ML20141M645
| ML20141M645 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 11/19/1996 |
| From: | NEBRASKA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20007C401 | List: |
| References | |
| NUDOCS 9609230115 | |
| Download: ML20141M645 (250) | |
Text
{{#Wiki_filter:; 1 I 1 1916. Cooper Nuclear Station I Emergency Exercise EXERCISE MANUAL Neiin4su Penuc Powen DistnicT g y?o tl] ([ )(,o 4 M
l 1 i TABLE OF CONTENTS l VOLL3fE 1
)
GENERAL INFORMATION l
- 1. INTRODUCTION
- 2. SCOPE AND OBJECTIVES 2.1 Scope l
2.2 Objectives 2.3 FEMA Extent Of Play agreement letters to Nebraska and Missouri i I
- 3. GENERAL EXERCISE INFORMATION l
3.1 Facilities Activated
- 3.2 Exercise Organization
! 3.3 Conduct of the Exercise 3.4 l Precautions and Limitations i l 3.5 Abbreviations 3.6 Definitions 3.7 References
- 4. CONTROLLER / EVALUATOR INFORMATION 4.1 General Information I 4.2 Controller Instructions I 4.3 Evaluator Instructions 4.4 Personnel Assignments 4.5 Simulator Instructions
- 5. PLAYER INFORMATION 5.1 General Information i 5.2 Player Guidelines l 6. SCHEDULE OF EVENTS i
6.1 Times and Places 6.2 Travel Information Table of Contents for Sections 7-11 are contained in Wlume 11 of ihn Exerene .\tanual. Table cf c,mtents i c utesur:-ar-
I L1. INTRODUCTION l Cooper Nuclear Station (CNS), cwned and operated by the Nebraska Public Power District (NPPD), annually conducts an Emergency Preparedness Exercise for the purpose of deraonstrating that the NPPD emergency response organization can effectively meet its L responsibilities in protecting the health and safety of the residents of the Plume Exposure j Pathway Emergency Planning Zone in the event of a radiological incident at the plant. l l The NPPD response organization and facilities developed to respond to such an emergency are described in the CNS Emergency Plan. The Plan also describes support available from Federal, State, and local government agencies, and private organizations. The Plan describes a program of continuous preparedness, one element of which is the conduct and evaluation of this exercise. The purpose of this exercis,e is to evaluate the participating ponion of the NPPD emergency
- response organization in accordance with the CNS Emergency Plan and implementing procedures. Only participating portions of the NPPD CNS emergency organization will be evaluated in the exercise.
The exercise will be conducted and evaluated by NPPD and NRC personnel. Upon termination
- of the exercise, the NPPD Evairators will critique the respon>e of the players, assess the effectiveness of their response, and compile a Critique Report for distribution to NPPD l management to ensure appropriate actions are taken to resche any weaknesses identified. A draft copy of this Critique may be presented to the NRC evaluation team prior to their departure.
This Exercise Manual consists of two volumes; Volume I (Sections 1 through 6) provides information of general interest, instructions to participants, a schedule of associated events, a general description and overview of the exercise, including administrative and logistical information helpful to all participants. Volume II (Sections 7 through 11), which is subject to a limited, controlled distribution _ provides the scenario-specific information and supporting data for the sequence of events to Controllers, Evaluators and authorized observers. Exercise " Players" will not have orior access to or knowledge of ans of the scenario developed for this exercise. I I Intraluction Pa u l-1 C:. EXEl< SECTI A WP.* I, L
i 3 2. SCOPE and OBJECTIVES i i -1 4 2.1 SCOPE The 1996 Emergency Exercise is a full-scale exercise as defined in the CNS Drill and Exercise Manual. All major elements of the NPPD Emergency Plan for Cooper Nuclear Station will be demonstrated. Specific scope is indicated by the Extent of Play Checklist developed jointly by the Licensee and States at the annual Extent of Play meeting, and the Objectives, both of wnich follow. b l l 1 i l l r l Scope and Objectives Page 21 C:. EXER SECTI-6. WP5 l I
_ _ _ _ _ _ _ _ _ . _ . . _ . _ _ . . . . ~ _ . . . _ _ . _ _ _ . - _ _ _ . . _ . _ _ _ _ _ Extent of Play / Scoping document The following checklist should be completed to establish the extent of play f.sr each drill' exercise. The corapleted checklist will be used by the wenario deselopment team as the Je ii n enteria for the deselopment of the drill / exercise. Drill / Exercise
Title:
fd E $ Drill, Exercise Date: /Jeo /9. //95
/ ~ Duration: 7 hours Start Time: 6 8 CC Check each function to be demonstrated: Annotate as needed.
NPPD Facilities / Functional Areas to be activated: [N Simulator [] Control Room [k] TSC [ac] OSC [k] EOF [ar] In-plant repair teams [v] On-site monitoring teams [*] Downwind field monitoring teams (H Joint Information Center (JIC) [v] Public Affairs Duty Officer (PADO) ~ [Q. Load Dispatcher (i,f required by scenario) [;wi CAS (needed for assembly and accountability) [] Other: State / Local Governments: [N State of Nebraska [Q State of Missouri [] State of Iowa [] State of Kansas [=,] Nemaha County [41- Atchison County [] Richardson County [] Otoe County J [] Other: l Federal Government: l [] NRC (Headquarters) [] NRC (Region) [] NRC (Resident) [] NRC (Site Response Team) J
%pe ami Objecthes Pa w 2-: C:. EXER SECTI-6 WP5 l
i
[] FEMA [] Other: Medical Response: ['] On-site: [] Off-site: [] Nemaha County Hospital [] University of Nebraska Medical Center [] Otter: [] Transportation: _ [] Contaminated Personnel: How many? Emergency Notification Systems: [4 Emergency Alarm (via Gaitronics) [] Siren System Dc] Simulated , [] Emergency Broadcast System [ar} Simulated [] Pagers [.k] Simulated
,[M Other: 94csa P W E . e n r o A I.-
.)
Computer Systems: [.h} Simulator [41 PMIS [9 CNS DOSE l [] Automated Notification System [] Other: 1 Simulator Communications: PBX telephones [ ] Simulator booth b] Cross-tied to Real World GAITRONICS [ ] Simulator booth [.Q Cross tied to Real World ENS (FTS) telephone [ ] Simulator booth [r] Cross-tied to Real World Call-back phone [ ] Simulator booth [Q Cross-tied to Real World Radio console [ ] Simulator booth [M Cross-tied to Real World State Notification phone [ ] Simulator booth [W Cross-tied to Real World Degree of Simulation: [k] Anti Cs: [N first entry. each person [ ] all entries l Det Respirators (scenario dependent) [M one respirator per team, including communications. for one bottle. [ ] other: [2 Assembly & Accountability: ~ [] Site Evacuation: bst Simulated Scope imJ Objectnes Pa x .' J C: EXER SECT! 6. WP!
[>d KI (simulated) an Alf 47NM [h}- ~ Tools to worksite (Q Parts to worksite Dd use process, but do not issue parts he5d Operations Data Requirements: (OPS SDC representative) (k] Prepare work packages for work-in-progress (ar] Previous Shift information (Shift Turnover log) [Q Initial Conditions (v] Backup, Simulator ' Crash
- Messages
[v] Hardcopy data (PMIS Screens) () Graphs of affected parameters Radiological Data Requirements: (RAD SDC represene.tive) [] Prepare previous chen'istry data for initial conditions (W PASS sample data [] Other Chemistry data (W In-plant radiation monitors (Q- In-plant survey data: W} dose rate [A airborne sampling data { ] smear data (Q CAMS (Q On-site out-of-plant data [ht dose rate (S airborne sampling data [ ] smear data
. (A] Off-site monitoring data (k] dose rate (x] airborne sampling data
( ) smear data ( ) soil (' ] water [ ] vegetation [ ] liquid [] Ingestion Pathway data (At- Off site dose requirements: (to meet FEMA State objectises) (TEDE) (CDE) gggg pg i mile I mile 2 mile 2 mile WB . l l Scope ami Objectnes Paec 2-4 C: EXER SECTI-6. %P!
l > 5 mib_,_, 5 m!!e 10 mile 10 mile Radiation Detection Equipment to be used (list all meters and probes): On-site: Nebraska:Qsso~urip fNC ~ d{fus e22 (R RO L Lulla m MC. Cwleder -
%8%e PIL(o Meteorological Data Requirements:
W!nd Direction (from): /90 deg. Wind shift? Ald
~
Stability Class: D i [] NWS Ir. formation [] Drill / exercise findings will be presented to Management Review Board i [] List NRC open items to be closed; O A tti DMA {u n ds] , .6 0 E AJA t. tn [] Ust FEMA open items to be closed: l l Other Drill / Exercise Requirements: I [] QA will evaluate dri;l [] Off site observers l l Scope and Objecthes Pne25 C:. EXER SECTI-6. WP5
l 2.2 OBJECTIVES The following exercise objectives were submitted to the NRC 60 days prior to the Exercise date in accordance with requirements: They are divided by facility to aid in the evaluation of the:r demonstration. Control Room (Simulator)
- l.1 Recognize and classify emergency conditions and take appropriate actions to mitigate the efit. cts of the event.
- 1.2 Activate / augment the Emergency Response Organization (ERO), as appropriate, to respond to the emergency.
- l.3 Perform initial notification of off-site agencies (Federal. state, local) within applicable time limits and provide follow-up notitications as required, until relieved of this responsibility by the TSC or EOF.
1.4 Inform on-site personnel of conditions which may affect personnel safety. 1.5 Coordinate operator activities with the TSC. ; 1 1 Maintain command and control of all emergency activities directed from the Control 1.6 Room (Simulator).
- l 7 If required by the scenario, perform accurate and timely dose assessments until i relieved of this duty by the EOF.
J l
- l.8 If required by the scenario, make immediate protective action recommendations. l 1.9 Upon activation of the EOF, perform a clear transfer of responsibility for emergency management, dose assessment and protective action recommendations.
1.10 Maintain emergency logs and records. 1
- l.12 Upon termination of the drill, conduct a critique of the Control Room (Simulator) emergency response.
Scope and Objectnes Paec 2-0 C:. EXERiSECTI 6. WPS
r Technical Support Center (TSC)
*2.1 Staff and declare the Technical Support Center operational.
*2.2 Recognize emergency conditions and recommend appropriate actions to mitigate the effects of the event.
2.3 Relieve Control Room (Simulator) of Emergency Notification System (ENS) Communicator responsibilities.
*2.4 Evaluate on-site radiological conditions.
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' 2.5 Inform on-site personnel of emergency conditions which may affect personnel safety.
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*2.6 Coordinate the deployment of emergency response personnel for in-plant activities with the OSC.
*2.7 Perform radiological surveys to verify the habitability of the TSC.
2.8 Maintain command and control of all emergency activities directed from the TSC. 2.9 Maintain emergency logs and records. 2.10 Evaluate the adequacy, availability and reliability of emergency equipment in the TSC (controller objective). .
*2.11 Upon termination of the drill, conduct a critique of the Technical Support Center emergency response.
l l l Scope and Objectnes Paec 2-7 C:. EXER.SECTI-6. WP5
(...-- 7---.-.- Operations Suppori Center (OSC)
*3.1 Staff and declare the OSC operational.
*3.2 Establish and maintain communications with the TSC.
*3.3 Perform radiological surveys to establish OSC habitability.
*3.4 Establish and maintain contamination controls for the OSC.
3.5 If needed, demonstrate the ability to decontaminate personnel and equipment.
*3.6 Coordinate and direct the actions of emergency response teams.
l 3.7 Determine requirements for protective clothing, dosimetry and re'spiratory protection. 3.8 Ensure emergency response teams' exposures are ALARA. 3.9 Request emergency exposure limits authorization, as needed. l ? 1 l 3.10 Assemble and brief teams to collect reactor coolant, air. or other samples (using l PASS or other means), if requested. 1 3.11 Collect and analyze the above sample (s), if requested. l 3.12 Exercise proper sample handling, contamination control, and exposure control during l the collection of samples.
*3.13 Maintain command and control of all emergency activities directed from the OSC.
3.14 Maintain emergency logs and records. l 3.15 Evaluate the adequacy, availability and reliability of emergency equipment in the OSC (controller objective). l *3.16 Upon termination of the drill, conduct a critique of the OSC emergency response. f-l l l Swpe and Ohjectives Paec :-S C: EXER.SECTI-6. WP5 l l l
l l-l Emergency Operations Facility (EOF) l
*4.1 Staff and declare the EOF operational. l
( L '4.2 Establish and maintain communications with the TSC and other emergency response j facilities. 4.3 Receive turnover from the Control Room (Simulator) on classi6 cation. noti 6 cation l status, protective action recommendations made, dose assessment. etc. l, l l *4.4 Perform radiological surveys to establish habitability of the EOF. I ! l l l
*4.5 Notify off-site agencies and provide follow-up noti 6 cations per EPIP 5.7.6. !
l 4.6 Assemble and dispatch off-site survey teams, as required. l 4.7 Coordinate and direct the actions of the off-site survey teams. if dispatched.
- j. 4.8 Perform off-site dose assessment.
]
! l l 4.9 Make protective action recommendations based on plant conditions, dose projections l l and weather conditions, or other factors. l l \ l 4.10 Evaluate dose projections and field data to determine the need for revisions to. ) protective action recommendations, l I i 4.11 Evaluate the need for K1 for emergency response personnel. Authorize use of KI, if 1 appropriate. ! 1 4.12 Evaluate the need for the use of emergency exposure limits and approve extensions. I 1 1
*4.13 Evaluate the need for evacuation or dismissal of non-designated personnel.
*4.14 Provide emergency information to the Joint Information Center (JIC).
4.15 initiate reentry / recovery discussions as emergency conditions warrant. 4.16 Maintain command and control of all activities directed from the EOF. 4.17 Maintain emergency bags and records.
- . 4.18 Evaluate the adequacy, availability and reliability of emergene,s equipment in the l Emergency Operanons Facility (controller objectise).
l *4.19 Upon completion of the drill, conduct a critique of the EOF emergency response. Scope ami Objntnes Paec 2-9 C:. EXER SECTI 6. WP3 1
On-site Radiological Monitoring Teams 5.1 Assemble teams and prepare for dispatch (receive brie 6ng by Chem /RP Coordinator. don PCs, obtain respirators. obtain dosimetry, check equipment), if needed. 5.2 Perform radiological surveys as directed. 5.3 Collect and analyze air, gas, coolant, or other sample, as directed. 5.4 Maintain communications with the OSC Supervision. i 5.5 . Monitor individual radiation dose and maintain exposures within authorized limits. 5.6 Upon completion of the task, provide a debriefing to the OSC Supervision. 5.7 Maintain logs and records. 5.7 Evaluate the adequacy, availability and reliability of equipment used by the in-plant survey teams (controller objective).- l l l 4 l Swpe amt Objectives Pace :-10 C:. EXER SECTI-6. WP5
Off-site Field Monitoring Teams 6.1 Assemble teams and prepare for dispatch. (check equipment and vehicles. establish communications with the EOF. and receive a briefing by the Radiological Assessment Coordinator). 6.2 Perform radiological surveys as directed by the Radiological Assessment Coordinator. 6.3 Collect air, soil, vegetation, or other samples as requested by the Radiological
' Assessment Coordinator.
6.4 Maintain communications with the EOF. 6.5 Monitor individual radiation dose and maintain exposures within authorized limits. 6.6 Complete all paperwork and logs. ! l 6.7 Evaluate the adequacy, availability, and reliability of the otY site field monitoring team equipment (controller objective). I l l l l l l l Scope and Objectnes Paec 211 C:. EXER SECTI-6. WP5 l 1
i Joint Information Center UIC) ! 7.! Staff and declare the JIC activated. l 7.2 Obtain timely and accurate emergency information from Cooper Nuclear Station. 7.3 Prepare accurate information for release to the public. 7.4 Prepare accurate information for release to NPPD employees. 7.5 Provide CNS/NPPD background information to the media, upon request. 7.6 Monitor media broadcasts. l 7.7 Identify rumors and provide correct information.
- 7.8 Demonstrate the ability to respond to questions from the media and/or public concerning real or rumored events at CNS.
7.9 Coordinate with State personnel concerning the release of information to the public, i 7.10 Evaluate the adequacy, availability, and reliability of emergency equipment in the JIC I (controller objective). I 7.11 Conduct a critique of the JIC emergency response. Six Year Matrix Objectives None l l l l l I i Scope and Objectives Page :-)2 C:. . !EXERtSECTI-6. WP5 I
l l
. 2.3 FEMA Extent Of Play letters to Nebraska and Missouri l
1 l i l l l l l l l l l Scope and Objectives Pace 2-13 C:. . tE.VRtSECTI-6. WP5
j j Federal Emergency Management Agency Region VII
. . .'3:3 Grand Bhd . Suite 900 Kansas City. .NIO 61108 2670 c: : _:
'^c Mr. Jerry B. Uhlmann. Director State Emergency Management Agency P. O. Box 116 Jefferson City, Missouri 65102 I
l
Dear Mr. Uhlmann:
4
SUBJECT:
Cooper Nuclear Station Extent of Play for the Nosember 1996 Full Scale and Reentry, Return, Relocation, and Recovery Exercise The following comments are provided for clarification of exercise requirements regarding objectives number 1, 2, 4, 5, 6, 8, 10, 11, 13, 14, 15, 16, 17, 18, 22, 28, 20 - 30 as we discussed in the extent of play meeting held on June 21,1996. Ther - tives that do not require further clarification and are not included ' d' l Obiective Number 1 - Mobilization: At / e them
/
on standby must be actually made. 4 j . 'e'
, 'a The demonstration at the Lamkin Gymnas it of sequence. The date and time of the demon the extent-of-play meetuij;. it will not be necessary his facility since they were demonstrated during th ty ,
be prepositioned, however, the issuance of radi s must not be accomplished prior to evaluator an Prepositioning of any additional staffis not auti , office prior to the exercise. Your request m .. will be prepositioned and which facility (ies) will be affect Current rosters must be presented identifying the individuals who will maintain around the clock operation at all evaluated facilities except for the Missouri Dose Assessment Team, pursuant to the agreement during the June 21.1996, extent-of-play meeting. Obiective Number 2 - Facilities: All facilities must be fully set up as they would be to support i an actual emergency. This would include the availability of operational telephones and other equipment as required for response to an emergency.
J d Obiective Number 4 - Communications: We will expect demonstration of the primary and at i least one backup communication link identined in the plans for full demonstration of this objec-l tive. His must be demonstrated at all facilities evaluated. All etaluated facilities and Held J teams are required to demonstrate the capability to access at least one communication system that is independent of the commercial telephone system. We will request copies of all messages and logs of message traf6c. Obiective Number 5 - Emergency Worker Exnosure Control: Emergency workers must wear appropriate direct-reading and permanent record dosimetry and have access to a dosimetry charger in accordance with state and local plans and procedures. In addition, they must demonstrate basic knowledge of dosimetry, radiation exposure limits. and turn back exposure limits through an interview process. Procedures to monitor and record dosimeter readings and 1 to manage radiological exposure control must be demonstrated. Obiective Number 6 - Field Radiological Monitorine: Each of the deployed Held monitoring teams must take radiation measurements at a minimum of six locations to identify the plume. A demonstration of an operational check of the instmments utilizing a check source is required. , Infomtation on the proper reading or range of readings should be attached to or accompany the i instrument. Obiective Number 8 - Radiciodine Samnling: The field teams must demonstrate the criteria listed under this objective as they would in an actual emergency. Transport of samples to the i laboratory will not be required pursuant to the June 21,1996, meeting, however, the FEMA evaluator will need to see the physical transfer of the samples including the custody forms from the Missouri Field Team to a courier, i.e., MoNET, National Guard, or other expeditious means l pursuant to the plan. Obiective Number 10 - Alert and Notification: The 15-minute clock will begin when the offsite authorities make the decision to notify the public of a Site Area Emergency. When that occurs, the offsite orgamzations will have 15 minutes to activate the alert system and disseminate an initial Emergency Alert System (EAS) [formerly Emergency Broadcast System] message. The initial EAS message needs simply to identify the emergency classi6 cation level and include instructions to stay tuned to the radio station. Within the aforementioned 15 minutes, actual l contact of the EAS station and dissemination of the initial message to the radio station must be demonstrated. i An evaluator will be assigned to KFEQ EAS station to observe the station's procedures for broadcasting the messages. We expect to see actual receipt of the messages from the county l EOC. Following receipt at the station. procedures to broadcast the messages must be fully ! demonstrated up to the point of transmission. Actual broadcast of the messages or EAS test messages are not required. The 15-minute clock stops when the broadcast (simulated) of the EAS message by the radio station is imtiated. The FEMA esaluator will remain at the EAS l 2
_ . . - .~ _ _._ _ _ _._ _ ._ _ . _ _ _ _ _ _ _ _ _ _ . . _ _ . _ . l
. station until the termination of the exercise to observe receipt and broadcast procedures for all EAS messages. Copies of all EAS messages will be requested from the facility. ;
1 l The procedures for siren activation must be demonstrated up to the point of actual activation and must be completed within the 15-minute time frame. Actual siren activation may be simulated. In addition. tone alert radio and weather radio activation may be simulated. Obiective Number 11 - Public Instructions: The 15 minute requirement will not be applied to subsequent protective action instructions provided to the public after the initial notification. However, subsequent messages should be disseminated in a timely manner. Also, the procedures for providing the messages to the radio station remain the same as indicated for objective number 10. Messages should be all inclusive by including previously identified areas as well ! j as new areas. Procedures must be demonstrated, if appropriate, to ensure that EAS messages containing Protective Action Recommendations (PARS) that have been changed are rescinded and not repeated by the EAS station.
- Obiective Number 12 - Emereenev Information - Media: Media briefings will be conducted !
at the Joint Information Center (JIC) located in the Nebraska Public Power District Building in Columbus, Nebraska. Obiective Number 13 - Rumor Control: Each rumor control staff member, at the JIC, must demonstrate the capability to respond to an average of at least six calls per hour throughout the i emergency phase. The staff should demonstrate the capability to monitor the contents of I broadcast media coverage of the emergency situation. Any trends in rumors identified by the ! rumor control staff must be addressed in news releases or media briefings. l
.1 Obiective Number 14 - Pota==ium Iodide (KD: Although the decision to recommend the use of KI is not due for demonstration during this exercise, it is possible that the scenario could require it. If the decision to use KI is made, the instructions must be appropriately disseminated to all personnel including those deployed (simulated) for traffic and access control and other missions. However, as this is a group B objecti"e, if the decision to use KI is not required by the scenario, all emergency workers, at all facilities, will be expected to demonstrate this objective i through an interview of their knowledge of the procedures for the authorization and the use of I Kl. . Actual administration of K1 will be simulved. Verification of K1 supplies will be l
! accomplished during this exercise at facilities where K1 is stored pursuant to the plan. l i Obiective Number 15 - Special Pooulations: Telephone calls to special facilities and transpor-tation providers may be simulated. However, all facilities and transportation providers which , ! are required to be notified must be clearly identified and the simulated contacts appropriately i documented. Telecommunications Device for the Deaf (TDD) calls to the hearing impaired
- population will be simulated and appropriately documented.
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.- - - .. . .- - . . = -- - .- _ . - . .
t Obiective Number 16 - School Evacuation: We will expect the capability to evacuate schools be demonstrated by the Rock Port Elementary School in the Rock Port Ri! School District, Rock Port, Missouri. An exercise evaluator will be assigned to interview the district superintendent (or other designated school official) and principal. in addition, at least one school bus driver must be available for an interview to determine their l awareness of and preparedness for the evacuation of school children. This will include ! demonstration of objectives number 4, 5 and 14: communications, emergency worker expo-sure, and use of KI, respectively. The bus driver must have dosimetry and KI available for this
' demonstration. The interview described above will be conducted out-of-sequence from the l
exercise, during the aftemoon of November 18,1996. The time for the interview will be determined later. During the emergency phase of the actual exercise on November 19,1996, all appropriate actions (e.g., notifications, EAS messages, etc.) must be demonstrated by the EOC staff for any i public or private schools or day care facilities affected by protective action recommendations. Actual telephone calls do not need to be made; however, all contacts which would be required should be appropriately documented. Obiective Number 17 - Traflic and Access Control: Deployment of traffic and access control personnel to assigned locations will be simulated. At least two individuals who would perform traffic and access control must be available at the Atchisen County EOC for an interview. During the interviews, all personnel will be expected to demonstrate knowledge of their roles and responsibilities concerning traffic and access control, as well as appropriate knowledge i concerning dosimetry and potassium iodide procedures. Obiective Number 18 - Registration. Monitorine. and Decontamination: At the Lamkin 1 Gymnasium Reception and Care Center, the number of evacuees required to be monitored within 12 hours is 527 (20% of evacuees assigned to the Center). According to the plan, one portal monitor will be available at this facility and.will require one MoNet member to operate it. At l least one individual with a CD V-700 must be available, pursuant to the plan, as a backup in the j event the portal monitor cannot be used for some reason. In addition to the monitor for initial evacuee monitoring, at least two monitors must be available for the remonitoring of evacuees (male and female) following decontamination efforts. Therefore, at least three trained monitors with handheld instmments must be available for this demonstration of evacuee monitoring. If vehicle monitoring will be done concurrently with evacuee monitoring, additional monitors must be available for this demonstration. Pursuant to the plan, MoNet, the National Guard, and the Fairfax, Tarkio, West Atchison, and Polk Township Volunteer Fire Departments provide trained monitors for this Reception Center. Therefore, the monitors available for this demonstration must represent those resources. At least six simulated evacuees per initial monitoring station (total of six) must be processed into the reception center to allow demonstra-tion at this facility of monitoring, decontamination, and registration capabilities. The actual l number of simulated evacuees can be fewer than six as each simulated evacuee can be monitored
I more than once. The monitoring sequences for each simulated es aeuee will be timed by the evaluators in order to determine whether the reception center can adequately meet the twelve-hour requirement referenced above. Decontamination procedures must be initiated (simulated) for at ! east one female and one male evacuee. l The Lamkin Grenasium Reception and Care Center facilities utilized for monitoring and i decontaminatica e ' evacuees must be fully activated and setup to receive evacuees for evaluation. This would include full staffmg of personnel required to accomplish monitoring and decontamination of evacuees and vehicles. The individuals who perform monitoring must demonstrate an operational check of the ! instruments, utilizing a check source, prior to monitoring. Information on the proper reading or l range of readings should be attached to or accompany the instrument. Instrument operability i checks and issuance of dosimetry at this facility must be observed by the evaluators. l Vehicle monitoring must be demonstrated at the Lamkin Gymnasium Reception and Care Center. This will include monitoring of both the interior and exterior of at least two vehicles. Monitoring of the air filter will not be required. Actual decontamination of vehicles will not be required; however, the vehicle decontammation area must be set up and the individuals assigned ; to this duty must be present. This portion of the objective will be accomplished by interview i including demonstration of appropriate knowledge of decontamination action levels. 1 1 Pursuant to the plan, all organizations who provide resources in support of reception and care center activities, must be present for evaluation at the Lamkin Gymnasium Reception and Care Center. This would include the Nodaway County Division of Family Services, American Red C'r oss, monitoring resources (MoNet, National Guard, volunteer fire departments) as required, University Campus Police, and the Maryville Public Safety Department. Qbiective Number 22 - Emereency Worker Monitoring and Decontamination: Full credit for emergency worker monitoring and decontamination will be granted upon the successful i demonstration of objective number 18 at the Lamkin Gymnasium Reception and Care Center. l Obiective Number 28 - Relocation. Reentry. and Return - Decision Makine: This objective will not be evaluated during this exercise. The State of Missouri will demonstrate this objective during the Callaway Full-Scale Ingestion Exercise which will be held in September 1997. However, it has been agreed that the State of Missouri may perform portions of this objective for training purposes only and will not be evaluated on their performance.
)^
Obiective Number 29 - Relocation. Reentry. and Return - Imnlementation: Responsible OROs should demonstrate the capability to implement the protective action policies, to include: ) J 1
_. _ .-__...._ _._.__._._ _ .-~ ._ _-_ __ - . . - _ . _ .- _ . _ _ _. ...__ ___ l (a) Identify resources and personnel for implememing the protective action policies; (b) Develop appropriate public instructions and in:mution releases: (c) Identify materials, resources. personnel and their placement: (d) Provide prompt notification of relaxed emergency phase protective actions to appropriate response organizations, including those responsible for congregate care; i i (e) Commit resources and personnel to control access to the restricted' zone l within the evacuated area, (these will not necessarily be the same access control points established for the emergency plume phase of the accident); i ( ! (f) Commit resources and personnel for traffic control and transportation . ! l assistance; l (g) Reinstitute essential services; l (h) Issue public instructions;
)
1 (1) Coordinate the commitment of resources and personnel for return of I l evacuees into areas of unrestricted reoccupancy; i (j) Coordinate the commitment of resources and personnel necessary for relocation of persons from areas not originally relocated but who are found to be receiving an annual cumulative dose from ground deposition in excess of state PAGS; (k) Commit resources and personnel to implement controlled access into the !
- restricted zone; i
(1) Coordinate the commitment of resources and personnel for decontamination of essential facilities; and, (m) Coordinate the commitment of resources and personnel for implementation . of public services based upon information provided by exercise controllers.
)1 Obiective Number 30 Hour Staffine: This objective will be demonstrated at the Lamkin Gymnasium Reception and Care Center by interviewing both shifts of personnel for the ;
l Relocation Center Manager. Monitoring Supervisor. and Recistration Coordinator positions. ' 1 e
-. w, .-.
. ._ _ .. _ .m.-- _ _ . _ _ _ _. -_ _ _ _ . _ _ - _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ . . _ . _ . - Ifyou have any questions or concerns regarding the aforementioned agreements, please contact Tonya Leibold at (816) 283-7085. Sincerely,
)
GMCe%i Robert G. Bissell RAC ChairmadChief Training, Exercises, and Evaluation Branch cc: Ihor Husar, PT EX-RG Kathryn Cole, PT-EX-RG Charles Hackney & Gail Good, NRC IV Mike Krumland, NPPD Bob Dye, EPA, Region VII Joe H. Keller, INEL 1 7
j Federal Emergency Management Agency
+[ Region VII
,, , 2323 Grand Bhd . Suite 900 Kansas City. MO 62108 2670 SEP - 3 :996 William E. Whitney. Assistant Director State Emergency Management Agency 1300 Military Road i
Lincoln, NE 68508 I
Dear Mr. Whitney:
p i SUBJECT; Cooper Nuclear Station Ex TI ./
'{ ale and 4d Reentry, Return, Relocatioi )
The following comments are provided f( arding objectives number 1, 2, 4, 5, 6, 8, 10, 1.1, as we discussed in the extent of play meeting held es that do not require further clarification and are i Obiective Number 1 - Mobilization: All t .
. .. ,.. a them on standby must be actually made. Your request to preposition the State of Nebraska liaisons I reporting to the Joint Information Center; the Nemaha County EOC; Richardson County EOC; I Rad. Health Monitoring Teams; and Emergency Operations Facility, is approved. These individuals cannot arrive at their respective facility until one hour (1) after receipt of the ALERT emergency classification level. Prepositioning of any additional staffis not authorized, except by written approval from this office prior to the exercise. Your request must include which staff positions will be prepositioned and which facility (ies) will be affected.
Demonstration of Objective 18 to correct the 1994 Area Requiring Corrective Action (ARCA) at the Richardson County Reception Center, will be held in conjunction with the Otoe County Reception Center demonstration at Nebraska City. Richardson County will have one monitor present to accomplish the demonstration. The demonstration will be held on November 20. 1996, at 7:00 p.m., and will require the demonstration of appropriate monitoring techniques and knowledge ofdecontamination action limits. All personnel at the Otoe County Reception Center may be prepositioned. The issuance of radiological instrumentation and operability checks must not be accomplished prior to evaluator arrival l Current rosters must be presented identifying the individuals v ho will maintain around the clock operation at all evaluated facilities. i
Objective Number 2 - Facilities: All facilities must be fully set up as they would be to support ! an actual emergency. This would include the availability of operauanal telephones and other equipment as required for response to an emergency. 1
! l Obiective Number 4 - Communications: We will expect demonstanon of the primary and at least one backup communication link identified in the plans for full demonstration of this objec-tive. This objective must be demonstrated at all facilities evaluated. All evaluated facilities and field teams are required to demonstrate the capability to access at least one communication system that is independent of the commercial telephone system. We will request copies of all
- messages and logs of message traffic.
