apparent that a participant is making a mistake, i
- 12. If you must intervene with participant adions and the participant disagrees with your instrudions contad l the Lead Controller to resolve the mnflict. '
- 13. Respond to participant's questions but do not prompt participants to take a specific action.
- 14. If a real emergency occurs in your area of play, suspend your portion of the scenario and notify the lead controllerimmediately.
L E9!d1
- 1. Dont leave your post at key times.
- 2. Dont prompt the participants to take action.
l ! 3. Dont coach the partopents.
- 4. Dont criticize parhcipant edions durin0 the scenario.
- 5. Dont forget to call the Lead Controller to seek ad Ace or help if needed
- 6. Do not allow federal evaluators to issue messages 6nstruchons to' participants if tiley want to initiate actions, receive authorization from the Lead Controller before complying with their wishes Participants should, however, answerqueshons directed to them by evaluators.
- 7. Do not allow portapant adsons to continue if they would obvioudy impair scenario continuity.
CRITIQUE PROCESS The NRC considers evalushon of participant performance as a critical factor Iri their overall assessment of the ANO EP program. They examine critique results for objectivity, candor, and most importantly, the ability of the evalushon process to dated and acknowled0e weaknesses. The overall objodive of the cribque process is to provide an analysis of participant performance and idenOfy strengths and areasI'orconedion
- 1. Partecioents immediately following the scenario, critiques will be conduded in each Cmergency Response Facility. The purpose of these critiques will be to solicit input from the participants ice considershon in the overall evaluation 3
- 11. Evaluators The Evaluator Droup will consist of 1015 people (depending upon the requirements of the scenario) assigned to observe and evaluate approximately 12 different functional areas or Emergency Response Facility operations. These areas are indicated on the accompanying organization chart with the number of evaluators for each area in parenthesis Personnel will be assigned to this group based on their expertise in these specific areas. Personnel assigned to this group will typically be those with past experience as evaluators, participants in scenario development, and members of the Emergency Response Organizauon.
4 At the conclusion of the scenario, evaluators will submit their critique results to their group Lead Evaluators. lll Group Lead Evalustors A typical ERO critique organization contains five Group Lead Evaluators. Often they will be qualified ERO members who are not f=iticif=tiis in the scenario. They will be assigned to their group based upon its association with the ERO position to which they are assigned. Each Group Lead Evaluator will have several Evaluators reporting to them. Group Lead Evalustors will obtain initial critique results from the Evaluators in their group as soon as possible following the scenario. They will then meet with a Lead Evaluator to present and discuss each finding. The purpose of the evaluation will be to observe performance, determine the most significant weaknesses and/or deficiencies, and present them for conedion. The Lead Evalustors should examine eaab finding and pnoritize them as they relate to or demonstrate a failure to sabsfy the followmg
- NRC regulations (most significant)
- NRC guidana
- ANO procedures
+ Scenario objectives
. Suggested program improvements (least significant) in this manner, each finding will have a well defined basis as justific:ation for the final exercise assessment, IV. Evaluation Forms Evaluation Summary Sheets are provided to Lead Evaluators. A summary sheet should be completed for i
each critique finding prior to the Group Lead Evaluator meeting with the Lead Evaluator. ! Evaluation Checidists are provided to all evalustors. Their purpose is to assess performance of certain l key activibes and to document findings regarding the success or failure to accomplish the objedives. These forms are to be submitted to Emergency Planning as soon as possible following the critiques Evaluators are encouraged to mantain chronological logs during the scenario. l 4
VI. Summary Following the scenario Evaluators will most with their designated Group Lead Evaluators and present their findings. The pmduct of these initial group critiques will be a list of findings and supporting information. A finding should focus on identification of a problem rather then a rnere report of an observed consequence. For example, a finding that states Hoefkations were not made in e timely marvW is less useful and more dScult to corred without accompanying information describt:vj the etM cause. Group Lead Evaluators will compile the results of the initial critique and then meet with the Lead Evaluator. The Lead Evaluators will then prioritize the findings 1 1
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1 CRITIQUE ORGANIZATION , 1 See Management Emergency Plannry Staff - 1 I I I I Group 1 Group 2 Group 3 Grow 4 Group 5 i Lead 3veluetor Lead Evoluetor Lead Evalustor Lead Evalustor Lead Evaluator l EOF Director REAM Shift Supt. OSC Director TEC Director ) Grog i Group 2 Group 3 Group 4 Group 5 Evalustors Evalustors Evaluutors Evalustors Evmiustors !
- ECF (2) - Dose Assessmert (1) - Control Room (2) - OSC (1) - TSC (2)
- Public/ Media - Offsite Monnonry (2) - Onste Mon. (3)
Info (1) - Medical Emer. (2)
- Media Carter (1) - Repairl Damego Cortrol(4)
- PASS (1) i 6
ARKANSAS NUCLEAR ONE Evaluation Checklist Control Room Date: Evaluator: Attached are the objectives applicable to this facility or area of evaluation. Each objective is to be evaluated using the items listed for that objective. An objective may apply to more than one area. Your evaluation needs only to address your assigned group's or response center's role in meeting the objective. Use this checidist and any additional notes that you may have taken to evaluate the ERO's performance in meeting each objective. Evaluation items are to be judged SAT, UNSAT, or N/A. SAT indicates that performance was adequate in meeting the objective. UNSAT indicates that the item was not met. N/A indicates that the item either was not observed or did not appY to your facility or group. Complete these forms and give them to the Lead Evaluator or Emergency Planning representative for your facility or group at the completion of the critique session. Page 1 of 5
- 1. Demonstrate the use of the Emergency Action Level procedure for SAT UNSAT N/A Emergency Class declarations.
1.1 Use of 1903.010 to determine Emergency Class O O O 1.2 Clear announcement of the declaration made O O O 1.3 Continued review of 1903.010 after an emergency declaration O O O Comments: 6
- 2. Demonstrate proper selection of Protective Action SAT UNSAT N/A Recommendations (PARS) and timely delivery of PARS to ADH.
2.1 Cormct PAR selected based on scenario events O O O 2.2 Delivery of PAR to ADH was timely 0 0 0 Comments:
- 3. Demonstrate the transfer of Emergency Direction and Control SAT UNSAT N/A (ED&C) responsibilities, from the IR8 to the ERO.
3.1 Complete tumover was given to the TSC Director or EOF Director O O O Comments: l Page 2 of 5
- 4. Utilize the Safety Parameter Display System (SPDS) to monitor SAT UNSAT N/A selected plant parameters.
4.1 SPOS was used effectively O O O Comments:
- 6. Demonstrate notification and deployment of the initial Response SAT UNSAT N/A 8taff (IRS) and Emergency Response Organization (ERO).
. 6.1 Staffing needs conectly identified using 1903.011 O O O 6.2 Communicator use of 1903.011 forms O O O l l- 6.3 Communicator notified IRS as directed by the SS O O O Comments:
- 7. Demonstrate notification of the Arkansas Department of Health SAT UNSAT N/A (ADH) within 15 minutes of the declaration of an Emergency Class.
7.1 Communicator conectly completed 1903.011 Y/Z forms O O O 7.2 Communk:stor notified ADH within 15 minutes of declaration O O O Comments: Page 3 of 5 l
- 8. Demonstrate notification of the Nuclear Regulatory Commission SAT UNSAT N/A (NRC)in accordance with 10CFR60.72 (may be simulated if the NRC chooses not to participate).
8.1 Communicator notified NRC immediately following ADH O O O 8.2 Communicator provided NRC with accurate information O O O Comments: 1 l
- 12. Demonstrate establishment of communications between the Control SAT UNSAT N/A Room, TSC, OSC, EOF, NRC, and State emergency responsa officials.
O O O 12.1 Communications established with other onsite response centers O O O 12.2 Communications established with offsite response centers. Comments:
- 14. Demonstrate radiation and contamination monitoring in the SAT UNSAT N/A Emergency Response Facilities (ERFs). )
14.1 Facility surveyed and results reported to appmpriate personnel O O O 14.2 Control points established as necessary 0 0 0 Comments: ) Page 4 of 5
- 15. Demonstrate effective and accurate information flow within and SAT UNSAT N/A between each Emergency Response Facility (ERF).
15.1 information flow within the facility was effective and accurate O O O 15.2 Information flow between ERFs was effective and accurate O O O Comments:
- 16. Demonstrate an effective teamwork response within and between SAT UNSAT N/A mach ERF.
16.1 Teamwork was displayed in the facility 0 0 0 16.2 Teamwork was displayed between the ERFs O O O Comments: 1 l l l I l i Page 5 of 5 1
ARKANSAS NUCLEAR ONE Evaluation Checklist Technical Support Center Date: Evaluator.' l Attached are .he objectives applicable to this facility or area of evaluation. Each objective is to be evaluated using the items listed for that objective. An objective may apply to more than one area. Your evaluation needs only to address your assigned gmup's or response center's role in meeting the objective. 1 Use this chocidist and any additional notes that you may have taken to evaluate the ERO's perfonnance in meeting each objective.
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Evaluation items are to be judged SAT, UNSAT, or N/A. SAT indicates that performance was adequate in meeting the objective. UNSAT indicates that the item was not met. N/A Indicates that the item either was not observed or did not apply to your facility or group. 4 Complete these forms and give them to the Lead Evaluator or Emergency Planning representative for your facility or group at the completion of the critique session. l Page 1 of 5
- 1. Demonstrate the use of the Emergency Action Level procedure for SAT UNSAT N/A Emergency Class declarations.
1.1 Use of 1903.010 to determine Emergency Class O O O 1.2 Clear announcement of the declaration made O O O l 1.3 Continued review of 1903.010 after an emergency declaration O O O Comments: l l
- 2. Demonstrate proper selection of Protective Action SAT UNSAT N/A Recommendations (PARS) and timely delivery of PARS to ADH.
2.1 Coned PAR selected based on scenario events O O O 2.2 Delivery of PAR to ADH was timely 0 0 0 Comments: l
- 3. Demonstrate the transfer of Emergency Direction and Control SAT UNSAT N/A (ED&C) responsibilities from the IRS to the ERO.
l 3.1 Complete tumover was given to the TSC Director or EOF Director O O O Comments: l I i t Page 2 of 5 l 1
- 4. Utilize the Safety Parameter Display Sy stem (SPDS) to monitor SAT UNSAT N/A selected plant parameters.
4.1 SPDS was used effectively D D D Comments:
- 7. Demonstrate notification of the Arkansas Department of Health SAT UNSAT N/A (ADH) within 18 minutes of the declaration of an Emergency Class.
7.1 Communicator correctly completed 1903.011 Y/Z forms D D D 7.2 Communicator notified ADH within 15 minutes of declaration D D D Comments: i
- 8. Demonstras notification of the Nuclear Regulatory Commission SAT UNSAT N/A (NRC) in accordance with 10CFR80.72 (may be simulated if the NRC chooses not to participate).
8.1 Communicator notified NRC immediately following ADH D D D 8.2 Communicator provided NRC with accurate information U U U Comments: l l Page 3 of 5
l I 9. Demonstrate activation of the Technical Support Center (T8C) SAT UNSAT N/A
- within approximately one hour following the declaration of an l ALERT or higher emergency cleas.
[ 9.1 TSC set up using 1903.065A D D D 9.2 TSC activated within one hour of ALERT or above O O O 9.3 TSC adequately staffed when declared operational D D D Comments
- 12. Demonstrate establishment of communications between the Control SAT UNSAT N/A Room, TSC, OSC, EOF, NRC, and State emergency responsa officiais.
O O O 12.1 Communications established with other onsite response centers D D D 12.2 Communications established with offsite response centers. Comments:
- 14. Demonstrate radiation and contamination monitoring in the SAT UNSAT N/A Emergency Response Facilities (ERFs).
14.1 Facility surveyed and results reported to appropriate personne! D O O 14.2 Control points established as necessary D D D Comments: i l l l Page 4 of 5
- 15. Demonstrate effective and accurate information flow within and SAT UNSAT N/A between each Emergency Response Facility (ERF).
15.1 Information flow within the facility was effective and accurate O O O 15.2 Information flow between ERFs was effective and accurate O O O Comments: l I i
- 16. Demonstrate an effective teamwork response within and between SAT UNSAT N/A (
each ERF. l l 16.1 Teamwork was displayed in the facility 0 0 0 16.2 Teamwork was displayed between the ERFs O O O i Comments: l i 1 ( l 1 l l 1 l 1 l l Page 5 of 5
ARKANSAS NUCLEAR ONE Evaluation Checklist Operational Suonort Center Date: Evaluator: Attached are the objectives applicable to this facility or area of evaluation. Each objective is to be evaluated using the items listed for that objective. An objective may apply to more than one area. Your evaluation needs only to address your assigned group's or response center's role in meeting the objective. Use this checklist and any additional notes that you may have taken to evaluate the ERO's performance in meeting each objective. Evaluation items are to be judged SAT, UNSAT, or N/A. SAT indicates that performance was adequate in meeting the objective. UNSAT indicates that the item was not met. N/A indicator, that the item either was not observed or did not apply to your facility or group. Complete these forms and give them to the Lead Evaluator or Em6aency Planning representative for your faciitty or gmup at the completion of the critique session. l I i k I l Page 1 of 5 i r _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ . __ A
- 10. Demonstrate activation of the Operational Support Center (OSC) SAT UNSAT N/A within approximately one hour of the declaration of an ALERT or higher emergency class.
10.1 OSC set up using 1903.066A O O O 10.2 OSC activated within one hour of ALERT or above O O O 10.3 OSC was adequately staffed when declared operational O O O 10.4 Adequate number of craft personnel assembled in Assembly Area O O O l Comments: 1L Demonstrate establishment of communications between the Control SAT UNSAT N/A Room, TSC, OSC, EOF, NRC, and State emergency rtsponse officiais. O O O 12.1 Communications established with other onsite response centers O O O 12.2 Communications established with offsite response centers. Comments: j 1 l Page 2 of 5
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- 13. Demonstrate radiation and contamination monitoring of plant areas SAT UNSAT N/A by the onsite section of the Emergency Radiation Team.
13.1 Equipment checked '.or operability prior to use O O O 13.2 Proper surveys performed during entry , O O O 13.3 Survey results promptly reported to the HP Supervisor O O O 13.4 HP provided guidance to other ro-entry team members O O O Comments: l l l l
- 14. Demonstrate radiation and con 3mination monitoring in the SAT UNSAT N/A Emergency Response Facilities (ERFs).
14.1 Facility surveyed and results reported to appropriate personnel O O O 14.2 Control points established as necessary 0 0 O l Comments:
- 15. Demonstrate effective and accurate infonnation flow within and SAT UNSAT N/A between each Emergency Response Facility (ERF).
15.1 Information flow within the facility was effedive and accurate O O O 15.2 Information flow between ERFs was effective and accurate O O O Comments: I Page 3 of 5
- 16. Demonstrate an effective teamwork response within and between SAT UNSAT N/A each ERF.
16.1 Teamwork was displayed in the facility 0 0 0 16.2 Teamwork was displayed between the ERFs O O O Comments:
- 19. Demonstrate the capability of the Post Accident Sampling System SAT UNSAT N/A (PASS) to analyze the primary system (RCS).
19.1 PASS team selected and briefed O O O 19.2 PASS team property obtained requed.ed samples O O O 19.3 Sample results promptly reported to the Nuclear Chemistry Mgr. O O O Comments: 1 Page 4 of 5 l
- 27. Demonstrate the formation of Repair and Damage Control Teams SAT UNSAT N/A and initial recovery and reentry actions.
27.1 Missions identified by TSC clearly understood in OSC O O O 27.2 Team composition appropriate for task to perform O O O ! 27.3 Teams briefed adequately by OSC staff O O O 27.4 Teams dispatched and tracked effectively from the OSC O O O 27.5 Repair status communicated promptly to TSC O O O 27.6 Retuming teams debriefed by OSC staff O O O l Comments: i I l l l l Page 5 of 5 l l
ARKANSAS NUCLEAR ONE Evaluation Checklist l Emernency Operations Facility Date: Evaluator: j Attached are the objectives applicable to this facility or area of evaluation. Each objective is to be evaluated using the items listed for that objective. An objective may apply to more than one area. Your evaluation needs only to address your assigned group's or response center's role in meeting the objective. Use this checidist and any additional notes that you may have taken to evaluate the ERO's performance in meeting each objective. Evaluation Nems are to be judged SAT, UNSAT, or N/A. SAT indicates that performance was adequate in meeting the objective. UNSAT indicates that the item was not met. N/A indicates that the item either was not observed or did not apply to your facility or group. Complete these forms and give them to the Lead Evaluator or Emergency Planning representative for your facility or group at the complebon of the critique session. i l-Page 1 of 7
- 1. Demonstrate the use of the Emergency Action Level procedure for SAT UNSAT N/A Emergency Class declarations.