1 i Obiective Number 5 - Emereeney Worker Exnosure Control: Emergency workers must m.r
. appropriate direct-reading and permanent record dosimetry and hase access to a dosimetry j charger in accordance with state and local plans and procedures. In addition, they must demonstrate basic knowledge of dosimetry, radiation exposure limas. and turn-back exposure i limits through an interview process. Procedures to monitor and record dosimeter readings and ,
, to manage radiological exposure control must be demonstrated. Obiective Number 6 - Field Radiological Monitoring: Each of the deployed field monitoring 4 teams must take radiation measurements at a minimum of six locations to identify the plume. A demonstration of an operational check of the instruments utilizing a check source is required. I information on the proper reading or range of readings should be attached to or accompany the instrument.
- Obiective Number 8 - Radioiodine Samnling
- The field teams must demonstrate the criteria ;
listed under this objective as they would in an actual emergency. Transport of samples to the ' l laboratory will not be reqtured pursuant to the June 21,1996, meeting. The transport of samples j j will be demonstrated during the June 1997 Ft. Calhoun Full-Scale Ingestion Exercise. Obiective Number 10 - Alert and Notification: The 15-minute clock will begin when the offsite authorities make the decision to notify the public of a Site Area Emergency. When that l occurs, the offsite organizations will have 15 minutes to activate the alert system and disseminate l an initial Emergency Alert System (EAS) (formerly Emergency Broadcast System) message. l i 4 The initial EAS message needs simply to identify the emergency classitication level and include l instructions to stay tuned to the radio station. Within the aforementioned 15 minutes, actual contact of the EAS station and dissemination of the initial message to the radio station must be demonstrated. An evaluator will be assigned to KFAB EAS station to observe the station's procedures for broadcasting the messages. We expect to see actual receipt of the messages from the county EOC. Following receipt at the radio station, procedures to broadcast the messages must be fully demonstrated up to the point of transmission. Actual broadcast of the messages or EAS test
i messages are not required. The 15-minute clock stops when the broadcast (simulated) of the EAS message by the radio station is initiated. The FEMA evaluator will remain at the EAS station until the termination of the exercise to observe receipt and broadcast procedures for all EAS messages. Copies of all EAS messages will be requested from the facility. j The procedures for siren activation must be demonstrated up to the pomt of actual activation and must be completed within the 15-minute time frame. Actual siren aemation may be simulated. In addition, tone alert radio and weather radio activation may be simulated. Obiective Number 11 - Public Instructing The 15-minute requirement will not be applied to subsequent protective action instructions provided to the public after the initial notification.
, However, subsequent messages should be disseminated in a timely manner. Also, the procedures for providing the messages to the radio station remain the same as indicated for objective number 10. Messages should be all inclusive by including previously identified areas as well as new areas. Procedures must be demonstrated, if appropriate, to ensure that EAS messages containing Protective Action Recommendations (PARS) that have been changed are rescinded and not repeated by the EAS station.
j Obiective Number 12 - Emernency Information - Media: Media briefings will be conducted at the Joint Information Center (JIC) located in the Nebraska Public Power District Building in Columbus, Nebraska. Obiective Number 13 - Rumor Control: Each rumor control start memb:r, at the JIC, must demonstrate the capability to respond to an average of at least six calls per hour throughout the emergency phase. The staff should demonstrate the capability to monitor the contents of broadcast media coverage of the emergency situation. Any trends in rumors identified by the rumor control staff must be addressed in news releases or media briefings. Obiective Number 14 - Potassium Iodide (KIh Although the decision to recommend the use of KI is not due for demonstration during this exercise, it is possible that the scenario could require it. If the decision to use KI is made, the instmetions must be appropriately disseminated to all personnel including those deployed (simulated) for traffic and access control and other missions. However, as this is a group B objective,if the decision to use K1 is not required by the scenario, all emergency workers, at all facilities, will be expected to demonstrate this objective through an interview of their knowledge of the procedures for the authorization and the use of Kl. Actual administration of KI will be simulated. Verification of K1 supplies will be accomplished during this exercise at facilities where KI is stored pursuant to the plan. Obiective Number 15 - Snecial Populations: Telephone calls to special facilities and transpor-tation providers may be simulated. However, all facilities and transportation providers which are required to be notified must be clearly identified and the simulated contacts appropriately documented. Telecommunications Device for the Deaf tTDD) calls to the hearing impaired population will be simulated and appropriately documented. l 4
- Obiective Number 16 - School Evacuation
- We will expect the capability to evacuate schools
- be demonstrated by the Locust Grove Schoolin the Auburn School District. Aubum, Nebraska.
1 An exercise evaluator will be assigned to intersiew the district superintendent (or other designated school official) and principal. In addition, at least one school bus driver must be available for an interview to determine their awareness of and preparedness for the evacuation of school children. This will include l demonstration of objectives number 4,5, and 14: communications, emergency worker exposure, and use of KI, respectively. The bus driver must have dosimetry and KI available for this demonstration. The interview described above will be conducted out-of-sequence from the exercise, during the afternoon of November 18,1996. The time for the interview will be determined later. Adequate demonstration of objective 5 by the transportation provider from the Locust Grove Elementary School will correct the ARCA identified during the November 16, 1994, exercise. During the emergency phase of the actual exercise on November 19.1996, all appropriate actions (e.g., notifications, EAS messages, etc.) must be demonstrated by the EOC staff for any public or private schools or day care facilities affected by protective action recommendations. Actual telephone calls do not need to be made; however, all contacts which would be required should be appropriately documented. Obiective Number 17 -Traffic and Access Control: Deployment of traffic and access control personnel to assigned locations will be simulated. At least two individuals who would perform traffic and access control must be available at each county EOC for an interview. During the interviews, all personnel will be expected to demonstrate knowledge of their roles and responsibilities concerning traffic and access control, as well as appropriate knowledge l concerning dosimetry and potassium iodide procedures. Obiective Number 18 - Renistration. Monitorine. and Decontamination: , At the Otoe County Reception Center, the number of evacuees required to be monitored within twelve hours is 335 (20% of evacuees assigned to the center). Based on a monitoring time of 90 seconds pursuant to the plan, two (2) monitors would be required in order to monitor that number within twelve hours per FEMA-REP-14. In addition to the two monitors performing initial evacuee monitoring, at least two monitors must be available for the remonitoring of evacuees (male and female) following decontamination efforts. Therefore, at least four trained monitors from Otoe County's monitoring resources must be available for this demonstration of evacuee monitoring. At least six simulated evacuees per initial evacuee monitor (total of 12) must be processed into the reception center to allow Otoe County to demonstrate monitoring, decontamination. and registration capabilities. The actual number of simulated evacuees can be fewer than 12 as each simulated evacuee can be monitored by each of the monitors more than once. The monitoring sequences for each simulated evacuee will be timed by the evaluators in 4
l l order to determine whether the reception center can adequately meet the twelve-hour requirement - referenced above. 1 Decontamination procedures must be initiated (simulated) for at least one female and one male evacuee. The Nebraska City /Otoe County Reception Center facility unlized for monitoring and decontamination of evacuees must be fully activated and setup to receive evacuees for evaluation. This would include full staffing of personnel required to accomplish monitoring and decontamination of evacuees and vehicles. The individuals who perform monitoring must demonstrate an operational check of the instruments, utilizing a check source, prior to monitoring. Information on the proper reading or range of readings should be attached to or accompany the instrument. Instrument operability checks and issuance of dosimetry at this facility must be observed by the evaluators. 1 Vehicle monitoring must be demonstrated at the Center. This will include monitoring of both I the interior and exterior of at least two vehicles. Monitoring of the air filter will not be required. l
- Vehicle monitoring will be accomplished following evacuee monitoring. Actual decontamina- l tion of vehicles will not be required; however, the vehicle decontamination area must be set up and the individuals assigned to this duty must be present. This portion of the objective will be accomplished by interview including demonstration of appropriate knowledge of decontamina-tion action levels.
All organizations who provide resources in support of registration center activities, must be present for evaluation at the Nebraska City /Otoe County Reception Center. Pursuant to the plan, this would include Nebraska City and Otoe County officials as well as the American Red Cross. Obiective Numher 19 - Conereente Care: In order to demonstrate this objective, the Middle , School and Senior High School in Nebraska City, Nebraska, will be evaluated on the adequacy of facilities for providing congregate care. These facilities must be open to allow a review by L the FEMA evaluator. To assist the FEMA evaluator, floor plans for each facility will be provided by the American Red Cross pursuant to discussion during the extent-of play meeting l on June 21,1996. The FEMA evaluator will conduct a walk through orthese facilities to determine, through observation and inquiries, the adequacy of the physical facilities, equipment, i personnel, supplies, and procedures. It is not necessary to set up operations as they would be in an actual emergency. Congregate care staff should demonstrate the capability to ensure that evacuees have been monitored for contamination and are uncontaminated before being allowed to enter the facility. According to the plans, The Richardson and Otoe County Chapters of the
~
American Red Cross, and Nemaha County as required. provide resources and support for the congregate care centers. Therefore. a reptesentative from each of these organizations, must be ( present during the evaluation. i 3
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Obiective Number 22 - Emercenev Worker >fonitoring and Decontamination: This objective will be demonstrated at the Auburn Fire Department by the Auburn Fire Department
- personnel. Successful demonstration of this objective. will close the two ARCAs assessed during the November 16.1994, exercise.
The individuals who perform monitoring must demonstrate an orerational check of the instruments, utilizing a check source prior to monitoring. Information on the proper reading or range of readings should be attached to or accompany the instrument. Demonstration of personnel and vehicle monitoring and decontamination will be the same as l previously described for Objective 18. Obiective Number 28 - Relocation. Reentry. and Return - Decision \1akirig: This objective will not he evaluated during this exercise. The State of Nebraska will demonstrate this objective during the Fort Calhoun Full-Scale Ingestion Exercise which will be held in June 1997'. However, it has been agreed that the State of Nebraska may perform portions of this objective for traming purposes only and will not be evaluated on their performance. l Obiective Number 29 - Relocation. Reentry. and Return - Imnlementation: Based on information provided by exercise controllers, responsible OROs should demonstrate the capability to implement the protective action policies, to include: l (a) Identify resources and personnel for implementing the protective action j policies; 1 l _(b) Develop appropriate public instructions and information releases; (c) Identify materials, resources, personnel and their placement; (d) Provide prompt notification of relaxed emergency phase protective actions to appropriate response organizations, including those responsible for i congregate care; l (e) Commit resources and personnel to control access to the restricted zone , I within the evacuated area,(these will not necessarily be the same access control points established for the emergency plume phase of the accident): { (f) Commit resources and personnel for traffic control and transportation assistance-i tg) Reinstitute essential services: (h) Issue public instructions: 6 ,
-. . . . . . . . ~ . _ -. - _._ - .. - - - - .-. .- - . . _ _ _ .
(1) Coordinate the commitment of resources and personnel for return of evacuees into areas of unrestricted reoccupancy: (j) Coordinate the commitment of resources and personnel necessary for relocation of persons from areas not originally re oeated but who are found to be receiving an annual cumulatise dose frc a ground deposition in excess of state PAGS: i (k) Commit resources and personnel to implement controlled access into the I restricted zone; 1 (1) Coordinate the commitment of resources and personnel for decontamination ofessential facilities; and. (m) Coordinate the commitment of resources and personnel for implementation of public services based upon the information provided by exercise controllers. 1 Obieetive Number 30 Hour Staffing: Twenty-four (24) hour staffing must be demonstrated by an actual shift change of all key staff. Double staffing will not be allowed as an acceptable demonstration of this objective. The shift change must occur to allow the second l shift individual to demonstrate the capability to perform the appropriate responsibilities required i of the position. Therefore, the time for the shift change will be suggested by controller input. For traming purposes, first shift personnel can remain in the facility after the tumover but are not to be involved in any exercise decision-making. Incoming personnel must receive an adequate turnover briefing before relieving outgoing personnel. We will expect this objective to be demonstrated by the State Emergency Operations Center, Dose Assessment / Field Team Coordination, Field Teams, and the Richardson County Emergency Operations Center. For each of these functions, all key staff pursuant to the plan must demonstrate a shift change. Key staff for the State are identified on pages 6 through 8 of the State plan, and for Richardson County
- on pages 8 and 9 of the Richardson County plan.
Pursuant to an August 29,1996, discussion between your staff and my office, FEMA Region Vil will be responsible for publicizing the public meeting to be held on November 21,1996, time to be determined later. I l l \ . _ _ _ _ _
+
1 i l ifyou have any questions or concems regarding the aforementioned agreements please contact 1- Tonya Leibold at (816) 283-7085. i Sincerely. j kcAM(./ l M 4 Robert G. Bissell
- RAC Chairman / Chief
- Training, Exercises. and Evaluation Branch
! cc: Ihor Husar, PT-EX-RG j Kathryn Cole, PT-EX-RG Charles Hackney & Gail Good, NRC IV
- Mike Krumland, NPPD 1 Bob Dye, EPA, Region VII i
Joe H. Keller, INEL i J j i n 1 0 1 a ' 1 , 1 a i i e t l a e ] '. J
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- 3. GENERAL EXERCISE INFORMATION 3.I' Facilities Activated 3.1.1 The Nebraska Public Power District
- a. Control Room (Simulator)
- b. Technical Support Center (TSC)
- c. Operatibns Support Center (OSC)
- d. Emergency Operations Facility (EOF)
- e. Offsite radiation monitoring teams
. 3.1.2 Ofsite Agencies 1996 is a biennial exercise year. The States of Nebraska and Missouri and plume i
- exposure counties will participate in this exercise. FEMA will evaluate State and local emergency response.
- a. Nebraska Emergency Operations Center, Lincoln. NE
- b. Missouri Emergency Operations Center, Jefferson City. MO
- c. Nemaha County Emergency Operations Center. Auburn. NE
- d. Atchison County Emergency Operations Center. Rock Port, MO q 3.2 Exercise Organization J l
The Organization participating in the exercise consists of the Exercise Director, Exercise Coordinator, Facility Lead Controllers, Controllers. Evaluators, Observers, and Players as follows: 3.2.1 Exercise Director (Emergency Preparedness Manager) The Exercise Director is responsible for the post-exercise Controller debriefing, the CNS exercise critique, and NRC cri;ique and exit meeting. Subsequent to the exercise, he will direct the preparation of a consolidated evaluation package and preparation of an itemized list of recommended corrective actions. l 3.2.2 Etercise Coordinator The Exercise Coordinator is responsible for the conduct of a successful exercise and will coordinate exercise preparations including the development of the scenario package. The Exercise Coordinator will ensure the safe conduct of the exercise and ensure tnat the conduct of the exercise does not adversely impact the operation of the station. He is responsible for resolution of any General Etercne Injhrmatium Paec 3-1 C E.\ER..\ECTl_6 WP3
l scenario-related questions. The Exercise Coordinator w;ll assist with the preparation of the consolidated evaluation package. 3.2.3 Controllers Controllers are qualified personnel selected to perform functions as follows: A Lead Controller is assigned to each emergency response facility. The Lead , Controller is responsible for all Controller, Evaluator, and Observer activities l in a given facility and, as appropriate, its associated teams. Controllers for teams or sub-areas of a facility report to the Lead Controller of that facility. Controllers will deliver Exercise Messages or Data to designated Players at specified times and places during the exercise, inject or deliver contingency messages as required, and keep the exercise actiom moving according to the scenario, observe the exercise at other assigned loca: ions, and prepare an evaluation. Controllers will submit written obsenanons to the Lead Facility Controller who will summarize all comments for submittal to the Exercise Coordinator. Controllers are provided with the instructions contained in Section 4.0 of this manual. 1 3.2.4 Evaluators Evaluators are personnel assigned to evaluate the etYectiveness of personnel, l organizations, and activities in response to the scenario. They will evaluate l performance on the basis of standards or requiremen:s contained in the Emergency Plan, Implementing Procedures, exercise messages, or as described herein. Most Controllers will also function to evaluate the facility or function to which they are assigned. They will document their findings on evaluation forms. 3.2.5 Obseners A limited number of Observers may be allowed to watch the Exercise. They are prohibited from interaction with the Players. The purpose of their attendance is generally personal education. 3.2.6 Inspectors inspectors are members of the NRC evaluation team and may have prior knowledge of the exercise scenario. At their assigned locations they will observe the exercise and prepare an evaluation to be presented at the exit l meeting and critique. I i I Generist Esercase Int:>nmetron P.sec .4 2 C EXER AECTI_^ MP3
3.2.7 Players Players include station and other utility personnel assigned to perform emergency functions as described in the Emergency Plan and Implementing Procedures. Players from offsite organizations and agencies (County, State, and private industry) are also participants in the exercise. 3.3 Conduct of the Exercise The exercise will timulate a radiological incident at the Cooper Nuclear Station in order to allow demonstration of the effectiveness of NPPD Emergency Plan for CNS, emergency response personnel, facilities, and equipment. It will be initiated by abnormal events requiring the Shift Supervisor to implement the Emergency Plan. 3 All notifications to NPPD, State and local responders ui'l be made in accordance with applicable procedures and policies, to the actual agencies. or to a Control Cell (for those agencies not participating). The exercise will include the un of a " live" simulator. The CNS Simulator will duplicate plant response to actioris taken by the on-shift crew of operators. Indications and annunciators which are modeled by the software will be available to indicate to the crew the status of systems and equipment. a> the operators respond to the scenario.
"Real time" data from the Simulator will also be fed to other emergency response {
facilities (TSC and EOF) using terminals connected to the Simulator. The terminals will provide Players in these facilities similar information normally available through the Plant Management Information System (PMIS). The Simulator will be the central point for dissemination of plant data and is the key to ensuring that the exercise progresses on schedule. In the event of a failure of the Simulator computer, the Exercise Coordinator will determine the course of action. , An attempt may be made to " reset" the Simulator and start over. or at a designated place. If this is unsuccessful, the Exercise Coordinator may direct that plant indications, parameters and annunciators be provided to the Control Room operators (and others) using message forms and plant data sheets. Plant information is provided on these data sheets similar in format to what the Simulator would provide. This is so that at no time will the messages " prompt" the Players or provide undue assistance in recognition of events. To more closely approximate the data that would be available in an actual emergency situation. information asailable on PMIS will also be provided in the TSC and the EOF where output consoles are located. l Contingency messages are to be delisered onh when condmons desenhed m the l l General Etercise injhrman,m Pa.:c 3-3 C EAER .\ELTI.6 wPS l l
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Controller notes have been met. Receipt of a contingency message by a Player is
~NOT necessarily indicative of an error, and should not be construed as such. Some data on these messages, for example, is provided only when specific actions have been taken to access the information or when a particular extent of play activity is required to demonstrate a exercise objective or to keep the Scenario on its timeline.
Radiological and meteorological data. presented in this manual and any information included in the supplemental scenarios will be disseminated by Controllers only when Players demonstrate the capability to obtain the information from appropriate sources. At no time, unless noted speci6cally as an exception, will information be provided at a point where it would not be available in a real emergency. Controllers shall deliver allinformation and messages in the time and manner described on the message form or as directed at the Controller brienng. Controllers may inject other information or change a message to ensure that the exercise progresses as planned only with the concurrence of the Exercise Coordinator. l Players are expected to " play" the scenario to the extent permitted by their Controller. That is, response to each situation should be as. realistic as possible, without i simulation, consistent with the maintenance of personal and plant safety. I Notifications of, and contact with supervisors, plant management, and offsite agencies - l 3 will be made in accordance with applicable procedures and instructions (unless a Controller issues instructions.to the contrary). Only those simulations identi6ed by a Controller or speci6cally identi6ed in brietings are permi>sible. Non-participating organizations may be simulated through the use of the Control Cell. 3.4 Precautions and Limitations This section provides information for all exercise participants regarding guidelines to be followed throughout the conduct of this exercise. Prior to initiation of the exercise, pre-exercise briefings will.be held to review the exercise process and expectations with exercise participants. 3.J.1 Actual Emergencies it will be the responsibility of any Exercise Controller. Observer. Evaluator. or Player who becomes aware of an actual emergency to stop exercise response in his/her immediate area and immediately contact 1) the reai Control Room and then 2) the Exercise Coordinator. The exercise will be suspended until the real emergency has been appropriately evaluated. The Exercise Coordinator or Exercise Director will make a determination whether to continue. terminate or re-schedule the exercise.
.A. J. 2 UllMifi* CimdiHtm.\
General E.sercise infinmation Paec 3 J C EXER .\EL7l_b % P3
I I At no time during the course of the conduct of thn exercise shall any Controller, Evaluator, Observer, Player, or Inspector undertake any action l which would place either an individual or component in an unsafe condition.
; All personnel are responsible for intervening in such a case and terminating
- the unsafe activity immediately.
No action will be taken which reduces the margin of safety in the olant. 3.4.3 Operating Equipment } i ;
- Ali (simulated) repair activities associated with the scenario will be simulated j with extreme caution around operating equipment. There are to be ng manipulations of any plant operating systems, valves, breakers, or controls in j 1 response to this exercise. These are to be simulated coordinating with your Controller. No pressurization of tire hoses, discharging of fire extinguishers, or initiation of any fire supprmion systems are allowed without Controller'
- approval. No such actions we be allowed within plant buildings.
1 f 3.4.4 Public Announcements All te'lephone communications, radio transmissions, and public address i announcements related to the exercise must begin and end with the statement.
"This is a drill". Should a Controller witness an exercise participant not observing this practice, it is the Controller's responsibility to remind the individual of the need to follow this procedure.
l
- Care must be taken to assure that any non-participating individuals who may j observe exercise activities or overhear exercise communications are not misled into believing that an actual emergency exists. Any Controller who becomes aware of an individual or group who may have become alarmed or confused i about the situation, should. explain the nature and intent of the exercise.
3.4.5 Motor Vehicle Response All motor vehicle response to this exercise, whether it be ambulance, tire f fighting equipment, police / security vehicles or field monitoring teams shall follow normal motor vehicle laws, including posted speed limits stop lights / signs, one way streets, etc. Red lights and.'or sirens will ngj be operated l on emergency vehicles for the purposes of th' exercise. 1 a 1 1 ) i General Eterme In/hrmatiem % :e 3 ? C EXER $ECT) 6 uP5 I 4
i l i 3.5 Abbreviations Reactor AC Auxiliary CD Condensate Drain Condensate CDP Computer Data ACB Air Circuit Breaker Processing ACAD Atmosphere CFiCFD Condensate Filter l Containment Demineralizer Atmosphere Dilution CHF Critical Heat ACD Auxiliary Flux Condensate Drains Cl Chemistry ACRS Advisory Committee Instrumentation l on Reactor CIC Component L . Safeguards identification l ADS Automatic Code Depressurization CM Condensate l System Makeup ALARA As Low As CMFLPD Core Maximum l Reasonably Fraction of Achievable Limiting Power ALRW Augmented Liquid Density i Radwaste CNS Cooper Nuclear j ANN Annunciator Station ' AOG Augmented Off Gas CNSNO CNS Number AOV Air Operated Valve (Used for part APRM Average Power numbers only) Range Monitor CP Process AR Air Removal Computer ARM Area Radiation CPP Control Power Monitor Panel AS Auxiliary Steam . CRDM Control Rod ASB Auxiliary Steam Drive Mechanism Boilers CR Control Room ATS Alarm Trip Setting CRS Control Room ATWS Anticipated Supervisor , Transient Without CS Core Spray Scram CSCS Core Standby BF Booster Fan Cooling System BLDG Building CSP Core Spray Pump BOP Balance of Plant CST Condensate l BPV Bypass Valve Storage Tank BUCLE Backup Core Limits CW Circulating Water Evaluation CWP Circulating Water BWR Boiling Water Pump General E.sercose Irt]hrm<stiam P<rc< 3-0 t Este >Ecri_s ars
i l DBA Design Basis ~ Device Accident HCU Hydraulic DEH Digital Electro- Control Unit Hydraulic System HEPA High Efficiency DG Diew! Generator Particulate DPM- Disintegrations Per Absorber Minute HP Health Physics or DV Drain Valve or High Pressure Dump Valve HPCI High Pressure DW Demineralized Coolant injection , Water HVAC Heating. l ECCS Emergency Core Ventilating, and Cooling Systems Air Conditioning ECST Emergency HX Heat Exchanger l Condensate Storage lA Instrument Air i Tank I&C Instrumentation-EDF Equipment Data File and Controls l
- EE Electrical Equipment ILRT Integrated Leak ,
l EF Exhaust Fan Rate Test ! EOF Emergency INPO Institute of . Operations Facility Nuclear Power I EOP Emergency Operations Operating Procedure INTK Intake Structure EPIP Emergency Plan IRM Intermediate implementing Range Monitor l Procedure EPRI Electric Power JIC Joint Information l Research Institute Center EQ Equipment LCO Limiting Qualification Condition for ERP Elevated Release . Operation Point - LER Licensee Event ES Extraction Steam Report ! ESS Engineered LLRT Local Leak Rate , Safeguard System Test l l : FEMA Federal Emergency LOCA Loss of Coolant Management Agency Accident FO Fuel Oil LPAP Low Power FP Fire Protection Alarm Point FPC Fuel Pool Cooling LPCI Low Pressure and Cleanup Coolant injection G.E. General Electric LPSP Low Power l GM Geiger-Mueller Setpoint l HAD Heat Actuating LPRM Local Power - \ General Eserciw Int;n mariam Pace 3 ' C EXER >ELTif %PS l-
Range Monitor Maintenance LSA Low Specific PMIS Plant Activity Management MC Main Condensate Information
.MCC Motor Control System Center Q.A. Quality MCPR Minimum Critical Assurance Power Ratio Q,C. Quality Control MOV Motor Operated REM Rod Block Valve Monitor 4 MPC Maximum RCIC Reactor Core Permissible Isolation Cooling l Concentration REC Reactor i MS' Main Steam Equipment l MSIV Main Steam Line Cooling i Isolation Valve RF Reactor l
MSL Main Steam Line Feedwater or 'MWR Maintenance Work Recire Fan t Request RFP Reactor Feed NPPD Nebraska Public Pump Power District RFPT Reactor Feed - NPSH Net Positive Suction Pump Turbine Head RHR Residual Heat NRC. Nuclear Regulatory Removal Commission RMA Radiation NRHX Non-Regenerative Monitoring - Heat Exchanger ' Area l NSSS Nuclear Steam RMCS Reactor Manual Supply System Control System OBE Operating Basis RMP Radiation Earthquake Monitoring - ' OG Off Gas Process OPL Operating Plant RMV Radiation Limits Monitoring - OSC' Operations Support Valve Center RO Reactor Operator PASS Post-Accident RPIS Rod Position . Sampling System Information
-PC- Primary System Containment RPS Reactor P&lD- Piping and Protection System Instrumentation RPV Reactor Pressure Drawing Vessel PM Preventatis e RRP R eactor Gs trerit! Etercure In]<rrmistrum Par;:e J S C EXER AECTI.6 %PS
1 I I Recirculation Pump Vessel Bottom) 1 RRMG Reactor TB Turbine Building l Recirculation MG TEC Turbine i Set Equipment RSCS Rod Sequence Cooling i Control System TG Turbine RTD Resistible Generator l Temperature TIP Traversing In-Detector Core Probe RTS Reactor Trip System TLD Thermoluminesce i RWCU Reactor Water nt Dosimeter Cleanup TSC Technical Support RWM Rod Worth Center Minimizer USAR Updated Safety l l SA Service Air Analysis Report l SDC Shutdown Cooling WT Water Treatment SDV Scram Discharge Volume SDM Shutdown Margin SGT or SBGT Standby Gas Treatment SJAE Steam Jet Air Ejector SLC Standby Liquid Control SORC Station Operations Review Committee SPDS Safety Parameter Display System SRAB Safety Review and Audit Board - SRM Source Range Monitor SRO Senior Reactor Operator SRV Safety / Relief Valve SS Shift Supervisor SSE Safe Shutdown Earthquake STA Shift Technical Advisor SW Service Water TAF Top Active Fuel 1352.56" Abose l General Eteniw In);>nnanum Paec 3 9 C EXERhELTl 6 %P3
m _ _. _ _ ,___ __ . _ _ . _ _ _ _ ___ _ _ _ _ _ _ _ _ _ _ l 3.6 Definitions l l ALERT: The level of emergency classi6 cation which indicates that events a e in progress or have occurred which invohe an actual or potential substantial degradation of the level of safety of the plant. l l ANTICIPATED TR ANSIENT WITHOUT SCR AM ( ATWS): Failure of the reactor l control rods to insert into the core upon a scram signal from the Reactor Protection l System or the failure of said system to initiate a SCRAM when Reactor Protection System trip limits have been exceeded.
- ASSESSMENT ACTIONS
- Those actions taken during or after an accident to obtain l and process information that is necessary to make decisions to implement specific l emergency measures.
i CONTROL ROOM (CR): The principle onsite location from which the reactor is controlkd and from which emergency control is initially esercised. CONTROLLER: A member of the Exercise control group, assigned to one or more activities or functions for the purpose of keeping the action going according to a scenario, resolving scenario discrepancies, and supervising the actions of the players. CORRECTIVE ACTIONS: Those emergency measures :aien to improve or terminate an emergency situation. , DECONTAMINATION: The process'by which the body or an object is relieved of radioactive substances (contamination). l~ DOSE ASSESSMENT: The process of estimating the amount of radiation a person
- will potentially receive as a result of exposure to a radiological release.