1.1 Use of 1903.010 to determine Emergency Class O O O l 1.2 Clear announcement of the declaration made O O O 1.3 Continued review of 1903.010 after an emergency declaration O O O Comments: ! I l l l l I 2. Demonstrate proper selection of Protective Action SAT UNSAT N/A Recommendations (PARS) and timely delivery of PARS to ADH. l j 1 2.1 Correct PAR selected based on scenario events O O O 2.2 Delivery of PAR to ADH was timely 0 0 0 Comments:
- 3. Demonstrate the transfer of Emergency Direction and Co:strol SAT UNSAT N/A (ED&C) responsibilities from the IR8 to the ERO.
3.1 Complete tumover was given to the TSC Director or EOF Director O O O Comments: i l I Pagt: ' ' oi 7
- 5. Demonstrate coordination with the Arkansas Department of Health SAT UNSAT N/A (ADH) and NRC to downgrade the emergency or transition to the recovery phase (may be simulated if the NRC chooses not to participate).
O O O 5.1 Plant status discussed with ADH and NRC O O O S.2 ADH and NRC concurrence obtained Comments:
- 7. Demonstrate not!fication of the Arkansas Department of Health SAT UNSAT N/A (ADH) within 15 minutes of the declaration of an Emergency Class.
7.1 Communicator correctly completed 1903.011 Y/Z forms O O O 7.2 Communicator notified ADH within 15 minutes of declaration O O O Comments:
- 8. Demonstrate notification of the Nuclear Regulatory Commission SAT UNSAT N/A I (NRC) in accordance with 10CFR50.72 (may be simulated if the NRC chootes not to participate).
8.1 Communicator notified NRC immediately following ADH O O O 8.2 Communicator provided NRC with accurate information U U U Comments: l I Page 3 of 7
- 11. Demonstrate activation of the Emergency Operations Facility (EOF) SAT UNSAT N/A within approximately one hour following the declaration of an ALERT or higher emergency class.
11.1 EOF set up usinD 1903.065A O O O 11.2 EOF activated within one hour of ALERT or above O O O 11.3 EOF adequately staffed when declared operational O O O Comments:
~
- 12. Demonstrate establishment of communications between the Control SAT UNSAT N/A Room, TSC, OSC, EOF, NRC, and State emergency response officials.
O O O 12.1 Communications established with other onsite response centers O O O 12.2 Communications established with offsite response centers. Comments:
- 14. Demonstrate radiation and contamination monitoring in the SAT UNSAT N/A Emergency Response Facilities (ERFs).
14.1 Facility surveyed and results reported to appropriate personnel O O O 14.2 Control points established as necessary 0 0 0 Comments: I Page 4 of 7 i
)
~
- 18. Demonstrate effective and accurate information flow within and SAT UNSAT N/A between each Emergency Response Facility (ERF).
15.1 Information fle ithin the facility was effective and accurate O O O 15.2 Information floa.v between ERFs was effective and accurate O O O Comments: l 1 1 1
- 16. Demonstrate an effective teamwork response within and between SAT UNSAT N/A each ERF.
16.1 Teamwork was displayed in the facility O O O 16.2 Teamwork was displayed between the ERFs O O O Comments:
- 17. Demonstrate coordination of response efforts with ADH and NRC SAT UNSAT N/A officials.
17.1 ANO and ADH personneljointly determined appropriate O O O responses to scenario conditions 17.2 ANO and NRC personnel dimmad accident response activities O O O Comments: Page 5 of 7
- 30. Dwnonstrate activation of the Emergency News Center (ENC) at the SAT UNSAT N/A EOF.
30.1 ENC activated and staffed in a timely manner O O O 30.2 Press conferences were organized and publicized O O O 30.3 Personnel were available for public inquiries O O O 30.4 News releases accurately prepared and disseminated frequently 0 0 O i 30.5 Visual aids were used effectively 0 0 0 30.6 Media were instructed on building access and ENC operation O O O 30.7 News releases were approved by the EOFD D D D 30.8 Rumom and distorted information were corrected expeditiously 0 0 0 30.9 Logs were maintained O O O Comments: l l I r i Page 6 of 7
i I I l l
- 31. Demonstrate production and delivery of information in joint ANO SAT UN3AT N/A '
and ADH news from the ENC located within the EOF. 31.1 Press conferences were organized and publicized O O O 31.2 ANO personnel and ADH personnel held joint news conferences O O O ! Comments: 1
- 33. Demonstrate coordination between ANO and the Corporate SAT UNSAT N/A Emergency Center (CEC) at Echelon.
33.1 ANO personnel requested assistance as required from the CEC D D D Comments: l
- 34. Demonstrate security procedures for the site and the Emergency SAT UNSAT N/A Operations Facility.
34.1 Secunty established for EOF protected area O O O 34.2 EOF personnel displayed ID badges O O O 34.3 Appropriate security measures for the site implemented O O O Comments: Page 7 of 7 L___________________ ____
ARKANSAS NUCLEAR ONE Evaluation Checklist Dose Assessment Date: Evaluator: Attached are the objectives applicable to this facility or area of evaluation. Each objective is to be evaluated using the items listed for that objective. An objective may apply to more than one area. Your evaluation needs only to address your assigned group's or response center's role in meeting the objective. Use this checklist and any additional notes that you may have taken to evaluate the ERO's performance in meeting each obsective. Evaluation items are to be judged SAT, UNSAT, or N/A. SAT indicates that performance was adequate in meeting the objective. UNSAT indicates that the item was not met. N/A indicates that the item either was not observed or did not apply to your facility or group. Complete these forms and give them to the Lead Evaluator or Emergency Planning representative for your facility or group at the completion of the cdtique session. l t Page 1 of 3 l
b
- 20. Utilize the Radiological Dose Assessment Computer System SAT UNSAT N/A (RDACS) to demonstrate dose assessment capabilities.
20.1 Dose Assessment Team assembled in a timely manner O O O 20.2 Dose assessment equipment was property used O O O 20.3 Plume was defined and tracked O O O I 20.4 DAS provided updates to the REAM O O O Comments:
- 24. Demonstrate offsite radiological field monitoring by the offsite SAT UNSAT N/A section of the Emergency Radiation Team.
24.1 Offsite team (s) assembled in a timely manner O O O l 24.2 Instruments checked for operability before dispatch O O O l 24.3 Team received clearinstructions fmm OMS O O O 24.4 Sample points readily located O O O 24.5 Samples property packaged and labeled. O O O 24.6 Dosimeters periodically read and results reported to OMS O O O 2-4.7 Teams completed forms property 0 0 0 Comments: l l t Page 2 of 3 i
- 25. Demonstrate coordination of offsite radiological field monitoring SAT UNSAT N/A with State personnel.
25.1 ANO and ADH personnel discussed offsite monitoring strategy C O O 25.2 Survey results shared between ANO and ADH O O O Comments: l i i
- 26. Demonstrate coordination between field monitoring teams and dose SAT UNSAT N/A assessment personnel.
26.1 Sample locations coordinated between DAS and OMS O O O 26.2 Field data provided to DAT O O O Comments: l
- 42. Demonstrate the use of potassium iodidelKI) for a postulated SAT UNSAT N/A I l accident.
I l 42.1 Evaluate the need for issuing to Offsite Monitoring Teams O O O 42.2 K1 administered in accordance with 1903.035 O O O Comments: I' l l Page 3 of 3
I I OBJECTIVES 4 f l l
ARKANSAS NUCLEAR ONE REX-96 BIENNIAL EXERCISE AUGUST 19,1998 ATTACHMENT 1 - OBJECTIVES One Year Obiectives i NUMBER NUREG.0654 PROCEDURE DESCRIPTION l REFERENCE REFERENCE
- 1. 1.1,1.2, D.1, D.2 1903.010 Demonstrate the use of the Emergency Action Level (EAL)
Classification procedure for Emergency Class Declarations.
- 2. J.7 1903.011 Demonstrate proper selection of Protective Action 1904.002 Recommendations (PAR's) and timely delivery of PAR's to the ADH.
- 3. A.1, A.3, A.4, B.7 1903.064 Demonstrate the transfer of Emergency Direction and Control B.6, B.9 1903.065 (ED&C) responsibilities from the IRS to the ERO.
1903.067
- 4. 1.1,1.2 1903.066 Utilize the Safety Parameter Display System (SPDS) to monitor selected plant parameters.
- 5. D.1,D.2 1903.067 Demonstrate coordination with the Arkansas Department of Health (ADH) and NRC to downgrade the emergency or j transition to the recovery phase. (The NRC may be simulated if
! they choose not to participate) l 6. 5.1, E.2, E.3, J.1 1903.011 Demonstrate notification and deployment of the initial
- 1903.062 Response Staff (IRS) and the Emergency Response Organization (ERO).
- 7. E.1. E.2, E.3, J.1 1903.011 Demonstrate notification of the Arkansas Department of Health (ADH) within 15 minutes of the declaration of an Emergency Class.
- 8. E.1, E.2, E.3, J.1 1903.011 Demonstrate notification of the Nuclear Regulatory Commission (NRC)in accordance with 10CFR50.72 (may be simulated if the NRC chooses not to participate).
- 9. E.2, E.4, F.1, F.2, 1903.065 Operational Technical Support Center (TSC) within H.6, *8.1, *8.2, 1903.011 approximately one hour following the declaration of an Alert or
*8.3, *8.4, A.1, higher Emergency Class.
A.3, A.4, B.7, B.8, B.9
- 10. E.2, E.4, F.1, F.2, 1903.066 Operational Operational Support Center (OSC) within H.6, *8.1, *8.2, 1903.011 approximately one hour following the declaration of an Alert or
*8.3, *8.4, A.1, higher Emergency Class.
A.3, A.4, B.7, B.6, B.9
- 11. E.2,E.4,F.1,F.2, 1903.067 Operational Emergency Operations Facility (EOF) within H.6, *8.1, *S.2, 1903.011 approximately one hour following the declaration of a Site Area
*8.3, *8.4, A.1 A.3 Emergency or General Emergency.
A.4. B.7. B.8. B.9 1
l l One Year Objectives NUMBER NUREG.0654 PROCEDURE DESCRIPTION REFERENCE REFERENCE
- 12. E.2, E.4, F.1, F.2, 1903.064 Demonstrate establishment of communications between the H.6, *8.1, *8.2, 1903.065 Control Room, TSC, OSC, EOF, NRC and State emergency
'8.3, *8.4, A.1, 1903.066 response officials.
1903.067
- 13. E.2,E.4,F.1,F.2, 1903.043 Demonstrate radiation and contamination monitoring of plant H.6, *8.1, *8.2, 1905. series areas by the onsite section of the Emergency Radiation Team.
*8.3, *8.4, A.1,
- 14. E.2, E.4, F.1, F.2, 1903.043 Demonstrate radiation and contamination monitoring in the H.6, *8.1, *8.2, 1905. series Emergency Response Facilities (ERF's)
*8.3, *8.4, A.1, i
- 15. None 1903.064 Demonstrate effective and ac., urate information flow within and 1903.065 between each Emergency Response Facility (ERF) 1903.066 1903.067
- 16. None 1903.064 Demonstrate an effective teamwork response within and 1903.065 between each ERF.
1903.066 1903.067
- 17. None 1903.064 Demonstrate coo tfi. nation of response efforts with ADH and 1903.065 NRC officials.
1903.066 1903.067
- 24. E.2, E.4, F.1, F.2, 1905.002 Demonstrate offsite radiological field monitoring by the, offsite H.6, *8.1, *8.2, section of the Emergency Rediation Team.
*8.3, *8.4, A.1,
- 27. E.2, E.4, F.1, F.2, 1903.033 Demonstrate the formation of Repa:r and Damage Control H.6, *8.1, *8.2, 1903.066 Teams and initial recovery and reentrj actions.
*8.3, *8.4, A.1, M.1 2
Six Year Objectives NUMBER NUREG-0654 PROCEDURE DESCRIPTION REFERENCE REFERENCE
- 19. l.2 1905.003 Demonstrate the capability of the Post Accident Sampling System (PASS) to analyze the RCS.
- 20. l.3,l.4,1.6,1.8,1.9, 1904. series Utilize the Radiological Dose Assessment Computer System
*6.10 (RDACS) to demonstrate dose assessment capabilities.
- 21. None 1903.042 Demonstrate coordination between ANO and the Pope County Emergency Medical Service (PCEMS) staff for the handling of a simulated injured and radioactively contaminated individual.
(Note: Performed out of sequence)
- 22. None 1903.042 Demonstrate coordination between ANO and the St. Mary's Hospital Staff for the handling of a simulated injured and radioactively contaminated individual. (Note: Perfonned out of sequence)
- 25. l.3,1.4,1.6,1.8,1.9, 1905.002 Demonstrate coordination of offsite radiological field monitoring
*8.10 with State personnel.
- 26. l.3,1.4,1.6,1.6,l.9, 1905.002 Demonstrate coordination between field monitoring teams and
*8.10 '1903.067 dose assessment personnel.
1
- 32. N.2.b,0.4.d 1903.066 Demonstrate Fire Brigade response to a simulated fire onsite.
1203.034 i
- 30. G.4.c 1903.068 Demonstrate the activation of the Emergency News Center 1903.011 (ENC) in the EOF.
- 31. G.4 1903.068 Demonstrate production and delivery of information in joint 1903.067 ANO and ADH news conferences from the ENC located within the EOF.
- 33. O.4.1 1903.067 Demonstrate coordination between ANO and the Corporate 1903.068 Emergency Center (CEC) at Echelon.
- 34. O.4.d 1903.065 Demonstrate secunty procedures for the site and the ]
1903.067 Emergency Operation s Facility (EOF).
~
- 42. J.6.c 1903.035 Demonstrate the use of potassium iodide for a postulated accident.
l. i i l 1 3 L______-_______--_____________. . _ _ _ _ - _ _ . _ _ _ _ - - - _ _ _ _ . __ - - .
l LIST OF SIMULATED ACTIVITIES l
- 1. NRC Operations Center Communications The NRC Operations Center will not be participating in this exercise. A controller station will be established during this exercise to simulate ENS conversation between ANO and the NRC.
- 2. Plant Evacuation / Accountability l The plant evacuation will be simulated during this year's Exercise.
Appropriate checklists will be completed by participants as though a real evacuation was occurring, however, Controllers will intervene to ensure that personnel are not evacuated from the site. The evacuation announcement over the PA system will be simulated. Due to the simulation of the plant evacuation, accountability will also be simulated. 3 Field Monitorino Team 1
- a. Due to the expense of cilver zeolite cartridges, charDal 1 ridges l will be used as a substitute.
l b. To prevent undue public concern, respirators and/or protective clothing will not be worn in the field.
- c. If required, the Field Monitoring Teams will demonstrate the Potassium lodide (KI) process including distribution but will not actually take the Kl tablets. M&M's will be substituted.
- 4. Roosir and Damsoe Control Team l a. Manipulation and repair of plant equipment will be simulated with the exception of mock-ups staged during the exercise.
- b. Repair and Damage Control team access to plant areas will occur to the extent allowed by actual in-plant radiation levels.
- c. If required, white training P.C.'s normally stored for drill / exercise purposes in OSC Emergency Kit A' will be worn instead of regular yellow P.C.'s.
I
- d. Identified Radiological areas of the exercise scenario will be posted in accordance with current Radiation Protection Procedures. The postings should include the phrase "this is a drill"
i
- e. If required, SCBA's will be obtained, checked, donned and a negative pressure test of the mask will be performed. The SCBA's will be worn to the job site but the masks will not be worn to the job site.
When communications are made by a team member to the OSC, the communicating team member will place his respirator to his face prior to communicating. Exercise controllers will keep track of the available air supply per bottle.
- f. If equipment parts are required, the team members will go to the warehouse, locate the parts, but will not actually draw the parts.
- 5. Medical Emeroency l The Pope County Emergency Medical Service (PCEMS) will not be participating in the Exercise. They will be exercised out-of-sequence on August 18,1998 under FEMA evaluation.
St. Mary's Hospital personnel will not be participating in the Exercise. They will be exercised out-of-sequence on August 18,1998 under FEMA evaluation. University of Arkansas Medical Science Center (UAMSC) will not be participating in this year's Exercise.
- 6. Fire Emeroency '
- a. Participants will be given verbal information concerning the extent of the fire and smoke in the affected area by the Controller.
- b. The discharging of extinguishing agents will be simulated.
- c. For the purpose of this exercise, the Fire Brigade Training Crew will respond to the fire emergency.
i
NARRATIVE
SUMMARY
The exercise will begin at 0800 on August 19,1998. Unit I has been operating at 100% power for 105 days. The following conditions currently exist: Unit 2 is currently in an unscheduled outage which began on August 1,1998 due to steam generator tube leakage, and is not expected to return to power until September 15,1998. At approximately 0530 on August 19,1998, Unit 1 entered a 7 day time clock per Technical Specification 3.4.4.2. During the performance of surveillance 1106.006 ! Supplement 3, Steam Admission Valve CV-2617 failed closed. The valve was ( stroked closed. Shortly after indicating closed, position indication was lost in the l Control Room. The Waste Control Operator (WCO) was sent to the breaker for CV-2617 (breaker B-6241) and reported that there was no local indication and l that it appeared that the thermal overloads might be tripped. The WCO was ( directed to reset the thermal overloads. Position indication was regained for about ! 5 seconds, and then lost again. Due to the duration of the time clock, a Priority 2 ! Job Request was submitted. Because of the proximity to nonnal shift turnover time, and the stan of the normal workday, no personnel were called out. The Planning and Scheduling Liaison was notified of the condition at ~0600 and will ensure CV-2617 gets on today's work schedule. No funher troubleshooting l was performed. Local verification at the valve indicates CV-2617 is closed. The ; L valve will be left in its current configuration until the Electricians can perform an j . initialinspection. Appropriate management personnel are informed of the CV-2617 failure at the morning meeting. At approximately 0800 hours, the "C" Reactor Coolant Pump (RCP) upper oil system will develop a leak of 25 gpm. This will cause the upper oil reservoir to slowly lower at
~15"/ min. As the oil level lowers, pump vibrations will develop. At approximately 0815, "C" RCP vibrations will cause annunciator K08-B6 (RCP Vibration) to alarm. Inspection of the RCP Vibration monitoring rack will indicate that "C" RCP vibrations are at the alert level and fluctuating.
, At approximately 0819, annunciator K02-F8 (Programmable Alarm) will alarm due to a l low oil sump level on "C" RCP. l ! I ! I I l l 1 a
Per AOP 1203.031 Section 5, the crew will begin reducing power to <60% in preparation for removing the "C" RCP from service. As power is reduced the condition will worsen, and when power falls below 90%, the third stage seal will fail, the rotor will lock, and the . pump will trip (approximately 0830). The crew should take actions to stabilize the plant ! l at ~75% power in 3 pump operations. ' Due to the destruction of the pump, metal fragments are released into the RCS, and will cause a Vibrations / Loose Parts alarm (K08-C4) on the RCS Vessel and the "A" OTSG. The alarm will_nal be grossly above the setpoints so as to alarm the crew to take drastic actions. i i The Shift Superintendent notifies plant management, System Engineering, and predictive l maintenance to investigate and analyze the Vibrations / Loose Parts alarm. At approximately 0900, due to the released foreign material from "C" RCP, a tube leak develops in the "A" OTSG and quickly rises to ~75 gpm. In addition to this, the SIMS system server will fail. Efforts to recover it will take until ~1200. In conjunction with the tubeleak:
- a. The crew should initiate a plant shutdown at d5%/ min and enter EOP 1202.006 (Tube Rupture).
- b. When determined that the leak is greater than 50 gpm, but within HPI pump capacity, the SS should declare an ALERT per EAL 2.2.
EAL 2.2 - RCS LEAKAGE RCS LEAKAGE > NORlWAL MAKEUP CAPACITY (50 GPM) The SS directs the Unit 2 Shift Engineer to make the appropriate notifications to the
- Arkansas Department of Health (ADH) and the NRC. The Emergency Response l Og Adon (ERO) will be activated via the plant paging system and the Computerized Notification System (CNS).
- a. As part of the EOP actions, the EFW Steam Admission valve from the affected OTSG (CV-2667) is closed. This renders P-7A inoperable and requires entry into a 72 hour time clock per Tech. Spec. 3.4.4.3.
- b. Nuclear Chemistry is contacted to begin dose assessment, and to assist in determining the tube leak size and whether or not it is stable.
A local evacuation of the Turbine Building or affected portions raay be directed by the SS. 2 i
P Plant shutdown should be complete by ~0945. A controlled cooldown of the RCS will be commenced, and feedwater will be shifted to the Auxiliary Feedwater pump (P-75). Once feedwater has been shifted to P-75, a leak upstream of CS-5B (Manual inlet Isolation to the "B" polisher) will begin. The leak will quickly grow to the point where it is flooding the Unit 1 Turbine Building Bowling Alley. This will require that the secondary system be secured and feedwater be transitioned to EFW. At ~1000 the Technical Support Center (TSC) and Operational Support Center (OSC) should be staffed and operational. The Emergency Operations Facility (EOF) may be staffed and operational. Investigation of the condensate rupture will be pursued, and recovery of CV-2617 may become a priority. Recovery plans will be implemented by the OSC staff under the direction of the OSC Director. At approximately 0950, after the secondary system has been secured and EFW actuated using P-7B, the WCO will report P-7B is makmg a loud screeching noise. He can see oil on the floor, and oil spraying from the inboard end of the pump. This will prompt the crew to secure P-7B. If this is not done within a few minutes, the pump will trip on overcurrent due to bearmg failure. At this point the crew will be at a decision branching point: P_ath_l The crew / TSC will open CV-2667, and supply steam to P-7A from the affected OTSG. This will cause an immediate and unmonitored release path via P-7A, but will supply water to the OTSGs, and allow cooldown of the plant. This will escalate the Emergency Classification to a Site Area Emergency per EAL 3.4. EAL 3.4 - SECONDARY SYSTEM EVENTS OTSG Tube Rupture with primary leakage > normal makeup capacity (50 gpm) with ongoing steam release. l Path 2 The crew / TSC may attempt to prevent a release entirely by shifting to HPI l Cooling. If this is attempted, it will escalate the Emergency Classification to a Site Area Emergency per EAL 6.11. EAL 6.11 - SAFETY SYSTEM FUNCTION l Degraded Hot Shutdown Capability, Loss of all feedwater. If this path is chosen the ERV pilot valve will reposition, but the ERV will not open due to binding. Per the EOP, pressure should then be raised to lift the Code Safeties at 2500 psig. Due to incorrect settings, the Code Safeties will not lift until RCS pressure is >2900 psig. The crew will not raise RCS pressure substantially above 2500 psig, but instead should throttle HPI to limit pressure to 2500 psig maximum. 3
The crew / TSC may decide to open the RCS high point vents. If so, the valves will reposition, but no pressure relief will be achieved. (During the previous outage, the manual isolations were closed and never verified open). Ormil, the amount of HPI that can be injected will be insufficient to provide adequate core cooling. The crew may attempt to steam the affected OTSG (which has a 75 gpm tube leak), and even with this, the core will not be adequately cooled. All of this will drive the crew to realize that P-7A must be used. Regardless of which path is taken, the crew will ultimately end up using P-7A for core cooling, and the resultant steam release will cause an SAE to be declared. The declaration will prompt the following major response actions:
- Notifications to offsite authorities. - Plant Evacuation determination. ,
I l
- Efforts will focus on opening CV-2617. l As me crew attempts to cooldown using P-7A, the pump will spuriously trip.
Investigation will reveal no apparent problems, but the WCO will have difficulty resetting the pump. P-7A will spuriously trip and may have its linkage broken due to troubleshooting efforts. The resultant loss of core cooling may prompt the initiation of HPI cooling if not attempted earlier. If so, the same conditions will result, causing a return to P-7A for core cooling. (P-7A will become available). At approximately 1050, due to the RCS heating up when P-7A is tripped and the initial debris released into the RCS, a fuel failure condition will develop and escalate to ~5% failed fuel. This will be indicated by the Letdown Process Monitor (if letdown is in service), the Seal Return Cooler Area Monitor, the Reactor Building Area Monitors, and the Reactor Building (RB) Air Particulate Detector (APD). After evaluating conditions, the crew / TSC should determine that >l% failed fuel exists, which will escalate the Emergency Classification to a General Emergency per EAL 1.7. EAL 1.7 - PRIMARY SYSTEM EVENTS
- Loss of or challenge to all 3 Fission Product Barriers.
The declaration will prompt the following major response actions:
- Notifications to offsite authorities 1
i 4 i
- Protective Action Recommendation to offsite authorities as follows:
Evacuate: 2 mile radius and 5 miles downwind Shelter: The remainder of the 10 mile EPZ (Minimum PAR at General Emergency) Post Accident Sampling (PASS ) will be initiated in order to determine the extent of the fuel damage. Assessment of offsite dose will be performed by the Dose Assessment Team and offsite 6 eld monitoring teams.
- Plant recovery planning will be underway in all of the Emergency Response Facilities.
Priority will be placed on terminating the offsite release. If the crew / TSC has not utilized HPI cooling at this peint (and realized it is ineffective due to the plant failures), there is a strong possibility they will attempt it now. If so, they will eventually determine it will not work and go back to P-7A. Once it is known that using P-7A is the only effective cooling source, efforts will be focused on:
- a. Opening CV-2617
- b. Weld repair of the condensa*e piping
- c. Bearing replacement on P-7B With the ener==61 compiktion of any one of these paths, offsite release from the affected OTSG may be terminated. . As onsite and offsite conditions improve, discussions will
. begin to determine the appropriate time for downgradmg from a General Emergency to a lower emergency class or to transition into a recovery phase.
At ~1200 the Control Room receives a report from an Auxiliary Operator (AO) of smoke in the area of the Cardox System on the 372' elevation of the Turbine Building. After
- further investigation, the AO reports to the Control Room that the C-7, Main Generator i Bearing Oil Vapor Extractor, has smoke coming from the pump motor. The SS will notify l the Fire Brigade. The Fire Brigade will assemble and extinguish the fire.
l The exercise is scheduled for termmation at 1400 hours. 5
i
-+ .e w *
, . . . . .m i
E l l l l l DETAILED SCENARIO . i I l l i
l DETAILED DESCRIPTION OF EVENTS i
- This section contains a chronological listing of major scenario events and anticipated responses. It is intended for use as an aid for effective placement of t
controllers, evaluators and observers. The anticipated responses listed in this section do not necessarily include all of the acceptable actions by players and should not be used as basos for performance evaluation. Evaluations of player decisions and actions should be based on appropriate implementation of the Emergency Plan and procedures. INITIAL CONDITIONS I i At 0800 on August 19,1998, Unit 1 is operating at 100% power. The unit has , ! been operating at 100% power for the past 105 days. The unit entered a 7 day l time clock at 0530 per Tech. Spec. 3.4.4.2 due to CV-2617 (Steam Supply to , P-7A) failing closed during its surveillance last night (1106.006 Supp 3). CV- )
- 2617 stroked closed, and indication in the Control Room was lost. Its breaker (B-6241) was checked, and the thermal overloads were found tripped, with the breaker closed. The thermal overloads were reset and indication was regained.
The thermal overloads tripped 5 seconds later. No further attempts at ! troubleshooting have been made. Due to the proximity to turnover and start of the normal work day, a Priority 2 Job request was written .for CV-2617. Operations management has been informed of this condition. The Plann%g and l Scheduling (P&S) Liasion requested that CV-2617 be left undisturbed until l electricians have a chance to look at it. i Unit 2 at ANO is currently in an unscheduled outage which began August 1, 1998 and is scheduled to continue until September 15,1998. l
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EXERCISE MESSAGES i 9 i I
c. MESSAGE NO.1 TO: Shift Superintendent FROM: Control Room Controller LOCATION: Unit 1 Simulator Control Room TIME: 0800 MESSAGE: THIS IS A DRILL DO NOT initiate actions which may affect normal plant operations. Refer to the attached Shift Turnover form for initial plant conditions. e 4 l' t______ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ___ _ __ _ _ _ __ _ ____ _ _ _ _ _ . _ __ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _
INITIAL CONDITIONS 1 ! At 0800 on August 19,1998, Unit 1 is operating at 100% power. The unit has been operating at 100% power for the past 105 days. The unit entered a 7 day - l time clock at 0530 per Tech. Spec. 3.4.4.2 due to CV-2617 failing closed during its surveillance last night (1106.006 Supp 3)l CV-2617 stroked closed, and indication in the Control Room was lost. Its breaker (B-6241) was checked, and l the thermal overloads were found tripped, with the breaker closed. The thermal overloads were reset and indication was regained. The thermal overloads tripped 5 seconds later. No further attempts at troubleshooting have been made. l Due to the proximity to turnover and start of the normal work day, a Priority 2 Job request was written for CV-2617. Operations management has been informed of this condition. The Planning and Scheduling (P&S) Liasion requested that CV-
'2617 be left undisturbed until electricians have a chance to look at it.
Unit 2 at ANO is currently in an unscheduled outage which began August 1, 1998 and is scheduled to continue until September 15,1998. l l l. i I
MESSAGE NO. 2 )i TO: Inside AO FROM: Inside AO Controller LOCATION: Unit 1 AO Shack TIME: ~0830 MESSAGE: THIS IS A DRILL DO NOT initiate actions which may affect normal plant operations. If asked to check breaker H-12 for the "C" RCP, Notify the IAO that the OVERCURRENT FLAG is tripped. l l t i j l l
MESSAGE NO. 3 ( TO: Inside AO FROM: Inside AO Controller LOCATION: Unit 1 AO Shack TIME: 0900 l l MESSAGE: THIS IS A DRILL DO NOT initiate actions which may affect normal plant operations. Refer to marked up copy of 1203.014 " Control of Secondary Contamination" for messages the IAO may need. l-l r fl ' u_
ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE TITLE: CONTROL OF SECONDARY SYSTEM PROC / WORK PLAN NO. REV. CONTAMINATION 1203.014 11 EXP.DATE SAFETY-RELATED N/A SyEs ONO CONTROLLED COPY # l5 ,AOE , Or , m NS sNO 1 Self Check. 2 ., -7 : 3
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FORM TITLE: FORM NO. REV. LIST OF AFFECTED PAGES 1000.006A 44 1
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' C G30 I_ _ 1203A14 REV*
i CONTROL GF SECONDARY SYSTEM CONTAMINATION 11 l CHANGE: t , DISCUSSION This procedure is used in the event of a primary to secondary SG tube leak. The Building. intent is to prevent an un-monitored radioactive release from the Turbine Instructions are provided to minimize both the spread of contamination and personnel exposure to radiation. Also contaminated providedwater. in this procedure are instructions for handling large amounts of j 1.0 SYMPTOMS Control of secondary system contamination required by either small Steam Generator Tube Leaks (1203.023) or Tube Rupture (1202.006). 2.0 IMMEDIATE ACTION 3.0 g .lgw ffep M 38 FULLOW-UP ACTIONS . 3.1 If trench dump is in progress, Tollowing handswitches in OIT: stop trench dump by placing the i e Trench susp Pump (P-122A)
- Trench Sung Pump (P-1225) )
Emergency Trench Sump Pump (P-97) l [ 3.2 g shutdown is required, perform the followir,g:
- 3.2.1 Align Condensate Polishers to prevent wide spread l
ygg8 contamination of polisher resin and reduce secondary system activity level as follows: I A. Inform Control Room personnel of intent to remove all : l but two polishers from service. (goep c, ( Q Z /S) i . To minimize radiation exposure to personnel at the polisher controls and in the train bay, it is preferred that C & D polishers remain in service. l Mh. M only one polisher is in service and tiow can be maintained >1500 gpm/ polisher with two polishers, perform the following:
- 1. Place an idle polisher in service per Condensate Domineralizer System Operation and Regeneration (1106.024), section 10.
- - - - - - - - - - uu C.
If more then two polichsrs cra in corvica, remov3 all but two polinhors from servic3, whilo maintaining required polisher flow rates and adequate MEW Pump (s) suction (CS-27). pressure by throttling open Polisher Bypass Required polisher flow rate - 1500 to 3550 gpm/DI
. Adequate MFW Pump suction pressure - >280 psig 3.2.2 f I_f,"A" SG is affected, perform the following:
A. Notify Control Room that Main Steam to B & D MSR will
. be isolated.