, DRILL: A supervised event aimed at evaluating, developing, and maintaining skills j m a particular operation. l- EMERGENCY ACTION LEVELS (EALs): Radiological dose rates; specific L contamination levels or airborne waterborne or surface deposited concentrations of !. radioactivity; or speci6c plant conditions that may be used as thresholds for initiating specific emergency measures. Genend Esercise Injhnnatoon Pa;c.h!O l' EAER .\ECTif WP3
. - . . ~ .- . . - . - . . - _ - _ . - . - _ . - . - - _ _ - _ . . - - - - . - . _
f EMERGENCY OPERATIONS CENTER (EOC): An emergency response facility 2 from which government officials exercise direction and control. The EOCs are l located as follows: i l State of Nebraska: 1300 Military Road Lincoln NE
- State of Missouri: 1717 Industrial Drive 1 Jefferson City, MO l
Nemaha County: Auburn Fire Station Auburn, NE Richardson County: County Courthouse (Basement) Falls City. NE l Atchison County: 101 Highway 136 East Rock Port, MO . j EMERGENCY OPERATIONS FACILITY (EOF): The NPPD emergency response facility from which overall direction and control.a're exercised for emergencies at CNS. The facility also provides a. central point of contact for communications and external (non-NPPD) organizations, and is fully activated for emergencies classified as an Alert or higher. EMERGENCY PLANNING ZONES (EPZs): The land areas encompassed within approximately 10 and 50 mile radii of CNS, in which protective actions nuy t>e necessary to protect the public in the event of a nuclear plant accident. The 19 mile zone is referred to as the Plume Exposure EPZ: the 50 mile zone is termed tne Ingestion Exposure EPZ. EMERGENCY RESPONSE FACILITY: Any of several oasite and offsite centers which are activated to coordinate emergency actions. Included in this category are the Control Room. Technical Support Center. Operations Support Center. Emergency Operations Facility Media Release Center. and State and local Emergency Operations Centers. EV A LU ATOR: A member of the exercise evaluation group assigned to one or more activities or functions for the purpose of evaluating and making recommendations for improvement. An evaluator may sene in a dual capacity as both a Controller and Evaluator. EXCLUSION AREA: The area surrounding the CNS in which the NPPD has the
~
authority to detdrmine all actisities including exclusion or removal of persons and Genent! Ewrciw Injbnnarian Pa:c 31I t EXER hECTIf WF5
. .__ _ __ ~ . _ , . ._._.. _ . _ _ _ _ _ _ __ _ _ _ _ __. _.. _.__._._ . _ _
l property from the area during accident conditions. EXERCISE: A ; event which tests the overall functions and capabilities of organizations involved in responding to an emergency situation. An exercise will usually simulate an emergency that results in offsite radiological releases which ; require response by offsite authorities. I GENERAL EMERGENCY: The most severe level of emergency classification which indicates that events are in progress or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. Release of radioactive material can be reasonable expected to exceed PAG exposure levels offsite. I INGESTION PATHWAY: .The exposure mode for which :he zone of concern j encompasses an area of approximately 50 mile radius from ingestion of contaminated water or foods; such as mild or fresh vegetables. The period of potential exposure , l could range in length from hours to months. JOINT INFORMATION CENTER HIC) formerly MEDI A RELEASE CENTER: An emergency response facility, staffed by NPPD. local. State. NRC and FEM A officials. The JIC provides a forum and point of contact for a coordinated release of news and information to the news media, general public, datrict employees and special interest groups. OBSERVER: An individual authorized to observe the Exercise, but is not authorized to interact with the players. OFFSITE: All areas outside the Protected Area (the area outside the fence. May also be used to refer to areas over which NPPD has no jurisdiction or control over i persons' actions. For example, when refering to a release 'offsite' OFFSITE would l be synonymous with OWNER-CONTROLLED AREA (OCA), below. ONSITE: All areas within the Protected Area (the area inside the fence) surrounding CNS. OFFSITE MONITORING TEAMS talso called Downumd Survey teams): Tw o-person teams responsible for monitoring radiation levels in the environment and collecting soil, air, vegetation, snow, and water samples for laboratory analysis. OPERATIONS SUPPORT CENTER (OSC): An onsite emergency response facility which provides a location where emergency response teams can be assembled and , coordinated during an emergency. l , Generau Eterme Injhrmarium Pax 3 l: C EXER AELTl} %P3
i l l OWNER-CONTROLLED AREA: The area around the CNS that is owned /and to l which the access controlled, by NPPD. l PARTICIPANT: An individual who has some part in the Exercise, whether as an Evaluator, Controller. Player or Observer. l PLAYERS: All individuals (CNS. NPPD personnel, and mdividuals from offsite organizations and agencies) who are assigned to perform functions of the emergency response organization, as described in the appropriate Emergency Plan and Emergency Plan Implementing Procedures. PLUME EXPOSURE PATHWAY: The exposure mode for which the zone of concern encompasses an area of approximately a 10 mile radius around CNS. The principle exposure sources in this area: 1) whole body euernal exposure to gamma radiation from the plume and deposited material, and L mhalation exposure from the passing radioactive plume. The period of potential expo >ure could range from hours to days. POPULATION AT RISK: Those persons for whom protective actions would be taken. PROTECTED AREA: The area within the Site Boundan encompassed by physical barriers and to which access is controlled for security purposes. PROTECTIVE ACTION: Those emergency measures taken after an accident or an uncontrolled release of radioactive materials has occurred. for the purpose of preventing or minimizing radiological exposures to personnel that would otherwise occur. PROTECTIVE ACTION GUIDES (PAGs): Projected radiological doses to individuals in the general population which warrant protective action following a release of radioactive material. SITE AREA EMERGENCY: The level of emergency classification which indicates that events are in progress or have occurred which involse actual or likely major failures of plant functions needed for protection of the publ c. Any releases of radioactive material are not expected to exceed Protection Action Guide (PAG) exposure levels, except within the Site Boundary. TECHNICAL SUPPORT CENTER (TSC): An onsite emergency response facility for use by technical and management personnel in support of the command and control functions executed in the Control Room. l Pace 313 C EVER . RECTI _6 % P3 Gerseral Esercr<e forfonmittor
I I I t l UNUSUAL EVENT: The lowest level of emergency classification, which indicates that events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant. 3.7 References 3.7.1 CNS Emergency Plan - Nebraska Public Power District 3.7.2 CNS Emergency Plan implementing Procedures l l 3.7.3 CNS Technical Specifications l l 3.7.4 CNS Updated Safety Analysis Report 3.7.510 CFR 50.47, 50.54 and Appendix E 3.7.6 NUREG 0654/ FEMA-REP-1. Rev. I 3.7.7 CNS Piping and instrumentation Drawings
)
General Dercise Injbrmatwn Pa;c 3 iJ C. EXEP .\ECTI_A u PS
I
- 4. CONTROLLER / EVALUATOR INFORMATION 4.1 General Information Each Controller / Evaluator should be familiar with the foi;owing:
4.1.1 The objectives of the Exercise (Section 2.0). 4.1.2 Applicable precautions and limitations (Section 3.01. ' 4.1.3 The exercise scenario, including the initial conditions and the expected course l of action to be taken (Section 7.0). i l l 4.1.4 The various plant locations to be involved in the scenario and specific items :o l be observed at those locations. 4.1.5 The evaluation checklists. l 4.2 Controller Instructions
- 4.2.1 Controllers will position themselves at their assigned locations 15-30 minutes l prior to the activation of the facility or team for whreh they have
- responsibility.
t 4.2.2 Communications will be tested prior to exercise commencement. All facility l clocks are to be synchronized with the Simulator clock. 4.2.3 All Controllers will comply with instructions from their Lead Facility Controller and Exercise Coordinator. 4.2.4 No messages shall be delivered out of secuence or other than as written unless I authorized by the Exercise Coordinator. 4.2.5 Controllers will nol provide information to the Players regarding scenario progression or resolution of problems encountered in the course of the l simulated emergency. The exercise participants are expected to obtain i information through their own organizations and exercise their own judgement in determining response actions and resolving problems. 4.2.6 in the event a Player insists that certain parts of the scenario are unrealistic. Controllers hase authority to remind Players that the purpose of the exercise is to demonstrate the effectiveness of the Emergency Plan if an emergency occurred. The Controller may clarify any questions regarding scenatic
'ontent.
Corttroller'Esaluator liithrnrarion P. tee J-l c Ext.8.snitf, aes i
4.3 Evaluator lustructions - Each Evaluator will take detailed notes regarding the progress of the exercise and resoonse of the exercise carticioants at their assigned locations. Each Evaluator ; should note arrival and departure times of participants, times when major activities or l milestones occur, and problem areas encountered. Esaluator>' comments will be used i to reconstruct the exercise chronology and preparing a wro'en evaluation of the ! exercise. ! l Evaluation criteria are provided to the Controller / Evaluator organization. These are to be completed and provided to the Exercise Coordinator at the conclusion of the j exercise. ' l 4.4 Personnel Assignments ' Controller / Evaluator organization assignments are listed in Table 4.4-1 I 4.5 Simulator Instructions The simulator will be relied on primarily for data generation and plant response interactions with the Control Room crew. Should it malfunction or go off-line (e.g., ; a loss of power to the Training Center), the Exercise Coordinator has several options i to choose from. They include: 1
<a stopping the exercise and conducting it the following day (provided Simulator repairs can be performed);
1 i e completing the exercise using the data sheets provided in the Exercise Manual; or ?
- ending the exercise if most o'f the objectives have been demonstrated. (Unmet 2
objectives would be re-scheduled for a later date.) i ~ l l l I 4 t i J J Co stroller' Evaluator injhnnatwn Pa;c t .' C EXER .\Es TI 6 kPS l
_ _ _ . . _ _ _ . . _ _ . _ _ _ _ _ . . _ _ _ _ . _ _ _ . _ _ _ .._ _ _ _ _ ._ m . . . _ CONTROLLER / EVALUATOR ASSIGN \f ENTS TABLE 4.4-1 CONTROL ROON! SIMULATOR Robert Hayden Exercise Coordinator
. Dave Vanderkamp Control Room Activities Duane Shallenberger Control Room Operators Brian Murphy Control Room Activities Don Dea Instructor Station Operator OPERATIONS SUPPORT CENTER Mike Krumland LEAD OSC Controller Duane Anno Controller / Controller Larry Cade Chemistry /HP Activities Wade Towne Repair / Rescue / Reentry Teams Chuck Behr Repair / Rescue / Reentry Teams Jerry Patterson Repair / Rescue / Reentry Teams Ed Bishop Repair / Rescue / Reentry Teams Steve Anderson Repair / Rescue / Reentry Teams Joe Harpham Repair / Rescue / Reentry Teams Todd Lavigne Repair / Rescue / Reentry Teams Kurt Jennings Repair / Rescue / Reentry Teams Jerry Whisler in-plant Rad Monitoring Teams Bruce Duncan ' In-plant Rad Monitoring Teams Joe White In-plant Rad Monitoring Teams u Bill Bowles Fire Brigade Team
) Ed Jackson Operations Teams Carl Holm Operations Teams Kent Chrisp Operations Teams l TECHNICAL SUPPORT CENTER Jim Kelsay LEAD TSC Controller Cory Kelsey TSC Controller Phillip Wade TSC Evaluator l Brian Newell TSC Evaluator Kent Sutton TSC Engineermg Controller Contiraller Evaluator Irf rrumtrium Paec t 3 c EXER M Tl_6 uP5
l EMERGENCY OPERATIONS FACILITY l l Brad ' Houston LEAD EOF Controller l Ken Pounders EOF Management Jim Long EOF Evaluator Terry Brown Dose Assessment ae:n nies TBD Field Team Coordina:;on l DOWNWIND SURVEY VElllCLES Larry Corey N.P.P.D. D/W Team #1 Mike Dorn N.P.P.D. D/W Team : l TBD Missouri D/W Team :1 ! TBD Missouri D/W Team :: l TBD Nebraska D/W Team ri TBD Nebraska D/W Team :: i , I i f JOINT INFORMATION CENTER LIIC) i 1 Noreen Thoms LEAD JIC Controller TBD flC Evaluator TBD JIC Controller i l l l i , Controller' Evaluator Intbnn<uton l'a t d-J L E\ER Mt T) n A PS i l
. _ l
- 5. PLAYER INFORMATION S.1 General Information This section provides guidelines for all exercise Players. which should be followed throughout the conduct of the exercise. A pre-exercise briedng will be held for Players to review the exercise process. including "Precaunon and Limitations" in Section 3.4, and the following information.
The success of the exercise is largely dependent upon Player reaction, Player knowledge of their appropriate Emergency Plan and implementing Procedures, and an understanding of the purpose of the exercise. Initial conditions which will affect Player action or reaction will be provided to the Players at the time the exercise begins. However, most of the elements of the exercise play will be introduced ~ through the use of controlled casualties on the " live" simulator. Players, therefore. are responsible for initiating actions during the exercise in accordance with instructions for their particular function. Each Player will advise his/her Controller prior to performing required emergency actions during the simulated activities to ensure that the Player is credited for his/her actions. Players are reminded not to be excessively. critical with the mechanics or cause of the execise scenario. This exercise is desiened to evaluate 'he Emergency Plan. Imolementine Procedures. and the Emereenev Response Orgamzation.~ Additionally, I the exercise is a training vehicle for NPPD personnel to practice coordination with outside organizations in a simulated emergency environment. Players should note any needed improvements which come to their attention 'during the exercise and submit them to the appropriate Controller at the conclusion of the exercise. I
- it is necessary to postulate a series of equipment failures and other combinations of events, in order to develop an accident sequence that culminates in a significant release of radioactivity to the environment. Please accept exercise information and messaces as written. and rescond as thouch the deoicted event occurred. If corrective ;
actions are discovered that would terminate the emergency. they should be identi6ed l to a Controller so that the exercise can continue on schedule. l S.2 Player Guidelines l 5.2.1 Maintain a serious, professional attitude throughout the exercise. 5.2.2 Teamwork is essential: Do your job and then help other people do theirs. For example, if you know certain information should be asailable, ask for it. This makes you look good and may reduce a deficiency for someone else. l Player Infonnatwn Pax bl DRt EMR SELTI * \\ PS i l
l l 5.2.3 Brainstorm and look for all oossible solutions or consequences of events. i Maintain the " big picture" of what is happening. 5.2.4 Identify yourself by name and function to the Controller in your area. 5.2.5 If you are entering normal nuclear station radiation areas. observe all rules and 1 procedures. No one rincludine Controllers) is exemnt from normal station radiofonical oractices and orocedures. NOTE: DO NOT ENTER ACTUAL HIGII RADIATION AREAS IN Tile PLANT; FOLLOW ALARA PRINCIPLES. 5.2.6 Observe all normal security orocedures. All normal security procedures are in effect without exception. If a security condition arises. obey immediately the directions of Security Guards. 5.2.7 Initiate actions in accordance with instructions and responsibilities. 5.2.8 Communications should be concise and formal with use of abbreviations-minimized. Always include "This is a drill". 5.2.9 Use and demonstrate knowledge of the Emergency l>!an and Implementing Procedures. 5.2.10 No action will be taken which reduces the margin of safety in the plant. No other actions will be simulated without Controller approval. 5.2.11 Keep a list of items you believe will improse the Emergency Plan and/or procedures. Provide this to your Controller / Evaluator at the end of the exercise., l 5.2.12 Remember one of the main purposes of a exercise is for you to assure yourself that you are a'dequately prepared. Areas for improvement or lessons learned, when identi6ed, will improve your overall emergency preparedness. i i ! l I Player Infhnn inon. Pa .; < <: DR1 EXER AECTI), aP$ l 1 i
j 6. SCHEDULE OF EVENTS 6.1 Times and Places l Event Place Time p_ ale i Exercise Controller / Auditorium 08:00-12:00 Nov 15 Evaluator Walkthrough i NRC Entrance EOF 09:00-11:00 Nov 18 l and Facility walkthrough NRC Scenario brief EOF 13:00-14:30 Nov 18 Exercise Player Auditorium 15:00 16:00 Nov 18 Briefing Conduct of Exercise / Va'rious All Day Nov 19 Player Critiques ! Controller Critique ' EOF 08:00 Nov 20 l Session l i FEMA Exi; with Auditorium 10:30 , Nov 20 Sta es/ Counties Exercise Critique TBD 08:00-09:00 Nov 21 Presentation to NRC Exercise Critique TBD 09:00-10:00 Nov 21 by NRC and exit ' FEMA Public meeting Auditorium 12:30 Nov 21 Player De-brief Auditorium 13:00 Nov 22 I Schedule of Dents P.tec 0 I DRV EXER SECTI o WP5 l 1
6.2 Travel Information/ Permission to Observe For prior arrangements, questions, or permission to obserse. contact: hir. Robert W. Hayden P.O. Box 98 Brownville, NE 68321 (402) 825-5270 Airnorts
- 1. Omaha, NE - Approximately 75 miles. From airport, take Route 75 South (-2 mi), Route 6 East ( ~ l mi), Interstate 29 South ( ~65 mi),
Route 136 West to Brownville (~5 mi), follow signs to Cooper Nuclear Station (~ 2 mi).
- 2. Kansas City, htO'- Approximately 90 milei. From airport, go East, take Interstate 29 North ( ~ 80 mi), Route 136 West to Brownville ( ~ 5 mi), follow signs to Cooper Nuclear Station (- 2 mi),
hiotels
- 1. Rock Port inn (816)~44 n282 Rock Port, h10
- 2. Oak Grove inn (816) 744-5357 Rock Port, h10
- 3. Palmer House (402) 274-3193 Auburn, NE 4 Auburn inn (402) 274 3143 Auburn, NE
- 5. Arbor hianor (402) :~a-M63 Auburn. NE Food:
A contract food service provides hot breakfast and lunch. weekdap only. There are also a number of vending machines on-site and in the Training building (off site). In addition there
- l. are numerous small restaurants in nearby commumties.
- Scheslule nf Etrno Pa s b .' DRV EXER SECTI 6 WP5
TABLE OF CONTENTS VOLUME 2 SCENARIO-SPECIFIC INFORMATION (confidential)
- 7. SCENARIO OVERVIEW / OPERATIONS INFORMATION 7.1 Close of Business, day before conditions 7.2 Initial Conditions, day of conditions 7.3 Simulator SET-UP, Triggers 7.4 Narrative Description (Executive Summary) 7.5 Supplemental Scenario Overview
- 8. ON-SITE RADIOLOGICAL CONDITIONS 8.1 Data generation assumptions and methodology 8.1.0 Area Radiological Maps 8.2 Release Source Term 8.3 Reactor Water Activity 8.4 Reactor Building Activity 8.5 Release rate at the Elevated Release Point (ERP) ,
I
- 9. OFF-SITE RADIOLOGICAL CONDITIONS 9.1 Downwind Survey Team CONTROLLER Data Sheets 9.2 Recovery, Re-entry, Relocation objective (offsite) demonstration data
- 10. Joint Information Center (JIC) rumor messages Table of Contents for Sections 1-6 are contained in Volume 1 of this Exercise Manual.
l l
7.0 SCENARIO OVERVIEW / OPERATIONS INFORMATION 7.1 Close of Business, day before conditions November 18. 1996. Over the last two days western Nebraska has experienced a major winter storm. A major sleet storm deposited large quantities of ice on NPPD transmission lines in the western half of the state. This was followed yesterday by a shift to an arctic jet stream pattern with high winds which dropped temperatures into the single digits. The icing of power lines has resulted in severe line losses for NPPD. Gerald Gentlemen station has lost all major transmission lines East, and is also off the grid. Extremely low temperatures, combined with high winds have made restoration of lines very , difficult. Eastern Nebraska experienced severe icing also, but with only moderate winds. The Missouri River has experienced moderate ice flows for two days. Tonight's forecast is for light snow over the eastern third of the state. Temperatures are again expected to dip to near zero. Winds are currently from the Northwest, and are expected to shift to the South early Tuesday morning. Copy of today's (simulated) Plan of the Day (POD) available, including RCIC motor operated valve operability surveillance, scheduled for 1900 today. l l ! l l t 1 1 Operational Data P.ter 7 f C: EXER SEC77 II. 5
7.0 SCENARIO OVERVIEW / OPERATIONS INFORMATION 7.1 Close of Business, day before conditions November 18. 1996. Over the last two days western Nebraska has experienced a major winter storm. A major sleet storm deposited large quantities of ice on NPPD transmission lines in the western half of the state. This was followed yesterday by a shift to an arctic jet stream pattern with high winds which dropped temperatures into the single digits. The icing of power lines has resulted in severe line losses for NPPD. Gerald Gentlemen station has lost all major transmission lines East, and is also off the grid. l Extremely low temperatures, combined with high winds have made restoration of lines very difficult. Eastern Nebraska experienced only slight icing, but with moderate winds. The Missouri River has experienced moderate ice flows for two days. Tonight's forecast is for light snow over the eastern third of the state. Temperatures are again expected to dip to near zero. Winds are currently from the Northwest, and are expected to shift to the South early Tuesday morning. Copy of today's (simulated) Plan of the Day (POD) available, including RCIC motor operated valve operability surveillance, scheduled for 1900 today. Operational Data Page 7-1 C:. . tEXER\ SECT 711. WP5
7.3 Simulator SET-UP, Triggers Reset Simulator to Initial Condition (IC) file 61. This IC includes cold weather conditions, DG# 1 running and synchronized to the grid, and RCIC out of service. The volume in the drywell floor drain sump is also artificially increased to allow a quicker calculation of a leak. Write sump integrator number into T.S. log to facilitate calculation of leak rate. (Subtract 2500 from the current value displayed, and record on the T.S. log as the 0000 value). This will yield a leak rate of >5 gpm. Core is Middle of Life (MOL) Rod pattern is Page 66, rod 34-19 at position 16. Mark the following Simulator labels in grease pencil to simulate conditions. -Tainter gate, 25 % -De-icing gates, full open. D to E bay crosstie, closed. -REC temperature control valve 72 degrees l TENDAMATIC 'C-A-B' Sample point- RWCU ) Air Ejectors- RED in service ! REC 'B' Hx in service TEC 'A' Hx in service Simulator triggers:
- 1. Leak in Primary Containment. ~5 gpm NOUE event
- 2. DG #1 fire. ALERT event
- 3. Mark Moore line lost
- 4. Loss of intake screens, 'D' CW p. ump trip
- 5. Scram, ATWS, spurious group 1 isolation, fuel damage. S.A.E event (s)
- 6. Loss of condenser vacuum l
- 7. available
- 8. HPCI steam line break. General Emergency event
- 9. available
- 10. C Bay Icing
- 11. B Bay icing
- 12. A Bay icing
- 13. -D Bay icing (if started)
- 14. E Bay icing (optional)
Operational Data Pace 7-3 C:. 1 EXER; SECT 7-II.WPS
7.4 Narrative Description (Executive Summary) A portion of this scenario is based upon real events in the industry. The loss of circulating water / service water mimics the Wolf Creek eventfrom the winter of 1996. Also the instability or loss oflarge portions of a power distribution grid were seen in the western U.S. July 2 and August loth,19%. Numbers in Ibrackets1 reference the Suoolemental Scenario associated with the event (st RCIC is out of service due to a motor valve operator. The LCO was entered at 2100 yesterday. [1] 1 Diesel Generator # 1 four hour monthly operability is in progress when the day begins. This . diesel generator will be involved in a fire at 0845. When the Station Operator was aligning the ) DG for its start he placed the fuel oil booster pump in HAND rather than the pre-post tube oil I pump. The control switches are next to each other. This provides a continuous source of fuel i to the fire. [3] l l At 0800 indications exist that an unidentified leak has occurred in the drywell. After the 'F' l sump (floor drain) pumps, operators will be able to calculate a leak rate of approximately 5gpm, l or at least an increase of greater than 2gpm within a 24hr period. A NOUE should be declared l on EAL 2.1.3. [2] l l At 0845 (when the DG#1 logs are being taken) a fuel oil line cracks and sprays oil on the hot exhaust manifold of the diesel driven starting air compressor. The fuel ignites. The station operator will perform an emergency shutdown of the DG and evacuate the room. After the CO2 in room # 1 discharges, he will still ' hear' the roar of the fire as it is fed by a pressurized spray of diesel fuel via the fuel oil booster pump. An ALERT should be declared on EAL 5.2.1. [3] ~ The CO2 system initiates, but is vented off due to the DG room HV exhaust fan not tripping. CO 2from DG room #2 is also discharged into room #1, but because the exhaust fan remains on, the fire is not extinguished. The fire continues to burn, fed by fuel oil, but affects only the diesel driven starting air compressor. Damage to the diesel generator is minimal (charred paint, soot) [4] Offsite fire-fighting assistance should be requested. A contingency message will ensure this request is really made, to demonstrate a six-year objective. [13] The fire may be extinguished after offsite assistance is obtained, and appropriate firefighting techniques are demonstrated. (controller discretion) Damage assessment teams will determine the DG as operable as soon as the belts from the electric motor to the air compressor are repaired. [3] Operational Data Paec 7- t C:. . ' EXER; SECT 7-11. WP5
At 1000 the htark Moore line is lost. Doniphan dispatcher will report it down. No repair is possible. [5] At 1045 the intake screens begin to ice up. Controllers will inject malfunctions from 1045 to 1115 interactively in response to operator actions and decisions. All attempts to keep the screens operating will fail. D and E bays may be crosstied. The goal is to mimic the Wolf Creek icing event but ' time' the plant scram for as near 1115 as possible. This will maintain the integrity of the radiological release data, affected by time of shutdown. Eventually C/W pump (s) will trip and condenser vacuum will be lost. [7] If the tainter gate position is attempted to be changed, it will be discovered that the gate will not move. Investigation reveals two problems (the second not being immediately evident). First, the shear pin in the drive mechanism is sheared, disabling the motor drive for gate position. l Second, if the pin is repaired, or an attempt is made to move the gate manually, it will be l discovered that the west end of the gate is bound up. It will raise but not lower past its initial position (~25 % indication). [6] A scram (manual or automatic) will occur at approximately 1115. Several rods do not insert, either on the scram or with the Alternate Rod Insertion (ARI). A Site Area Emergency (SAE) should be declared on EAL 3.3.4. Rods may be manually inserted following appropriate actions. [8] The ATWS condition will cause fuel cladding damage. In-containment radiation will increase, hiain Steam Isolation Valves (htSIVs) will close. HPCI should therefore be used to control level l and pressure in the reactor. If Condensate Booster pumps are used for level control the RFP l l Startup flow control valves will not open as indicated by no flow. The feedwater injection will
- not function due to a broken air line on the Startup flow control valves. If operators then attempt l to open the RFP discharge valves and freewheel the pumps, they will not open due to a l malfunction in the timer circuitry.. A close signal causes the RFP outlet valves to return to closed whenever opened. [9]
The HPCI controller will exhibit erratic performance. hianual control will function OK. [10] , l i At 1200 the HPCI steam line will break in the torus area. PCIS valves do not isolate it. Isolation signals are apparent, but the inboard valve position indications go away at the break, and the outboard valve fails in an intermittent position. Radioactive steam is released into the reactor building. By the time the steam line breaks, in-containment radiation monitors will have increased to greater than 250 R/hr. [12] l l A General Emergency should be declared on EAL 2.4.1 Two success paths exist: 1
- 1. hlanual closure of the outboard HPCI steam supply isolation valve in the Angle Opmuional Data Page 7-5 C:. \ EXER; SECT 7-11. WP5 ,
1 1 l
t l l l l Valve room, or l 2. Restoration of the HPCI inboard isolation valve power supply, and closure of the valve. Both the control power and a main power fuse have blown. \ l A controller message may delay these options (if necessary) for only a short period (~ 15 min).
'ldis will effectively ' fill' the reactor building with radioactive steam (providing a source term).
This steam leak will cause high temperatures in several areas of the reactor building. The leak ! l is relatively small, so these temperatures will not immediately exceed the maximum safe l operating temperatures in more than one area for about ten to fifteen minutes. When two areas exceed maximum safe operating temperatures, the Emergency Operating Procedures (EOPs) i direct that the reactor be emergency depressurized. l The release into the reactor building is picked up by SBGT, filtered, and released via the Elevated Release Point (ERP). Due to only minor fuel damage, and multiple reduction ! mechanisms acting on the release, the release off-site will be small. Downwind survey teams I will locate, track, and measure the release. PARS provided at the General Emergency should l not need to be increased. I At 1530, indications are received in the Control Room that a fire has started in the Standby Gas Treatment System charcoal beds. High temperatures, high moisture, and high Dp all point to the fact that the charcoal beds have become saturated with radioactive iodines. Before it is possible to successfully dispatch an operator and radiological technician to the area to open the fire suppression deluge system block valve, the indications change to indicate that the charcoal l beds have burned through. Although the release rate 'seen' by the ERP monitor does not change, the componenets of the release have significantly changed. Radioactive iodines and particulates, previously filtered out of the release, are no longer filtered. The on-site portion of the exercise will terminate when objectives have been demonstrated. Data in support of the Re-entry, Recovery, Relocation objective (offsite objective) is contained in section 9.2 ~... . . - A 36 hour simulated time jump will occur at this point. A half hour break will be taken to allow Controllers to station themselves at the EOF and County EOCs. Data allowing demonstration of the Relocation, Re-entry, and Recovery will be available. States will be provided witha mock DOE flyover map. Using this map, they may request data on radiological deposition (i.e. direct radiation from the deposited materials). Isotopic data will also be available for areas where deposition would have occured.
. . ~
Operational Data Pace 7-6 C:. . \ EXER \ SECT 7-l1. WP5 l
CLASSIFICATIONS / TIMES 0800 NOUE EAL 2.1.3, Drywell leak 0845-0900 ALERT EAL 5.2.1, Fire with the potential to affect safety systems. 1115 SAE EAL 3.3.4, Failure of RPS, including ARI, to initiate and complete a scram 1200 G.E. EAL 2.4.1, Loss of two out of three fission product barriers, with the possible loss of the third, i l l I 1 _ Operational Data Page 7-7 C:. . \EXERtSECT7 l1.WP5
7.5 Supplemental Scenario Overview A brief synopsis of the Supplemental Scenarios (supporting the detailed response to plant problems during the course ofthe Etercise) is provided below. Detailed packages are provided to Controllers responsible for the control of these supplementals. The scenarios below are anticipated. The controller organization will also attempt to respond to unanticipated actions of the players, ad hoc.
- 1. RCIC motor operator. Work in progress.
-work package a'nd plausable malfunction.
-information on any available on-site spares
-current status of job
-possible use of RCIC manually operating valve MO-131
- 2. Small leak in the drywell )
-Control Room Tech Spec log entry to allow calculation of leak rate ;
-mass change in the sump to cause the sump pump to pump (in IC 61)
-control of leak ' size' via Simulator to maintain drywell pressure <2#
- 3. Diesel Generator fire.
-location of fire, picture
-messages for station operator to read back to the Control Room i -data for off-site firefighting responders 4
-contingency message to ensure off-site firefighting resources are really requested
) 4. Diesel Generator HVAC failure to isolate
-Malfunction of room purge switch failure
-cause of the CO2 system not to isolate the supply or exhaust fans.
4 5. Loss of 345 KV power lines.
; -data from Doniphan on lines feeding GGS, and which make up our grid such that only CNS, Sheldon, and other NPPD peaking units are on-line.
-relay flag data on loss of 345 KV lines
- 6. Tainter gate position indicator failure.
-data on gate, motor, position indicator, etc
-drawing / print j 7. Intake screen failures due to severe icing.
4 -possible mock-up, preferably in the intake structure. j -messages for maintenance personnel to relay back to their OSC 4
- 8. Stuck rods. ATWS.
j -data on cladding damage j operational Data Page 7-8 C:. .\EXERtSECT7-11.WP.S k 7
, , . . , , , ,, -- - ,~. , - - .-
l t
-follow up information on why control rods did not insert on the scram
- 9. Broken air line on RFP Startup Flow Control Valves.
-location of line break
-verification of commonality i
- 10. HPCI controller malfunction in the Control Room.
-HPCI controller schematic, loss of ' Auto' function cause
- 11. Failure of HPCI auto isolation on steam line break.
l -blown fuses (control power and main power fuse) on HPCI inboard isolation valve. )
-intermediate indications on outboard isolation valve. l i
- 12. Manual closure of HPCI outboard steam isolation valve. l l -Reactor building conditions at the desired time of closure.
-rad, temp, steam, etc.
-messages for operator closing the valve i 13. Coordination of off-site fire fighting agency in on-site fire supression activities (in a Vital l Area).
1 1 i I-l I-Operational Data Pace 7-9 C:. . \ EXER \ SECT 7 II. WPS l
. - _ ~ ~ . ~ . . . - .. .. - -- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1996 Exoecies ScenedeTbnetne vesseew naisessh lecitembrashe.Gessuf Emergensy. TAR.t.(1.Retensel 91116 AM MgM taal Q 3Rs Area Buses EAL 314 91048 en hube screen % CW pump stp,less et vammsp. Werk WoepoEresbest testdesemeben, postseesvereMe DiseetOsnareJrAre. ALERT EAL811. DGwsecoverums. W leek. NOUE EAL 2.1.3 Temei
- 't e t rurmirig kr survessenos toine 0830) 064E OF00 0790 an00 0890 0000 Sete 1000 SMS 1100 11M 1m 1290 ISM 1988 1404 1488 tem tess operariamal Data l' age 7-10 C:. 1 EXER \ SECT 7-II.WP5
= - - - _ .- - - - . - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ . . _ - - - __ . _ - - _ _ _ - . _ _ _ ____a
- - . . . . . _ . _ _ . _ _ ._.m . _ . . . . _ _ . _ _ _ _ _ - _ _ . _ _ _ _ . . . _ _ . _ . -
96 ops.xis Select func. key or turn on c@ 800 Nov 19.1996 lPMis 04: ISC/ EOF PLANT STATUS l i REACTOR l l CONTAINMENT l Power 100 %APRM 1.s I aime TAF 200.8 iNCil Drywell pressure 0.234 PSIG Pressure 1010 PSIG Drywell Temperature 115 DEGF Coolant temp (loop A) NA DEGF Torus level 12.8 FEET ' Coolant temp (loop B) NA DEGF Torus temperature 79.8 DliGF Drywell cooling fans ? ON 1CCS l D/W Rad Ili-Rng Airlock 10.67 R!llr i DiW Rad fli-Rng 1. adder 9.7 R/llr ilPCI OFF GPM , RCir Off GPM Primary Containment intact? Secondary Containment intxt ?