B. Close B & D MSR Main Steam Isolation (CV-6865). C. Close Main Steam "A" Drain to E-11A (MS-4A).
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3.3 .' ( Notify Health Physics of any known secondary system to atmosphere leakage for evaluation of leakage containment-and posting requirements, g g M NWA) 3.4 Initiate condensate Domineralizer System Operation and Regeneration
' (1106.024) Attachment E, " Condensate Reject to the Flume" and submit to Nuclear Chemistry.
3.5 I,f necessary to preclude developing an excess of contaminated water, verify Hotwell Makeup from CST (CV-2873)Rce closed and Wopen associated supply breaker (B2255), pg c c,e m i 6 Tie c.+id M 3.5.1 Verify Condensate Reject to CST (CV-2877) closed and associated supply breaker open (B1255). 3.6 Terminate all unnecessary operations such as feed and bleeds, blowdowns, etc, in the Turbine Building that would increase the volume of water collected in the turbine b1dg trench. g g g g I/d l l . l
1203.014 CO OL OF SECONDARY SYSTEM C8NTAMINATION 1 l l 3.7 Notify Chemistry to isolate unnecessary samples and sample cooling water sources such as in secondary sample room, miscellaneous coupon racks, environmental monitoring, etc. 3.8 Minimize the spread of contamination to connected systems as follows: l l 3.8.1 Isolate Extraction Steam to the Plant Heat Exchanger l (VHE-1) by closing Plant Heat Exchanger (VHE-1) Ext Steam ' Supply Regulator (CV-5833) Inlet and Bypass: ]
- EX-5833-1
- EX-5833-3 3.8.2 close condensate Storage Tank (T-41) Heating Steam Supply Isolation (EX-9).
3.8.3 Close Main Steam "B" to Unit II Concentrator (MS-35). 3.8.4 Supply Gland Seal from SU Boiler e h l 3.8.5 Inform Nuclear Chemistry personnel to secure all secondary samples not required. 3.9 When Nuclear Chemistry analyses are complete and satisfactory, contact Control Room to determine if hotwell reject to the flume is required. l 3.9.1 If directed by control Room, reject to'fiume using ' 1106.024, Attachment E. 3.10 Verify turbine oil sump pump discharge aligned to the turbine building trench as follows: 3.10.1 Verify Floor Drain Sump Pump Disch Common Isol. to Turbine Building Trench (FYD-143) open. 3.10.2 Verify Floor Drain Sump Pump Disch common Isol. to OWS (FYD-144) closed. 3.11 .I_f, Nuclear Chemistry requests pumping turbine building trench to T-50, perform the following: 3.11.1 Request Hechanical Maintenance to install a temporary hose from EMER Trench Sump P-97 DISCH to OWS (FYD-123) to T-50. 3.11.2 Close Trench Pumps Combined DISCH to OWS (FYD-124). 3.11.3 Caution-card or install equivalent permanent placard on the l following valves stating: " Current contamination controls require turbine building sumps to be counted and released via Neutralizing Tank (T-50). Do not open without Shift Superintendent's permission". , I ~ l
- Trench Pumps Combined DISCH to OWS (FYD-124) i
- Floor Drain Sump Pump Disch common Isol to OWS (FYD-144)
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l l * , CHANGE: 3.1 4
,' Pump turbine building tranch to T-50 for analysis and
/ release as nacassary low enough to get oil while ensuring trench is not pumped in T-50, 3.11.5 Treat dumps from turbine building trench and T-50 as radioactive.
3.11.6 ' Either caution-card the foliowing equipment or install L. equivalent permanent placards to require Nuclear Chemistry sample prior to discharge. !
- Neut. TK T-50 Drain ISOL (PMU-32)
{ EMERG Trench Sump PMP P-97 handswitch and pushbutton Trench Sump PMP P-122A handswitch and pushbutton Trench Sump PMP P-122B handswitch and pushbutton l .. I i 1 1 1
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l l l MESSAGE NO. 4 , i TO: Electricians / Mechanics FROM: Electrical Controller LOCATION: CV-2617 in the Unit 1 Penthouse l TIME: ~0940 1 MESSAGE: THIS IS A DRILL l l DO NOT initiate actions which may affect normal plant operations. l (Initialinspection of the MOV) (After removing the cover) l You discover that the roll pin on the toraue switch has been sheared. l \ (The electricians decide that the valve needs to be taken slightly off the closed seat manually. They engage the clutch and it shears the decluth shaft. The handwheel spins freely) l Note: SIMS on the Entergy Network has failed and is not available. (After finally locating and obtaining the proper psts, the electricians / mechanics retum to the valve). At 1210 the valve is successfully repaired.
- At 1215 the valve is successfully opened.
l l l I i
l MESSAGE NO. 5 l TO: Electricians / Mechanics FROM: Electrical Controller l LOCATION: CV-2617 in the Unit 1 Penthouse TIME: 0945 i MESSAGE: THIS IS A DRILL 1 l DO NOT initiate actions which may affect normal plant operations. (Initialinspection of the MOV) > (After removing the cover) l l You discover that the roll pin on the torque switch has been sheared. l l (The electricians decide that the valve needs to be taken slightly off the closed seat manually. They engage the clutch and it shears the decluth shaft. The handwheel spins freely) Note: SIMS on the Entergy Network has failed and is not available. (After finally locating and obtaining the proper parts, the electricians / mechanics return to the valve). , At 1210 the valve is successfully repaired. l l At 1215 the valve is successfully opened. 1 j l l l 1 L l
l MESSAGE NO. 6 TO: Inside AO FROM: Inside AO Controller LOCATION: South End ofUnit 1 Bowling Alley TIME: 0945 i MESSAGE: THIS IS A DRILL DO NOT initiate actions which may affect normal plant operations. I Notify the AO that there is a significant condensate leak near the inlet valve area on the , polishers about midway down. At this point he can't determine the exact location. but the leak has got to be at least 100 gpm. l l 1
MESSAGE NO. 7 TO: Inside AO i FROM: Inside AO Controller LOCATION: South End ofU-l Bowling Alley l TIME: -0945 I I I MESSAGE: THISIS A DRILL ' DO NOT initiate actions which may affect nonnal plant operations. Notify the IAO that the leak is getting significantly worse, and that water is spraying everywhere. He can't tell the exact source, and recommends securing the condensate , pumps. Water is pouring down into the basement and down the bowling alley, i l l l I l i
MESSAGE NO. 8 TO: AO FROM: AO Controller LOCATION: U-1 Bowling Alley TIME: -0945 MESSAGE: THIS IS A DRILL DO NOT initiate actions which may affect normal plant operations. When the condensate pu nps are secured: Notify the AO that the leak appears to be upstream of the "B" polisher manual inlet isolation. It is currently gravity draining the rest of the nter in the affected header, and slowing down. He can't exactly locate the source of the leak. It could be a weld failure, or just a leak in the pipe itself.
hESSAGE NO. 9 TO: WCO FROM: WCO Controller LOCATION: Unit 1 Auxiliary Building at P-7B TIME: 0950- l MESSAGE: THIS IS A DRILL DO NOT initiate actions which may affect normal plant operations. Notify WCO that P-7B is making an unusual squealing noise. There's oil spraying from the forward end of the pump and the pump is starting to vibrate. f
MESSAGE NO.10 TO: WCO FROM: WCO Controller LOCATION: Unit 1 Auxiliary Building at P-7B TIME: 0950 ! MESSAGE: THISIS A DRTLL I { DO NOT initiate actions which may affect normal plant operations. ' When P-7B is stepped, tell the WCO that the Inboard Pump Bearing Oil sightglass has i been broken off. There's no visible oil level looking down into the hole, and the bearing I housing is hot enough to burn your hand. l I
MESSAGE NO. I1 l TO: WCO FROM: WCO Controller LOCATION: Unit 1 Auxiliary Building at P-7A I TIME: ~1000 MESSAGE: THIS IS A DRILL DO NOT initiate actions which may affect normal plant operations. Ifused, tell the WCO that P-7A is running satisfactory. 1 l _ ________.___.___.___--.-__.__.___.___._____.__.-...._____________...__._._.__._m_ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ ___ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - . _ _ _ . . _ _ _ _ . . _ _ _ .
MESSAGE NO.12 TO: AO, Mechanics / Welders FROM: Mechanical Controller LOCATION: Condensate pipe area in the Unit 1 Turbine Building TIME: ~1000 MESSAGE: THIS IS A DRILL DO NOT initiate actions which may affect normal plant operations. (Upon arrival to the affected area) After investigation, you see a hole in the condensate pipe approximately 3" long and .5" wide. This hole was caused by erosion. (The mechanics / welders will begin to repair this pipe) At ~1400 the repairs to the condensate pipe will be successfully completed. f
MESSAGE NO.13 TO: Mechanics FROM: Mechanical Controller LOCATION: P-7B, Unit 1 Aux. Building TIME: ~1010 MESSAGE: THIS IS A DRILL DO NOT initiate actions which may affect normal plant operations. (Upon arrival at the pump) You see oil on the pump and floor. You smell burned metal similar to bearings being burned. Upon investigation it is determined that the inboard pump bearing has failed. Note: SIMS on the Entergy Network fails and is unavailable. After finally obtaining the proper parts the mechanics return to the pump. (The mechanics will begin to repair this pump) At 1300 the repairs will be successfully completed. l
1 MESSAGE NO.14 TO: WCO l FROM: WCO Controller I LOCATION: Unit 1 Auxiliary Building at P-7A l TIME: ~1015 ; I MESSAGE: THIS IS A DRILL j l
,DO NOT initiate actions which may affect normal plant operations.
P-7A has tripped for no apparent reason. l (WHEN the WCO resets P-7A) It was difficult to get it to stay latched. i k .
l l MESSAGE NO.15 l 1 TO: WCO FROM: WCO Controller I LOCATION: Unit 1 Auxiliary Building at P-7A TIME: ~1020 ! MESSAGE: THIS IS A DRILL DO NOT initiate actions which may affect normal plant operations. (2ND spurious trip ofP-7A) You don't know why P-7A tripped. l (WHEN he resets P-7A) The tappet didn't seem to drop in properly but it did reset. l IF questioned about the tappet, tell him it seemed like it was stuck somewhat, and finelly dropped into place. He recommends a mechanic come look at it. ' I i I i 1 i l l 1 l r
L MESSAGE NO.16 r TO: WCO FROM: WCO Controller LOCATION: Unit 1 Auxiliary Building at P-7A TIME * ~1040 MESSAGE: THIS IS A DRILL DO NOT initiate actions which may affect normal plant operations. (P-7A has tripped again, the mechanic is on-site to inspect the linkage) Tell the WCO that the mechanic slipped, and grabbed hold of the Trip Throttle Valve linkage. Because of this, it bent, and while trying to straighten it, the rod has sna
! I MESSAGE NO.16 TO: WCO ! FROM: WCO Controller l l LOCATION: Unit 1 Auxiliary Building at P-7A I TIME: ~1040 ; l l MESSAGE: THIS IS A DRILL , . 1 h 1 DO NOT initiate actions which may affect normal plant operations. ; (P-7A has tripped again, the mechanic is on-site to inspect the linkage) l Tell the WCO that the mechanic slipped, and grabbed hold of the Trip Throttle Valve l linkage. Because of this, it bent, and while trying to straighten it, the rod has snapped. ; i l l u ___ _ _ _ _ _ _ _ _ _ _ _ _ _ . - _ _ _ _ _ _ - - - - _ _ . - _ _ - - - - - - - _ - - - - . _ - _ _ .- - - . - - - _ - . - - _ - -
l MESSAGE NO.17 , TO: WCO/ Mechanic FROM WCO Controller i LOCATION: Unit 1 Auxiliary Building at P-7A l 1 TIME: ~1055 MESSAGE: THISIS A DRILL DO NOT initiate cetions which may affect normal plant operations. l Tell the WCO/ Mechanic that temporary repairs have been made to the P-7A linkage and that they think they can latch P-7A. { (Ifinstructed to latch P-7A) P-7A has successfully latched. i L__________-
1
- MESSAGE NO. I8 1
! TO: AO 1 FROM: AO l LOCATION: Area near the Cardox System on the 372' elevation of the Turbine Building. ! 1 TIME: ~1200 MESSAGE: THIS IS A DRILL l DO NOT initiate actions which may affect normal plant operations. You smell smoke and see that the area you are in is moderately smoky. i I 4 l l l l i l i I I 1 l L-___-_------------------_-----------_-----_-------------------------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -- ---- J
- MESSAGE NO.19 i
! TO: AO l l FROM: AO Controller LOCATION: Area near the Cardox System on the 372' elevation of the Turbine Building TIME: ~1205 MESSAGE: THIS IS A DRILL DO NOT initiate actions which may affect normal plant operations. l l I l After further investigation you see and smell smoke coming from the C-7 Main Generator Bearing Oil Vapor Extractor pump motor, i L_. . _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
i . i MESSAGE NO.20 TO: Fire Brigade Leader l l FROM: Fire Controller i LOCATION: Area near the Cardox System on the 372' elevation of the Turbine I Building ! TIME: ~1215 MESSAGE: THISIS A DRILL l DO NOT initiate t.ctions which may affect normal plant operations. (Upon arrival of the Fire Brigade) e You smell and see smoke coming from the C-7 Main Generator Bearing Oil Vapor Extractor pump motor. (After the Fire Brigade discharges their extinguishers)
. The fire is extinguished.
t l l l l ( l o_ ___- -- -
I MESSAGE NO. 21 i TO: Mechanics / Electricians at CV-2617 l l FROM: Mech / Elec Maintenance Controller LOCATION: Unit 1 Penthouse TIME: ~1215 , 1 l MESSAGE: THIS IS A DRILL ! DO NOT initiate actions which may affect normal plant operations. CV-2617 has been successfully opened. i l' l l I
MESSAGE NO. 22 TO: PJ & RW Manager FROM: TSC Lead Controller LOCATION: TSC TIME: ~1300 MESSAGE: THIS IS A DRILL DO NOT initiate actions which may affect normal plant operations. Scenario Note: This injected message is being issued solely to demonstrate the KI implementation process. This information is not consistent with other scenario data. Request that a survey be taken in the plume path onsite where the expected Iodine d concentration is approximately 4.0 E pCi/cc and the tirae in the plume for the H.P. survey team will be 2 minutes. Evaluate the need for K7 and make appropriate recommendations. Ensure that this survey team is disr,atched from the OSC. L__._____________.__._.__________._.______________ . _ _ . _ _ _ _ _ _ _ . _ . _ _ _ . _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ .
i i 1 MESSAGE NO. 23 ' TO: Control Room Status Board Communicator FROM: Lead Exercise Controller LOCATION: ControlRoom TIME: ~1400 MESSAGE: THISIS A DRTLL l DO NOT initiate actions which may affect normal plant operations. Terminate the drill. (Send message over the headset) i
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g n -<w > APPENDIX A INPLANT OPERATIONS DATA a I l l l i i-
J ta f" -l8l -l_11 111
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i 1 11 1111 111 1 ! ! ! 11 1 11 ! ! i 1 l l i l l i ! !Ti. l.l.i.l l i l i.l.i.l l.! ! ! _- _- ~ _. _ _ _ _
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_ I c 2 8 7 1 0 2 9 7 6 5 2 0 8 6 3 1 8 6 4 1 9 7 5 4 3 2 0 9 8 7 5 4 3 1 0 9 8 M 4 2 1 09 4 8 8 4 83 83 83 83 82 82 82 82 8 1 81 5 1 51 5 1 5 1 5 1 5 0 5 0 50 5 0 50 0 0 0 9 9 F 5 5 5 4 4 4 4 F 3 3 3 3 2 2 2 2 2 2 2 2 2 2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 E IM00 01 02 03 04 05 00 01 02 03 04 05 00 01 0 2 03 0 4 50 0 0 10 O!. 0 0 0 0 0 0 0 0 0 0 0 T : : : : : : : : : : : : : : : : : : : : . 3: 4: 5:0 :1 : 2 3 4 5 0 1 2 3 8 8 8 8 8 8 9 9 9 9 9 9 0 0 0 0 0 0 1 1 1 1 1 1 2 2 2 2 2 2 3 3 0 0 0 0 0 0 0 0 0 0 0 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 l
CONTAINMENT RADIATION MONITOR , I
l La O sa e C k mC m e4 .O .4 M ., e m .t e8 9
-- g
- 48 E e.
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- 4 4J C
O U M M M M M M M M M M M M M M M M M N N N N N N N N N N N N N N N N N N N , g C O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O i e k I e t 4 1 6 0 8 I I e i I I I e I e I e e i e e s e e e e e e I e t , g E M M M M M M M M M M M M M M M M M M M M M M M M M M M M M M M M M M M M i # ! % m e e e e e e m e m e e e e e m m O M @ m @ d w e e e e m N m o e W O P 43 5 9 9 9 9 9 9 9 9 9 9 9 W W W W *
- m m e O m et m e e N N w w m O @ W m v c O 9 @ M @ cg y ce e &
O. O. O. O. O. O. O. O. O. O. O. e O. O. O. O. O. e e. . M. . e. . e e. . m. e. M. e N. e N. e.
@ N @ N N N N N @ @ @ N N @ N N N O O N Y Y Y Y N N N @ @ @ b b e N m m O O O O O O' O O ,O O O O O O O O O O O O O O O O O O O O O O O O
- O rg N M .O .O O N M . O N M . . O N ,O , m rg N . .O O N M , m g.e .. o..
e e e a e e e e e e e m O O O O O O eg eg ce a c4 eg N N N N N N M M M M M M M.. O O O O O O O O O O O O eg eg c4 eg eg eg eg eg eg e c4 eg eg e ce eg c4 eg m eg n eg eg w L___-____________________________________________________________________________________________________
APPENDIX B IN-PLANT 4 AND ONSITE l RADIOLOGICAL DATA
This section only includes the maps for the affected areas of the plant. The radiation levels, contamination levels, and air activity levels for all other areas of the plant are "AS READ". Radiation levels are given in units of mrem /hr unless otherwise noted. j Contamination levels are given in units of counts per minute (cpm) above background on a disc smear (100 $ 2 cm2). If a large area smear (9 ft ) is taken, multiply the I given number by 100. . Air activity levels are given in units of cpm above background in the format " particulate filter / charcoal cartridge" (for example,100/250 means 100 cpm above background on the particulate filter and 250 cpm above background on the charcoal cartridge). 1 i f r
1 Radiation Levels Unit 1 Auxiliary Building, Elevation 335'(North End) Time Zone 2 Prior to 1100 AS READ
*1100 10-1130 ' ' ' 20 -
1200 25-1230 30-1300 30. 1330 : 25 : 1400 25
*1f letdown is secured, dose rates will remain 'AS READ".
l I
C
/
C
/ :
D D w e i 2 m m g e v
# p p I
' e c c ly a R f t
t
" ye r o s e s e 2 e
- k yl r n n o
- " el r v I t t # t s
I a I a a eh e to e
';Wt n ar Cu D
i g t e te t s n D t s D ,
- n a a e a e n - o ubm r P
%e .t e
m R e s o D l u R e s o i t n u o D l u g I t n u o D l e u g 3 BMQJo i o # P r o y e v S e p u I N xai RDT D C a D c- C C a k B C C a k " W u P A B R S I I D y t v i ta a it s D c g r a A i n e d a m/ e S M o. R
-_] __-]__-
P _ _ DN _ _- __-_ _ [_ B t a e
)
) mn c o mc qi t s a 0 0 co 3 s s (
r n g0 1 l r 2 c- Fai( da no 2 d ei nRt a at oc o a e t c pl a r D C h. 5 1 taS ra e Cl nt e g o osImrs i s s s s N wp*' T-15 2 T- e te et e E : to o o to
- nn e e nn I
I e e DDDD t l O S.
/
N i Dl O5 l V
'5 E 3
3
- i L
E
)
t a e m- sr X D U C ( e A p 36 t a l R U i e o B " d D s o o' t e n t o t e n c n t a o e n p { 8 s o Z i m A de wr C o p 36 C a S" " 3 F t oh nt c o e )m et s e e s3 o0 n r s e o is A wle r n gD (s D hte u n n i o A oJdae
,sc it p s n 5 s e R) et 8 n -i ra 2 e l
u aF R 1 r a+ e - s Tc h/ r t d n /aa cC
- ( r o
_ e mt ee c pnt e r 1 md oCRaR n0 r 0-2 hmt f. , i0 a e o e0 msfo s A 6 2-r 1 a < mDi l Ts l 1' s g reGc nas 0 a t F a1 r: I- -
- t b
e T iat s oe on3 d l t e unC1 e( r m_ [. s e s 0 p a
] i t
neDe6 oR diaa1 r3 o e/2 e n m t 1 IJ , }2, a m1 Dor i i M r
'r_i l -
. 2 RS*
- F l
Radiation Levels Unit 1 Auxiliary Building, Elevation 335'(South End) Time Zono2. Prior to 1 S READ 1000 AS READ - 1030 AS READ
*1100 6i 1130 ; "' 210"' '
1200 15: 1230 o :20:
- lf letdown is secured, dose rates in ZONE 1 will remain the same as the 1030 reading. The dose rates in ZONE 2 sill remain 'AS READ".
Air Activity Levels Unit 1 Auxiliary Building, Elevation 335'(South End) Time j r : - Prior to 1 9AS READ L , , 1000 , M A S R E A D E, 1030 rtAS READ >
*]100 :"JAS READ :
1130 12l!! RAS READ Mi!; 1200 4AS READb 1230 4 IAS READW ' 1300 WAS READ s 1330 D]AS... READ S :.:... l l l l l I
C
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D D w i e m m y e g s e p p c y a R f c c n r o t e 2 e e l kel y ev r o 1 s e u I n e ta D D te a t s n D t a t. s n D t a q e rl eh iyW- t n'o'r o b h r o i s v r e P e g a FeyDBa i M W'o C e t a e c e e o t p # R u u I u I u J # y e u I D t t
%e e e D D n u
D g
. n u g v P v S N xai
. t m s o
l a l a o l a k o l a k r u W r u P A _ RDT D C C C C B C C B S R S I I D . t y i t a i v s a t g D c n r A i d a a e e m/ R SM P o. DN _ _[ --_-_- _ Z _ _ _ ,___ __ _2 _ __ B t
)
a e ) mn m c o qi c s ta 0 0 c 3( sg 0 1 lo T - r n i( r a S !
- - ad ne Fd ei a o ms M^
U R bg t nR a at c a c pl a o o er t D" 4 taS r a e nt e g 31
- Clo oslmra l
D. i i P s s s s e e e e N l 2 t t t o o o o t E _. nnn e e ene I l DDDD~ O S.
/
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a t 3 B P P P D e X 6 ( U A 3 T- T
- O _
DB @ O R t e a I e U w s o d D t e t n Ei27 v o t c e n a n e s t n o p i i o de wr) sC h,w m V R o p E P t oh e mte C a p L E A vEF P
?
f nt c o e o0 n s s3 e 8 I S. i( sD e r e A 3- k wl r n s gD F E hte dd um n o V oer ae i t _ s n e aR) e s e t ma r a e l n u sF mm Rs a+ r e _ h r t a dr
/
m /a a( cG e mt e c o _ r pnt e - md oCRaR 2 n0 r _ 0-2 yl i 0 = e0 r 1
=
e s fo o s - A a s
< =a Di I g reGc F t L N P. i n a s tal 0 r d st e n b
e al e u onC1 t o 3
- a. _ r neDe6 s e s 0 oR t 1 i
t 3 o p d a i w2 Do 1
/ e n mr a a n1 M RS*
- F l
I Radiation Levels ! Unit 1 Auxiliary Building, Elevation 354' l I Zone 2 l j Prior to 1100 . ~AS READ -
*1100 _ g 10-i .. - [2 x 1300 jl i
130:
. . ~ .
l
]g LY .
l
*1f letdown is secured, dose rates will remain "AS READ".
l
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. c -. ye r r
e s e e 2 e yl r v o I chhno arCe n # o l t a I t a t a . t a g t eo r i s eg D D D e t n
, D e t
t s n t s n i ub h r e P a e a e e c t o p # u R u I u I t u Fye"3 '* i M Q JoO # y e u I D e D t n D n D v P v S N %. e a* s u g u l g r w r P A x t l a o l a o l a k o a k u u RD C D C C C B C C B S R S I I D s ' t s h g I r a
^ d m
e a e m/ R S M ' - - ~ E_[~_((- P" D _ _[- _ _ _ .. _ _ Z_ _ t B
)
a e
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mn c o m c qi t 0 s a s 0 c 3 ( g0l o r n1 r I adi(ne a F d ei a o ms t nR a c a l A l B N t a t c o o e pl a r aS r a e A 9 9 t nt e g E - o o ma r R - Cl l s l A C C , s s s s l l e e e e L t o t o o o t t A nnnn e e e e R DDDD c. t N
. O S.
E / G . OIL OR
- I
'4 5 0 )
" a 3
3 ,3 t e X. O 4 - - B ( U O S 4 R e
@U E
t A I T OE-T- g a. 1 R a U N 3 L-- e s d de o E O 3-1 t D t n P E o t c e n a O n e e i! j! t o s n p i o de w C r C A m o a e r 1 t e oh nt s s3 iwle r n e e )m o0 n s e c ot (s D s e n uWD oen ht l o e t i s ll l s e n a- F u aR) a r a mR t e V. h r s e+ r ms ad _ E / m/a( a cGr t o L e r mt pnt ee c _ 1 E md oCRaR n0 r 0 - i0 a e o e0 msfo 3 A I
.5h
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s
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t 0 _ t e n3 r o e
- b e u nC1 ._
m r s e s0 . u neDe6 oR t 1 _ N i t r3 o p i a a1 da e/ nmr e a RS*
- F m1 2 Do M
l
Radiation Levels ' Unit 1 Turbine Building, Elevation 335' Zone 1 M Zoney __ _}. Zone 4 i AS READ o AS READ AS READ . ; M. e. eee e e 2.5 . .
- AS READ AS READ M' 5.0 '
M AS READ AS READ M ' 7.5 M AS READ AS READ M 7.5 M ~AS R'EAD AS READ M 7.5 6 AS READ AS READ M 5.0 - 6 AS READ AS READ ' M 5.0 6 . AS READ AS READ [ ' 2.5 ,- lM AS READ' AS READ 2.5 M AS READ AS READ Contamination Levels Unit 1 Turbine Building, Elevation 335'
- Zone 1 -6 Zone 3 Zone 4 A$ READ M AS READ AS READ M. .e eee- e e AS READ iM AS RE,AD AS READ M ~AS READ _-6 , AS READ AS READ, M AS READ 6 600 AS READ M M AS READ 800 AS REAP M AS READ M .q 800 AS READ M AS READ 6 800 AS' READ M AS READ iM 800 AS READ M AS READ ' M 800 AS READ M AS READ . M 800 AS READ Air Activity Levels Unit 1 Turbine Building, Elevation 335' I
.M Zone 1 M. Zone 3 . _ Kone 4
.Me ee ' AS READ M AS READ AS READ AS READ M AS READ AS READ e- e AS READ M AS READ AS READ M ' AS READ .M , 100/100 AS READ M AS READ NM 150/200 AS READ l m M
AS READ AS READ
, [M
. fM 100/100 AS READ -
AS READ AS READ i M AS READ M AS READ AS READ ( _M AS READ _ M AS READ AS READ M AS READ M AS READ AS READ
# p p c a e t
t c c n ly yr R s s e 2 e k yl e r n te n i te # te u el r v o I a I a . a a q eh e to s D lyW n ra Ce r e te D t s D t s D e r t i v t a e a e n e n F i ai o ub ht- r. r R u R u I u I e o e u yD D M QJoO p
%e e m
e s D l e s D t n u D g t n u D g e v r y e v S u o l l o o r RDT
- x. tai D C a
D a a k o la k u w r u P C C C B C C B S n S l l y ta a i i t t v - D c r a A e m/ S M o. P DN - _- ~ _- _- _- -
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Radiation Levels Unit 1 Turbine Building, Elevation 354' _6 Zone 1 +@ Zone 3 _ _ _ . ZoneL4_. M AS READ -M AS READ AS READ . M AS READ 7 -M . AS READ , AS READ M 8 _M AS READ AS READ M 15 M. AS READ. 'AS READ M 15. M y READ .
'AS READ M 15 AS READ ~ AS READ M 10 - . M %S READ AS READ M. 10 M AS READ' - AS READ
_M 8 (M ' AS READ AS READ-M 8 AS READ AS READ Contamination Levels Unit 1 Turbine Building, Elevation 354' M Zone 1 [ M Zone 3 ' Zone 4 iM AS READ li 6 AS READ AS READ M AS READ c-
- AS REA'D . AS READ dlIeM AS READ
- AS READ AS READ eDIeM 600* M 600 AS' READ 5_IeM 800 6 800 AS READ
_M 800 .ei .,800 AS READ __ M 800 :
- 8p0 AS READ 800 M 800 -
AS READ sg 800 , M 800 .
'AS READ
*I S 800-
.6 *800 AS READ Air Activity Levels ,
Unit 1 Turbine Building, Elevation 354' Zone 1 M Zone 3 _ _ Zone 4 M, AS READ . AS READ AS READ
._ M AS READ AS READ AS READ M AS READ M AS READ y. AS READ
.M 100/100 [M AS READ AS READ eM 150/200 6 . AS READ AS READ
- M p 100/100 M AS READ AS READ EM ' AS READ M. AS READ AS READ M_ AS READ MsAS READ AS READ M AS REA.D AS READ A$ ' READ
_ M ' AS R6AD _ _ _ _ _M AS READ AS READ
m m y g e p p c a R
. c c n ly r t
e k y e r s n e e 2
# e u el v o ta t
a q eh o r i s I e D t s D t s D r ilyWt n e Ce : n t a n e n e F ai - o b ht r o e p R I u I u yDBM JoO # y u
%e D e t t e e n u
D g n D g e v P v S t m s u r W r P o o l l xai a k o a k u u RDT D C C C B C C B S R S H y t i a t v 2 it D c r A e e m/ SM P o. D N _ -
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Onnito Radiological Data This section contains the radiological information for the plant site outside of plant buildings. Centerline and Plume Edge radiation levels are given in units of mrem /hr unless otherwise noted. Airborne l' ' air activity levels are given in units of counts per minute above background. l l l 1 l l l I l l
I I Onsite Radiological Data l ANO Plant Site { Centerline Plume Edge Airborne l l Radiation Raalation Air Activity I Time Levels Levels Levels Prior to 1050 AS READ AS READ AS READ j 1050 158 0.05 29000 1100 283 0.05 35000 1110 288 0.05 27000 1120 282 0.05 21000 1130 304 0.05 19000 1140 392 0.05 21000 1150 359 0.05 16000 1200 381 0.05 15000 1210 466 0.05 17000 1220 401 0.05 13000
,.,1230 757 0.05 22000 1240 675 0.05 18000 1250 501 0.05 12000 1300 547 0.05 12000 1310 649 0.05 14000 1320 859 0.05 17000 1330 727 0.05 13000 1340 521 0.05 9000 1350 AS READ AS READ AS READ 1400 AS READ AS READ AS READ l
A T D A D n E , co i r a T L , - ; I - wy3 A - A C , s ' R I G O O '< P E L
" c g '< +
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- E N T E
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R , d g i n d g N E l E M . E e t r e n E e A L m e m P E u C l u e P l P m O u N l P A N O I T A C O L
APPENDIX C RADIOCHEMISTRY DATA l
l RCS RADIOCHEMISTRY DATA
- I l
l
E- -E -E-E- E - -E -E-E- E- -E-E- E- E- -E+E +E + 1 0 6 8 4 1 7 4 0 6 1 7 3 9 5 1 7 3 1 7 3 9 5 1 7 3 9 4 0 6 2 8 4 EE + E+ E+E+E+E+E +E + EE + E+ E+E+E+E+ 3 1 12 3 8 7 5 3 41 3 3 9 3 9 93 2 9 929 1 9 91 0 0 9 0 9 9 2 1 1 0 0 0 98 98 88 88 88 7 7 6 6 9 8 8 9 9 9 9 9 9 8 8 8 8 I 3 2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 2 2 3 3 3 3 3 3 3 3 3 3 3 3 3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 5 --E - - - - - -E -E-E- E- -E-E- E- E- +E E + E+ E+E+E+E+E+E +E + + E+ E+E+E+E+E +E 3 9E2E 6 8 5E E E 3 7 3 0 7 5 3 1 0 9 EE 8 8 0 6 4 5 5 5 5 7 0 5 3 5 1 2 8 1 1 6 4 6 2 1 0 7 4 0 7 4 1 8 4 1 8 5 0 8 5 0 3 41 53 1 6 06 2 3 2 9 6
- 0 5 1 7 4 1 1 0 0 0 9 9 9 8 8 8 7 7 9 3 8 3 7 9 2 9 2 5 7 0 e . . . . . .