- C/S A 'GPM '
C/S 11 ' PM RilR A OI F 0GPM RilR C O!;F l POWER AVAILABLE l RilR 11 OFF 0GPM 345/161 (startup xfmr) 2.6 MW , RllR D OFF 69 KV Emerg MW . DG #1 3xtn KW ADS AIITO?. M ANil All!_LLS?_ AllTO DG#2 1 KW A B _C D_E _F G _Il
'%IMsT TR AIN A?_II .'_ _ OFF CFM l OFF- OI:F ; <TU RPV PRIMARY SECONDARY RADIOACllVh O -SIM U LATOR--- CONTROL CONTAINMENT CONTAINMENT RELEASE 00 F 1 =CI. EAR F2 = F3 = M ENU F4 = SPDS INP r F5 = F6 =
CANC fl ARDCOPY = CONSOLE = MODE = EVENT = , Page 7.1- I s i t
- - - . .- ____ _ ____-_-__ __-___=.__ _ _ _ _-. _ _ _ _ - _ _ - _ _ _
960ps.x1s select func. key or turn-on ax!c 815 Nov 19,1996 lPMi$ 04: ISC/ EOF PLANT STATUS l REACTOR l l CONTAINMENT l Power 100 %APRM l.sl alune TAl 200.4 INCII DryweII pressure 0.45 PSIG ' Prewure 1010 PSIG Drywell Temperature 115 DIiGF Coolant temp (loop Al NA DEGF Torus level 12.H FEET ! Coolant temp (loopIll NA DEGF Torus temperature 79.x DEGl: Drywell cooling fans ? ON 1 -( ~( 'S j D/W Rad Ili-Rng Airlock 10.67 Rtilr i D/W Rad Ili-Rng Ladder 9.7 R/llr ; llirl OFF GPM RUIC Oil GPM Primary Containment intact? Secondary Containment Intact ? OSA 'GPM CeS 11 GPM - RilR A OI:F 0GPM RilR C OI:F l POWER AVAILABLE l , t RilR 11 OI:F 0GPM 345/161 (startup xfmr) 2.6 MW ; RilR D OI F 69 KV Fmerg MW ' DG #1 3800 KW AllTO? M ANilAI.? I lS?
^
ADS AtilO DG#2 i KW A 11 C D E _F._G_Il ,
%ItG 1 'l R AIN A?_H?,_ OFF CFM OFF-OI:F i CPli RPV PRIMARY SECONDARY RADIOArlivh O SIMtil.AlOR- CONTROL CONTAINMENT CONTAINMENT RELEASE 00 Fl = Cl. EAR Fl = F3 = M ENU F4 =SPDS INPT F5 = 16=
CANC II ARDCOPY = CONSOLE = MODE = EVENT = I Page 7.1- 2 i P
}
i I k
- - - _ - _ - - - -_ - - ___-_-__-_._ _ --_ _ .-- _----_ _ - - -__- a - - _ _---___-a --- - ---____--_-
96 cps.xis Select lunc. Ley or turn on axle 830 Nov 19.1996 04: ISC/ EOF PLANT SIAT US lPMIS ] REACTOR l l CONTAINMENT l Power 100 %APRM I.sl aho.e TAl- 200.4 INCil Dstwcil pressme i PSIG Pressure 1010 PSIG Drywell TemperAure 115 DEGF Coolant temp (loop Al NA DEGF Torus !cve! 12.8 FEET Coolant temp (loopIll NA DEGF Torus temperature 79.X DFGI:
~
Drywell cooling fans ? ON lCCS l D/W Rad Ili Rng Airlock 10.67 R/llr D/W Rad Ili-Rng 1. adder 9.7 R/llr 111'r1 OFF GPM Rrir Oil GPM Primary Containment intact! Secondary Containment Intact ? C/S A 'GPM C/S 11 GPM i RilR A OI F 0GPM RilR r OI 1: l POWER AVAILAllLE l RilR 11 OFF 0GPM 345/I61 (stanup xfmr) 2.6 MW RilR D 01:1: 69 KV Emerg MW DG#1 3M00 KW j ADN AllI~O? M ANtf Al? I.LS?. AllTO DG#2 i KW A 11 C D E F G_Il SilG I I R AIN A! D? OFF CFM OI F- OFF
- PRIMARY CI'll RPV SECONDARY R Adit)Ar i lVli O
-SIM Lll_A I OR- CONTROL CONTAINMENT CONTAINMENT REl.EASli 00 i 11= CLEAR F2 = F3 = M EN U F4 = SPDS INPT I:5= I:6= -
CANC ll ARDCOPY = CONSOI.E = MODli= EVENT = M-Page 7.1 3 i h
96 cps.xis Select func. Ley or turn on code 845 I Nov 19.1996 lPMIS 04: ISC/ EOF PLANI SIAIUS l-RiiACTOR l l CONTAINMENT l Pow er llX) %APRM 1.sl afwive TAI 200.4 INCil Drywell pressure 1.1 PSIG Prewure 1010 PSIG Drywell Temperature 115 DiiGl: Golant temp (loop A> NA DEGF Torus level 12.8 FEliT Ci=>lant temp floop Ill NA DEGF Torus temperature 79,8 DliGI: Drywell cooling fans ? ON
- 1. ( < s l D/W Rad Ili-Rng Airl:0 10 fi7 R!Ilr D/W Rad Ili-Rng Ladder 9.7 R!Ilr litrl 01:l GPM RCIC Oil GPM Primary Containment intace?
Secondary Containment intac ! C/S A ~ GPM ns 11 GPM RilR A OI I: OGPM RilR C 01I l POWER AVAILABLE l RilR 11 OI F 0GPM 345/161 (startup xfmn 2.6 MW RIIR D OFI; 69 KV Emerg MW DG //l 1800 Kw Al)N AtilO? M ANil All' l.l.S? AtlTO DG#2 i KW A 11 C D li I G 11 silG I I R AI N A? 11? OfI Cl M 011- 01I: E Pt i RPV PRIMARY SECONDARY RADIOACIIVE O FIM t II. A I OR- CONTROL CONTAINMENT CONTAINMENT Rlil.liASli 00 1:1 -Cl. liar l2= F3 = M EN U F4 = SPDS INPT I:5 = 1:6= CANC ll AR DCOPY = CONSOI.li = MODii= EVliN t - Page 7.1- 4 __ =.
96 ops.xis h!cci func. key or turn-on cixle 900 Nov 19,1996 lPM S 04: 15C/ EOF PLANT STATUS l R$ ACTOR l l CONTAINMENT l Pim cr 100 %APRM lsi alime TAF 200.4 INCil Drywell pressure 1.1 PSIG Prewure 1010 PSIG Drywell Temperature 115 DEGF Cool.mi temp (loop Al NA DEGF Torus level 12.8 FlitiT , Umilant temp (Imip Ill NA DEGF Turus temperature 79.M DliGI: Drywell cooling fam ? ON 1.CCS l D/W Rad Ili-Rng Airlock 10.67 Rillr D/W Rad Ili-Rng Ladder 9.7 R/llr lil'Cl OFF GPM RCIC Oil GPM Primary Containment intact? Secondary Containment intact ? C/S A , GPM - CIS 11 GPM RilR A 011: OGPM RilR C 01I l POWER AVAILAllLE l RIIR 11 OFF 0GPM 345/161 (startup xfmr) 2.6 MW RilR l} OFF 69 KV Emerg MW DG#1 l KW Al)N AllTO? M ANilAl.? LLS? AttlO DG#2 i KW A B C' D E F,G_Il ; silGT TRAIN A?_ B? _ OFF CFM i OFF-OFF ' CPli RPV PRIMARY SECONDARY RADIOACllVh O I
-SIM tit.A I OR- CONTROL CONTAINMENT CONTAINMENT RELEASE 00 I
F1 = Cl. EAR 1:2 = F3 = MENU F4 = SPDS INPT 1:5 = F6 = l CANC II ARDCOPY = CONSOLE = MODE = liVENT = Page 7.l- 5 l
96 ops.xis t
k;G: lime key or turn on cexte 915 ,
Nov 19,1996 lPMiS 04: ISC/LGF PLANT STAIUS l t RiiArlOR l l CONTAINMENT l l'ou er 1(X) %APRM l.sl alune i Al 2(NL4 INCil Drywell pressure 1.1 PShi , Prew ure 1010 PSIG Drywell Temperature 115 DEGl: Coolant temp iloop Al NA DEGF Torus level , 12.x 1:lifiT
- Ciwilant temp t !< = >p t h NA DEGF Torus temperature 79.x DliGF Drywell cooling fans ? ON ,
D/W Rad Ili Rng Airic;L 1 -( 'CS l 10 67 R 'llr D/W Rad fli-Rng 1. adder 9.7 R/lf r flPCI OI:F GPM , RCIC 0 11 GPM Primary Containment intact? Secondary Containment intact ? C/S A .GPM , C/s 11 GPM RilR A 01-1 OGPM RIIR C 01-1 l POWER AVAILABLE l RilR 11 OFF 0GPM 345/161 (startup xfmr) 2.6 MW RilR D Ol;I: 69 KV Emerg MW DG#1 1 KW ADS Alf i'O? M ANIIAl.? 1.1.S? AllTO DG*2 i KW A 11 C D. E F G_ Il SI!GI IR AIN A? 11 ? OFF CFM O!-F- OI:F CPli RPV PRIMARY SECONDARY R ADIOAC livi: 0 SIMlit.AIOR- CONTROL CONTAINMENT CONTAINMENT REl. EASE 00 I-l = Cl. liar Fl = F3 = M ENU F4 = SPDS INPT F5 = I:6= CANC ll ARDCOPY = CONSOLE = MODE = EVENT = Page 7.1- 6
96 ops.nis Select func. key or turn on code 930 Nov 19.1996 lPMIS 34: ISC/ EOF PLANT STATUS ] , REACTOR l l CONTAINMENT l Power 100 %APRM l.sI +ne TAI: 200.4 INCil Drywell pressure 1.1 PSIG Prewure 1010 PSIG Drywell Temperature i15 DEGF Gmlant temp (loop A) NA DEGF Torus level 12.8 FEET Gmlant temp (loop Ib NA DEGF Torus temperature 79.8 DEGF Drywell cooling fans ? ON I:C( S l D/W Rad Ili-Rng Airimk 1017 R/Ilr D/W Rad fli-Rng Ladder 9.7 R/llr llPCI Of F GPM RCIC Off GPM Primary Containment intact? Secondary Containment intact ? C/S A [GPM C/S 11 GPM RllR A 01:I: OGPM RIIR C OFF l POWER AVAILAllLE l RilR 11 OFF 0GPM 345/161 (startup xfmr) 23. Mw RIIR D OI F 69 KV Emerg MW DG #1 I KW ADN AlflO? M ANil AI.? 1.1.S? AllTO DG#2 i KW ' A Il C D li F G 11 silGI IRAIN A? It? OFF CFM OI-F OI-F [ ( 'i't i RPV PRIMARY SECONDARY R ADIOAC livh O
-SIM 111.AT OR - CONTROL CONTAINMENT CONTAINMENT REl. EASE 00 ,
I I = Cl. EAR l2= F3 = M EN U F4 = SPDS INPT F5 = F6 = CANC 11 ARDCOPY = CONSOLE = MODE = liVENT= i Page 7.1- 7
96 cps.xls Elect func. Ley or turn-on code 945 Nov 19,1996 lPMIS 04: TSC/ EOF PLANT STATUS l REACFOR l l CONTAINMENT l , Power 93 %APRM 1.sI above TAF 200.4 INCil Drywell pressure i.I PSIG t Prewure 1010 PSIG Drywell Temperature i15 DEGF Coolant temp (loop Al NA DEGF Torus level 12.8 FEET Coolant temp (loop B) NA DEGF Torus temperature 79.X DFGF Drywell cooling fans ? ON I C( S l D/W Rad fli-Rng Airlock 10.67 R/ilt D/W Rad fli-Rng 1. adder 9.7 R/llr IllTI 01:l GPM . RCIC Oft GPM Primary Containment intact! Secondary Containment intact ? C/S A , GPM C/S 11 GPM RilR A 01 F 0GPM RilR C 01:l l POWER AVAILABLE l RilR 11 OFl OGPM 345/161 (startup xfmr) 2.6 MW RilR D OFF 69 KV Emerg MW DG#1 I KW TDS ALITO? MANllAll? I.lS? ~ AtlTO DG#2 i KW s dBCDEFGIl
%IIGI IR AIN A! I!? OFF CFM OFF-OFF CPil RPV PRIMARY SECONDARY RADIOACllVE O
-SIMill A1OR - CONTROL CONTAINMENT CONTAINMENT RELEASE 00 Fl = Cl. EAR F2 = F3 = M ENU F4 = SPDS INPT F5 = F6 = ,
CANC llARDCOPY= CONSOLE = MODE = EVENT = Page 7.1- M i 4
96 cps.xis r Select func. Ley or turn-on code 1000 Nov 19,1996 lPMIS 04: T5C/ EOF PLANT STATUS l REACTOR l l CONTAINMENT l ' Power 93 %APRM l.sl almve TAl; 200.4 INCll Drywell pressure 1.1 PSIG ; Pressure 1010 PSIG Drywell Temperature 115 DEGl' Coolant temp (loop A) NA DEGF Toms level 12.8 FEET
- Coolant temp (loop B) NA DEGF Torus temperature 79.8 DEGF Drywell cooling fans ? ON :
lCCS l D/W Rad Ili Rng Airlock 10.67 R!Ilr D/W Rad Ili-Rng Ladder 9.7 R/ilt IIPCI OFF GPM RCIC Off GPM primary Containment intact? Secondary Containment Intact ? C/S A GPM . C/S 11 GPM RIIR A 01:l OGPM RilR C OFF l POWER AVAILAHLE l RilR 11 OFF 0GPM 345/161 (startup xfmr) 2.6 MW RilR D OI:F 69 KV Emerg MW , DG#1 I KW ADS AllFO? M ANtlAll! l.LS?_ ALITO DG#2 i KW ; A. B_C D _E F_G II_ NilG l' I'R AIN A? R? _ OFF CFM OFF- OFF ( PU RPV PRIMARY SECONDARY RADIOAC l lV h O l
-SIMtil.ATOR. - CONTROL CONTAINMENT CONTAINMENT RELEASE 00 Fl = CLli AR F2 = F3 = M ENU F4 = SPD3 INPT F5= F6 =
CANC II ARDCOPY = CONSOLE = MODE = EVENT = Page 7.1- 9
96 cps.xis Sekst fune Ley or turn-on cmle 1015 Nov 19,1996 lPMIS 04: 15C/ EOF PLANT STATUS l REACTOR l l CONTAINMENT l Pow er 93 % APRM l.s I alm e 'I A F 200.4 INCil Drywell pressure I.I PSIG Prewure 1010 PSIG Drywell Temperature 115 DIiGF Coolant temp (!twip A) NA DEGF Torus level 12.8 FEliT Cixilant iemp tlawip H) NA DEGF Torus temperature 79.8 DI.GF Drywell cooling fans '? ON Lers l D/W Rad Ili-Rng Airlotk 1017 R/Ilr D/W Rad Ili Rng Ladder 9.7 R/llr IIPCI OI:F SPM RCIC Of f GPM Primary Containment intact? Secondary Containment Intact ? C/S A ,'GPM C/S 11 GPM RilR A OFF 0GPM RilR C OI:F l POWER AVAILABl.E l RIIR 11 Ol:F 0GPM 345/161 (startup xfmr) 23. MW RIIR 1) OI:F 69 KV Emerg MW DG#1 i KW
\DN AIITO? M ANtf AI ? I.I.S? AllIO DG#2 I KW A B,C D E F G_II_
SilG l' TR AIN A'? B? OFF CFM OFF- OFF UPU RPV PRIMARY SECONDARY RADIOAClivE O
- SIMtil.ATOR- CONTROL CONTAINMENT CONTAINMENT REl. EASE 00 1:1 = Cl. EAR F2 = F3 = MENU F4 =SPDS INPT F5 = F6 =
CANC ll AR DCOPY = CONSOI.E= MODE = EVENT = Page 7.1- 10 L_ ._ _ _ - _ _ - - _ . _ _ - - - . - -
96 ops.x1s Select func. key or turn-on code 1030 Nov 19.1996 lPMIS 04: TSC/ EOF PLANT STATUS l REACTOR l l CONTAINMENT l . Power 90 %APRM l.tl aime I Al 2tM).4 INCil Drywel! pressure f.! PSIG Prewure 1010 PSIG Drywell Temperature 115 DEGF t Coolant ten.p tioop A) NA DEGF Torus level 12.8 FEET Coolant temp floop n) NA DEGF Torus temperature 79.8 DEGF Drywell cooling fans ? ON , 1 C('s l D/W Rad Ili Rng Airkick 10.f>7 R/Ilr D/W Rad fli Rng Ladder 9.7 R/Ilr ' ilPCI OFF GPM , RCIC Off GPM Primary Containment intact? l Secondary Containment intact ? C/S A GPM r/S 11 GPM l RIIR A e .51 1: OGPM RIIR C 011: l POWER AVAILABLE l , RilR 11 OFF 0GPM 345/161 (startup xfmrt 2.6 MW i RIIR D OI:I: 69 KV Emerg MW f DG #1 i KW
.\lIs Alit (i? M ANIf Al ? l.l.S? A11TO DG#2 i KW A 11 C D li F G 11 ,
silG l'~l R AI N A? H? OFF CFM ! OI:F- Ol iF CPli RPV PRIMARY SECONDARY RADIOACllVh O
-SIMill.ATOR - CONTAINMENT CONTAINMENT RELEASE I CONTROL 00 i
I:I = Cl. liar F2 = F3 = MENU F4 = SPDS INP F F5 =- I:6 = CANC II ARDCOPY = CONSol.E = MODE = EVENT = ; Page 7. l- 11 F l r
96 cps.xis Select func. key or turn-on cmfe 1045 Nov 19.1996 [PMis 04: ISC/ EOF PLANT STAI US l RiiACIOR l l CONTAINMENT l Power 90 %APRM < l.si alune 1 A1 200.4 INCil Drywell pressure 1.1 PSIG Prewure 1010 PSL9 Drywell Temperature 115 DIiGF Ci=>lant temp II. op A) NA DEGF Torus level 12.8 FlitiT Ci=>lant temp t loop Ill NA DEGF Torus temperature 79.x DIiGl: Drywell ct. O g fans ? ON 1-C( 's l D/W Rad Ili og Airlock 9 68 R.'llr D/W Rad Ili-Rug 1. adder H.8 Rillr llPCI OFF GPM RCIC Olf GPM Primary Containment intact ? Secondary Containment Intact ? ! C/S A .'GPM I CIS 11 GPM RilR A OI F 0GPM I RilR C OI I: l POWER AVAILA11LE l Rl!R lt OI I: OGPM 345/I61 (startup xfmr) 2.6 MW RilR D OI-F 69 KV Emerg MW DG#1 I KW ADS AllTO? M ANtIAI!? I.IS? AllTO DG#2 i KW A!!C DliI Gll sil(il I R AIN It ' CFM A' OI 1: [ 01:l: OI-F t ( Pii RPV PRIMARY SECONDARY R AI)lO AC l lV E O SIM t II.A I OR CONTROL CONTAINMENT CONTAINMENT REl.liASli 00 l I = Cl. liar F2 = F3 = M EN U F4 = SPDS INP I' 1:5 =- I6= l i CANC ll AR DCOPY = CONSOLli = MODli = liven I .- Page 7.1- 12 , t
96 ops.x1s Selet.t func. key or turn-on tode - 1IfX) Nov 19,1996 lPMIS M: ISC/ EOF PLANT STAl US l Rl!ACIOR l l CONTAINMENT l Power 65 % APRM l_sI alune TAl: 200.4 INCil Drywell pressure 1.1 PSIG Prewure 1010 PSIG Drywell Temperature l l:. DE(;F Cowilans temp (lixip An NA DEGF Torus level 12.M FliliT Coolant temp t l< = >p it ) NA DEGF Torus temperature 79.x DIiGl 9rywell cixiling fans ? ON 1 C( 'S l D/W Rad Ili-Rng Airlock 35.31 Rllir D/W Rad Ili Rng bdder 32.1 R/llr llPCI OFF GPM RCIC Off GPM Primary Containment intact? Secondary Containment Intact
- C/S A 'GPM CIS 11 GPM RilR A Ol-I: OGPM RilR C 01:1: l POWER AVAILAHLE l RilR 11 OFF 0GPM 345/161 (startup xfmr) 2.6 MW RIIR D OI:F 69 KV Emerg MW DG#1 i KW TDN AttTO? MANilAI!' l.LS? AtilO DGN2 i KW A 11 C D E F G 11 SilGI 1 RAIN A? It? OFF CFM OI:F - 01:1 CPti RPV PRIMARY SECONDARY RADIOAC 1IV E O SIMill.A IOR - CONTROL CONTAINMENT CONTAINMENT RElJiASli 00 1:l = Cl. liar F2 = F3 = M ENU F4 =SPDS INPT l5= F6 =
CANC ll ARDCOPY = CONSOLE = MODE = liVliNT = Page 7.1- 13
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96 ops.x1s Select func. Ley or turn on code i130 E Nov 19.1996 lPMIS 04: TSC/ EOF PLANT STATUS l REACTOR l l CONTAINMENT l Pow er 0.1 %APRM Lsl alune TAl; 194 INCil Drywell pressure 1.1 PSIG Pressure 800 PSIG Drywell Temperature i15 DEGF Ciwilant temp (loop A) NA DEGF Torus level 12.8 FEET r Coolant temp sloop II) NA DEGF Torus temperature 79.N DEGF Drywell cooling fans ? ON l Eccs l D/W Rad lli-Rng Airlock 361 R/lfr D/W Rad Ili.Rng Ladder 330 Rillr ilPCI ON 4200 GPM RrtC Olf GPM Primary Containment intact? l Secondary Containment intact ? r/S A 'GPM i CIS 11 GPM RilR A ON 79(M) GPM RilR C OI F l POWER AVAILABLE l l RilR 11 ON 8(NX) GPM 345/161 (startup xfmr) 2.6 MW [ RilR D OFF 69 KV Emerg MW + DG#1 i KW TDN AllTO! MANilAll! Lt.S?_ INiilillT DG#2 I KW ! A B ,C _D E F G II l SilG l' I R AI N A? B? 3340 CFM ON-ON CPil RPV PRIMARY SECONDARY RADIOACilVE O l
-SIMtil.A IOR- - CONTROL CONTAINMENT CONTAINMENT RELEASE 00 i
Fl = Ct. EAR l'2 = F3 = M EN U F4 = SPDS INPT F5 = 1:6= CANC II ARDCOPY = CONSOLE = MODE = EVENT = Page 7.1 15 t i t i
-. . . . ~ . - - ~ - - - - - - _ - - - - - - - - - - - - - - - - - - - _ - _ - - _ _ _ _ - - - - - - _ _ - - - - - - - . - - - - - - _ - - - - - - - - - - . _ - _ - _ _ _ _ _ _ _ - - - - - - - - _ . - - - - - - - - - - - - - - - - - _ 96 ops.xis Select func. Ley or turn on code 1145 E Nov 19.1996 lPMIS 04: TSC/ EOF PLANT STATUS l REACTOR l l CONTAINMENT l Power 0.1 %APRM i AI anne TAF 2(X).4 INCil Drywell pressure 1.1 PSIG Prew ure 750 PSIG Drywell Temperature 115 DliGF Coolant temp floop A) NA DEGF Torus level 12.9 FiiET Coolant temp tioop B) NA DEGF Torus temperature 79.8 DIiGF Drywell cooling fans ? ON I:( CS l D/W Rad fli-Rng AirlotL 415 N R/lf r D/W Rad Ili-Rng 1. adder 37M R/llr llPCI ON 42tX) GPM RCIC Off GPM Primary Containment intact? ' Secondary Containment intact ? C/S A 'GPM C/S It 'GPM i RIIR A ON 79tN) GPM RIIR C OFl l POWER AVAILAllLE l RilR I! ON M(KX) GPM 345/I61 (startup xfmr) 2.fi MW RIIR D OFF 69 KV Emerg MW DG #1 I KW , ADS ALITO? M ANIIAlf? 1.LS?_ INillIllT DG#2 i KW . A Il C D li_ F G _Il SilG l' I R AIN A? Il!. 3340 CFM UN-UN CPt s HPV PRIMARY SECONDARY R ADIOAc ilvh O
-SIMill.A I OR - CONTROL CONTAINMENT CONTAINMENT Rlil.fiASli 00 ,
FI = Cl.FAR I:2 = F3 = MENU F4 =SPDS INPT F5 = I:6= i CANC ll ARDCOPY = CONSOLE = MODIi= livliN T = ~ Page 7.1 - I f>
96 cps.xls Sclett fune. .,y or tum on code 1200 E Nov 19.1996 l1%185 04: ISC/ EOF PLANT Sl ATUS l REAClOR l l CONTAINMENT l Pow er 0.1 %APRM lal aime TAI 2(X).4 INCll Drywell pressure 1.1 PSIG Prewure 640 PSIG Drywell Temperature i15 DiiGF Coolani temp tloop A) NA DEGF Torus level 13 FEliT Coolans temp tioop 11) NA DEGF Torus temperature 79.8 DliGl: Drywell cooling fans ? ON IrCS l D/W Rad Ili-Rng Airlock 419.1 R/llr L)/W Rad Ili-Rng Ladder 3XI R!Ilr llPCI ON 2500 GPM RCIC Oil GPM Primary Containment intact? i Secondary Containment Intact ? C/S A GPM CIS 11 GPM RilR A ON 79(M) GPM RilR C OI:F l POWER AVAILABLE l l RilR 11 ON 8000 GPM 345/161 (startup afmrt 2.6 MW RllR I) OIF 69 KV Emerg MW DG#1 i KW ADS AllTO? MANUAL? LIS!~ INillRIT DG#2 i NW A R C D E .F G_II. i silG l~ I R AI N A?..B? 3340 CFM ON-ON ( Pli RPV PRIMARY SECONDARY RADIOACilVE O
--SIMllLATOR - CONTROL CONTAINMENT CONTAINMENT i REl.EASli 00 FI = CLEAR F2 = F3 = M ENU F4 = SPDS INPT F5 = F6 =
CANC ll ARDCOPY = CONSOLE = MODE = EVENT = Page 7.1- 17 i e I
. _ _ _ _ _ _ _ _ _ . .~ _. ~ . _ . . _ _ . . _ . . . - _ . . .. _ ._ .__ . _ . _ . . _ _ _ . .. .
96 cps.xis Selett lunc. key or turn on cmic 1215 E Nov 19,1996 lPMIS (M: ISC/ EOF PLANT STATUS l REAClOR l l CONTAINMENT l Pim er 0.1 %APRM l.sI almve 'l Al: 200.4 INCil Drywell pressure 1.1 PSIG Piewure 600 SIG Drywell Tempera:ure 115 DEGF Coweltnt temp (lexip Al NA DEGF Torus !cvel 13 IIlliT riu lant temp aliep 111 NA DEGF Torus temperature 79.8 DiiGI: l Drywell cooling fans ? ON 1 C( 'S l D/W Rad Ili-Rng Airliwk 419.1 R/Ilr D/W Rad Ili-Rng Ladder 3XI R/llr IIPCI TRIP GPM RCIC Olf GPM Primary Containment intact? Secondary Containment Intact ? C/S A 'GPM r/S 11 GPM RilR A ON 79(Mi GPM RilR C 01:I: l POWER AVAILAllLE l . 345/161 (startup ximo 16 MW RIIR 11 ON 8(MX) GPM , RiiR D Of I: 69 KV Emerg MW DG#1 i KW ADS AtGOf M ANIIAl.? 1.lS? lNilllilT DG#2 I KW A Il C_ D E F G II_ silGT TR AIN A?_ 3? _ 3340 CFM ON-ON UPli RPV PRIMARY SECONDARY RADIOACllvi. O .
-SIMill.A IOR -- CONTROL CONTAINMENT CONTAINMENT RELEASE 00 FI Cl. EAR F2 = F3 = M ENU F4 = SPDS INPT F5 = F6 =
CANC II ARDCOPY = CONSOLE = MODE = EVEN I~ = ! Page 7 l- lx
96 cps.xis Sclect f unc. Ley or turn on code 1230 E , Nov 19,1996 lPMIS (M: ISC/ EOF PLANT STATUS l REACTOR l l CONTAINMENT l Pow er 0.1 %APRM l.sI aim e I AI 200.4 INCII Drywell pressure i.I PSIG ! Pressure 540 PSIG Drywell Temperature i15 DEGF Coolant (cup (loop Al NA DEGF Torus level 13 1 liliT Coolant temp tloop 11) NA DEGF Torus temperature 79.8 DEGF Drywell cooling fans *? ON IT 'US l D/W Rad Ili Rng Airlock 419.1 R/Ilr D/W Rad fli-Rng Ladder 3MI Rllir ilPCI 1 RIP GPM ; RCIC Off GPM Primary Containment intact? Secondary Containment intact ? C/S A 'GPM " C/S 11 GPM RIIR A ON 79tN) GPM RilR C 01:1: l POWER AVAILAllLE l RllR 11 ON 8tXX) GPM 345/161 (startup xfmO 2. t. MW RIIR D 01:1: 69 KV Emerg MW : DG #1 i KW
\DS AllIO? M ANilAI.? 1.1.S? INililllT DG#2 I KW A 11 C D li I G ll i SilGI IR AIN A? Il? 3340 CFM ON-ON CPt i RPV PRIMARY SECONDARY RADIOACllVE o
-St MII1.A I OR - CONTFtOL CONTAINMENT CONTAINMENT REl.liASli 00
)
1:I = Cl. liar F2 = F3 = M ENU F4 = SPDS INPT F5 = I:6= CANC II ARDCOPY = CONSOLE = MODli= livliNT = Page 7.1- 19 i I 5
96 cps.xls Select func. Ley or turn on code 1245 E Nov 19.1996 [PMIS 04: TSC/ EOF PLANI STATUS l
- RiiACIOR l l CONTAINMENT l Pow er 0.1 %APRM l.sI alwise I AF 200.4 INCil Drywcil pressure i.I PSIG Prew ure 2(X) PSIG Drywell Temperature iIS DIEGF riwilant temp stoop A) NA DEGF Torus level 13 FlifiT Unwilant temp tiiwipIll NA DEGF Torus temperature x2 DliGF ;
Drywell cooling fans 2 ON 1 rt 's l D/W Rad Ili-Rng Air!<w;L -119.1 Rillr D/W Rad Ili.Rng 1. adder IMI R/llr , llPCI TRIP GPM P Refr Of f GPM Primary Containment intact t Secondary Containment intact ? r/S A ' GI'M res 11 GPM RllR A ON 7900 GPM RilR (' OI:F l POWER AVAILAllLli l RilR 11 ON 8(MM) GPM 345/161 (stariup ximo 26 MW t RilR D Of F 69 KV Emerg MW DG#1 I KW
\DN AllTO? M ANilAl? I.I.S? liMRG Dl!P DG#2 i KW !