X 5 4 4 3 3 3 3 3 3 3 2 2 2 2 2 2 2 3 8 1 1 2 2 3 3 3 4 4 4 5 5 5 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 4 4 4 4 4 4 4 4 4 4 4 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0
- - - - - - - - - - - - - - - - - + + + + + + + + + + + + + + +
3 E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E 3 6 1 6 9 7 9 5 9 4 8 3 8 2 7 2 6 1 5 7 0 7 6 8 7 0 0 5 7 4 8 7 3 1 8 5 4 6 1 8 8 7 7 6 6 5 5 4 4 3 3 9 0 7 8 5 3 1 9 6 2 8 4 9 4 9
- 6 3 0 7 5 2 2 2 2 2 2 2 2 2 2 2 2 7 8 7 6 1 3 5 6 8 0 1 3 4 6 e .
7 X 3 3 3 2 2 2 2 2 2 2 2 2 2 2 2 2 2 3 5 7 9 1 1 1 1 1 2 2 2 2 2 2 2 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 m - - - - - - - - - - - - - - 0 - +0 +0 +0 0 + 0 + +0 +0 +0 +0 +0 +0+ 0+ 0 04 0
+
3 E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E 3 2 5 5 9 6 6 3 0 6 2 8 848 07 76 3 9 5 7 4 1 8 5 2 9 6 3 1 8 6 3 1 9 1 4 6 0 5 2 0 0 0 9 9 8 6 6 5 3 1 8 6 4 1 9 7 5 2 0 8 6 3 1 a - 9 7 6 4 3 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 0 0 0 0 9 9 9 9 9 8 8 8 t e . . . . . . . . . . . . . . . . . a X 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 7 7 7 7 7 7 7 6 6 6 6 6 6 6 6 D 8 9 y 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 0 0 0 0 0 0 0 0 0 0 9 r 1 t m + + + + + + + + + + +0 + 0+ 0 + 0 0 + +0+ 0 + +0 0 0 0 0 0 0 0 0 0 0 0 0 0
+ + + + + + + + + + + +
s 1 E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E 8 0 0 0 0 0 0 0 0 0 9
,i 3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 9 1 7 3 9 5 0 6 2 8 4 0 6 2 8 4 9 m 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4 2 1 1 0 0 0 9 9 8 8 8 7 7 6 6 x 1 e e
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. w 3d C 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0
#4 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4M + + + + + + + + + + + + +- + + + + + + + + + + + + + + + + + + + + + d +
C M M M M M M M M M M M M M M M M M M M M M M M M M M M M M M M M M M M M m O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O m O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O M g C. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. j M C O O O O O O O O O O O O O O O O D O O O O O O O O O O O O O O O O O O P o 8 8+ 8 8+ 8 8+ 8+ 8+ 8 8 8 8 8 8+ 8+ 8 8 8 8+ 8 8 8 8 88 8 8 8+ 8+ 8 8 8+ 8+ 8+ 8 8 8
+ + + +
M M M M M M M M M M M M M M M M M M M M M M MM M M M M M M M M M M M M w O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O m O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O M g O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. M O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O 0 C 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8+ 0 0 0
+ + +
0 0
+ +
0
+
0 0
+ 4 0
+
0
+
0
+
0
+
0 0 0 0 0
+ + + + +
0 0 0 0
+ + + +
0 0 0 0 0 0 0 0 0 0 0 0 0 0
+ + + + + + + + + + + + + +
M M M M M M M M M M M M M M M M M M M M M M M F M M M M M M M M M M M M m O O O O O O O O O O O O O O O O O O O O O O r O O O O O O O O O O O O O m 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 M g O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. M O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O C 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 O O O O O O O O O O O O O O O O O O O O O O O O U O O O O O O O O O O O
+ + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + + +
M M M M M M M M M M M M M M M M M M M M M M M M M M M M M M M M M M M M N O O O O O O O O O C C O O O O O O O O O O O O O O O O O O O O O O O O O m O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O M g O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. M O O O O O O O O O O O O O O O O OO O O O O O O O O O O O O O O O O O'O M E 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 O M N m w m O M N m v W C H N m m O M m w W O M m w W O M N m..w m M.
- g. w.. N.. .. N..
m e s m e m m e e m e m O O O O O o M M M M M M N N N N N N M m m m M M C O O O O O O O O O O O M -4 M M M M M M M M M M M M M M M M M M M M M M I
APPENDIX D l l METEOROLOGICAL DATA i 1 l
a 8 t 9 a 9 D
- 1 l
,ca 8
C 9 1 i g t lo 1 ; u r o g u e A te a M t e h 8 2 7 1 T 0 7 2 1 3 1
. . . 9 4 7 . 0 2 4 7 8 5 1 2 9 0 1 4 0 0 8 4 1
9 3 8 3 a 0 9 0 1 0 0 1 1 0 0 00 0 1 0 0 0 1 1 0 2 2 1 1 2 1 1 0 m1 1 1 1 1 1 1 1 9 1 1 1 1 1 1 1 9 1 1 1 1 1 1 1 1 1 1 1 1 9 1 1 10 1 0 g i S _ S 0 8 1 1 3 6 6 4 0 9 1 9 5 7 7 3 1 1 6 1 6 8 5 0 1 8 4 0 4 3 2 8 3 8 0 W 5 4 6 5 6 5 4 5 5 5 5 4 5 4 5 6 6 5 4 5 5 5 5 6 6 5 6 5 5 6 6 5 5
)
m o 0 0 0 00 0 0 0 0 r 0 0 00 0 0 00 0 0 0 00 0 0 01 00 0 0 0 0 0 0 0 rf . e( 6 3 8 0 8 4 7 9 6 2 2 2 2 2 2 2 2 2 4 3 8 5 9 7 4 3 7 3 7 8 7 5 3 6 9 7 4 7 2 3 7 8 w 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 oD L W S 2 7 9 3 0 9 8 0 9 6 9 3 7 3 0 1 8 9 1 6 8 9 2 8 9 1 1 1 1 3 8 1 1 W 5 5 4 7 7 4 5 5 4 5 5 5 4 f 5 6 4 4 5 5 5 5 5 5 5 7 8 5 5 5 5 6 5
)
m o 0 0 0 0 0 00 0 0 r . 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 rf 4 3 0 6 3 6 5 1 4 5 7 6 3 6 2 e( p 2 2 3 2 2 2 2 2 2 2 2 2 2 2 2 4 8 5 6 4 3 5 3 1 4 6 9 5 5 5 9 0 7 pD 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 3 2 2 UW E _ M 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 I T 01
- : 2: 3: 4: 5: 01 : :2: 3: 4: 5: 01 : :2 :3: 4: 5: 0: 1: 2: 3 : 4: :5 :01: 2: 3: 4: 5 : : 01: 2: 3
- 8 8 8 8 8 8 9 9 9 9 9 9 0 0 0 0 0 0 1 1 1 1 1 1 2 2 2 2 2 2 3 3 3 3 0 0 0 00 0 0 0 0 0 0 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
,11
No data saved for 8:00:00 CDT 19-AUG-98
.DDS Bulletin # 870 8:37:39 GMT 19-AUG-98 915 FPUS$4 KLZK 100834 WSIPPS:100836 ZFPAR ARKANSAS ZONE FORECASTS NATIONAL WEATHER SERVICE LITILE ROCK AR 400 AM CDT WED AUG 191998 ARZOO3>007 012>016-023 024-102100-BAXTER-BOONE-CLEBURNE-FULTON INDEPENDENCE-IZARD-MARION-NEWTON-SEARCY-SHARP-STONE-VAN BUREN-
- 400 AM CDT WED AUG 191998
.TODAY... PARTLY CLOUDY THIS MORNING... SUNNY THIS AFIERNOON. HUMID WITH A 40 PERCENT CHANCE OF' THUNDERSTORMS. HIGH IN THE UPPER 80S. NORTH WIND 5 TO 10 MPH. AVERAGE RAINFALL 1/4 INCH.
. TONIGHT... PARTLY CLOUDY. A 20 PERCENT CHANCE OF THUNDERSTORMS. LOW NEAR
- 70. NORTIEAST WIND 5 TO 10 MPH. AVERAGE RAINFALL 1/10 INCH.
. THURSDAY... PARTLY SUNNY AND HUMID WITH A 30 PERCENT CHANCE OF THUNDERSTORMS. HIGH IN THE 90S. NORTHEAST WIND 10 TO 15 MPH.
S$ ARZO21-022-030-031 037>041 -102100 CONWAY-JOHNSON-LOGAN-MONTGOMERY-PERRY-POLK-POPE-SCOTT-YELL-400 AM CDT WED AUG 191998
.TODAY. PARTLY CLOUDY THIS MORNING...SUNNYTHIS AFTERNOON, HUMID WITH A 5 PERCENT CHANCE OF THUNDERSTORMS. HIGH IN THE 90'S. NORTHEAST WIND 5 TO 10 MPH. AVERAGE RAINFALL 1/4 INCH.
. TONIGHT... PARTLY CLOUDY. A 20 PERCENT CHANCE OF THUNDERSTORMS. LOW NEAR
- 70. NORTHEAST WIND 5 TO 10 MPH. AVERAGE RAINFALL 1/10 INCH.
. THURSDAY... PARTLY SUNNY AND HUMID WITH A 30 PERCENT CHANCE OF THUNDERSTORMS. HIGH IN THE 90'S. NORTH WIND 10 TO 15 MPH.
l $$ ARZ008 009 017 018 025>028-032>036-042>073-102100 ARKANSAS-BRADLEY-CALHOUN CLARK-CLAY-CLEVELAND-COLUMBIA-CRAIGHEAD-CRITTENDEN-CROSS-DALLAS-DESHA-DREW-FAULKNER GARLAND-GRANT-GREENE-HEMPSTEAD-HOT SPRING-HOWARD. JACKSON-JEFFERSON-LAFAYETTE-LAWRENCE-LEE-i LINCOLN-LITTLE RIVER-LONOKE-MrI.T_FR-MISSISSIPPI-MONROE-NEVADA-OUACHITA-PHILLIPS-PIKE-POINSETT-PRAIRIE-PULASKI RANDOLPH-SALINE-l- SEVIER ST. FRANCIS-UNION-WHITE-WOODRUFF- ! 400 AM CDT WED AUG 191998 l
.TODAY... CLOUDY THIS MORNING... PARTLY SUNNY THIS AFTERNOON. HUMID WITH A 10 PERCENT CHANCE OF THUNDERSTORMS. HIGH FROM 90 TO 95. NORTH WIND 10 TO 20 MPH. AVERAGE RAINFALL 1/10 INCH.
.TONIGiff... PARTLY CLOUDY. A 20 PERCENT CHANCE OF THUNDERSTORMS. LOW FROM
--__--,------,-,,--n, - - - - - - . - - . - - - , . - - , - - - - - - - - - . - - - - - - - - . - , , , - . - - - - - , - - -
70 TO 75. NORTHEAST WIND 5 TO 10 MPH. AVERAGE RAINFALL 1/10 INCH.
. THURSDAY... PAR 1LY SUNNY AND HUMID WITH A 30 PERCENT CHANCE OF THUNDERSTORMS. HIGH FROM 90 TO 95. NORTH WIND 10 TO 15 MPH.
l I L
i l APPENDIX E RADIOLOGICAL RELEASE DATA 1 i l I l I I
_ 0 0 0 0 0 09 9 9 0 0 0 0 0 0 0 0 6 6 6 6 6 6 7 7 7 7 7 7 7 7 7 7 7 q 1 1 1 1 1 1 0 001 1 1 1 1 1 1 1 0 0 0 0 0 0 0 00 0 e - - - - - - - - - - - - - - - - - - - - - - - - - - 0-0 0 0 7 cE E E E E E E E E E E E E E E E E E E EE E E E E E E E E E E E E E 3 e4 4 4 4 4 4 6 5 8 4 2 4 7 5 4 1 1 7 5 7 2 9 2 3 9 4 5 3 8 0 3 5 1 s1 1 1 1 1 1 3 1 3 5 0 6 9 6 4 1 5
- /1 1 1 1 o1 . . .
1 1 5 3 1 9 8 8 04 9 5 1 3 6 5 0 8 4 07 5 2 1 3 8 4 6 1 6 3 3 4 2 9 7 2 4 7 0 5 1 7 5 4 2 5 4 C C3 3 3 3 3 3 1 1 1 9 8 7 7 6 5 5 5 2 2 1 1 1 1 9 8 7 6 5 5 4 4 3 3 3 0 0 0 0 0 0 8 8 8 8 8 8 8 8 8 8 8 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 1 1 1 1 1 1 0 0 0 0 0 0 000 00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 q - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ecE E EE E E E E E E E E E E E E E E E E E E E E E E E E E E EE E 1 e4 4 4 4 4 4 8 6 0 6 4 3 1 9 5 8 8 9 5 8 1 1 8 3 6 4 0 1 9 2 1 5 4 8 3 s1 1 1 1 1 1 1 3 7 1 7 4 2 0 0 0 1 4 3 2 3 4 5 8 1 5 0 5 0 7 4 1 9 7 - 1 /1 1 1 1 1 1 4 2 0 9 7 6 5 4 3 2 1 3 1 9 7 5 3 1 0 8 7 5 4 2 1 0 8 7 - - L . . . . . . I C3 3 3 3 3 3 3 3 3 2 2 2 2 2 2 2 2 5 5 4 4 4 4 4 4 3 3 3 3 3 3 3 2 2 - 8 _ 1 5 5 5 5 5' 5 4 4 4 4 4 4 4 4 4 4 4 00000 0 0 001 1 1 1 1 1 1 1 9 q 0 00 0 0 0 0 0 000 0 00000 0 00 0 0 0 000 0 0 0 0 0 0 0 0 _ 1 a e - - - - - - - - - - - - - - - - - + + + + + + + + + + + + + + + + - t 3 cE E E E EE E E E E E E E E E E E E EE E E E E E E E E E E E E E E 3
,Da 31 e7 7 7 7 7 7 8 8 2 2 7 6 07 9 4 2 4 1 2 9 2 2 1 8 6 8
_ 3 5 5 2 6 8 8 9 s2 2 2 2 2 2 1 00001 3 4 6 9 2 4 8 8 4 8 8 5 8 9 5 3 07 4 0 6 2
' 19 - /88 8 8 8 8 1 09 8 7 6 5 4 3 2 2 4 4 4 4 3 2 1 9 7 0 1 2 2 3 4 4 5
_ G ei . . - t N I X C4 4 4 4 4 4 3 3 2 2 2 2 2 2 2 2 2 2 3 4 5 6 7 8 8 9 1 1 1 1 1 1 1 1 - r P ' _ u - gS u _ -A _ 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 _ q 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 e - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - _ 7 cE E E E E E E E E E E E 3 COO O O0O4 3 7 3 3 1 8 3 8 0 8 1 /O O OO0O6 4 0 9 5 5 E E E E E 5 5 1 4 0 E E E E 5 6 8 4 6 2 2 4 7 E 9 EE E E E 0 7 8 7 2 4 8 8 1 5 E E E E 6 4 5 8 7 7 3 4 0 E 6 E E 06 0 2 L oC O. O. O. D. 0. O. 8 . 43 3 6 0 C u2 2 2 2 2 2 9 8 7 6 5 5 4 4 3 3 3 5 1 8 5 3 5 3 1 6 2 1 1 1 9 8 1 1 7 6 5 4 4 3 7 1 6 2 9 6 4 3 3 2 2 2 2 2 2 - 1 1 1 1 1 1 9 9 9' 9 9 9 9 9 9 9 9 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 1 1 1 1 1 1 0 0 0 000 00 000 0 0000 0 0 00 0 0 0 00 0
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 0 q
_ ecee E E E E2 E EE E E E EE E E E E E E E 5 E E E E E E E E E E E - 1 cO0 0 00O5 9 1 3 1 7 9 7 0 8 0 6 8 5 8 6 9 7 9 6 6 1 9 2 7 6 9 4 _ 3 /O0 000O9 7 7 7 8 9 1 4 8 1 6 3 9 6 3 1 9 8 7 7 7 8 8 0 1 3 5 8 6 5 0 9
- C O. .0. 00 0. O. .1 0 9 8 7 6 . .