A 11 F D li F G 11 MiGI IRAIN A? 11 ? 3340 CFM ON.ON CPil RPV PRIMARY SECONDARY RADioAClivi. O 4 SIMII 1.A I OR CONTROL CONTAINMENT CONTAINMENT REl.liASli 00 ' I:1 =Cl liar I-2 = F3 = M ENU F4 = SPDS INPr 15a l 6 -- , CANC ll ARDCOPY = CONSOt.E= MODli - liVliN 1 = Pace 7.1- 20 i t t i i m_ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
96 cps.xis Select func. Ley or turn on code 1300 E Nov 19,19% lPMIS 04: ISC/ EOF PLANT STATUS l REACTOR l l CONTAINMENT l Pow er 0.1 %APRM l.sI alwwe ~I Al- 200.4 INCil Drywell pressure 1.1 PSIG Pressure 100 PS!G Drywell Temperature 115 DEGF Coolant temp aloop A) NA DEGF Torus level 13 FEET Ceulant temp floop H 6 NA DEGF Torus temperature 83 DliGF Drywell cooling fans ? ON I C( 'S l D/W Rad Ili Rng Airlock 419.1 R/llr ; D/W Rad Ili-Rng Ladder 381 R/llr llPCI TRIP GPM RCIC Off GPM Primary Containment intact? Secondary Containment Intact ? , r/S A .'GPM ' r/S It GPM k RilR A ON 7900 GPM RIIR C OI F l POWER AVAILABLE l RIIR 11 ON 8(XX) G P M 345/161 (startup xfmr) 2.6 MW RilR D OFI 69 KV Emerg MW l DG #1 I KW
\DN AIITO? M ANllAI.? 1.1.S? IiMRG DIiP DG#2 i KW A Il C D li F G 11 t SilG T IRAIN A? Il? 3340 CFM ON I O N' !
UPil RPV PRIMARY SECONDARY R AI)lOAr livl. O
-SIMiri.ATOR -- CONTROL CONTAINMENT CONTAINMENT REl.EASEi 00 '
I l = Cl. EAR F2 = F3 = MEN U F4 =SPDS INPT I:5= F6 = CANC II AR DCOPY = CONSOLE = MODE = EVliNT = , Page 7.1- 21
. . _ . --._.m._ - _ _ .- - - - - -- - - - ------ -------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 960ps:xis f Select func. Ley or turn on code 1315 E - Nov 19,1996 > lPMIS nt: ISC/ EOF PLANT STATUS l r RiiAC'l OR l l CONTAINMENT l Pow er 0.1 %APRM
- 13I alune I A1: 200 4 INCII Drywell pressure I,I PSIG Preuure 60 PSIG Drywell Temperature 115 DI!GF Coolant temp s loop A > NA DEGF Torus level -
13 1:I:lil' i finilam temp Ih uip 11 NA DEGF Torus temperature M2.4 DI.GF i Drywell cooling fans ? ON i l t rS l D/W Rad Ili-Rng Airlock 419,1 R 'll D/W Rad fli-Rng Ladder 3MI R/llr lilt'l IRIP GPM RCIC Off GPM Primary Containment intaet? , Secondary Containment intact ? C/S A 'GPM ! C/S 11 GPM , RilR A ON 79(M) GPM RilR C 01:1: l POWER AVAILABLE l RilR 11 ON M(MM) G P M 345/161 (startup xfmr) 2.6 MW , RilR D OI-F 69 KV Emerg Mw DG#1 1 KW ADS AllTO? M ANil Al.! 1.LS?, liMRG DIiP DG#2 i KW ; A Il C _D _E F G _ll SilG I I R AIN A'? !!! 3340 CFM ON - 05' CPli RPV PRIMARY SECONDARY RADIOArilVI: 0
-SIMllt.ATOR-- CONTROL CONTAINMENT CONTAINMENT RELEASli 00 f f = Cl.FAR F2 = F3 = M ENU F4 = SPDS INPT F5 = F6 =
CANC ll AR DCOPY = CONSOI.E = MODE = EVENT = , Page 7.1 "
96 ops,xis Select func. key or turn-on code 1330 E Nov 19.1996 lPMIS nt: ISC/ EOF PLANT STATUS l REACTOR l l CONTAINMENT l Pow er 0.1 %APRM I.si alw w e T A l: 200.4 INCil Drywell pressure I.I PSIG Prewure 60 PS!G Drywell Temperature 115 DEGF Coolant temp aloop A) NA DEGF Torus level 13 FEET Cool.mt temp floop 11) NA DEGF Torus temperature 80.8 DliGF Drywell cooling fans ? ON i I;CCS l D/W Rad fli-Rng Airlock 419.1 R/Ilr D/W Rad fli-Rng Ladder 3M1 R/llr IIPCI TRIP GPM RCIC Oft GPM Primary Containment intact? Secondary Containment Intact ? C/S A GPM cts 11 GPM i R!!R A ON 79(N) GPM RilR C OI:I: l POWER AVAILABLE l , i RilR 11 ON 8(MW) GPM 345/161 (startup xfmr) 2.6 MW ' RilR D 01-1 69 KV Emerg MW DG #1 i KW
\DS AllTO! M ANtlAll? LIS! liMRG Dl!P DG#2 I Kw A 11 C D li F G 11 l i
silG l' I R AIN A '? 11 ? .U40 CFM ON-ON i cPti RPV PRIMARY SECONDARY R ADIOAC ilV h O
.SIMlit.A I OR- CONTROL CONTAINMENT CONTAINMENT Rlil.I!ASli 00 I I = Cl. liar l-2 = F3 = M ENU F4 = SPDS INPT I5= I:6=
CANC fl AR DCOPY = CONSOI.E= MODE = liVliNT = 5 Page 7. l- 23 i i
96 cps.xis Select lunc. key or turn-on code 1345 E Nov 19.1996 lPMIS 04: TSC/ EOF PLANT STATUS l REACTOR l l CONTAINMENT l Power 0.1 %APRM l.tl alue TAl; 200.4 INCil . Drywell pre". , II PSIG Pressure 60 PSIG Drywell Temperature i15 DEGF Coolant temp floop Al NA DEGF Torus level 13 1;EET Coolant temp floop Ill NA DEGF Torus temperature 79 DEGF Drywell cooling fans ? ON ICCS l D/W Rad Ili-Rng Airlock 419.1 R/llr D/W Rad Ili-Rng Ladder 181 R/lle llPCI TRIP GPM RCIC Oil GPM Primary Containment intact? Secondary Containment Intact ? C!S A GPM CrS 11 GPM ON 78x10 GPM ; RilR A RilR C 01:l; l POWER AVAILAllLE l RIIR 11 ON 8(XX) GPM 345/161 (startup xfmr) 2.6 MW RilR 1) OI l; 69 KV Emerg MW DG#1 l KW AI)S AllTO? M ANtlAl;? LLS? liMRG DIiP DG#2 i KW A 11 C D li F G 11
\ltG f I R AIN A? 11 ? 3340 CFM ON ON
('Pil RPV PRIMARY SECONDARY R ADIOAC l lVI: O SIMtit ATOR- CONTROL CONTAINMENT CONTAINMENT REl.l!ASli 00 FI = Cl. liar 1:2 = F3 = M EN U F4 = SPDS INPT 15 = 1:6= CANC ll ARDCOPY = CONSOLE = MODE = EV EN I' = Page 7.1- 24
96 ops.xls Sclett func. Ley or turn on code 1400 E Nov 19.1996 lPMIS 04: ISC/ EOF PLANT STAIUS l RiiACIOR l l CONTAINMENT l Pow er 0.1 %APRM l.sl atwne I Al: 2(N).4 INCil Drywell pressure I.I PSIG Prewure 60 PSIG Drywell Temperature 115 DEGF Coolant temp sloop Al NA DEGF Torus level 11 FliET ('oolant icinp a loop 11) NA DEGF Torus temperature 79.4 DliGl Drywell cooling fans ? ON s- r( 'S l D/W Rad Ili-Rng Airim.L 419.I R/Ilr D/W Rad Ili-Rng Ladder 1x1 Rillr IIPCI 'I RIP GPM RUIC Off GPM Primary Containment intact? Secondary Containment Intact ? U/S A 'GPM ('/S 11 GPM RilR A ON 79(M) GPM RIIR C OI:I' POWER AVAILA11LE l l RilR R ON 8(XX) GPM 345/161 (startup xfmr) 2.6 MW RIIR D 01:l: 69 KV Emerg MW DG#1 1 KW ADS AllTO? MANilAL? 1.LS? I!MRG DEP DG#2 I KW A 11 C D E F .G 11 silGT IR AIN A? 11? 3340 CFM ON-ON ( Pli RPV PRIMARY SECONDARY R A DIOAC l lV E O SIM I fl.A I OR - CONTROL CONTAINMENT CONTAINMENT REl.EASli 00 I l-I r CI. EAR F2 = F3 = M ENU F4 = SPDS INPT I:5 = F6 = CANC ll ARDCOPY = CONSOLE = MODli= liv EN I' = Page 7. I- 25
960ps.xls klett lune. Ley or turn on code 1415 E Nov 19.1996 lPMIS ut: ISC/ EOF PLANT STAl US l REACTOR l l CONTAINMENT l Pow er 0.1 % APRM l.sl aliine I AI: 200.4 INCII D:ywell pressure I.I PSIG Pressure (d) PSIG Drywell Temperature 115 DI!GF Gui!.mt ternp (loop A) NA DEGF Torus level I3 Fl!IiT C =>lant iciup tiinip fli NA DEGF Torus temperature 79.8 DiiGi: Drywell cooling fans ? ON Ir('s l D/W Rad Ili Rnp Airlock 419 i Relir D/W Rad Ili Rng 1. adder 381 Rtilt I I P('l TRIP GPM RCIC Oil GPM Primary Containment intact? Secondary Containment intact ? CIS A 'GPM C S 11 GPM RilR A ON 7'X M) G P M RIIR r OI:F l POWER AVAILAllLE l RilR 11 ON 8(MN) G P M 345/I61 (startup xfmn 2. t. MW RilR D OI:F 69 KV limerg MW DG#1 i KW AI)s AIIIO? M ANil AI.? 1.I.S? liMRG DFP DG#2 I KW A Il C_D li_F G_Il_ SilG I I R AIN A? B? 3340 CFM ON-ON CPli RPV PRIMARY SECONDARY R ADIOAr livh O hlMill.A IOR - CONTROL CONTAINMENT CONTAINMENT RELEASE 00 1:1 = Cl. liar I2= F3 = M ENU F4 = SPDS INPT F5 = 1:6 = CANC ll AR DCOPY = CONSOLE = MODE = EVliN I' = Page 7. l- 26
i 960ps.xls Select func. key or turn on axle . 1430 E Nov 19.1996 ! lPMIS 04: ISC/ EOF PLANT STATUS l REACTOR l l CONTAINMENT l Power 0.1 %APRM 1.sl ah m e IA l- 200.4 INCil Drywell pressure 1.I PSIG Prewure 60 PSIG Drywell Temperature 115 Dl!GF I Coolant temp (Imp A > NA DEGF Torus level 13 FEliT Cmlant temp tloopIll NA DEGF Torus temperature 79.H DEGI: Drywell cooling fans ? ON l li'US l D/W Rad Ili Rng AirlmL 419 i R!Ilr D/W Rad Ili-Rng Ladder 381 Rtilr flPCI 1 RIP GPM l RCIC Olf GPM Primary Containment intact? Secondasy Containment Intact ? CIS A 'GPM C/S 11 GPM f RilR A ON 79(N) GPM RIIR C OI F l POWER AVAILAHLE l i RilR It ON 80(M) GPM .345/I61 (startup xfmn 2 . t. MW RilR 1) OI:F 69 KV Emerg MW DG #1 1 KW
.\DS Allio! M AN!!Al.? I.I.S? IiMRG DiiP DG#2 I Kw A .II C D _li f G 11 SilGI IRAIN A? 11? 3340 CFM ON-ON CPII RPV PRIMARY SECONDARY R ADIDAf ilVh O
-SIMlil.ATOR- - CONTROL CONTAINMENT CONTAINMENT RELEASli 00 l-1 = Cl. EAR F2 = F3 = M EN U F4 = SPDS INPT I:5 = l ti =
CANC ll ARDCOPY = CONSOLE = MODIi= EVENT = Page 7.1- 27 _ - _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - _ _m
_ _ . . _ - _ . . . . - . = ._ . _ - - 96 cps.xis select func. key or turn-on ctxle 1445 E Nov 19,1996 lPMIS 04: ISC/EOI- PLANI STAIUS l RiiACIOR l l CONTAINMENT l , Pow er 0.1 %APRM ! 1.sl alune I Al: 2tK).4 INCII Drywell pressure 1.1 l'SIG Prewure 60 PSIG Drywell Temperature 115 DIiGI: Guilant temp floop Al NA DEGF Torus level 13 1:liET n=>lant temp floop Ill NA DEGF Torus temperature 79 x DliGl: Drywell cixiling fans ? ON I ( 1 's l D/W Rad Ili-Rng AirimL 419 i R/Ilr i D/W Rad Ili Rng Ladder 3MI R/llr llPCI TRIP GPM RrtC 0 11 GPM Primary Containment intact! Secondary Containment Intact ? C/S A 'GPM CIS 11 GPM ! RilR A ON 79iU GPM RilR C 011 l POWER AVAILAHLE l RIIR 11 ON R(K10 GPM 345/161 (startup xfmrt 2.fi MW RilR D OI:l: 69 KV Emerg MW DG#I I KW
.\ DN AtiTO? M ANIIAI.? 1.l_S! I NIRG DliP DG#2 i KW A 11 C D li I G II SilG l' 1 R AIN A? H? 3140 CFM ON-ON
('Pli RPV PRIMARY SECONDARY R Al>lO A( ' l iv h O SIM t 'I . A I OR -- CONTROL CONTAINMENT CONTAINMENT REl.liASli OO I i:1 - Cl.li AR I:2 = F3 = M ENU F4 = SPDS INPT I:5 = I:fi = i CANC ll AR DCOPY = CONSOLE = MODli= liv liN I - Page 7. I- 2M i i
. - - _ - - . _ . _ _ _ _ _ _ . _ - _ _ . _ . _ - _ - _ _ . _ . _ _ _ _ _ _ _ _ - _ - - - _ _ _ - _ . __1 _ ____
960ps.xls Select func, key or turn-on code 1500 E Nov 19.19% lPMIS 04: ISC/ EOF PLANT STATUS l RiiACTOR l l CONTAINMENT l Pow er 0.1 %APRM . l .s l aim e i Al- 200.4 INCil Drywell pressure 1.1 PSIG Prewure 60 PSIG Drywell Temperature 115 DliGF Coolant temp tiemp A) NA DEGF Torus level 13 I:liliT Cimlant temp ilimp Ill NA DEGF Torus temperature 79.M Dl!GI Drywell cooling fans '? ON I O('S l D/W Rad Ili-Rng Airlock 419.1 Rrilr D/W Rad Ili-Rng 1. adder 381 R,Ilr ; ilPCI 'I RIP GPM RFIC Off GPM Primary Contaimnent intact? Secondary Containment intact ? l CIS A GPM C/S 11 GPM RilR A ON 7900 GPM RllR C 01-1: l POWER AVAILAllt.E l RilR 11 ON 8000 GPM 345/I61 (startup xfmr) 2.6 MW i RilR D OI-F 69 KV Emerg MW DG#1 i KW
\DS All'lO? M ANil Al.* I.l S? liMRG DliP DG#2 I KW A 11 C'D li.F G.II I'
SHUT 1R AIN A? H? 3340 CFM ON-ON' CI'I t RPV PRIMARY SECONDARY R ADIOAr ilvh O SIMill.A IOR -- CONTROL CONTAINMENT CONTAINMENT R El.EASli 00 I:1 =CI liar F2 = F3 = M ENU F4 = SPDS INPT F5 = F6 = CANC ll AR DCOPY = CONSol.E= MODE = liVliNT = Page 7.1- 29 i i
96 ops.xls i select func. Ley or turn on code 1515 E , Nov 19.1996 ! ll%11S. (M: TSC/ EOF PLANT STAl'US l l REAC'IOR l l CONTAINMENT l Power 0.1 %APRM , Ialalune'IAl- itXL4 INCil Drywell pressure 1.1 PSIG , l Prewure 60 PSIG Drywell Temperature 115 DEGF ' Coolant temp al wip At NA DEGF Torus level 13 I:lilir nuilant remp si uip 11: NA DEGF Torus temperature 79.8 DFGI- ' Drywell cooling fans ? ON I ( s 's l DiW Rad Ili-Rng Airlock 419.1 R'llr ! D/W Rad fli-Rng La&ier 3MI Rill IIPCI TRIP GPM : RCIC Oil GPM Primary Containment intact? Secondary Containment intact ? ! C/S A GPM C!S Il GPM i RilR A ON 7900 GPM ! RilR C 01-1: l POWER AVAILABLE l { RilR 11 ON 8000 GPM 345/161 (startup xfmr) 2.6 MW ! RilR D - 69 KV Emerg MW t DG#1 Kw
\DS AlJIO? M ANilAl;? 1.iS? IiMRG DliP DG#2 Kw A B C D_ E_F_ G 11 SitG I I R AI N A? . H! 3340 CFM }
ON-ON CPil RPV PRIMARY SECONDARY R ADIDAC i lV E o f CONTAINMENT CONTAINMENT REl.EASli 00
-SIMill.A 1OR -- l CONTROL f Fl = CI. liar F2 = F3 = MENU F4 =SPDS INPF F5 = F6 = ;
i CANC ll ARDCOPY = CONSOLE = MODE = EVENT-- ! L PagC 7.I- 30 i _ _ _ _ _ - _ _ _ - - - - - _ _ - _ _ _ _ _ _ _ _ _ _ =
96 ops.xis Select func. key or turn-on code - 1530 E Nov 19,19% lPMIS 04: ISC/ EOF PLANT STATUS l REACTOR l l CONTAINMENT l Power 0.1 %APRM l 1.t 1 atwwe TAF 200.4 INCil Drywell pressure 1.1 PSIG Prevure 60 PSIG Drywell Temperature i15 DEGF n=>lant temp (lixip A) NA DEGF Torus level 13 I:liET nwilant temp fliusp lip NA DEGF Torus temperature 79 M DFGl: Drywell cooling fans ? ON , IcrS l D/W Rad Ili-Rng Airlock 419.1 R/llr l D/W Rad Ili-Rng Ladder 3MI R/llr ' ilPCI TRIP GPM RCIC Oli GPM Primary Containment intact? Secondary Containment Intact ? r/S A 'GPM - r/S 11 GPM
^
RilR A ON 7'R K) G P M RIIR U 01I: l POWER AVAILAllLE I i RilR It ON RtXXIGPM 345/161 (startup xfmo 26 MW RIIR !) 69 KV Emerg MW DG #1 KW ADS AllTO? M ANIIAl.? 1.1.S? EMRG DiiP DG#2 KW ; A 11 C .D E.F G ll - 7 silGT IRAIN A? .B? _ 3340 CFM ON-ON CPli RPV PRIMARY SECONDARY R ADIOAC l lVI: O SIMiit.ATOR CONTROL CONTAINMENT CONTAINMENT REl.EASli 00 F l = Cl. EAR I2= F3 = M ENU F4 = SPDS INPT F5 =- I:6= CANC il ARDCOPY = CONSOI.E = MODE =- I:VI.N I = 1 Page 7.1- 31 k 6
96 ops.xls Sclect func. Ley or turn-on code 1545 E Nov 19.1996 lPMIS 04: ISC/ EOF PLANT STATUS l REACTOR l CONTAINMENT l l Pow er 0.1 %APRM I.sl aime TAF 200.4 INCL { Drywell pressure 1.1 PSIG Prewure 60 PSIG Drywell Temperature 115 DEGF Coolant temp (loop A) NA DEGF Torus level 13 I:EliT Coolant temp (loop Ill NA DEGF Torus temperature 79.H DEGl: Drywell cooling fans *! ON laTS l D/W Rad fli Rng Airlock 420.2 R!Ilr D/W Rad fli-Rng I. adder 382 R/llr I1101 'I RIP GPM i R( IC Off GPM . Primary Containment intact? Secondary Containment intact ? C/S A 'GPM C!S 11 GPM l I RilR A ON 79(M) GPM RilR C 01 F POWER AVAILABLE l l RilR !! ON 8(XX) GPM 345/161 (startup xfmt) 26 MW RilR D 69 KV Emerg MW DG#1 KW ADS AllTO? MANilAl.? I.LS? IiMRG DIiP DG#2 KW A 11 C D. li, F. G II . l Sl!G T I R AIN A? Il? 3340 CFM UN-ON fI CPti RPV PRIMARY SECONDARY RADIOACllVE O SIMtII.A IOR- - CONTROL CONTAINMENT CONTAINMENT RELEASE 00 l F1 =CI. EAR Fl = F3 = M ENU F4 =SPDS INPT FS = I:6= i i CANC II AR DCOPY = CONSOLE = MODE = EVENT = Page 7. l- 32 i l
PMIA., ELS 0800 SELE CT I UP4C. KEY OR TURN ON CODF - 11/19/96 E PMIS 05: RAD VALUES ARM MSL/MSIV BUILDINGS REACTOR f UF L POOL ARE A 129 O MR11R MSL A RAD 467 MR/HR EFF RAD MON A O.39 MR/HR F UEL POOL ARE A 1.2 MR/HR MSL B RAD 428 MR/HR EFF RAD MON B O.41 MR/ItR NEW FUEL AREA O.1 MH/HR MSL C RAD 483 MR/HR EFF NRML RNG 4.10E + 01 UCt/SEC HWCU PRECOAT 6 8 MR!HR MSL D RAD 389 MR/HR FLOW 4.69E + 04 CFM h RWCU SLUDGE O.7 MR/HR SKID HE ALTH - NRML kg@B nom TIP INDE X 28.6 MR/HR LIQUIDS 11P DRIVE 1.9 MR/HR TURBfNE CRDiHCU SOUIH 1.0 MR/lfR RW EFF MON 4.71E + 00 UCl/CC EFF NRML RNG 2.43E + 01 UCl/SEC CRD.HCU NOR1H 3 6 MR/HR ST/ EFF MON 2.1 CPS EFF HIGH RNG ' O OOE + 00 UCI/SEC llPCI PUMP ROOM O 2 MR/HR REC MON 11.3 CPS FLOW 140000 CFM HitH HOOM SW 7.8 MR/HR J Normet ItHR ROOM NW 10.2 MRIHR SJAE SKID SKID HEALTH HEALTH
- HIGH - NRML b 5..q[s $i/ Normal HCIC/CS ItOOM NE 2.7 MR1tR l CS HOOM SE 2 6 MR/HR SJAE A FIAD 5 MR/HR AOG/RW '
f RONT ST ANDARD 143 O MR/HR SJAE B RAD 6 MR/HR EFF NRML RANGE 1.04E e 02 UCl/SEC ItJRB MF // COltH O.1 MR/HR SJAE A FLOW 50 CFM EFF HIGH RNG 4.10E
- 01 UC1/SEC i.
IURB HSMI COHR O 1 MR/HR SJAE B FLOW 49 CFM FLOW 36000 CFM Rf P ARE A 110 MR11R SKID HE ALTH NRML ? Normal e COrJD PlJMP ARE A O.1 MR/HR ERP SKID HEALTH HIGH ' Normal . CON 1ftOI ItOOM 0 0 MR/HR CUNI ColtH GHADL 0.3 MH4tR EFF NRML RNG 4.7 t E + 00 UCl/SEC MPF_ l HW COrJ1 rot itOOM O.0 MR/liR EFF HIGH RNG 4.30E + 00 UCl/SEC EFF PART 1.OOE 12 UCl/SEC itW l' UMP HOOM S I MR HR FL OW 3.36E
- 03 Cf M EFF GAS 4.400 01 UCl/St C HW tlASI MI NI 21 MILHR HEALTH NRML ! Normal .
DI MIN VLV 1400M 19 MR;ltR HEALTH HIGH ' Normal l HW CONV AISI L 0.3 MH f fR IUHtlS AHf A 0 0 Mit ilH RW L All 3 9 MH'llH COMBINI O fil OG E i F LUENT HADIAllON CL Niittl WGL F ASI 3 9 MH liR E XCE EDING E XCE E DING Cl N1 R:1 UGE WE Si 41 MH HR TECH SPECS 10 X TECH SPECS DRYWELL M No.; .
,iNo; i l
DW AlHlOCK 10 7 R llR DW t ADDE H 9 1 R 'lin (pg RPV PRIMARY SECONDARY RADQAcityg O SIMtit AIOH CONTHOf CONTA2rM[NT CON T AINMf MT nggg i I . Lii AH &2- F 3 = MLNU F4 = SPOS INPI Fb= F6= CANC HARDCOPY = CONSOLE - MODE - EVENT = l t
PMtw MLS 0815 - SIliCT IUNC KE Y OR TURN ON CODE 11/19/96 E PMIS 05: RAD VALUES ARM MSL/MSiv . BUILDINGS REACTOR f UE L POOL AltF A 129.0 MR!HR MSL A RAD 46? MR/HR EFF RAD MON A O.39 MR/HR IUEI POOL AHE A 1.2 MR!Hfl MSL B RAD 428 MR/HR EFF RAD MON B O.41 MR/HR Nt W f Uf L ARE A O 1 MR/HR MSL C RAD 483 MR/HR EFF NRML RNG 4.10E + 01 UCl/SEC itWCU IPE COA T 6.8 MR/HR MSL D RAD 389 MR/HR FLOW 4.69E + 04 CFM HWCU SI UDGE O 7 MR!HR SKID HEALTH - 14RML {.MMormd itP INDE X 28.6 MR/HR UQUIDS ' IIP DRIVL 1.9 MR/HR T UR8tNE CHD:HCU SOUIH 1.0 MR/HR RW EFF MON 4.83E + 00 UCI/CC EFF NRML RNG 2.43E + 01 UCI/SEC CitD,HClj NORTH 3 6 MR/HR SW EFF MON 2.1 CPS EFF HIGH RNG O.OOE + 00 UCl!SEC i tl1;I IUMP ltOOM O 2 MR1 tit REC MON 11.3 CPS FLOW 34o000 cpy ,
+
Hitit i400M SW T8 MilAIR ~ . SKID HEAL TH NRML EM Normd filth HOOM NW 10.2 MR/HR SJAE SKID HEALTH - HIGH [7[{hhormal 14CIC/CS ROOM NE 2.7 MR/HR e CS ROOM SE 2 6 MR!HR SJAE A RAD 5 MR/HR AOG/RW f I RONI ST ANDAHD 143.0 MR/HR SJAE B RAD 6 MR/Hil - EFF NRML RANGE 1.04E + O2 UCl/SE C IUHEl MEIZ COHit 0.1 MR/HR SJAE A FLOW SO CFM EFF HtGH RNG 4,10E
- 01 UCl/SEC ItHtil IISMI COllit O 1 MfUllR SJAE B FLOW 49 CFM FLOW 35000 Cf M i itf P AHf A 11 O MRIHR SKID HEALTH - NRML 4 '.' t Normal COND PtlMP Alti A O 1 MR/flR ERP SKID HE ALTH . HIGH < NormW =
(:ONIHOI ItOOM O O MR/ItR LONI COf tli GilAD1 0.3 MR/ flit EFF NRML RNG 4.83E + 00 UCl/SEC M_P_F , ItW COtJIHOL HOOM O O MR/HR EFF HIGH RNG 4.30E + 00 UCl/SEC EFF PART 1 OOE 12 UCl/SEC ttW IUMP ltOOM 5.1 MH'HR FL OW 3.36Ey 03 CFM EFF GAS 4 40E 01 UCl/ SIC- , ItW IIASI Mt N i 2.1 Mit flH IIEALTH NRML ' Normal [ DEMIN VIV ItOOM i 9 M!t.llR llE AtTH HIGH
- Normal t i F1W CONV A!Sil O 3 Mit IIH L f OHilS Altl A O O Mit tIR stW l AB 3 9 Mit;ttR COMBINED BLDG EFf LUENT RADIAllON CE N11tif 0GE E ASI 3 9 MR/HH EXCEEDING EXCEEDING CENTIMI UGF WE ST 4.1 MA/HR TECH SPECS 10 X TECH SPECS i DRYWELL dk+ '
b[ t$ j f)W AlHtOCK 10 7 H itR ; DW I ADDf H 9.7 Ft itR f gpg stry PftSAARY SECONDARY RADCACTIVE o ; SIMut AIOl{ ( DN1 rot CONTAr#UENT CONTAWMENT RELEASE 00 , i1 Lt 1 All f2 F 3 - MLNU F4 = SPDS INPI FS - F6= , CANC HARDCOPY= CONSOLE - MODE - EVENT = ;
m% as 0830 Sit f CT F UNC. KEY OR IURN ON CODE 11/19/96 'E , PMIS 05: RAD VALUES i
.t ARM MSL/MSIV SUILDINGS REACTOR iUti POOL AHLA 129 O MR/HR MSL A RAD 467 MR/HR EFF RAD MON A O.39 MR/HR F Uf I POOL AHE A 12 MR/HR MSL B RAD 428 MR/HR EFF RAD MON 8 0.41 MR/liR '
PJE W f Ull Alti A O 1 MR/HR MSL C RAD 483 MfMtR EFF NRML RNG 4.10E + 01 UCl/SEC j HWCU Pit [COAI 6 8 MRiflR MSL D RAD 389 MR/HR FLOW 4.69E + 04 CFM RWCtJ SLUDGl O 7 MR'ltR SKn HE ALTH - NRML gyjg gg i:P trJt)E X 28 6 MR/HR LIQUIDS iip DnivE 1.9 MR/HR TURBtNE f:HD 11C0 SOUlli 1.0 MR/HR RW EFF MON 4.32E + 00 UCl/CC EFF NRML RNG 2.43E
- 01 UCl/SEC CitD itCU NOHill 3 6 MRittR SW EFF MON 2.1 CPS EFF HIGH RNG O OOE
- 00 UCl/SEC HPt .t 141MP HOOM O 2 MR/ SIR REC MON 11.3 CPS FLOW 140000 CFM HIHI HOOM SW 7 8 MR/lin SKID HEALTH - NRML { ,
%rmd i itt1H HOOM NW 10.2 MR/HR SJAE SKlD HEALTH . HIGH hvi ki? Normal l Itcic CS HOOM Ni 2.1 MR/HR ,
CS itOOM St. 2 6 MR/HR SJAE A RAD 5 MR/HR AOG/RW i HONI S t ANDAHO 143 O MR/liR SJAE B RAD 6 MIMiR EFF NRML RANGE 1.04E o 02 UCliSEC IUHit MI // COHH O 1 MR!HR SJAE A FLOW 50 CFM EFF HIGH RNG 4.10E
- 01 UCl/SFC 1LHttt HSMI COHit O I MR/ttR SJAE B FLOW 49 CFM FLOW 36000 Cf M -'
. t l ni P Ant A i 1 O MH/HR SKlO HL ALTH NRMLf . No' md e
( OtJD lilMP AHI A O I MRettR ERP SKID HE Al TH ltlGH c' Nor'mel CONIHOi HOOM O O MRilin CONI COHH GHADI O 3 MR/HR EFF NRML RNG 4.32E + 00 UCI/SEC M_M HW t otJIstut 6400M O O MR/HR EFF HtGH RNG 4.30E + 00 UCl/SEC EFF PART 1 OOE 12 UCl/StC stW quMP itOOM 51 MR ltR F LOW 3.36E
- 03 CFM EFF GAS 4 40g 93 gcy 3g g I
HW liA51 ML fJ I 21 MH liH llE ALTH NRML cf.;..> Normal D' MtN VI V ItOOM 19 MH/flR HEALTH HIGH ' ~ " Ntumal itW E.ONV AISI E O .I MHillH ! It HHIS Alti A O H MH llH HW I All J9 MitltH COMiltNi D IH DG Ili t ut NI HADIAllutJ ; t I Nilul OGI t Ahl 3 9 MH llH E XCE E DING E XCE EDING , ClFJIitit tlGE WLSI 41 MR:llR TECH SPECS 10 X TECH SPECS j DRYWEll . No : 1 Noi DW Allti OCK 10 / H HR , DWlADDIR 9 I H IIH j r ( pgg HPw PftIMARY SE CONDARY ngoinacygyg g simul Al Oft ((W f HOI CONTAINMENT CONTAINMEN T gg gggg , tt t ti AH F2. F 3 = MLNU F 4 - SPDS INPI FS- F6= CANC HARDCOPYa CONSOL E MODE - EVENT I [ l r i
- . . ~ . , .-+=~~.-c ~~n.a ~-.~-.-u.-
PMtwa XtS I i 0845 - SFtECT f t)NC KEY OR TURN ON CODE 11/19/96 E PMIS 05: RAD VALUES . ARM MSL/MSIV BUILDiptGS REACTOR f UEL POOL AHI A 129O MR4tH MSL A RAD 467 MRiHR EFF RAD MON A O.39 MR111R IUIL POOt.ARFA 12 MR/ItR MSL 8 RAD 428 MR/HR EFF RAD MON B O.41 MR/HR tJLW 5 UfI Allt A O 1 MR llR MSL C RAD 483 MR/HR EFF NRML RNG 4.1QE e 01 UCl/SEC HWCU Piti COAL 6 8 Mit itR MSL D RAD 389 MR/HR FLOW 4.69E e 04 CFM itWCU SI UDGE O 7 MR HR SKID HEALTH - NRML y@f (Nortnal ~ I:P Inot x 28.6 MHeHR LIQUIDS iip oltivl 19 MR,HR TURBINE CHD'ItC U SO OlH 1 O MR!itit RW EFF MON 4 32E + 00 UCl/CC EFF NRML RNG 2,43E e 01 UCitSEC CitD itCil N Oltill 3 6 MR/tlR SW EFF MON 2.1 CPS EFF HIGH RNG O OOE 6 00 UCl/SEC itM:t f atlMp itOOM O 2 MH lfft REC MON 11.3 CPS FLOW 140000 CI M filth HOOM SW 7 8 MHillH SKID HEAllH NRML f ' s Normd itHit HOOM f4W 10 2 MRittR SJAE SKID HEALTil- HIGH E f6 +7Norinal HCtt,CS ItOOM Ni 2.1 MH.HR CS ltOOM St 2 6 MR,ltH SJAE A RAD 5 MR/HR AOGIRW F HONT ST AfJDAllD 143 O MH!ltR SJAE B RAD 6 MHMR EFF NRML RANGE 1.04E
- O2 UCliSLC ItillB Mt // COHR O 1 MH ltR SJAE A FLOW 50 Cf M EFF HtGil RNG 4.10E e 01 UCl6EC iOltR BSMI ColtH O 1 MR ltR SJAE B FLOW 49 CFM FLOW 36000 CFM lti P AHI A 11 O MH1 tit SKlD HEALIH NRML iTO 'Nonnd I:UtJD PUMP AHI A O 1 Mit itR ERP SKID HE ALTH HIGH % s nom CotJiltOI HOOM O O Mititit CotJI CultH GHADL 0 3 MH ltH EF F NRML RNG 4.32E
- 00 UCl/SEC M_ Q ttW CordlHot HOOM O O MilitH EFF HIGH RNG 4.30E + 00 UCl/SEC EFF PART 1 OOL 12 UCitSEC
.tW l'IlMP ttOOM 51 MR lif t FLOW 3.36E e 03 CFM EFF GAS 4 40F 01 UCl sic itW HASI Mi tJI 2 i Mlt.itti ItEALTH NRML Normal hl MttJ VI V lit DOM I 9 MH1tH HEAtTH HIGH ' Normal HW CorJV AtSii O 3 MH llH I(HH)S AHi A O O MH ltH HW t AH 3 9 MH ltH COMHlf41 O lu DG Lill Of NI HADIAllofJ Cl FJIH!! 066 i ASI 3 9 MH stu EXCL E DING E XCE E DING Cl N I Hti llGI WI S I 41 MH ItH TECH SPECS 10 X TECH SPECS DRYWEL L .x !No5 % Nof Ep hw AlHt OCK 10 / It lift DW I ADI)I H 9 7 It Hit g apy PRNARY $t CONDA8tY RADIOACitvt o g MtJgA]t)H LFNfHOL CONTAINMENT CONTMNMENI RELEA$1 0o ,y g g g gg aj F3 w MENU - F4 - SPOS INPI F 5 . F6=
CANC s t ARDCOPY - CONSOti MODE - EVENTw
-_ . .--_n . --, . - . _ . _n, _ _ _ _ _ _ _ _ . . , _ , , _ . _
i
- PMiwo XLS t 0900 SillCT IUNC KEY OR TURN ON CODE .
11/19/96 E PMIS 05: RAD VALUES ARM MSL/MSiv BUILDtNGS REACTOR a i Ut t POOL Altl A 129 0 MR llR MSL A RAD 467 MR/HR EFF RAD MON A O.39 MR/HR F U[t POOL ARF A 12 MRittR MSL B RAD 428 MR!HR EFF RAD MON B O.41 MR/HR ' NEW IUf( Attl A O.1 MR/HH MSL C RAD 483 MR/HR EFF NRML RNG 4.10E + 01 UCl/SEC HWCU PHI CO AI 6.8 MRHR MSL D RAD .389 MR/HR FLOW 4.69E + 04 CFM I ItWCU St UDGE O.7 MR:HR SKID HEALTH - NRML Mi$QNormal ; IIP INDE x 28.6 MR1tR LIQUIDS ; ilP DHIVt 1.9 MR,HR TURBINE CRD1tCU SOulti 1.0 MR/11R RW EFF MON 4.32E + 00 UCl/CC EFF NRML RNG 2.43E + 01 UCt/SEC ; CHD llCU riORif t 3 6 MIMER SW EFF MON 2.1 CPS EFF HIGH RNG O 00E e 00 UCl/SEC HPCI stMP itOOM O 2 MR'itR REC MON 11.3 CPS FLOW 140000 CIM e HHH ltOOM SW 7.8 MR.ItR SKID HEALTH NRML ; , ~ NormW f fillR HOOM NW 10 2 MR!HR SJAE SKID HEALTH - HfGH E w Normal l HCIC/CS HOOM Nt 2.7 MR ltR ! cs itOOM St 2 6 MR11R SJAE A RAD 5 MR/HR AOG/RW I RONI SI ArJUAftD 143 O MH!!!R SJAE B RAD 6 MR/HR EFF NRML RANGE 1.04E + O2 UCl/SEC ' ItlHR ME// CORR O 1 MH/HR SJAE A FLOW 50 CFM EFF HIGH RNG 4.10E + 01 UCISEC Ittf4H ftSMI COltR 0.1 MRillH SJAE B FLOW 49 CI M FLOW 36000 CF M lli P AHI A 11 O MRitH SKlO HE AL IH NRML . Normel COND PtIMP AHL A 01 MH/itH ERP SKtD HE At TH - HIGH s ' i Normal ; CONiltOI ItOOM O O MH'llR 4.32E 4 00 UCl/SEC ; COrdt COHH GHAl)E O.3 MR11til EFF NRML RNG ME itW CONIHOt ROOM O O MHllR EFF HIGH RNG 4.30E + 00 UCl/SEC EFF PART 1.00E 12 UCI/SEC itW Pt)MP ItOOM 51 MR1tR FLOW 3.36E + 03 CFM EFF GAS 4 40E 01 UCleSF C [' ltW liASI MI N i 2.1 MilitH llE ALTH NRML :: Normal Di MtN VIV HOOM 1.9 MRiin HEALTH HIGH i Normal 1IW CONV AISII O 3 MH Itil i011 TIS AHI A O O MH Ilit HW I All .19 Mit t111 COMttlNL 1) til DO I I i L Ut N I itADI A I It tr4 t'.I N I Htt tini i ASI 3.9 MH itit EXCEE DING EXCEEDING ! Cf NIHti18GI WI SI 41 MH11R TECH SPECS 10 X TECH SPECS > i DRYWE Li .h- . NOI DW Alitt OCK 10 7 H lift 1)W 4 ADlit il 9 I H HR [ gpg RPV PRIMARY SECONDARY RAD *0ACirvi o I CON T 5tOL CONTAfNMENT CONTAINMfNT RfIE AM on SIMtil AIOlt I2- f3* MENU f4"SPOS .tNPI F5 f6= 6i t.tl AH CANC HARDCOPY = CONSOLE - MODE 4 EVENT-r
+
J PMt:ws MLS 0915 SEtICT f tJNC KEY OR TURN ON CODE 11/19/56 E PMIS 05: RAD VALUES ARM . MSL/M$lV BUILDINGS , REACTOR I Utt Po ol A HI A 129 O MR/HR MSL A RAD 467 MRHR EFF RAD MON A O.39 MRHR F UE L POOt Af tF A 1.2 MRHH MSL B RAD 428 MR/HR EFF RAD MON B O.41 MR.HR ! NEW f Ut i AHE A O 1 MR/HR MSL C RAD 483 MR/HR EFF NRML RNG ' 4.10E'+ 01 UCl/SEC ' HWCU PHECOAl 6 8 MR/HR MSL D RAD 389 MR!HR FLOW 4 69E + 04 CFM
- HWCU St UDGE O 7 MR/HR SKID HEALTH NRML $ Normd -f IIP INDL X 28 6 MR!HR LIQUIDS r IIP DRIVL 1.9 MR/HR TURBINE CRD/HCU SOUTil 1.0 MR!HR RW EFF MON 4.32E + 00 UCl!CC EFF NRML HNG 2.43E + Of UCIISEC CHD:HCU NOHill 3 6 MR!HR SW EFF MON 2.1 CPS EFF HIGH RNG itPCI PUMP ltOOM O.2 MRHR REC MON 11.3 CPS F LOW O OOE e 00 UCl/SEC '[
I40000 CI M ltitil I100M SW / 8 MFt/HR SKID HEALTH - NRML $,. , Nottnal itHR ROOM NW 10.2 MR/HR SJAE ;. Normal SKID HEALTH - HIGH h s , HCIC/CS f tOOM Ni 2 7 MRlHR CS HOOM St 2 6 MRzHR SJAE A RAD 5 MR!HR AOG/RW I HONT S1 AtJDAHO 143 0 MR/HFt SJAEBRAD 6 MR,HR EFF NRML RANGE 1.04E e 02 UCl/SEC IUHis MI // COHit O 1 Mil /HR SJAE A FLOW 50 CFM EFF HIGH RNG 4.10E o 01 UCl/SEC IUHR HSMI COHit O. I MR;llH SJAE B FLOW 49 Cf M F LOW 36000 CF M HFP Altf A 11 O MH lin SKID HE ALTH NRML . Normal COND PtJMP Alti A O 1 MHillR ERP SKID HEALTH HIGH : brmal , CONIHol ItOOM O O MR ltR CONI COHH GilADt O 3 MR llR EFF NRML RNG 4.32E e 00 UCI/SEC M_PF_ HW CotJIHol IIOOM O O MR/HR EFF HIGH RNG 4.30E + 00 UCI!SEC EFF PART 1 OOL 12 LICl/SE C I HW IUMP ltOOM $ 1 MR HR FLOW 3.36E + 03 CFM EFF GAS 4 40E 01 UCI,SI C ! HW llASI M1 N I 21 Mit HR HE ALTH NRML '
- Normal !
Ot MIN VI V ItOOM 19 MR<llR HE ALTil HIGH Normal flW CONV AISi t O 3 Mit:1 tit iOf ttIS AHI A OO MitalH , t itW I Alt 3 9 Mit liti COMillNI D H! IH i i l f l ut N I HAOl A llorJ ClNIHilIH.I I ASI 3 9 MHHH EXCE E DING E XCE E DING Cf NI Hti O GI WI SI 41 MR ltR TECH SPECS 10 X 1ECII SPECS ! I DRYWELL > ' c NO Lc O No).p) - 1 DW Allu OCK 10 / R ltR DW L ADDIIt 91 R ltR pg new f9tiMARY SECONDARY ftADf0 ACTIVE o SIMtJI AlOH E ON I Ho, CONTANMENT CONTAWMENT RELI ASE oo II Lt t All I1 I 3 " ML NU f 4 - SPDS INPI IS" f6a ' CANC H ARDCOPY - CONSOL E MODE - EVENT - i 4
PMtb IILS 0930 Si t f C T p lJfJC KEY OR TURN ON CODE 11/19/96 E PMIS 05: RAD VALUES ARM MSL/MSIV BUILDINGS REACTOR FUEL IM)Ot AHf A 129.0 MR!HR MSL A RAD 467 MR/HR EFF RAD MON A O.39 MR/HR ! f UEL POOL AHE A 1.2 MR$1R MSL B RAD 428 MR/HR EFF RAD MON B O.41 MRIHR rJEW iUfI AHL A O.1 MR.flR MSL C RAD 4.83 MR/HR EFF NRML RNG 4.10E + 01 UCl/SEC HWCU PHI COAI 6.8 MRfilR MSL D RAD 389 MR/HR FLOW 4.69E + 04 Cf M RWCU SIUDGE O.7 MR/HR SKID HEALTH NRML f 37^.- ? NormW IIP ltJDE X 28.6 MRIHR LIQUIDS IIP DitlVE 1.9 MRalR TURBINE 4 CRD4tCU SGuilt 1.0 MR/HR RW EFF Mote 4.32E
- 00 UC1/CC EFF NRML RNG 2.43E
- 01 UCl/SEC CitD/f tCtl FJOHill 3 6 MR.'HR SW EFF MON 2.1 CPS EFF HIGH RNG O OOE e 00 UCl!SEC l ItPCI PtIMP ltOOM O.2 MR lift REC MON 113 CPS FLOW 140000 Cf M HHf t HOOM SW 7.8 MR11R SKID HE ALTH . NRML jf < Normal HHR ftOOM NW 10.2 MR/HR SJAE SKID HEALTH - HIGH IM _> {Normat) {
HCIC/CS (tOOM NE 2.7 MRatR CS ROOM Si 2.6 MRatR SJAE A HAD 5 MR/HR AOG/RW [ f RONI St AflDARD 143.0 MR31R SJAE B RAD 6 MR'HR EFF NRML RANGE 1.04E + O2 UCl!SEC IUR8 Mi // COHR O.1 MR41R SJAE A FLOW 50 CFM EFF HIGH RNG 4.10E e 01 UCl/SFC It1815 ttSMI LORR O.1 MitAIR SJAE B FLOW 49 CFM FLOW 36000 Cf M lti P AH1 A 11.0 MR11R SKlO HEAL TH NitML '*'. s E Normal ERP SKID HEAL fil HIGH '
r.Orlo PtsMP Alti A O 1 MR llR ' Normal CONiltol itOOM O.0 MR,IIR C()tJ1 COHH GHADE O 3 MR/HR EFF NRML RNG 4.32E + 00 UCl/SEC M_P_F HW COf41 Hol ItOOM O O MR
IllRH USMI COHft 0.1 MR/HR SJAE B FLOW 49 CFM FLOW 36000 CFM
~
Hf P Af tI A 11 O MRMIR SKID HEALTH - NRML 71 A Normal i COND I41MP AHf A O 1 MR!lin ERP SKID HEALTH - HIGH 5 [1 Normal I CON! hoi stOOu 0 0 MRrHR - COttI COHH GHADE O.3 MR;HR EFF NRML RNG 4.32E + 00 UCl/SEC MPF ! ItW COrdfitot HOOM 0 0 MR/HR EFF HIGH RNG 4.30E e 00 UC1/SEC EFF PART 100E 12 UCI/SLC HW PtlMP HOOM S.1 MRitR FLOW 3.36E e 03 Cf M EFF GAS 4 40E Of UClist C L HW HASI MI Ni 2.1 MR/llH HEALTH NRML 'T4 i Normal ; f)E MIN Vt V ROOM 1.9 MR/Hil HE ALTH- HIGH Normal RW cot 4V AtSti O 3 MR'llR I IOlttlS AHf A O O MH'Hil
- HW t AH 3 9 Mit/11R COMBINED Ilt DG EliLUENT HADIAIlON '
CENIHiltluttASI 3 9 MH:HH EXCEEDING EXCEEDING l CE tilHil UGE WL Si 4.1 MHiHH TECH SPECS 10 X TECH SPECS f DRYWELL I [Noh bj,.j$ NoJ 'ag;n f I DW AlHL OCK 10.1 R llR ! DW i ADDI f t 9.7 Ft itR -! Cl>U ftPV PRIMARY SECONDARY RADIDACTIVE o SIMUL A IOH CONYnOL CONTAINMENT CONTAINMENT RELEASE oo 1-1_CILAH ll- F 3 = MENU F4 e SPDS INPI Fb- F6= 'i CANC HARDCOPY = CONSOLE 4 MODE ^ EVENT = [ i
?
i i
-es rf ----- - - _ - - - - _ - - -- - _ - - _ - - - - - - - - _ - - - - - - _ - - - - - - - - -
m.a uts 1000 set ECT IUNC KEY OR TURN- ON CODE 11/19/96 E PMis 05: RAD VALUES ARM MSL/MSIV BUILDINGS REACTOR i UE L POOL AHE A 129 O MR/HR MSL A RAD 467 MR/HR EFF RAD MON A O.39 MR/HR I UfI PCOL ARE A 1.2 MR/HR MSL B RAD 428 MR/HR EFF RAD MON B O.41 MR/HR NTW FUti ARE A O.1 M R.H R MSL C RAD 483 MR!HR EFF NRML RNG 4.10E + 01 UCl/SEC ltWCU PitECOr.I 6 8 MR/itR MSL D RAD 389 MR/HR FLOW 4.69E + 04 CFM HWCU St UDGE O.7 MR/ilR SKID HEALTH - NRML b ugd Normai TIP INDI X 28.6 MR/HR LIQUIDS IIP DRIVE 19 MR/HR TURBINE CitD/HCU SOUIH 1 O MR/HR RW EFF MON 4.32E +00 UCl/CC EFF NRML RNG 2.43E + O f UCl/SEC CHD.HCU NORill 3.6 MRHR SW EFF MON 2.1 CPS EFF HIGH RNG O.OOE + 00 UCliSEC 14PCI IHMP f tOOM O.2 MR HR REC MON 11.3 CPS FLOW 140000 CFM ltillt itOOM SW 7 8 MRiHR SKID HE ALTH - NRML 's. a ... Normal RHit HOOM NW 10 2 MR/HR SJAE SKID HEALTH - HIGH O *P' ;}hormal HCICICS ItOOM NL 2.7 MR/HR CS ItOOM SE 2.6 MR/HR SJAE A RAD 5 MR/HR AOG/RW i f itONI SI ANDAHD 143 O MR/f tR SJAE B RAD 6 MR/HR EFF NPML RANGE 1.04E e 02 UCitSEC i IURI! Mt // CORR O 1 MR/HR SJAE A FLOW 50 CFM EFF HIGH RNG 4.10E e 01 UCl!SEC IllHtt IISMI COHH O 1 MR/HR SJAE B FLOW 49 CFM FLOW 36000 Cf M ltiP AlltA 11.0 MR!!!R SKID HE At TH NRML ( ,, ^ .3 Normal ! COND PtIMP AHF A O I MR/HR EHP SKID HE At TH HtGH * Normal ~ Cutalliot HOOM OO MRIHR COrJI COHit 63tADI O 3 MR HR EFF NRML RNG 4.32E e 00 UCl/SEC ME ItW COrJiltOi HOOM O.0 MR/l R EFF HtGH RNG 4.30E 4 00 UCl/SEC EFF PART 1 OOE 12 UCI/SEC HW Pt)MP stOOM 51 MR.'ItR FLOW 3.36E + 03 CFM EFF GAS 4.40E 01 UCl/Sf C itW llASI Mt NI 2.1 MH:HR HE ALT H NRML - fNormal. Of MIN VI V ItOOM 1.9 MR!tlH ttE ALTH- HIGH <' > Normal itW COrJV AISII O 3 MR! Hit IOltOS Afti A O O MH ~lif t itW I Alt 3 9 Mit/ list COMBINt D Ill DG E I F t UE N I liADI A IION Cl NIHit LtGt i ASI 3 9 Mit lift EXCEEDING EXCEL DING C[ nihil tlGE WI SY 41 MR/liR TECH SPECS 10 X TECH SPECS f U ^ !; NC
- DRYWEI L Q1 9No llzu ;
UW Allti OCK 10.7 H HH OWtADDtn 9.7 R.HR I SECONDARY I HPV PRIMARY RADIDACT1vE o LPtl CONTANMENT CONTAWMENT l SIM UtAIOR CONTROL RELEASE l oo I 1 Cll AH I/. F 3 = MENU F4 = SPDS INPI f b -' f6= CANC HARDCOPYa CONSOLE - MODE = EVENT = i L
= - - - _ . _ _ - _ - . _ _ _ _ _ _ . . . - _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
PMNm XLS 1015 SilFCI FUNC KEY OR TURN ON CODE 11/19/96 E i PMIS 05: RAD VALUES ARM MStJMSIV BUILDINGS . REACTOR IUEL POOL AftE A 129.0 MR/HR MSL A RAD 467 MR/HR EFF RAD MON A O 39 MR/HR i IUtt POOL AftE A 1.2 MR/HR MSL B RAD 428 MR/HR EFF RAD MON B O.41 MR/HR NEW FUtt AHFA O.1 MR/HR MSL C RAU 483 MR/HR EFF NRML RNG 4.10E + 01 UCl/SEC HWCU (HE CO A T 6.8 MReHR MSL D RAD 389 MR/HR FLOW 4.69E + 04 CFM f tWCU St UDGl O.7 MRiHR SKID HE ALTH - NRML $Q-j Normal. IIP INDE X 28 6 MRittR LIQUIDS IIP DRivi 1.9 MR.11R TUR8INE CitDillCt1 S OLlift 1.0 MR/HR RW EFF MON 4.32E + 00 UCl/CC EFF NRML RNG 2.43E + 01 UCl/SEC ; CRD llCU NOHill 3.6 MR/lfR SW EFF MON 2.1 CPS EFF HIGH RNG O OOE + 00 UCl/SEC ! IIPCI PUMI' HOOM O 2 MR1tR REC MON 11.3 CPS FLOW 140000 Cf M HHH HOOM SW 7.8 MR/HR SKID HEAL TH - NRML .
/ Normal
- HHH ftOOM NW 10 2 MR!HR SJAE SKID HEALTH HIGH $[ [Ndrmal itCIC:CS ftOOM NE 2.7 MR/Ha ,
CS ItOOM SE 2.6 MR/HR SJAE A RAD 5 MR/HR AOG/RW l lItOfJ T SI ANDAl4D 143 O MR/HR SJAEBRAD 6 MR/HIi EFF NRML RANGE 1.04E
- O2 UCl/SEC itJfiH MI// CultH 0.1 MR/HR SJAE A FLOW 50 CFM EFF HIGH RNG 4.10E
- 01 UCl/SEC IllHit RSMI COHH 0.1 MR/ Hit SJAE 8 FLOW 49 CFM FLOW 36000 CFM lti P Alti A 11.0 MRillR SKID HE ALTH - NRML ! ^ E Normal i COND PtJMP AHf A O.1 MR!HR ERP SK!D HE AL Til - HIGH ~ : Normal I CONIf tOI HOOM O.0 MR/HR !
LONI CultH GHADI O 3 MR/HR EFF NRML RNG 4.32E + 00 UCliSEC E M ! ItW CONIf101 ROOM O O MR/HR EFF HIGH RNG 4.30E + 00 UCl/SEC EFF PART 1 OOE 12 UCl/SFC -- HW IuMP f tOOM S 1 MR/ItR FL OW 3.36E + 03 CFM EFF GAS 4 40E 01 1801 StC HW HASE Mt NI 21 MR'llH IfE AllH NRML - Normal ; Di MIN VI V ItOOM 1.9 MR lif t tit AtTit HtGH : Normal r RW CONV AISII O 3 Mit'llit IOHtiS Alt! A O.0 Mit llH ltW I AH 3 9 MH;HH COMBINED EllUG LFF LUENT RADIAllON Ct NIH!I UGt t ASI 3.9 MR;HR ~ EXCEEDING EXCEEDING Cf NIHlf tlGE WLST 4.1 MR/HR TECH SPECS 10 X TECH SPECS DRYWELL n 3NO3 + (NC l i, l)W AlltLOCK 101 R llR DW t ADDEH 97HHR RPV PPSAARY SE CGNDARY LPU RADIDACYlvE o SIMtIt AIOH CONTROL CONTAWMENT CONTAWMENT RELEASE m 6i (.i t Att F2 F3 m MENU F4 = SPDS INPI F 5 ' F6 4 ! CANC HARDCOPY.= CONSOLE - MODE = EVENT- .- _.-_ - - _ - - . - --- - - _ . - . . _ _ _ . .~ - _ - - -
. - . . . _ _ _ . m .. . ..m_ . . _ . - 4 - . ... ._. _ . ._m... __.- ~ - - ._ _ .. _ _ . . m - . . < & . . . . . _.. . . _i PMiw HLS 1030 i Si t FCT IONC. KEY OR TURN. ON CODE 11/19/96 'E l PMIS 05: RAD VALUES i ARM MSL/MSIV BUILDINGS REACTOR j F UIL POOL ARE A 129 O MR/ttR MSL A RAD 467 MR/HR EFF RAD MON A 1.2 MR/HR MSL B RAD 428 MR/HR O 39 MR/HR .i F UEL POO! ARE A EFF RAD MON 8 0.41 MRIHR ' NEW tutI ARE A O.1 MR'HR MSL C RAD 483 MR/HR EFF NRML RNG 4.10E + 01 UCl/SEC i RWCU P!tt COAT 6.8 MR/HR MSL D RAD 389 MRiHR FLOW 4.69E + 04 CFM RWCU SLUDGE O.7 MR/HR .x SKID HEALTH - NRML MM" "~ Normal IIP INDE X 28.6 MR!HR LIQUIDS fIP OfilVE 1.9 MR/HR TURBINE CitD ltCU SOUIll 1.0 MR!HR RW EFF MON 4.32E + 00 UCl/CC EFF NRML RNG 2.43E + 01 UCI!SEC [ CRD itCti NOHIH 3.6 MRiHR SW EFF MON 21 CPS EFF HIGH RNG O OOE
- 00 UCliSEC I HPCI l' UMP HOOM O 2 MR,HR REC MON 11.3 CPS FLOW 140000 CFM !
IIHFt ROOM SW 7 8 MR/HR # ' WNormal RitR ltOOM NW ItCIC.CS ItOOM NI 10.2 MR/HR
'2.7 MR!ltR SJAE SKID HEALTH - NRML @Q YQ SKID HEALTH HIGH (j ,
CS HOOM SL 2 6 MR/HR SJAE A RAD 5 MR/HR AOGtRW ; IRONI S1 ANDAHD 143.0 MR/HR SJAE B RAD 6 MR/HR EFF NRML RANGE 1.04E
- O2 UCI/St C ltJRB Mt // COf tFt O 1 MR/fl0 SJAE A FLOW 50 CIM EFF HIGH RNG 4.10E e 01 UCISEC i t uttil llSM I COltit 0.1 MReitR SJAE B FLOW 49 Cf M FLOW 36000 Cf M illP Alti A I 1 O MR/flR SKfD HE AtJH NRML 3 * ' ~ Normal COND l' UMP AHi A O,1 MR;HR ERP i SKID itE ALIH HIGH i ? Normal CONIHot HOOM O O MR/ttR ,
CONI COHit GitADE O 3 MR/HR EFF NRML RNG 4.32E + 00 UCl/SEC y M , RW CONiltOi ItOOM O O MR/HR EFF HIGH RNG 4.30E + 00 UC1/SEC EFF PART 1 OOE 12 UCitstC ItW 11JMP ItOOM 51 MR/HR FLOW 3.36E + 03 CFM EFF GAS 4 40g oy gcgfS,g itW 11 ASE Mt N I 21 MH/HR ltE ALTH NRML 6 Normal DL MIN Vt V HOOM 19 Mit/ttR HEALTH HIGH VNormal i ItW CONV AtSI t O 3 MR lift ! IOHtlS Alt! A O O Mit itR l ItW I All 3 9 MR Ilit COMBINt D lit OG II T LUENI HAO!AIlON l CLNIHil OGl i ASI 3 9 MR:itR EXCE E DING EXCEEDING CE NIHlf tJGt WL SI 4.1 MR/Hft TECH SPECS 10 X TECH SPECS [
^#
DRYWELL b.Noi ,
, ) Nohl- 3 f
DW Allit OCK 10 7 II/HR DW t ADDI ft 9. 7 R'HR LPO Rev MuMARY SECONDARY RADIOACTivt o ' SIMUL AIOlt CONTROL CONTAINMENT CONTAINMENT RELEASE oo t 3 = MENU F 4 = SPDS INPI tS* ' tI C4LAH tJ. t6= CANC HARDCOPY = CONSOLE - MODE ^ EVENT = L
PMtwoELS 1045 Sf LE C1 iUNC. KEY OR TURN ON CODE 11/19/96 E PMIS 05: RAD VALUES t ARM MStJMSIV BUILDINGS RE ACTOR I Uf L POOI ARE A 1290 MHatR MSL A RAD 432 MR/HR EFF RAD MON A O.39 MR4tR f UE L POOL AllE A 1.2 MRTHR MSL B RAD 421 MR/HR EFF RAD MON B O 41 MRalR f41 W f tili arf A O 1 MR,HR MSL C RAD 452 MR,ttR EFF NRML RNG 4.10E e 01 UCI/SEC ItWCU lill CO A I 6 8 Mit:ttR MSL D RAD 373 MR/HR FLOW 4.6DE
- 04 CFM H WCU Sit 1DGE O.7 MR/liR SKID HE ALTH - NRML E-f-i[ Normal TIP INDE X 28 6 MR/llR LlOUIDS ,
pp ongv[- 1.9 MRJfR TURBINE CRD llCtJ SOUlH I O MR/HR RW EFF MON 4.31E + 00 UCI/CC EFF NRML RNG 2.43E e Of UCI/SEC l CHD itCil NORIH 3 6 MR>llR SW EFF MON 2.1 CPS EFF HIGH RNG O OOE e 00 t1Cl/SF C l e IPCI 11JMP itOOM O 2 Mit,ltit REC MON 11.3 CPS FLOW I40000 ClM i FlitH ROOM SW / 8 MRiHR SKID tlEALTH NRML 3 Liu (Nolmet ItitR f tOOM NW 10 2 MRelift SJAE SKID HEALTH HIGH ' a. hNotma! ItCIC/C9 ItOOM NE 2.7 MR ltR , CS ItOOM SL 2 6 MHatR SJAE A RAD 5 MR44R AOG/RW IIto/JI SI ANDARD 143 O MRiHR SJAE B RAD 6 MR/ttR EFF NRML RANGE 1.04E e 02 UCl/StC ItJHH Mt // CORR O.1 MRAtR SJAE A FLOW 50 CFM EFF HIGH RNG 4.10E e 01 UCi/SEC 10HB HSMI CORR O 1 MRatR SJAE B FLOW 49 CFM FLOW 36000 CI M Rf P AHL A 10 0 MHiltR SKID tie ALTH NRML 4
. Normal COND 111MP AltE A O 1 MH1tR ERP SKID HE ALTH HIGH < ' , INormal '
C ordillot ItO O M O O MRJIII l COtJI Coltit GRA[)t O 3 MR SIR EFF NRML RNG 4.31E + 00 UC1/SEC E M f tW COtJIHOL llOOM O O MR/ Hit EFF HIGH RNG 4.30E + 00 UCl/SEC EFF PART 1 OOL 12 OCl/SE C itW I1JMP f tOOM $ 1 MRetIR FLOW 3.36E + 03 CFM EFF GAS 4 4 0[ og u ci,3g c ItW 13ASt Mi HI 21 MH3tR HEALTH NRML i Norrpol , OF Mit! Vt V ltOOM 19 MR/IIR HFALTH HIGH Normat l HW COf 4V AtSt i O :s MH IIH IOHLt% Alti A O D MH llH ltW t AH t 9 MH IIH COML!INE D Ht i G IIi1UlNI HADIAIlON ; CI Nlltit uGt I ASI :19 Mit,ltH EXCEEDING E XCEE DirJG . Cf NIlui UGE W1SI 4.1 MH/HR TECH SPECS 10 X TECH SPECS I DRYWELL
;W .Ndj DW Allt!OCK 9 I RJIIR DW L ADDE R 8 8 RctlR g pg) HPV PRsMARY SECONDARY RAogOACTfVE O SIMUt AlOil CONTROL CONTAINMENT CONTAINMENT RELEASE Oo '
F1 CliAH I2 F 3 = MLNU f 4 = SPDS INPI F b -- F6= ~ CANC HARDCOPYa CONSOt1- MODE - EVENT = l
PMih 1:LS 1100 it t i C T f UNC K E Y - OR TURN ON CODE 11/19/96 E PMIS 05: RAD VALUES ARM MSL/MSIV BUILDINGS REACTOR F ULL P001 AHL A 129.0 MR.1tR MSL A RAD 299 MR/HR EFF RAD MON A O 39 MR/HR I IUE L POOL AltE A 12 MRIHR MSL B RAD 293 MR/HFt EFF RAD MON B O.41 MR/HR NE W I Ut i Alti A O.1 MR/HR MSL C RAD ' 302 MR!HR EFF NRML RNG 4.10E + 01 UCl/SEC itWCtJ PHI COAT 6.8 MILHR MSL D RAD 280 MR/HR FLOW 4.69E + 04 CFM i 11WCU St UDGE 2.6 MR/HR SKID HEALTH - NRML [fg.g Nonnal gtp INDE X 44.0 MR/flR LIOUIDS IIP DHIVE- 1.9 MfLHR TUF1BINE t CitD/llCt i SOU til 2 5 MR/HR RW EFF MON 4.05E + 00 UCt/CC EFF NRML RNG 2.43E + 01 UCl/SEC CitD ItCO riOstill 8.3 MR'HR SW EFF MON 2.1 CPS EFF HtGli RNG O.OOE e 00 UCl/ SIC ; tiPCI PUMP HOOM O.2 MH/liH FIEC MON 11.3 CPS FLOW 140000 CFM HtIR HOOM SW 9.4 MR/HR SKID HEALTH NRML f A Monnal HitH ftOOM NW ' 10.2 MRiHR SJAE SKID itEALTH - HIGH b [ Mmai r HCIC/CS ROOM Nt 2.9 MR/flR ; CS ItOOM SE 2.7 MRittR SJAE A RAD 4 MR/HR AOGzRW l IRONT SI ANDAHD 143 O MR!HR SJAE B RAD 5 MR/11R EFF NRML 11ANGE 1.04E + O2 UCI!SF C !