1 i 4 4 3 4 2 1 7 6 5 4 3 2 1 1 0 9 8 7 I u2 2 2 2 2 2 2 2 1 1 1 1 1 1 1 1 1 3 3 3 3 2 2 2 2 2 2 2 2 2 2 1 1 1 6 6 6 6 6 6 5 5 5 5 5 5 5 5 5 5 5 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 q 0 0 0 0 0 0 0 0 0 0 0 0 0 0 C 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 e - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 3 cE E E E E 3 c00 0 0003 1 /00 0000O 3 EE E E E E E E E E 5E2 E1 3 7 2 4 0 9 0 6 03 8 2 7 2 7 2 6 5 5 4 4 EE E E E 0 6 9 09 7 3 7 09 5 2 8 5 0 E EE E E 7 5 3 2 2 7 3 7 9 9 6 2 7 2 7 E E E E E 4 9 6 7 1 7 3 8 1 3 E E 0 4 3 1
- i 1 .1. 1 eC 1 1 1
. . . . O. 98876 2 7 1 6 04 8 0 E u3 3 3 3 3 3 2 1 1 1 1 1 1 1 1 1 1 1 2 2 34 4 5 5 6 6 7 7 8 8 9 9 9 1 1 E
M0 0 0 00 00 0 00 0 0 0 0 0 0 0 0 00 0 0 0 0 00 0 0 0 0 0 0 0 0 0 0 I 01 2 3 4 5 01 2 3 4 5 01 2 3 4 5 01 2 3 4 5 01 2 3 4 5 01 2 3 4 5 T : : : : : : : : : : : : : : : : : : : : : : : : : : : : : : : : : : : : 8 8 8 8 8 8 9 9 9 9 9 9 00 0 0 0 0 1 1 1 1 1 1 2 2 2 2 2 2 3 3 3 3 3 3 0 00000 0 0 0 0 0 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
s 8 e
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3 , e C 9 a 1 c o l t n Re u g u o A it S e 7 7 7 7 7 7 7 7 7 7 8 8 8 8 8 8 8 3 3 3 3 3 3 3 3 3 3 3 3 4 4 4 4 t 0 0 0 0 0 aq -0 - - - - - 0 0 0 0 0 0
- - - - - 0 0 0 0 0 0 0 0 00 0 0 0 0 0 0 0 0 lu eE EEE E E E EEE E E E E E EE E E E E E E E E E E E E E E E E 5 7 1 5 8 7 1 8 9 5 0 3 8 04 7 3 6 1 6 5 9 5 8 9 0 4 5 0 5 1 5 4 1 c7 3 9 8 8 0 4 5 2 4 0 9 4 6 3 0 6 0 7 3 11 0 7 2 2 7 7 9 4 2 4 5 9 5 1 5 i3 5 2 08 7 5 5 3 1 0 8 9 1 5 05 2 8 5 05 2 9 6 4 2 t 1 .
1 0 1 2 4 8 r a -o 2 2 2 1 1 1 1 1 1 1 8 7 7 6 6 5 5 4 4 3 3 2 2 1 1 1 1 1 1 9 8 7 6 6 P c
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/e E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E i n1 7 5 1 9 6 8 2 9 05 2 9 7 3 8 0 0 1 7 3 5 2 3 7 4 2 2 2 1 0 7 3 7 7 5 Ci3 5 4 8 5 7 2 5 6 04 0 6 4 3 2 3 4 5 1 4 3 4 6 9 4 0 7 5 4 4 4 6 8 1 5
( d1 5 0 5 1 7 4 4 2 1 9 8 6 5 4 3 2 1 008 5 2 9 6 4 2 9 7 5 3 1 9 7 o - . . . . . . . eI I 5 5 4 4 3 3 3 3 3 2 2 2 2 2 2 2 2 1 1 9 9 9 8 8 8 8 7 7 7 7 7 6 6 6 6 6 t a - R q4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 e0 - 0 0 0 0 0 0 0 0 00 0 e - - - - - - - - - - 0- 0-0 0 +0 +0 + 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0
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s 3 E E EE E E E E E5E E E E E EE E E E E E E E E E E E E E E E EE E as3 9 6 5 2 5 9 7 5 5 5 4 3 0 5 8 8 5 9 0 1 4 0 0 6 8 8 3 6 5 2 6 7 5 1 4 5 ee1 3 7 5 7 2 0 3 1 0 0 1 3 6 9 3 8 4 8 3 3 9 2 1 6 8 7 6 4 2 0 7 4 1 8 4 06 2 9 6 2 086 ~ l m - 5 4 2 08 7 5 4 6 8 9 9 0 09 8 01 2 3 4 4 5 ea e 6 6 5 5 5 5 R G E 5 5 4 4 3 3 5 4 4 4 4 2 3 4 5 7 8 8 9 1 1 1 1 1 1 1 1 1 1 1 E M000 000 00 0 0 0 0 00 0 0 0 0 000 0 0 0 000 0 0 000 0 0 0 0 h I 01 2 3 4 5 01 2 3 4 5 0 1 2 3 4 5 01 2 3 4 5 0 1 2 3 4 5 0 1 2 3 4 c T : : : : : : : : : : : : : : : : : : : : : : : : : : : : : : : : : : : : n 8 8 8 8 8 8 9 9 9 9 9 9 000 000 1 1 1 1 1 1 2 2 2 2 2 2 3 3 3 3 3 3 a 0 0 0 0 0 0 0 0 0 0 0 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 r B F l
REX - 98 August 19,1998 Plume Data I l l l E---_----------------------
REX-98 August 19,1998 Plume Update 1 Time Stamp 1050 - 1100 Distance Gamma (mrem /hr) Iodine , Miles Centerline Plume Edge Net cpra 0.62 158 0.05 28571 l 1.00 1.45 2.00 2.50 3.00 3.45 4.00 4.50 5.00 6.00 7.25 8.00 9.00 10.00 _ _ _ -w-
PLUME CENTERLINE Plume Update Number ------------------------------- 1 Plume Update Time Stamp --------------------------- Initial Release ---------------------------------__ Mode ---------------------------------------------- CENTERLINE DOSE RATES DOSE RATES RADIUS SECTOR SEGMENT THYROID TEDE (31) (arem/hr) (aren/hr) 0.62 10 1 1.283E+03 2.041E+02 l l l j
- PLUME CENTERLINE DATA )
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REX-98 August 19,1998 Plume Update 2 Time Stamp 1100 - 1110 , 1 Distance Gamma (mrem /hr) Iodine Miles Centerline Plume Edge Net cpm 0.62 283 0.05 35268 1.00 223 0.05 28795 1.45 107 0.05 16138 2.00 , 2.50 _ 3.00 , ,_ 3.45 __ 4.00 4.50 5.00 _. 6.00 7.25 8.00 9.00 10.00 l
i ! PLUME CENTERLINE Plume Update Number ------------------------------- 2 Plume Update Time Stamp --------------------------- I n it i a l Re l e a s e --------------------.--------------- Mode ---------------------------------------------- l CENTERLINE DOSE RATES DOSE RATES RADIUS SECTOR SEGMENT THYROID TEDE l (mi) (aram/hr) (arem/hr) . 0.62 10 2 1.580E+03 3.391E+02 I 1.00 10 1 1.287E+03 2.685E+02 1.45 10 1 7.234E+02 1.325E+02 1 l ! 1 1 l i l PLUME CENTERLINE DATA Page 1 of 1
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0.62 288 0.05 26786 1.00 251 0.05 24107 1.45 141 0.05 15513 2.00 70.3 0.05 9531 2.50 3.00 3.45 4.00 4.50 . 5.00 6.00 7.25 8.00 9.00 10.00
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- 1.00 10 2 1.075E+03 2.890E+02 q 1.45 10 2 6.950E+02 1.658E+02 i 2.00 10 1 4.275E+02 8.563E+01 l
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REX-98 August 19,1998 Plume Update 4 Time Stamp 1120 - 1130 Distance Gamma (mrem /hr) Iodine Miles Centerline Plume Edge Net cpm 0.62 282 0.05 20848 1.00 268 0.05 19955 1.45 172 0.05 13862 . 2.00 87 0.05 8460 2.50 54 0.05 6429 3.00 35 0.05 4888 3.45 4.00 4.50 . 5.00 6.00 7.25 _ 8.00 9.00 10.00 l l
PLUME CENTERLINE Plume Update Number ------------------------------- 4 Plume Update Time Stamp --------------_-----_------ Initial Release ----------------------------------- Mode ---------------------------------------------- CENTERLINE DOSE RATES DOSE RATES RADIUS SECTOR SEGMENT THYROID TEDE (mi) (aren/hr) (aram/hr) 0.62 10 4 9.343E+02 3.146E+02 1.00 10 3 8.939E+02 2.991E+02 1.45 10 3 6.210E+02 1.942E+02 2.00 10 2 3.793E+02 1.006E+02 2.50 10 2 2.880E+02 6.408E+01 3.00 10 1 2.191E+02 4.235E+01 1 I l r 1 l PLUME CENTERLINE DATA Page 1 of 1
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REX-98 August 19,1998 Plume Update 5 Time Stamp 1130 - 1140 Distance Gamma (mrem /hr) Iodine Miles Centerline Plume Edge Net epm 0.62 304 0.05 18594 1.00 297 0.05 18192 1.45 200 0.05 12857 2.00 97 0.05 7188 2.50 67 0.05 5625 3.00 45 0.05 4509 3.45 32 0.05 3884 4.00 21 0.05 3058 4.50 , 5.00 6.00-7.25 8.00 9.00 10.00
l l PLUME CENTERLINE Plume Update Number ------------------------------ 5 l Plume Update Time Stamp --------------------------- Initial Release ----------------------------------- Mode--------------------------------------------- CENTERLINE DOSE RATES DOSE RATES l RADIUS SECTOR SEGMENT THYROID TEDE (mi) (area /hr) (arem/hr) 0.62 10 5 8.332E+02 3.332E+02 1.00 10 4 8.155E+02 3.254E+02 1.45 10 4 5.758E+02 2.200E+02 2.00 10 3 3.221E+02 1.082E+02 2.50 10 3 2.520E+02 7.628E+01 3.00 10 2 2.015E+02 5.255E+01 3.45 10 2 1.737E+02 3.858E+01 4.00 10 1 1.369E+02 2.574E+01 J i l l r i PLUME CENTERLINE DATA Page 1 of 1
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REX-98 August 19,1998 Plume Update 6 Time Stamp 1140 - 1150 Distance Gamma (mrem /hr) Iodine Miles Centerline Plume Edge Net cpm 0.62 392 0.05 20446 1.00 368 0.05 19308 1.45 241 0.05 13080
;{ 2.00 110 0.05 6741 2.50 77 0.05 5134 3.00 51 0.05 3906 3.45 39 0.05 3348 4.00 28 0.05 2902 4.50 20 0.05 .
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PLUME CENTERLINE Plume Update Number ------------------------------- 6 Plume Update Time Stamp --------------------------- t Initial Release ----------------------------------- 1 Mode ---------------------------------------------- 1 CENTERLINE DOSE RATES DOSE RATES RADIUS SECTOR SEGMENT THYROID TEDE (mi) (aren/hr) (area /hr) 0.62 10 6 9.163E+02 4.237E+02 1.00 10 5 8.648E+02 3.982E+02 1.45 10 5 5.864E+02 2.608E+02 i 2.00 10 4 3.017E+02 1.204E+02 2.50 10 4 2.299E+02 8.502E+01 3.00 10 3 1.746E+02 5.739E+01 3.45 10 3 1.504E+02 4.443E+01 l 4.00 10 2 1.296E+02 3.249E+01 d.50 10 1 1.151E+02 2.411E+01 5.00 10 1 9.451E+01 1.689E+01 l l l ( l I PLUME CENTERLINE DATA Page 1 of 1
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REX-98 August 19,1998 Plume Update 7 Time Stamp 1150 - 1200 , Distance Gamma (mrem /hr) Iodine Miles Centerline Plume Edge Net cpm 0.62 359 0.05 16138 1.00 359 0.05 16138 1.45 251 0.05 11696 2.00 132 0.05 6808 2.50 92 0.05 5045 3.00 58 0.05 3571 3.45 45 0.05 3013 4.00 32 0.05 2478 4.50 25 0.05 , 2210 5.00 19 0.05 2031 6.00 10 0.05 1563 7.25 8.00 9.00 10.00 I i
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l 1 1 PLUME CENTERLINE I Plume Update Number ------------------------------ 7 Plume Update Time Stamp --------------------------- I n it ia l Re l em a. --------------------------------- Mode--------------------------------------------- CENTERLINE DOSE RATES DOSE RATES RADIUS SECTOR SEGMENT THYROID TEDE (mi) (aram/hr) (aren/hr) 0.62 10 7 7.233E+02 3.839E+02 1.00 10 6 7.233E+02 3.839E+02 1.45 10 6 5.241E+02 2.686E+02 2.00 10 5 3.045E+02 1.420E+02 2.50 10 5 2.263E+02 9.960E+01 3.00 10 4 1.600E+02 6.361E+01 3.45 10 4 1.351E+02 4.989E+01 4.00 10 3 1.106E+02 3.596E+01 4.50 10 3 9.880E+01 2.835E+01 5.00 10 2 ?.072E+01 2.239E+01 6.00 10 1 7.028E+01 1.235E+01 1 1 PLUME CENTERLINE DATA Page 1 of 1
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REX-98 August 19,1998 Plume Update 8 Time Stamp 1200 - 1210 Distance Gamma (mrem /hr) Iodine Miles Centerline Plume Edge Net cpm 0.62 381 0.05 15067 1.00 381 0.05 15067 1.45 273 0.05 11071 2.00 136 0.05 5982 _ 2.50 100 0.05 4710 3.00 70 0.05 3616 3.45 54 0.05 2969 4.00 37 0.05 2254 4.50 29 0.05 . 1964 5.00 22 0.05 1719 6.00 14 0.05 1518 7.25 6 0.05 1116 8.00 9.00 10.00
l PLUME CENTERLINE Plume Update Number ------------------------------- 8 Plume Update Time Stamp --------------------------- Initial Release ----------------------------------- l Mode ---------------------------------------------- i I l CENTERLINE DOSE RATES DOSE RATES l
--------------__-----_------- l RADIUS SECTOR SEGMENT THYROID TEDE I (31) (area /hr) (ares /hr) 0.62 10 8 6.751E+02 4.040E+02 1.00 10 8 6.751E+02 4.040E+02 1.45 10 7 4.958E+02 2.898E+02 )
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REX-98 August 19,1998 Plume Update 9 Time Stamp 1210 - 1220 Distance Gamma (mrem /hr) Iodine Miles Centerline Plume Edge Net cpm 0.62 466 0.05 16518 1.00 456 0.05 16161 1.45 314 0.05 11384 2.00 145 0.05 5670 2.50 108 0.05 4420 3.00 72 0.05 3192 3.45 59 0.05 2790 4.00 44 0.05 2299 4.50 34 0.05 1920 5.00 25 0.05 1585 6.00 16 0.05 1295 7.25 10 0.05 1161 8.00 6 0.05 982 9.00 10.00
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Time Stamp 1220 - 1230 Distance Gamma (mrem /hr) Iodine Miles Centerline Plume Edge Net cpm 0.62 401 0.05 12679 1.00 401 0.05 12679 1.45 306 0.05 9888 2.00 170 0.05 5871 2.50 123 0.05 4397 3.00 80 0.05 3103 3.45 63 0.05 2567 4.00 46 0.05 2031 4.50 38 0.05 . 1808 5.00 31 0.05 1607 6.00 19 0.05 1183 7.25 12 0.05 982 8.00 9 0.05 938 9.00 5 0.05 804 10.00 l
I I PLUME CENTERLINE !b l Plume Update Number ------------------------------- 10 l Plume Update Time Stamp --------------------------- Initial Release ----------------------------------- Mode--------------------------------------------- CENTERLINE DOSE RATES l i DOSE RATES l RADIUS SECTOR SEGMENT TRYROID TEDE (mi) (aram/hr) (area /hr)
- 0.62 10 10 5.682E+02 4.197E+02 l 1.00 10 10 5.682E+02 4.197E+02 1.45 10 9 4.429E+02 3.209E+02 l 2 00 10 9 2.632E+02 1.792E+02 2.50 10 8 1.974E+02 1.292E+02 3.00 10 8 1.38ME+02 8.475E+01 3.45 10 7 1.153E+02 6.719E+01 4.00 10 7 9.131E+01 4.912E+01 4.50 10 6 8.107E+01 4.058E+01 5.00 10 5 7.196E+01 3.296E+01 h 6.00 10 10 4
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REX-98 August 19,1998 Plume Update 11 Time Stamp 1230 - 1240 Distance Gamma (mrem /hr) Iodine Miles Centerline Plume Edge Net epm 0.62 - 757 0.05 22143 1.00 666 0.05 19554 1.45 420 0.05 12500 2.00 166 0.05 5246 2.50 125 0.05 4152 3.00 89 0.05 3170 3.45 70 0.05 2589 4.00 49 0.05 1964 4.50 40 0.05 1696 5.00 31 0.05 1451 6.00 21 0.05 1205 7.25 13 0.05 893 8.00 10 0.05 826 9.00 7 0.05 804 10.00 4 0.05 670
l l f PLUME CENTERLINE Plume Update Number ------------------------------- 11 Plume Update Time Stamp --------------------------- Initial Release -----------------------------------
, Mode ----------------------------------------------
CENTERLINE DOSE RATES DOSE RATES RADIUS SECTOR SEGMENT THYROID TEDE (mi) (area /hr) (aren/hr) 0.62 10 11 9.925E+02 7.904E+02 1.00 10 10 8.756E+02 6.953E+02 1.45 10 10 5.602E+02 4.385E+02 2.00 10 9 2.354E+02 1.735E+02 2.50 10 9 1.856E+02 1.311E+02 3.00 10 8 1.415E+02 9.404E+01 3.45 10 8 1.157E+02 7.378E+01 4.00 10 7 8.806E+01 5.202E+01 4.50 10 7 7.574E+01 4.222E+01 5.00 10 6 6.511E+01 3.357E+01 6.00 10 5 5.390E+01 2.370E+01 7.25 10 4 4.028E+01 1.412E+01 8.00 10 3 3.694E+01 1.092E+01 9.00 10 2 3.577E+01 7.892E+00 10.00 10 1 3.008E+01 4.674E+00 1 l PLUME CENTERLINE DATA Page 1 of 1 I 4
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REX-98 August 19,1998 Plume Update 12 Time Stamp 1240 - 1250 Distance Gamma (mrem /hr) Iodine Miles Centerline Plume Edge Net cpm 0.62 675 0.05 17991 1.00 627 0.05 16763 1.45 409 0.05 11295 2.00 228 0.05 6629 2.50 145 0.05 4375 3.00 89 0.05 2857 3.45 73 0.05 2455 4.00 56 0.05 2009 4.50 43 0.05 1652 5.00 34 0.05 1384 6.00 23 0.05 1094 7.25 15 0.05 893 8.00 11 0.05 759 9.00 8 0.05 692 10.00 5 0.05 692 l
PLUME CENTERLINE O Plume Update Number ------------------------------- 12 j Plume Update Time Stamp --------------------------- 1 Initial Release ----------------------------------- Mode ---------------------------------------------- CENTERLINE DOSE RATES DOSE RATES RADIUS SECTOR SEGMENT THYROID TEDE (mi) (area /hr) (area /hr) 0.62 10 12 8.058E+02 7.024E+02 1.00 10 11 7.512E+02 6.520E+02 1.45 10 11 5.055E+02 4.257E+02 2.00 10 10 2.973E+02 2.376E+02 , l 2.50 10 10 1.964E+02 1.518E+02 3.00 10 9 1.280E+02 9.303E+01 3.45 10 9 1.101E+02 7.637E+01 4.00 10 8 9.013E+01 5.866E+01 4.50 10 8 7.435E+01 4.578E+01 l 5.00 10 7 6.223E+01 3.580E+01 I \m/ 6.00 10 6 4.931E+01 2.461E+01 l 7.25 10 5 3.947E+01 1.611E+01 8.00 10 4 3.391E+01 1.199E+01 9.00 10 3 3.092E+01 8.732E+00 10.00 10 2 3.062E+01 6.393E+00 i PLUME CENTERLINE DATA Page 1 of 1 1
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REX-98 August 19,1998 Plume Update 13 Time Stamp 1250 - 1300 Distance Gamma (mrem /hr) Iodine Miles Centerline Plume Edge Net cpm 0.62 501 0.05 12121 1.00 501 0.05 12121 1.45 379 0.05 9375 2.00 221 0.05 5804 2.50 165 0.05 4531 3.00 118 0.05 3415 3.45 86 0.05 2589 4.00 55 0.05 1786 4.50 47 0.05 1585 5.00 38 0.05 1406 6.00 25 0.05 1027 7.25 17 0.05 826 8.00 13 0.05 759 9.00 9 0.05 625 10.00 6 0.05 580
PLUME CENTERLINE Plume Update Number ------------------------------- 13 Plume Update Time Stamp --------------------------- Init ial Release ------~~-------------------------- Mode ---------------------------------------------- CENTERLINE DOSE RATES DOSE RATES l SECTOR SEGMENT THYROID TEDE RADIUS (ci) (area /hr) (aren/hr) 0.62 10 13 5.435E+02 5.188E+02 1.00 10 13 5.435E+02 5.188E+02 1.45 10 12 4.197E+02 3.927E+02 2.00 10 11 2.598E+02 2.299E+02 2.50 10 11 2.032E+02 1.716E+02 3.00 10 10 1.532E+02 1.228E+02 3.45 10 10 1.159E+02 8.988E+01 4.00 10 9 8.025E+01 5.811E+01 4.50 10 9 7.160E+01 4.908E+01 5.00 10 8 6.279E+01 4.054E+01 6.00 10 7 4.620E+01 2.632E+01 7.25 10 6 3.730E+01 1.774E+01 8.00 10 $ 3.375E+01 1.419E+01 9.00 10 4 2.786E+01 9.757E+00 10.00 10 3 2.582E+01 7.243E+00 i l I PLUME CENTERLINE DATA Page 1 of 1 l t L______________
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- REX-98 August 19,1998 Plume Update 14 Time Stamp 1300 - 1310 Distance Gamma (mrem /hr) Iodine Miles Centerline Plume Edge Net cpm 0.62 547 0.05 12277 1.00 547 0.05 12277 1.45 404 0.05 9174 2.00 216 0.05 5089 2.50 155 0.05 3839 3.00 118 0.05 3080 3.45 97 0.05 2679 4.00 74 0.05 2165 4.50 54 0.05 1652 5.00 38 0.05 1250 6.00 28 0.05 1049 7.25 18 0.05 781 8.00 14 0.05 692 9.00 11 0.05 625 10.00 7 0.05 513
PLUME CENTERLINE M Plume Update Number ------------------------------ 14 Plume Update Time Stamp --------------------------- Initial Release ----------------------------------- gode __ _____ ____________ _____________ ________ CENTERLINE DOSE RATES DOSE RATES RADIUS SECTOR SEGMENT THYROID TEDE (mi) (aren/hr) (aren/hr) 0.62 10 14 5.499E+02 5.653E+02 1.00 10 14 5.499E+02 5.653E+02 1.45 10 13 4.112E+02 4.179E+02 2.00 10 13 2.281E+02 2.234E+02 2.50 10 12 1.718E+02 1.611E+02 3.00 10 11 1.380E+02 1.224E+02 3.45 10 11 1.197E+02 1.014E+02 4.00 10 10 9.652E+01 7.686E+01 4.50 10 10 7.405E+01 5.669E+01 5.00 10 9 5.594E+01 4.012E+01 6.00 10 8 4.677E+01 2.983E+01 7.25 10 7 3.446E+01 1.880E+01 8.00 10 6 3.060E+01 1.493E+01 9.00 10 5 2.783E+01 1.154E+01 10.00 10 4 2.337E+01 8.078E+00 I j I ( PLUME CENTERLINE DATA Page 1 of 1
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REX-98 August 19,1998 Plume Update 15 Time Stamp 1310 - 1320 Distance Gamma (mrem /hr) Iodine Miles Centerline Plume Edge Net cpm 0.62 649 0.05 13616 1.00 635 0.05 13304 1.45 441 0.05 9353 2.00 211 0.05 4665 2.50 159 0.05 3616 3.00 107 0.05 2545 3.45 91 0.05 2254 4.00 74 0.05 1964 4.50 62 0.05 1763 5.00 50 0.05 1496 6.00 28 0.05 938 7.25 20 . 0.05 759 8.00 15 0.05 647 9.00 11 0.05 558 10.00 9 0.05 513 e
PLUME CENTERLINE Plume Update Number ------------------------------- 15 Plume Update Time Stamp --------------------------- Initial Release ----------------------------------- Mode-------------------------------------------- CENTERLINE DOSE RATES DOSE RATES RADIUS SECTOR SEGMENT THYROID TEDE (mi) (area /hr) (aren/hr) 0.62 11 15 6.098E+02 6.694E+02 1.00 11 14 5.965E+02 6.545E+02 1.45 10 14 4.193E+02 4.545E+02 2.00 10 13 2.093E+02 2.175E+02 2.50 10 13 1.618E+02 1.641E+02 3.00 10 13 1.145E+02 1.108E+02 3.45 10 12 1.014E+02 9.420E+01 4.00 10 11 8.818E+01 7.701E+01 4.50 10 11 7.849E+01 6.471E+01
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IGX-98 August 19,1998 Plume Update 16 Time Stamp 1320 - 1330 Distance Gamma (mrem /hr) Iodine Miles Centerline Plume Edge Net cpm 0.62 859 0.05 16920 1.00 786 0.05 15513 1.45 506 0.05 10134 2.00 240 0.05 5000 2.50 171 0.05 3661 3.00 114 0.05 2567 3.45 92 0.05 2121 4.00 68 0.05 1652 4.50 59 0.05 1540 5.00 51 0.05 1406 6.00 36 0.05 1094 7.25 20 0.05 737 8.00 17 0.05 647 9.00 12 0.05 536 10.00 9 0.05 491
PLUME CENTERLINE Plume Update Number ------------------------------- 16 Plume Update Time Stamp -------------------------- Initial Release ----------------------------------- Mode--------------------------------------------- CENTERLINE DOSE RATES DOSE RATES RADIUS SECTOR SEGMENT THYROID TEDE (mi) (ares /hr) (aren/hr) 0.62 10 16 7.582E+02 8.840E+02 1.00 10 15 6.953E+02 8.089E+02 j 1.45 10 15 4.538E+02 5.208E+02 2.00 10 14 2.242E+02 2.470E+02 2.50 10 14 1.644E+02 1.764E+02 3.00 10 13 1.147E+02 1.178E+02 3.45 10 13 9.517E+01 9.497E+01 4.00 10 12 7.412E+01 7.004E+01 4.50 10 12 6.856E+01 6.160E+01 ' h5.00 10 11 6.305E+01 5.349E+01 f 6.00 10 10 4.872E+01 3.709E+01 7.25 10 9 3.247E+01 2.139E+01 f.00 10 8 2.921E+01 1.760E+01 9.00 10 7 2.400E+01 1.269E+01 10.00 10 6 2.164E+01 9.859E+00 l PLUME CENTERLINE DATA Page 1 of 1 i -
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REX-98 August 19,1998 Plume Update 17 Time Stamp 1330 - 1340 Distance Gamma (mrem /hr) Iodine Miles "-nterline Plume Edge Net cpm 0.62 727 0.05 13326 1.00 _, 711 0.05 13058 1.45 495 0.05 9241 2.00 277 0.05 5402 _ 2.50 191 0.05 3839 3.00 126 0.05 2656 3.45 99 0.05 2143 4.00 72 0.05 1629 4.50 58 0.05 1384 5.00 47 0.05 1183 6.00 38 0.05 1049 7.25 24 0.05 759 8.00 17 0.05 603 9.00 13 0.05 536 10.00 10 0.05 446
PLUME CENTERLINE Plume Update Number ------------------------------- 17 Plume Update Time Stamp --------------------------- Initial Release ----------------------------------- Mode ---------------------------------------------- CENTERLINE DOSE RATES DOSE RATES RADIUS SECTOR SEGMENT THYROID TEDE (mi) (mren/hr) (aren/hr) 0.62 10 17 5.972E+02 7.465E+02 1.00 10 16 5. 84 5E+02 7.300E+02 1.45 10 16 4.143E+02 5.083E+02 2.00 10 15 2.421E+02 2.850E+02 2.50 10 15 1.715E+02 1.963E+02 3.00 10 14 1.189E+02 1.304E+02 3.45 10 14 9.612E+01 1.024E+02 4.00 10 13 7.299E+01 7.403E+01 4.50 10 13 6.164E+01 6.025E+01 5.00 10 12 5.248E+01 4.872E+01 6.00 10 11 4.730E+01 3.929E+01 7.25 10 10 3.387E+01 2.465E+01 8.00 10 9 2.687E+01 1.780E+01 9.00 10 8 2.407E+01 1.415E+01 10.00 10 7 2.022E+01 1.042E+01 i 1 1 PLUME CENTERLINE DATA Page 1 of 1 L 9 l
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REX-98 August 19,1998 Plume Update 18 Time Stamp 1340 - 1350 Distance Gamma (mrem /hr) Iodine Miles Centerline Plume Edge Net cpm 0.62 521 0.05 8884 1.00 521 0.05 8884 1.45 429 0.05 7388 2.00 270 0.05 4799 2.50 199 0.05 3661 3.00 146 0.05 2813 3.45 115 0.05 2277 4.00 80 0.05 1674 4.50 64 0.05 1406 5.00 50 0.05 1138 6.00 34 0.05 848 7.25 27 0.05 781 8.00 22 0.05 692 9.00 14 0.05 491 10.00 11 0.05 446
PLUME CENTERLINE Plume Update Number ------------------------------- 18 Plume Update Time Stamp --------------------------- Initial Release ----------------------------------- Mode ---------------------------------------------- CENTERLINE DOSE RATES DOSE RATES RADIUS SECTOR SEGMENT THYROID TEDE (mi) (mrem /hr) (area /hr) 0.62 10 18 3.979E+02 5.341E+02 1.00 10 18 3.979E+02 5.341E+02 1.45 10 17 3.312E+02 4.403E+02 2.00 10 17 2.153E+02 2.775E+02 2.50 10 16 1.639E+02 2.042E+02 3.00 10 15 1.263E+02 1.502E+02 3.45 10 15 1.023E+02 1.184E+02 4.00 10 14 7.480E+01 8.218E+01 4.50 10 14 6.253E+01 6.648E+01 5.00 10 13 5.070E+01 5.134E+01 6.00 10 13 3.824E+01 3.552E+01 7.25 10 11 3.541E+01 2.856E+01 8.00 10 10 3.091E+01 2.290E+01 9.00 10 9 2.178E+01 1.440E+01 10.00 10 8 2.027E+01 1.188E+01 l i l l PLUME CENTERLINE DATA Page 1 of 1 L_--___________-____-
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REX-98 August 19,1998 l Plume Update 19 Time Stamp Distance Gamma (mrem /hr) Iodine Miles Centerline Plume Edge Net cpm 0.62 BKG BKG 0 1.00 343 0.05 580 1.45 127 0.05 2165 2.00 230 0.05 3929 2.50 184 0.05 3214 3.00 140 0.05 2545 3.45 117 0.05 2210 4.00 91 0.05 , 1808 4.50 70 0.05 1451 5.00 55 0.05 1183 6.00 36 0.05 848 7.25 26 0.05 692 8.00 23 0.05 670 9.00 17 0.05 558 10.00 11 0.05 424
I PLUME C E !! T E R L I N E J Plume Update Number ------------------------------- 19 Plume Update Timo Stamp --------------------------- Initial Release ----------------------------------- l Mode ---------------------------------------------- i CENTERLINE DOSE RATES DOSE RATES RADIUS SECTOR SEGMENT THYROID TEDE 1 (mi) (mrem /hr) (area /hr) I I 0.62 10 19 0.000E+00 0.000E+00 1.00 10 18 2.613E+01 3.520E+01 1.45 10 18 9.669E+01 1.302E+02 , 2.00 10 17 1.756E+02 2.361E+02 l 2.50 10 17 1.439E+02 1.885E+02 l 3.00 10 16 1.141E+02 1.438E+02 l 3.45 10 16 9.897E+01 1.206E+02 ( 4.00 10 15 8.079E+01 9.380E+01 l 4.50 10 15 6.496E+01 7.255E+01 5.00 10 14 5.277E+01 5.637E+01 d / 6.00 10 13 3.320E+01 3.749E+01 7.25 10 12 3.070E+01 2.669E+01 8.00 10 11 2.984E+01 2.377E+01 9.00 10 10 2.475E+01 1.767E+01 10.00 10 9 1. 874 E+01 1.187E+01 l
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