,,_,s Iultti Mt // COttR O.1 Millitit SJAE A FLOW 50 CFM EFF HIGH llNG 4.10E
- 01 0C1:51 C IUltti HSMI COHla 01 MR11R SJAE B FLOW 49 CFM FLOW 36000 CFM Hi P AHL A 10 0 MR>lin SKID ltE Al T H NFIML i ^ (- Normal
- COND l' UMP Altl A O 1 Mil / lift ERP SKID HEALTH IltGH ' ^ ; idormal ,
CONIliot itOOM O O MH!llR . CONI COttH GitADt O 2 MR/HR EFF NRML RNG 4 O5E + 00 UC1/SEC MPF ltW CONIROL ltOOM O O MR/f tR EFF HIGH RNG 4.30E + 00 UCI/SEC EFF PART 1.00E 12 UC1/SI C HW PilMP itOOM 5 0 MH.HR FLOW 3.36E e 03 CFM EFF GAS 4 40p gi oggespc HW llASI MI N I 2.1 MR.HH . ItE ALTH NRML - ^ t Normel i DE MIN V8 V 1100M 14 Millin ilEALTH HIGH 1 Normal HW t'ONV Alhii O.:1 Mit Hit , 3OlHIS AHIA 'O O Mit IIH . ItW l AH 3 9 Mit lift COMBINils til DH t Iii UI NI HADIAIHIN CLHIHti tlGE I ASI 3 9 MH itR EXCLE DING EXCELDING Cf Hittif LIGE W1 S1 4.1 MR llR TECH SPECS 10 X TECH SPECS i DRYWELL %NC ( No _t .z_3 DW Allit OCK 35 3 H HR
- DW t ADDII; 321 R HR t
' my PRaAARY SECONDARY CPU RADeOACTfvf n SIMtil Alof t CONTROL CONTAINMENT CONTAmeMENT RELLASE oo ! II Cil AH 62 F3 = MENU f 4 = SPDS INPI F6
- F6= l CANC H ARDCOPY = CONSOLE - MODE - EVENT =
\
n h L
PM.s xt S , i 1115 Si t I C15 tJNC 1(E Y OR TUflN ON CODE 11/19/96 E i i PMIS 05: RAD VALUES ARM MSL/MSIV BUILDINGS l REACTOR F UF L l'OOL AHI A 129 0 MR/HR MSL A RAD 47 MRiHR EFF RAD MON A O.39 MR/HR F UE t POOL AHf A O 8 MR/HR MSL 8 RAD 48 MR/HR EFF RAD MON 8 0 41 MRit4R r f2FW FUEi AHI A O O MR HR MSL C RAD 48 MR!HR EFF NRML RNG 2.30E + 01 UCI/SEC ' ItWCU PHICOAI 6 8 MRlliR MSL D RAO 4 7 MR/HR FLOW 4.69E + 04 CFM RWCU SttJDGE 10 5 MR/HR HI SKID HEALTH - NRML l %, Normal LIQUIDS ; flP INDE X 122 O MR>ttR itP DHIVE 2.1 MR/liR T URBINE f CitI)11CU SOUllt 10.3 MR/ItR HI RW EFF MON 4.05E + 00 UCliCC EFF NRML RNG 2.43E 6 01 UCliSEC l (,Ito lects Nottill 13 8 MR'llR SW EFF MON 2.1 CPS EFF HIGH RNG O 00E i 00 UCl!SEC ! i tP(.l l1JMP itOOM O 2 MR HR REC MON 11.3 CPS FLOW 34o000 cg u [ ltilR ROOM SW 32 8 MR/HR Hi SKID HE ALTH - NRML % Normal [ Hlif t ROOM NW 25 7 MR11R SJAE SKlO HE AtTH - HIGH I Normal RCIC,CS ItOOM NI 3 6 MR/HR CS ItOOM St 3 6 MR/HR SJAE A RAD 7 MR/HR AOG/HW 1 f RONI ST ANDARO 18 O MR/HR SJAEB RAD 9 MR/HR EFF NRML RANGE 1.04E e 02 UCl/SEC ' IUltH MI // CORR O 1 MR ltR SJAE A FLOW 50 CFM EFF HIGH RNG 2.30E e 01 UCl/SEC 101111 t1SMI Coltit O 1 MR1til SJAE B FLOW 49 CFM FLOW 36000 Cf M Illl' Af t! A 100 MR/liR SKID HE ALTH NRML .; Normal q .ONO I11MI' AltE A O 1 MR/HR f_RP SKID ttE AL TH HIGH i Normal CotJiltol HOOM O O MRittR ; LOfit CORR GitApt O 2 MR/HR EFF NRML RNG 4 05E + 00 UCl/SEC MPF ; itW CONillOl HOOM O O MRilin EFF HIGH RNG 4.30E + 00 UCirSEC EFF PART 1 OOE 12 UCI!SEC ItW 511MP HOOM 5 O MR ltR FLOW 4.33E e 03 CFM EFF GAS 4 40F 01 tlCl/ SIC i Norrpal ! ItW llAbt Ml NI 2 1 M R Hit HE ALTH NRML lif Mif4 VIV ItOOM 14 MR,lIR HE ALTH HIGH ~ Normal itW LONV AISI( O 1 Mit flit i 10ltt15 Alti A O O Mit lif t ItW t All .I 9 MH llH COMl31NI18 til 00 L t iIULNI ItADIAIlON Li NIHlf U(si iASI J 9 Mit lift E XCEE DING E XCE EDING ; Cl NIHit tlGE wt SI 41 MR ltR TECH SPECS 10 X TECH SPECS t t DRYWELL :No" ; No ' 1)W Allti t)a 140 8 R llR OW l ADDIH 1280 HltR ( .l't l HPV PRNAAY SECONDARY RADIOACTIVE o + CONY ATNpfNT CONTAINMENT pgtg4gg , SIMUL AItlit CONTROL g0 12 F 3 = MENU 5 4 a SPDS INPI F5- F6
- tI Lil AH CANC HARDCOPYa CONSOLE -. MODE " EVENT = I L
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_ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .___-__-____ ______________=___-_____________ - __ -_______-__ E
PMua ULS SE t l C T I UNC K EY OR TURN- ON CODE 11/19/96 E PMIS 05: RAD VALUES ARM MSL/MSIV BUILDINGS l REACTOR f UE t POOL AHE A 129.0 MH/liR MSL A RAD 31 MR/HR EFF RAD MON A 11 MR4tR F UE1 IOOL ARE A 2.1 MRillH MSL B RAD 32 MRaiR EFF RAD MON B 12 MRaiR NE W Ftift AHE A O.1 MR,UR MSL C RAD 33 MR/HR EFF NRML RNG 8.OOE + 00 UCl/SEC HWCU l'Of COAI 8 O MRAIR MSL D RAD 32 MR/HR FLOW ISOL CFM i RWCU stiJDGE OSH OSH SKID HE ALTH - NRML [jf9 Normal - TIP INDE X 302.0 MR/HR HI LIQUIDS tlP DHivt 2.4 MR/HH TURBINE CHD!s tCtl Sou til 28.3 MRi14R HI RW EFF MON 8.OOE 01 UCl/CC EFF NRML FING 2.43E e 01 UCl/SEC CitD1100 TJOHIil 13 8 MH/IIH SW EFF MON 2.1 CPS EFF HIGH RNG O OOE
- 00 UCl'SEC t etti PtIMP ltOOM 16 O MRitit til REC MON 11.3 CPS FLOW 140000 Cf M ltilR HOOM SW OSH OSH SKtD HEALTH - NRML b " _Norrawl ItifR ltOOM NW OSH OSH SJAE SKID HEALTH - HIGH [E joifnal i itCtc CS HOOM NE 3 G MRHR CS HOOM SE 3 6 MH/HR SJAE A RAD 1 MR/HR AOG/RW iHONI SI ANDARD 18 O MR/HH SJAE B RAD 1 MR/HR EFF NRML RANGE 1.04E o 02 UCl/SEC '
ItlRH MT // COHR O 1 MR/IIR SJAE A FLOW 50 CFM EFF HIGH RNG 8 OOE e OO UCl/SEC 1Iistil HSM1 COHR O 1 MR/itH SJAE 8 FLOW 49 CTM FLOW 36000 ClM iil P AHf A 8 O M R'llH SKl0 HE AtTil NRML - ; Normal COND PtIMP Altf A O 1 MR HR ERP SKID HE ALT H - HIGH ? Normal CONiitt)l HOOM O O MH IfH CONI COllH GNADE O 2 MR.11H EFF NRML RNG 8.OOE 01 UCl/SEC y M ItW CONIHot HOOM O.O MR/HR EFF HIGH RNG 4.30E + 00 UCl/SEC EFF PART 1 OOL I? UCI/SE C itW Pt #MP ftOOM S O Mn:HR FLOW 4.33E o 03 CFM EFF GAS 4 40E 01 (JCISIC i ItW HALL Mt Ni 2.1 MH HR HE ALTH NRML 4 Normal DE MtN VI V HOOM 14 Mit11H HE ALTH. HIGH
- Normal t itW CONV AISi[ O.3 MH lfil '
IDHilS Alli A 0 0 Mit lif t HW l All 3 9 Mit ilH COMBINI D litiHiIii!Ut NI HADIAIlON Ct NiittilfGI i ASI J 9 MH stH EXCEE DING E XCEEDING CE N!HilllGI Wt SI 41 MH HR TECH SPECS 10 X TECH SPECS DRYWELL ., [No; 7 Noi [ DW AlH1 OC K 363 0 ft ttH [ DW l ADDilt 3300 R11H ( fg g nev PRtMAny SECONDARY RADtOACTfvE o f SIMUt A1()H CONTROL CONTAINMENT CONTAINMENT RELEASE w
,, og g an p2_ F3-MENU f 4 4 SPOS INPIFS= F6 e i CANC llARDCOPY= CONSOLE = MODE = EVENT = l t
. ,- +.&... ~ u . -
1 Pf@~s XLS I145 SEtICT ltJNC KEY OR TURN ON CODE - 11/19/96 E PMIS 05: RAD VALUES
-ARM MSL/MSIV BUILDINGS REACTOR f Uf1 POOL AltE A 129 O MR!HR MSL A RAD 31 MR/HR EFF RAD MON A ISOL MR/HR f UEl POOL AltE A 3 2 MR/HR MSL B RAD 32 MR/HR EFF RAD MON B ISOL MR/HR NE W I(11i Altt A O.1 MR/HR MSL C RAD 33 MR/HR EFF NRML RNG 2.30E + 01 UCl/SEC f tWCU Pf ti CO A T 11.0 MR/HR MSL D RAD . 32 MR/HR FLOW ISOL CFM RWCU SLUDGE OSH OSH SKID HEALTH - NRML L ? ' 5 hormal
' ' ' ~
IIP INDF X 337 O MR.HR HI LIQUIDS flP DRIVF 2.5 MR/HR TURBINE CRD'llCU SOUT H 31.8 MR/HR HI RW EFF MON 6.OOE-02 UCl/CC EFF NRML RNG 2.43E
- OI UCl/SEC CitD'liCU fJOHIH 13 8 MR.1tR SW EFF MON 2.1 CPS EFF HIGH RNG O OOE
- 00 UCist C itI4:1 PUMP ItOOM 16 7 MR/HR HI REC MON 11.3 CPS FLOW 140000 Cf M ItttR ROOM SW OSH OSH Ht R ftOOM NW OSH OSH SJAE SKID HE AL TH - NRML 77 ~ , A: SKID HEALTH - HIGH b Mrdal itCICrCS HOOM NL 3.6 MR/HR CS ItOOM SL 3 6 MR.HR 5JAE A RAD O MR/HR AOG/RW I ftONI St ANDAHD 8.9 MR/HR SJAE B RAD O MR/HR EFF NRML RANGE 1.04E
- O2 UCl/SEC IllitB Mi // COf tR O 1 MRittR SJAE A FLOW 50 CFM EFF HIGH RNG SJAE B FLOW 2.30E e 01 UCl/SEC IUltH (ISMI COltR O 1 MR,ilR 49 Cf M FLOW 36000 Cf M lif P ARF A 8 O MR/HR SKID HEALTH - NRML K i M Normat COND IUMP Af tf A O.1 MH/HR ERP SKID HEALTH - HIGH k;g f Normal CON 11tol itOOM O O MR.itR CONI COftft GitADE O 2 MR.11H EFF NRML RNG 6.OOE O2 UCl/SEC ME ItW CONif 40L llOOM O O MR/HR EFF HIGH RNG 4.30E + 00 UCl/SEC EFF PART 1 OOE 12 UCl/St C HW PUMP f tOOM 5 O MH llR FLOW 4.33E e 03 CTM EFF GAS 4 40E 01 UCl/SF C HW RASI Mt Ni 21 MR.HR HEALTH NRML t5 Normal OEMIN V1V llOOM 14 MILHH HE ALTH- HIGH Normal HW CONV AISti O 3 MR/liH IOHUS Atti A O O Mit IIH ltW L Alt 3 9 MH.itH COMBINED filDG Lf f LUENT HADIA!!ON CENiilli(fGI E ASI 3 9 Mit litt E XCEE DING EXCEL DING Cf NIHilUGE WEST 4 i MR/HR TECH SPECS 10 X TECH SPECS DRYWELL s 2.t 4.Na h 14: . {No '.y ^
DW AlltiOLK 415 8 R HR DW L ADDE R 318 0 R IIR LPU HW PRAAARY $fCONDARY stMUt AIOlt CONTHOL CONTAWMENT CONTAlhMENT REDtOACTrYE o f-3 = MLNU REuASE m s; cil An i2 f 4 - SPDS INPI fS= f6= CANC HARDCOPY= CONSOL E u MODE a EVENT &
~ . _ . . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
PM:%a MLS [ t i200 sfIECT IUNC KEY OR TURN ON CODE - 11/19/gs E PMIS 05: RAD VALUES j ARM MSL/MSIV BUILDtNGS I REACTOR ! i Ut L IUOL AltE A 129 O MR/HR MSL A RAD 31 MR/HR EFF RAD MON A ISOL MRHR f F tif t POOL AllE A 3 5 MR HR MSL 8 RAD . 32 MR/HR EFF RAD MON B ISOL MR/HR NI W I UI I Altf A O.1 MR/HR MSL C RAD 33 MR/HR EFF NRML RNG 2.30E + Of UCl!SEC l ItWCu l'fl[ CO A l 11.0 MR/HR MSL D RAD 32 MRIHR ' FLOW ISOL CFM i 4WCU SLUDGE OSH OSH SKID HEALTH - NRML M2"7 Normal [ I(P INDE X 342.0 MR/HR HI LIQUIDS ; IIP DRIVE 5.3 MR!HR Hi TURBINE , CRD/f tCO SOulti 32.3 MR/HR HI RW EFF MON 6.OOE O2 UCI/CC EF F NRML RNG 2.43E + 01 UC1/SEC I CHD11Ctl NOlt fit 13.8 MRitR SW EFF MON 2.1 CPS EFF HtGH RNG O OOE e 00 UCI!SEC I HPCI PUMP ROOM 16.8 MR/HR HI REC MON 11.3 CPS FLOW 140000 CFM . ItHit ROOM SW OSH OSH SKID HEALTH - NRML ftHH ROOM NW HCtC,CS ItOOM rJE OSH OSH 3 6 MR/HR SJAE SKtD HEALTH 6,g- HIGH {MRM No< mal' (-Mths t CS HOOM SL 3.6 MR/HR SJAE A RAD 0 MR/HR AOG/RW ! I HONI St ANDAltD 8.9 MRalR SJA.8B RAD 0 MR/HR EFF NRML ftANGE 1.04E + O2 UCl/SEC IURB Mt // CORR O.1 M R/itR SJAE A FLOW 50 CFM EFF HIGH RNG 2.30E e 01 UCl/SEC IUitB EISMI COHR O 1 MR/ttR SJAE B FLOW 49 CFM F LOW 36000 CIM ! Itf P Alt! A 6 O MR/HR SKID HEALTH NRML ? % J Normal . COND Pt)MP AHf A O.1 MRitR ERP SKlO HEALTH HIGH af , ( Normal [ CONIHOl ROOM 0 0 MR/HR CONI COHH GilADL O.2 MH!llR EFF NRML RNG 6.OOE O2 UCl/SEC MPF ItW CONIHot HOOM O O MR/HR EFF HIGH RNG 4.30E + 00 UCt/SEC EFF PART 1.OOE 12 UCl/SEC 'I ItW PtfMP HOOM S O MH;HR FLOW . 4.33E o 03 CFM EFF GAS 4 40E 01 UCl/SFC [ ltW HASt Mt N1 2.1 MR/HH HEALTH NRML y $Norrhol 14 MR'HR HFALTH HIGH Norrrial ; D[ MIN VI V It00M itW CONV AISIt O 3 MH/f tft , IOHllS Alti A O O MH'llH l H W t Att 3 9 MH 1911 COMBINLH Bt HG IIII ULN! IIADIAllON f ClNiittTUGE t ASI 3 9 MHillR EXCEEDING EXCEEDING C6 NIHtlUGE WEST 41 MRlHR TECH SPECS 10 X TECH SPECS DRYWELL [$MM.1 3ItitiNol-%3 t DW Allt!OCK 419.1 R HR i DW t ADDE H 381 O R HR & L CPU ev PRN Any MCONDARf RAO OACTWE o StMUL AIOlt CONTROL CONTAWENT CONTAMENT prtgAsg og j i2= F 3 = MENU F4 -,: SPDS INPI F5* F6= i1 ClI All CANC HARDCOPYa CONSOLE - MODE = EVENT = t i
PMtS% Als 16 5ElFCT FUNC KEY OR TURN ON CODE ,,9/96 E PMIS 05: RAD VALUES ARM MSL/MSIV BUILDINGS REACTOR F Ult IUOL ARE A 129 O MR.HR MSL A RAD 31 MR/HR EFF RAD MON A ISOL MR!HR I titt POOL AHf A 12.3 MH:ttR HI MSL B RAD 32 MR/HR EFF RAD MON B ISOL MR/HR rJtWfUII AHLA 1 1 MR/HR MSL C RAD 33 MR/HR EFF NRML RNG ISOL UCl/SEC HWCU PRI COAi 13 O MR!!!R MSL D RAD 32 MR/HR FLOW ISOL Cf M HWCU SlUDGI OSit OSH SKlO HEALTH NRML p , ' [ Normal IIP INDE X OSit OSit LIQUIDS gie pHIVE OSH OSH TUR8INE CHO IICU SOUlit OSH OSH RW EFF MON 5.28E + 04 UCl/CC EFF NRML RNG 2.43E + 01 UCl/SEC CHO ltCil tJOfillt 13 0 MR HR SW EFF MON 2.1 CPS EFF HIGH ftNG O OOE e 00 UCl/SEC llPCI ICMP ItOOM 6 8 MHillR HI REC MON 11.3 CPS FLOW 140000 Cf M Hillt HOOM SW OSH OStt SKID HEALTH - NFtML P ' ' Normal HHH ROOM NW OSit OSit SJAE SKID HEALTil HIGH E $ Normal HCIC,CS ROOM NI 18.0 bl HI CS HOOM SL USH OSH SJAE A RAD 0 MR!HR AOG/RW F HotJT ST ANDAltD 8 9 MR!HR SJAEB RAD 0 MR/HR EFF NRML RANGE 1.04E + O2 UCl/SI C IUHHMFilCOHH O 1 MRatR SJAE A FLOW O CFM EFF HIGH RNG O CFM ISOL UCl/SLC ltlHit BSMT COHn 01 MR'HR SJAE B FLOW FLOW 36000 CFM H6 P AltE A 3 9 Mit ltR SKlO itE AL TH - NRML ; . Normal COND PUMP AHf A O 1 MR:llR ERP SKID HE ALTH - HIGH i tsormat ( (ITJ 1 hot HOOM O O MR/HR ( 'ifJi CORR GI4ADI O 2 MR/HR EFF NRML RNG 5.28E + 04 UCI/SEC MPF HW CON t Rol HOOM O O MRTHR EFF HIGH RNG 4.30E + 00 UCl/SEC EFF PART 1.OOE 1;t UCI.Si C HW PUMP ROOM S O MR'HR FLOW 4.33E
- 03 CFM EFF GAS 4 40E Of UCl:SI C HW tlASE Mt NI 7 i MH HR llE AliH NRML . l Normal Of MIN VLV HOOM 14 Mit ilR itE ALTH HIGH :- Normat itW CONV AISi t O 3 Mit.IIH I()RtIS A:ll A O O MH
- til HW t All 3 9 MH,ltit COMBINED BtDG EF FLUENT HADIAllON Cl NIHilUGE t As 3 9 MR'HR EXCEED!NG EXCEEDING LEtJiltif UGE WLSI 41 MR'Itp TECH SPECS 10 X TECit SPECS ORYWELL $_ Noi INo; j OW AlHIOCK '3191 H itH
()W I ADOll; 381.0 R llR tiq) RPV 6% MARY SECONDARY RAOf0ACflVE o SIMUL A T OR CONIROL CONTAINMEleT CONTAINMENT pgtg g i1 -LtE AH I2 F 3 : MLNU f 4 = SPDS INPI Fb= F6 = CANC HARDCOPY= CONSOL E - MODE " ' EVENT. M' ~i'
PMISus ELS 1230 StilCT IONC KEY OR TURN ON CODE . 11/19/96 E PMIS 05: RAD VALUES ARM MSL/MStV BUILDINGS REACTOR I(JE I POOL AftE A 129 O MP HR MSL A RAD 31 MR!HR EFF RAD MON A ISOL MR/HR r i UEt POOL ARE A 12.3 *SR/ItR HI MSL B RAD 32 MR/HR EFF RAD MON B ISOL MR/HR tJL W ItlEl Alt! A 1.1 YRHR MSL C ftAD 33 MR/HR EFF NRML RNG ISOL UCl/SEC HWCU PHICOAT 14.0 MilittR MSL D RAD 32 MR!HR FLOW ISOL CFM HWCt1 St t H)GI USH OSH SKID HEALTH NRML @!W MNorrhal itPINDtX OSH OSH LIQUIDS j ItP DHIVE OSH OSH TURBINE
~;
CHD:ItCtl Soulis OSH OSti RW EFF MON 9.78E + 05 UC1/CC EFF NRML RNG 2.43E + 01 UCUSrc - CitD 1tCu tJolillt 13 8 Mit/ttH SW EFF MON 2.1 CPS EFF HIGH RNG G Obt ,00 UCPSE C ' Hitt PUMPltOOM 6 8 MR llH lli REC MON 11.3 CPS ELO'.V 140000 CIM OSit OSH HHR HOOM SW SJAE SKID HEALTH - NRML Kfx :., Normal Hitil itOOM NW OSH OSH SKID HEALTH HIGH F y@.[Norinal . ItCIC,CS f tOOM NI OSH OSH CS ItOOM SE OSH OSil SJAE A RAD 0 MR/HR AOG/RW IHONI St At4DAHO 8.9 MR,liR SJAE B RAD 0 MR/HR EFF NRML FtANGE 1.04E
- 02 UCl/SEC I itiRR MI // COitR O.1 MRiitit SJAE A FLOW O Cf M EFF HIGH RNG ISOL UC1/SEC ,
tUHu HSMI ruitH O I MH llH SJAE B FLOW O CIM FLOW 36000 Cf M up g. AHi A 1 O MH1 tit SKID HE ALIH - NRML : ' Normal i COND PtiMP Alti A O 1 MR/HH ERP SKID HEAlill - HIGH > Normal i CONiHO HOOM O O MH.HH ! Coral Cint:teADI O.2 MR' Hit EFF NRML RNG 9.78E + 05 UCl/SEC ME _ j HW CONIHot itOOM O O MHiltR tEFF HIGH RNG 4.30E + 00 UCl/SEC EFF PART 1 OOE 12 UCl/St C . HW PUMP ItOOM S O Mit/ltit FLOW 4.33E + 03 CFM EFF GAS 4 40E 01 UCt/StC t itW R ASI M1 NI 2.1 Mit HH HEALTH NRML '- 0 Normal .; DE MIN VI V HOOM 1.4 Mit lif t HE ALTit HIGH . Normal HW CONV Athi t O 3 MllllH IOtttJS Alti A O O MH lill ! H W t Alt 3 9 MH Iti: COM8tNI O lit 120 t I i L ULNI HADI AIION CENIHit tml i ASI 3 9 MH HH EXCE EDiNG E XCEEDING CF NIItti tml W1 S1 4.1 MR HH TECH SPECS 10 X TECH SPECS i DRYWEtt lyes L-- .s h --Noi , DW AlHI Ot.K 419 i R llH DW t ADDI H 381O R11R Leg) 8&V PRtMARY SECONDARY RAnayacigyg n StMtJt AI(lit CON ' Hot CONTAINMfNY CONTAmsMfMT ngma,g -g i tt Cli AH I/ f 3 uMLNU i 4 s SPDS INPI f 5 "- F- 6 6 ! CANC HARDCOPY - ONSO'E+
~
MODE -- EVENT. I l t
- _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - _ _ . _ _ _ _ _ _ - . - ~.
Puim xts "b Sill CT f UNC. KEY OR TURN- ON CODE 1 I19/96 E PMIS 05: RAD VALUES ARM MSL/MSIV - BUILDINGS REACTOR i Ut l W)Ot Alt! A 129 O MH:tlH MSL A RAD 31 MRiHR EFF RAD MON A ISOL MR/HR
,TUEl P001 ARF A 12 3 MR4tR HI MSL B RAD 32 MR/HR EFF RAD MON B ISOL MR/HR tifW TOFT AHIA 11 MH.HR MSL C RAD 33 MR/HR EFF NRML RNG , ISOL UCl/SEC HWCU Plit COAI 14 O MR;HR MSL D RAD 32 MR/HR FLOW ISOL CFM i RWCU StuDGE OSH OSH SKID HEALIH - NRML Ee T Nonns LIP INDE X OSit OSH LIQUROS IIP DRIVE OSH Ossi TURBINE CRD,ltCU SOUIll OSH OSH RW EFF MON 7.94E + 05 UCl/CC EFF NRML RNG 2.e3e , O n UCl/SEC CHD.llCU NOHIH 13 8 MRTHH SW EFF MON 2.1 CPS EFF HIGH RNG '
O OOE e 00 UCitSFC I(PCI liaMP HOOM 3 2 MR ttH REC MON 11.3 CPS FLOW i4oooo c,y , tillH ROOM SW OSH OSH OSit OSH SJAE SKID ttEALTH NRML [;ijQ*: Normal HHH HOOM NW SKID HEALTH - HIGH s ' yhd itCICICS HOOM NE OSH OSH CS itOOM SL OSH OSH SJAE A RAD O MR/HR AOG!RW i HON I S t AND AHD 8.9 MH/Itti SJAt. B RAD 0 MR/HR EFF NRML RANGE 1.04E 02 UCli. ~ I UHit Mt // COUR O 1 MRittR SJAE A FLOW O CFM EFF HIGli RNG ISOt UC1/SLC t ulta HSMI COHR O 1 MR!llR SJAE B FLOW O CFM FLOW 36000 Cf M Hi P Alt! A 1 O MR llR SKlO HE ALTH NRMLL -~ Normal CONI) PtlMP Alti A O.1 MR llR ERP SK!D ttE AL TH . HIGH *
,40rmal CONistot itOOM O.0 MR.1tR CONI COHit GHADE O 2 MH;lin EFF NRML RNG 7.94E 4 05 UCl/SEC MPF !
stW CONIHGt HOOM O O MR!lfR EFF HIGH RNG 3.16E + 05 UC1/SEC EFF PART 1 OOL 12 UCI!SLC
- ItW PtiMP 1400M S O MHJHR FLOW 4.33E + 03 CFM EFF GAS 4 4og og opg ggg ItW IMSI MI N I 21MRliR HEALTH NRML MW Normal i DE MIN VI V ItOOM i 1 MH liR HEALTH HIGH -
- S Normal HW CtlNV Alsli 01 MH lilt IOlttas AHI A O O Mit lif t itW t Alg '.I 9 MH Hit COMilINI D lit DG l i I L Ut N I HADI A 1 TON !
LE NIittilfGt i ASI 3 'l Mit llH EXCE LDING EXCELDING CI NIHITUGE WE ST 4.1 MR telt TECH SPECS 10 X TECH SPECS i OftYWELL IYes? .
? Noj.
I DW AtHt OCK 4191 It HH DW I ADDI H 381O FtliR Citj stW PRNARY SECONDARY RAQsOACTsv6 o SIMut AlOR E UN194 tit CONTAINMENT CON T AINMfN T gg g g iI Cl( AH I/ t J = MENU F4 = SPOS INPI &b- F6 = CANC llARDCOPY= CONSOLE - MODE - EVENT + J
PM!u ELS i 1300 st(f C i ftitJC K[ Y OnTURN ON CODE 11/19/96 E i PMIS 05: RAD VALUES ARM MSL!MSIV BUILCifdGS REACTOR I UT L POOt AltE A 129.0 MR/HR MSL A RAD 31 MR/HR EFF RAD MON A ISOL MR/HR I tJEl POOL Af tE A 12.3 MR/HR HI MSL B RAD 32 MR'HR EFF RAD MON B ISOL MR/HR NEW IU[t Alti A 1.1 MR/HH MSL C RAD .33 MRrHR EFF NRML RNG ISOL UCl/SEC RWCU Pf ti CO AI 14.0 MR/ItR MSL D RAD 32 MR/HR FLOW ISOL CFM HWCU SI UDGE OSH OSH SKlO HEALTH - NRML {, .. g Normal [ IlP INDE x OSH OSH LIQUIDS t IP OstlVE OSH OSH TURBINE CitD.IICU Soutil OSH OSH RW EFF MON 5.51E + 05 UCl/CC EFF NRML RNG 2.43E e Of UCl/SEC : CHO IfCO NOHIH 13.8 Mit llR SW EFF MON 2.1 CPS EFF HIGH RNG O OOE a 00 UCl/SEC HPCI PilMP ltOOM 3 2 MR llR REC MON 11.3 CPS FLOW 140000 Cf M L ltt til HOOM SW OSH OSH SKID HEALTH NRML { q .g. Normal i lit tH flOOM NW OSH OSH SJAE SKID HEALTH - HIGH ^ , , 1 Normal l t HCIC/CS ItOOM Nt OSH OSH j CS ROOM St OSII OSH SJAE A RAD O MR/flR AOG/RW fItONI SI AMDAHO 8 9 MRlHR SJAEB RAD 0 MR/HR EFF NRML RANGE 104E e O2 tlCl/SEC , IllitH MI // COttit 0.1 MR11R SJAE A FLOW O Cf M EFF HIGH RNG ISOL UCl/SEC Itittfi flSMI LOHH O I Mit/f1H SJAE B FLOW O Cf M FLOW 36000 CI M , HI P Altl A 10 Mit itR SKID i1E At i ti NRML L Normel COND PtIMP AHf A O I Mildift ERP SKID HEAL TH HIGH ' i Normal I CorJIllut itOOM ' O O MH/HH i ('ONI COHH GHA(>F 0 2 MR/itR EFF NRML RNG 5.51E + 05 UCl/SEC E M [ ltW CONiitot itOOM O O MH/ Hit EFF HIGH RNG 3.50E + 05 UCI/SEC EFF PART 1 OOE 12 UCl/SEC I stW PUMP itOOM S O MR;1tn FLOW 4.33E + 03 CFM EFF GAS 4 40F 01 UCl/SEC itW tlASt MI NI 2. I Mit.HH HEALTH NRML , Normal i OF MIN VI V ItOOM 14 Mit,llR HE ALTH- HIGH ; Normal HW CONV AISil O 3 MH llR IOHUS Alti A O O Mit itit l ItW t All J 9 Mit itH COMutNI O tillHilIil(H NI ItADtA floN ! Cl NIHtt tu.t i ASI J 9 MH ith E XCEL DING E XCt E DING ! Cl NittilllGE Wt S1 ' 41 MH;ltH TECH SPECS 10 X TECH SPECS
.' I DRYWEtt -
No LNo . : 2 DW AtHI 04.K 419 I H llH OW t ADDI tt 381 O H ltR ( LPU Rpy ppagany S C NOAW RAOt0ACDVE o SIMt4 AIOR CONTROL CONTAINMENT CONTAWMENT RELEASE 00 ! ti L t t AH fl. F3 4 MENU f 4 -SPDS INPI Iba F6
- CANC HARDCOPYa CONSOL E - MODE e- EVENT.-
1 { l
PMISus XLS 1315 SillCT FUNC KEY OR TURN ON CODE 11/1 gfg6 E PMIS 05: RAD VALUES & ARM MSL/MStV BUILDINGS 11EACTOR IUEl POOi AHI A 129 0 MR;HR MSL A RAD 31 MR/HR EFF RAD MON A ISOL MR;HR I UEt POOt ARE A 12.3 MR HR Hi MSL B RAD 32 MR/HR EFF RAD MON B ISOL MR/HR 1 TJ[W f Uf 4 Alt! A 1.1 MR,HR MSL C RAD 33 MR.HR EFF NRML RNG ISOL UCl/SEC l RWCU PHECOAi 14.0 MR;Hft MSL G RAD 32 MR/HR FLOW ISOL CFM RWCU StuDGE OSil OSH SKID HEALTH NRML ^Q ' 7:R. Norrnal
^ ~' ~
IIP lNDE X OSH OSH LIQUIDS I tP Oitivt OSH OSit TURBINE L.HD HCU SOUfil OSH OSH RW EFF MON 3.82E + 05 UCl/CC EFF NRML RNG 2.43E e 01 UCl!SEC ! CitD llCU HOHill 13 8 MR!ltR SW EFF MON 2.1 CPS EFF HIGH RNG O 00E + 00 UCl/SEC i tPCI PUMP ltOOM 3 2 Mit HR REC MON 11.3 CPS FLOW 140000 Cf M HHit itOOM SW OSH OSil SKtD HEAlf H NRML ". %rinat ; itHH llOOM NW OSH OSH SJAE SKID HE ALTH HIGH bY ,
*Et Norinal HCIC.CS HOOM NI OSH OSH ;
CS ftOOM SE OSH OSH SJAE A RAD 0 MR/HR AOG/RW IHONT ST ANDAltD 8.9 MFt/HR SJAE B RAD 0 MR/HR EFF NRML RANGE 1.04E e 02 UCl/SEC I UHH MI // COllH O I MR!HR SJAE A FLOW 0 CFM EFF HIGH FING ISOt UCt/SEC ' lifHtt itSMI ColtH O 1 Mit HH SJAE B FLOW 0 CFM FLOW 36000 Cf M Hi P ARI A 10 MR!HR SKID HE At iH NRML. , Normal CON () PUMP AHL A 0 I MR:HR ERP SKID HE Allit - HIGH . %rmal ' CONiltot itOOM 0 0 MR'HR CONI LOllH GRADt O 2 MR HR EFF NRML RNG 3.82E + 05 UCt/SEC ME ItW CONiltOt itOOM O O MR/ttR EFF HIGH RNG 5.51E o 05 UCl/SEC EFF PART 100f 12 UCl/St C itW PUMP itOOM S O MR/1tR FLOW 4.33E, + 03 CFM EFF GAS 4 40E 01 UCUS(C Itw itASI Me NI 2.I M H Hit HEALTH NRML L Normal Of MIN Vt V ItOOM 14 MitUR HEALTH H!GH ' Normal itW CONv AISI L 0 3 Mit'llit IOHHS AIU A G O Mit lif t . HW I All .I 9 Mit flit COMlllNI D ist i H i i i i i Ul N I ItADI A l(ON CI Nill!I UGl I ASI 3 9 MH itH E XCEEDING L XCE EDING CE Niitti(Hit WISI 41 Mit HH TECH SPECS 10 X TECH SPECS DRYWEtt i NC ' i No - OW Atill O(.K 419 I Illtft i f)W I ADDllt 381 O R llR g pry PRIMARY SECONDARY RAD 80ACilVE O CONTAINME N T CONTAINMENT Rf L EA$f m SIMut Af f)H CON T Hot ti Lti Alt I/. F 3 -MLNU f 4 - SPDS INPI t5- It a CANC HARDCOPY4 CONSOLE - MODE - EVENT -
PMib . ALS 1330 SE tECT IUNC KEY OR TURN ON t ODE 11/19/96 E PMIS 05: RAD VALUES . ARM MSL/MSIV ButLDINGS i REACTOR F UEt POOt AltE A I29.0 MR!ltR MSL A RAD 31 MR/HR EFF RAD MON A ISOL MRlHR IUFt POOL AllE A 12.3 MRIHR HI MSL B RAD 32 MR/HR EFF RAD MON B ISOL MR/HR NL W f UE L AHF A 1.1 MRlHR MSL C RAD 33 Mft/HR EFF NRML RNG ISOL UCI/SEC RWCU PitECOAI 14 O MR/HR MSL D RAD 32 MR/HR FLOW ISOL CFM HWCU SLUDGE OSH OSH SKID HEALTH - NFtML Mj.n~& Newerud , itP tNDE X OSIi OSH LIQUlOS ItP l)RtVE OSH OSH TURBINE CRD.'HCU SOUlli OSH OSH RW EFF MON 2.65E + 05 UCl/CC EFF NRML RNG 2.43E + 01 UCI/SEC CTtD:HCU NOftlit 13.8 MR/HR SW EFF MON 2.1 CPS EFF HIGH RNG O.OOE o 00 UCI/ SIC
- I tPCI I4 f Mi' HOOM 3.2 MR HR REC MON 11.3 CPS FLOW 140000 Cf M HitR ltOOM SW OSH CSH SKID HEALTH - NRML n - Norrnd !
RHR HOOM NW OSH OSH SJAE SKID HE ALTH HIGH h.g.; 'INo,MS HCIC/CS HOOM NE OSH OSH CS ItOOM SE OSH OSH SJAE A RAD 0 MR/HR AOG/RW fitONT ST ANDARD 8.9 MR/HR SJAE B RAD 0 MR/IIR , EFF NRML F1ANGE 1.04E e 02 UC1/SEC I URR Mt Il COHR O.1 MR/llR SJAE A FLOW O CFM EFF HIGH RNG ISOL UCl/SEC , I(11111 HSMI COpa 0.1 MR/HR SJAE B FLOW OCFM FLOW 36000 CfM HIl' Alt! A 1 O MR/itR SKID HE At ill . NRML - = Normal COtJu lisMP AHL A O.1 MRittR ERP SKID HEALTH - HtGH b [ Normd CotJIHot itOOM O O MR/HR < CONI COttH GRADE O 2 MR!!!R EFF NRML RNG 2.65E e 05 UCliSEC MPF t HW CONillOf HOOM 0 0 MR/ttR EFF HIGH RNG 3.50E + 05 UCl/SEC EFF PART 1.OOE 12 UCl/SE C I ttW IMIMi 1400M S O MR;tlFt FLOW 4.33E + 03 CFM EFF GAS 4.40E 01 UCl/ SIC itW llASE MI Ni 2.1 MR;llit HE ALTH NRML e i Notrnal
^
DE MitJ VtV HOOM 14 MRittR HEALTH- HIGH J Normal HW CONV AtSti O 3 MH'ItR [ IOltiIS Alti A O O Mit itll ' llW I Alt 19 MH itH COMH!Nt D HtIHillll UENI HADIAllON CE Nilus tuit ( ASI 3 9 Mit itit E XCE EDING E XCELDING CE NIHtf uGE WI SI 4 1 MH.HR TECil SPECS 10 X TECH SPECS DRYWELL ?:L No .i l 7Noi " j i DW Allit OCK 419.1 f t itR DW t ADDE Il 381.0 R HR Lpy HPV pneAARY SECONDARY RADIOACTrVE o CONTApsMENT CONTAmeMENT SiMUt AIOR CONTROL RELEASE m , 61 - Ct t AH t2- t 3 = MENU F4 = SPOS INPI i5" F6
- l CANC H ARDCOPY = CONSOLE - MODE = EVENT = i
_ _ _ _ _ _ _ _ _ _ . ,_m _. _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ PM!Sua XLS I 1330 SELECT FUNC. KEY OR TURN- ON CODE
- 11/19/96 E !
PMIS 05: RAD' VALUES ARM MSL/MSIV BUILDINGS REACTOR FUEL POOL AREA 129.0 MR!HR MSL A RAD 31 MR/HR EFF RAD MON A 0.39 MRMR FUEL POOL AREA 12.3 MR/HR HI MSL B RAD 32 MRIHR EFF RAD MON 8 0.41 MR/HR , NEW FUEL AREA 1.1 MR/HR MSL C RAD 33 MR/HR EFF NRML RNG ISOL UCl/SEC RWCU PRECOAT 14.0 MR!HR MSL D RAD 32 MRMR FLOW 4.69E + 04 CFM RWCU SLUDGE OSH OSH SKlO HEALTH - NRML QBg]?g TIPINDEX OSH OSH LIQUIDS TIP DRIVE OSH OSH TURBINE CRD/HCU SOUTH OSH OSH RW EFF MON 6.19E + 0S UCl/CC EFF NRML RNG 2.43E + 01 UCl/SEC CRD/HCU NORTH I 1.7 MR!HR SW EFF MON 2.1 CPS EFF HIGH RNG O.00E + 00 UCl/SEC HPC! PUMP ROOM 3.2 MR!HR REC MON 11.3 CPS FLOW 140000 CFM RHR ROOM SW OSH OSH SKID HEALTH NRML h N*y%gmet ; HHR ROOM tJW OSH OSH SJAE SKID HEALTH . HIGH 'i, [4 kmud RCIC/CS HOOM NE OSH OSH CS ROOM SE OSH OSH SJAE A RAD 0 MRIHR AOG/RW F ROrJT ST AND ARD 8.9 MR/HR SJAE B RAD O MR/HR EFF NRML RANGE l.04E o 02 UCI/SEC TURB MEZZ CORR O.1 MRlHR SJAE A FLOW SO CFM EFF HIGH RNG ISOL UC1/SEC 1 URB BSMI CORR O.1 MR/HR SJAE B FLOW 49 CFM FLOW 36000 CFM RI P ARE A 1.0 MR/HR SKID HEALTH - NRML Ll' W Nonal COND PUMP AftE A O.1 MR1HR LRP SKlO HEALTH - HIGH , Wrmel COrJIROL ROOM O O MR/HR , CONT CORR GRADE O.2 MR/HR EFF NRML RNG 6.19E + 05 UCl/SEC M_M ; HW CONTROL fiOOM O.0 MR'HR EFF HIGH RNG 6.19E
- 05 UCl/SEC EFF PART 100E 12 UCl/SEC RW PUMP ROOM S O MR/HR FLOW 3.36E + 03 CFM EFF GAS 4.40E 01 UCt/SEC !
RW BASLMitJi 2.1 MR/HR HEALTH NRML > ' Normal . OEMIN VLV HOOM 14 MR'HR HE ALTH. HtGH Normal ! RW CONV AtStt 0.3 MR:HR ; i TORUS AHf A O 0 MR:HR RWLAB 3 9 MRiHR COM81NLD BLDG EFFLUENT RADIATION Cf NTPIFUGE E AST 3.9 MRIHR EXCEEDING EXCEEDING t Cf NIRIFUGE WEST 4.1 MR/HR TECH SPECS 10 X TECH SPECS iNo' DRYWELL -nod i DW AIRLOCK 419.1 R.HR DW L ADDER 381.0 R'HR LPU #v PRIMARY E4CONDARY RANCWE o SIMUL ATOR CONYRGi CONTA W MT CONTAMNT RREAEE oo ! F 1.. (_t L AH F2= F3 = MENU F 4 = SPDS INPT F S = F6= - CANC HARDCOPY = CONSOLE = MODE = EVENT = ! i i t I
Puisos es 1345 i SELECT FUNC. KEY OR TURN ON CODE 11/19/96 E PMIS 05: - RAD VALUES ' ARM MSUMSIV BUILDINGS RFACTOR 3 FUEL PCOL ARE A 129.0 MR/HR MSL A RAD 31 MRMR EFF RAD MON A O.39 MRMR FUEL POOL AREA 12.3 MR/HR HI MSL B RAD 32 MR/HR EFF RAD MON B O.41 MRMR ; UEW FUEL AREA 1.1 MR/HR MSL C RAD 33 MR/HR EFF NRML RNG iSOL UCl/SEC RWCU PRECOAT 14 O MR/HR MSL D RAD 32 MR/HR FLOW 4.69E + 04 CFM RWCU SLUDGE OSH OSH SKID HEALTH - NRML $$h Norrnet flPINDEX OSH OSH Lioulos IIP DRIVE OSH OSH TURBINE CRO/HCU SOUTH OSH OSH RW EFF MON 5.2SE + OS UCl/CC EFF NRML RNG 2.43E + 01 UCl/SEC CRDMCU NORTH 11.7 MR/HR SW EFF MON 2.1 CPS EFF HIGH RNG O.OOE + 00 UCl/SEC HPCI PUMP ROOM 3.2 MR/HR REC MON 11.3 CPS FLOW 140000 CFM RHR ROOM SW OSH OSH SKID HEALTH - NRML $% 3 Norms RHR ROOM NW OSH OSH SJAE SKl0 HEALTH - HIGH $h J LNormal ' RCIC/CS ROOM NE OSH OSH CS ROOM SE OSH OSH SJAE A RAD 0 MR/HR AOG/RW f RONT ST ANDARD 8.9 MRMR SJAE B RAD 0 MR/HR EFF NRML RANGE 1.04E + O2 UCl/SEC IURB ME22 CORR O.1 MR/HR SJAE A FLOW SO CFM EFF HIGH RNG ISOL UCl/SEC IURB BSMT CORR O.1 MR/HR SJAE B FLOW 49 CFM FLOW 36000 CFM 1 O MR;HR Normal I RF P ARE A SKID HEALTH NRML [. LOND PUMP ARE A O.1 MR/HR ERP SKl0 HEALTH HIGH C . Normal * ( ONTROL ROOM O.0 MR/HR CONI CORR GRADE O.2 MR/HR EFF NRML RNG 5.25E + 05 UCl/SEC MPF , RW CONTFtOL ROOM O 0 MR/HR EFF HIGH RNG 5.25E + 05 UCl/SEC EFF PART 1.OOE 12 UC1/SEC f RW PUMP ROOM 5 O MR/HR FLOW 3.36E + 03 CFM . EFF GAS 4.40E 01 UCl/SEC ! t ftW BASEME NT 21 MR'HR HEALTH NRML ! Normal ' OEMIN VLV ROOM 1.4 MR/HR HEALTH HIGH ' Normal RW CONV AISLE O 3 MR;HR [ TORUS ARE A O O MRMR ! RW L AB 3 9 MRHR COMBINED t$t DG EFFLUENT RADIAllON LENTRIFUGE EAST 3 9 MR/HR EXCEEDING E XCEEDING ! t ENTRIFUGE WEST 41 MR/HR TECH SPECS 10 X TECH SPECS l DRYWELL . No .E I No ' . DW AIRLOCK 4191 R HR ' OW L ADDER 381.0 R'HR LPU HW PRNARY 6ECONDARY ggg SIMUL ATOR coNTRot CONT AmW NT CONTAm W NT mgg F 1 - ut AR F2= F3 = MENU F 4 = SPOS (NPT FS
- F6=
CANC HARDCOPY = CONSOLE = MODE = EVENT, i i _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _.______ _ _m_ _ ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
PMtso5 XLS 1400 SELECT FUNC. KEY OR TURN- ON CODE 11/19/96 E PMIS 05: RAD VALUES' ARM MSL/MstV SUILDINGS REACTOR FUEL POOL AREA I29 O MR/HR MSL A RAD 31 MR/HR EFF RAD MON A O.39 MRMR F UEL POOL AREA 12.3 MR/HR HI MSL B RAD 32 MR/HR EFF RAD MON B O.41 MRMR NEW F UEL ARE A 1.1 MR/HR MSL C RAD 33 MR/HR EFF NRML RNG ISOL UCl/SEC RWCU PRECOAT 14.0 MR/HR MSL D RAD 32 MR/HR FLOW 4.69E + 04 CFM RWCU StUDGE OSH OSH SKID HEALTH NRML Q ' Normal IIPINDEX OSH OSH LIQUIDS ItP DRIVE OSH OSH TURBtNE CRO/HCU SOUTH OSH OSH RW EFF MON 4.48E + 05 UCl/CC EFF NRML RNG 2.43E + 01 UCl/SEC CRD/HCU NORTH 11.7 MR/HR SW EFF MON 2.1 CPS EFF HIGH RNG O.OOE + 00 UCl/SEC HPCI PUMP ROOM 3.2 MRIHR REC MON 11.3 CPS FLOW 140000 CFM < RHR ROOM SW OSH OSH SKID HEALTH - NRML y , Noemel RHR ROOM NW OSH OSH SJAE SKID HEALTH HIGH b No,put RCIC/CS ROOM NE OSH OSH CS ROOM SE OSH OSH SJAE A RAD 0 MR/HR AOG/RW F RONT ST ANDARD 8.9 MR!HR SJAE B RAD 0 MR/HR EFF NRML RANGE 1.04E + O2 UCl/SEC T UR8 MEll CORR O.1 MR/HR SJAE A FLOW SO CFM EFF HIGH RNG ISOL UCl/SEC IURB BSMT CORR O.1 MRIHR SJAE B FLOW 49 CFM FLOW 36000 CFM RF P ARE A 1.0 MR/HR SKID HEALTH NRML ! Noemal COND PUMP ARE A O.1 MR!HR ERP SKID HEALTH HIGH Ndemal CONT rot ROOM O.0 MR/HR rONI CORR GRADE O 2 MR/HR EFF NRML RN3 4.48E + 05 UCl/SEC ME RW CONIROL ROOM O O MR/HR EFF HIGH RNG 4.48E + 0S UCt/SEC EFF PART 1.OOE 12 UCl/SEC RW PUMP ftOOM 5.0 MR/HR FLOW 3.36E + 03 CFM EFF GAS 4.40E 05 UCl/SEC , RW BASIME N1 2. I MR/HR HEALTH NRML Normal DEMIN VL V ROOM 14 MR.HR HFALTH HIGH N.umat RW CONV A15L L O 3 MH 'HR t ORUS AHf A O O MH/HR RW L AB 3 9 M9/HR CORBINED BLOG EFFLUENT RADtATION CENTRIFUGE EAST 3 9 MR/HR EXCEEDING EXCEEDING CEN1RIFUGE WEST 4.1 MR/HR TECH SPECS 10 X TECH SPECS i DRYWELL .No (No t DW AIRLOCK 419.1 R/HR DW L ADDER 381.0 R/HR Cry MPV P'tsM ARY fiCONDA3V RAD 80ACYNE o SIMUL AT OR CONMOL CONTAw W hT CONTAm WNT mgggg F 1 - CLL AR F2 F3 = MENU F 4 = SPDS INPT F S = F6= CANC H ARDCOPY = CONSOLE - MODE = EVENT = 6
PMtSOS HLS i4:S SELECT FUNC. KEY OR TURN. ON CODE 11/19/96 E PMIS 05: RAD VALUES ARM M St mlSIV postDeNGs REACTOR FUEL POOL AREA 129 O MR/HR MSL A RAD 31 MRMR EFF RAD MON A O.39 MR/HR FUEL POOL AREA 12.3 MR!HR HI MSL B RAD 32 MRMR EFF RAD MON B O.41 MRMR NEW FUEL AREA 1.1 MR/HR MSL C RAD 33 MR/HR EFF NRML RNG ISOL UCl/SEC RWCU PRECOAT 14.0 MR/HR MSL D RAD 32 MR/HR FLOW 4.69E + 04 CFM RWCU SLUDGE OSH OSH SKID HEALTH - NRML gy-jjg.,; W Tl?INDEX OSH OSH LIQUlOS YIP DRIVF OSH OSH TURBINE CHD/HCU SOUTH OSH OSH RW EFF MON 3.83E + OS UCl/CC EFF NRML RNG 2.43E + 01 UCl/SEC CRD/HCU NORTH 11.7 MRiHR SW EFF MON 2,1 CPS EFF HIGH RNG O.OOE + 00 UCl/SEC HPCI PUMP ROOM 3.2 MR/HR REC MON 11.3 CPS FLOW 140000 CFM RHR ROOM SW OSH OSH SKID HEALTH - NRML ki- 2Nonnel RHR HOOM NW OSH OSH SJAE SKID HEALTH - HIGH belbis Nosinal RCIC/CS ROOM NE OSH OSH CS ROOM SE OSH OSH SJAE A RAD O MR/HR AOG/RW
'RONT ST ANDARD 8.9 MR/HR SJAE B RAD 0 MR/HR EFF NRML RANGE 1.04E + O2 UCliSEC IURB ME22 CORR O.1 MR/HR SJAE A FLOW 50 CFM EFF HIGH RNG ISOL UC1/SEC TURB BSMT CORH O 1 MR!HR SJAE B FLOW 49 CFM FLOW 36000 CFM RIP ARE A O 9 MRIHR SKID HE ALTH - NRML ',' ' Normal LOND PUMP AHEA O.1 MR/HR ERP SKID HEALTH - HIGH I Nom al CONTHOL HOOM O.O MR!HR CONT CORR GHADE O.2 MR/HR EFF NRML RNG 3.83E + OS UCl/SEC MPF RW CONTHOL HOOM O O MR/HR EFF HIGH RNG 3.83E +0S UCl/SEC EFF PART 1.OOE 12 UCl/SEC RWPUMPHOOM S.O MR/HR FLOW 3.36E + 03 CFM EFF GAS 4.40E 01 UCl!SEC RW BASEMENT 2.1 MR/HR HEALTH NRML . '. Nonnal DI MIN VtV HOOM i _4 MR'HR HE ALTH- HIGH Normal HW C ONV Al'at L 0 3 MH 'llH IORUS AHL A O O MR'HH RWtAB 3 9 MH HH COMBINED HLOG EFFLUENT RADIAllON LtNTHIFUGE E Asi 3.9 MR.'HR EXCEEDING EXCEEDING C t NT RIFUGE WEST 4.1 MR/HR TECH SPECS 10 X TECH SPECS DRYWEtt NoE Nol .
DW AIRLOCK, 419.1 R;HR DW L ADDE R 381.0 R'HR LPU swv PRIMARY EECONDARY CogTAmWNT l l RAD 80ACTfVr. o SIMUL AT OR rrmfArx coNTAwwNT I l RELEAst oo F; LLLAH F2s F3 = MENU F4 = SPDS INPI F5= F6= ; CANC HARDCOPY = CONSOLE = MODE = EVENT = i __ -- a
PMisob nts 1430 SELECT FUNC. KEY ORYURN- ON CODE 11/19/96 E I PMIS 05: RAD VALUES i ARM MSUMSIV BUILDINGS REACTOR F UEL POOL AREA 129 O MR/HR' MSL A RAD 31 MR/HR EFF RAD MON A O.39 MR/HR ' FUEL POOL ARE A 12.3 MR'HR HI MSL B RAD 32 MR/HR EFF RAD MON B O.41 MR/HR NEW FUEL AREA 1.1 MRaiR MSL C RAD +33 MR/HR EFF NRML RNG ISOL UCl/SEC RWCU PRECOAT 14.0 MR4tR MSL D RAD 32 MR/HR FLOW 4.69E
- 04 CFM RWCU SLUDGE OSH OSH SKtD HEALTH - NRML C ~'. Norrnd
' ' ' ~
flPINDEX OSH OSH- LIQUIDS TIP DRIVE OSH OSH TURBINE CRDafCU SOUTH OSH OSH RW EFF MON 3.28E + 05 UCl/CC EFF NRML RNG 2.43E + 01 UCl/SEC CRD;HCU NORTH 11.7 MRaiR SW EFF MON 2.1 CPS EFF HIGH RNG O OOE + 00 UC1/SEC HPCl PUMP ROOM 3.2 MR/HR REC MON 11.3 CPS FLOW 140000 CFM HHR ROOM SW OSH OSH SKtD HEALTH NRML f ~ . Normd i RHR ROOM NW OSH OSH SJAE SKtD HEALTH - HIGH $ i N wrial RCIC/CS ROOM NE OSH OSH , CS ROGM SE OSH OSH SJAE A RAD O MR/HR AOG/RW f RONT 51 ANDARD 8.9 MR/HR SJAE B RAD 0 MR/HR EFF NRML RANGE 1.04E o 02 UCl/SEC
- f URB MEZZ CORR O.1 MR/HR SJAE A FLOW SO CFM EFF HIGH RNG ISOL UCl/SEC '
f URB BSMT CORR O 1 MR/HR SJAE 8 FLOW 49 CFM FLOW 36000 CFM HF P AftE A O.9 MRIHR SK!D HEALTH - NRML i Normal COND PUMP ARE A O.1 MR/HR ERP SKtD HEALTH HIGH ?, 'Normat ' CONIROL ROOM O.0 MR/HR t CONI CORR GRADE O 2 MR!HR EFF NRML RNG 3.28E + 05 UCl/SEC ME 8 W CONT ROL ROOM O O MR/HR EFF HIGH RNG 3.28E + 05 UCl/SEC EFF PART I .OOE 12 UCt/SEC HW PUMP ROOM S O MR,HR FLOW 3.36E + 03 CFM EFF GAS 4.40E 01 UCllSEC RW BASE ME NI 2,1 MR11R HEALTH NRML 7. Normat ! OE MIN Vtv ROOM i .4 MH HR HE ALTH. HIGH Normal HW L ONV A151L 0 3 MHettR IORUS ARE A O O MH HR ; RWtAB 3 9 MHJHR COMBINED tiLDG El FLUENT RADIAllON CEfJIRIF UGE E AS1 3 9 MR/HR EXCEEDING EXCEEDING i CENTRIFUGE WEST 4.1 MR/HR TECH SPECS 10 X TECH SPECS DRYWELL - . No ' , . /No; - I DW AIRtOCK 419.1 R/HR DW L ADDE R 381 O R'HR tPU HW P3'M arf MCONDARY AANACM o , SIMUL A T OR C ON T ROL CONTAWWNT CONTANWNY gmag t 3 ,- CLE AR F2- F3 = MENU F 4 = SPOS INPT FS= F6= CANC HARDCOPY = CONSOLE = MODE = EVENT. L i I t
PMtSO5 XLS i 1445 SELECT FUNC KEY OR TURN ON CODE 11119/96 E ' PMIS 05: RAD VALUES ~ ARM MSL/MStV BUILDINGS REACTOR F UEL POOL ARE A 129.0 MRIHR MSL A RAD 31 MR/HR EFF RAD MON A O.39 MR/HR i FUEL POOL AREA 12.3 MR/HR HI MSL B RAD 32 MR/HR EFF RAD MON B O.41 MR/HR ! NEW FUEL AREA 1.1 MR/HR MSL C RAD 33 MR/HR EFF NRML RNG iSOL UCitSEC RWCU PRECOAT 14 O MR'HR MSL D RAD 32 MR/HR FLOW 4.69E + 04 CFM RWCU SLUDGE OSH OSH SKl0 HEALTH - NRML LMj$RNormd ! TIPINDEX OSH OSH LIQUtOS TtP DRIVE OSH OSH TURBINE CHD/HCU SOUIH OSH OSH RW EFF MON 2.79E + 05 UCl/CC EFF NRML RNG 2.43E + 01 UCliSEC CRD/HCU tJORTH 11.7 MR/HR SW EFF MON 2.1 CPS EFF HIGH RNG O.OOE + 00 UCl/SEL HPCI PUMP ROOM ' 3.2 MR/HR REC MON 11.3 CPS FLOW 140000 CFM > RHH ROOM SW OSH OSH SKID HEALTH - NRML f. t rN Normel ; RHH HOOM tJW OSH OSH SJAE SKID HEALTH HIGH M m Normal RCIC/CS ROOM NE OSH OSH CS ROOM SE OSH OSH SJAE A RAD 0 MR/HR AOG/RW f HONT ST ANDARD 8.9 MR/HR SJAE B RAD 0 MR/HR EFF NRML RANGE 1.04E e 02 UCt/SEC TtiftB MEZZ CORR O.1 MH/HR SJA'E A FLOW SO CF M EFF HIGH RNG ISOL UCt/SEC IURR f3SMI CORH O.1 MR!HR SJAE B FLOW 49 CFM FLOW 36000 CFM
,tt P ARE A O.9 MRlHR SKID HE ALT H NRML;, Norm,I i
^
COND PUMP AREA O.1 MR/HR ERP SKID HEALTH HIGH (f. -L Normal CONTROL ROOM O.O MR!HR CONT CORR GRADE O.2 MR/HR EFF NRML RNG 2.79E + 05 UCl/SEC MPF RW CONT HOL HOOM O O MR/HR EFF HIGH RNG 2.79E + 05 UCl/SEC EFF PART 1.OOE 12 UCl/SEC RW PUMP ROOM S.O MR/HR FLOW 3.36E + 03 CFM EFF GAS 4.40E 01 UCl!SEC RW BASEMENT 2.1 MR/HR HEALTH NRML _ Normet OrMIN VLV HOOM t 4 MRlHR HEALTH HIGH Normal RW CONV AtSt E O 3 MR.'llH IOf(Ud ARE A O O MR IIH , RW L Alt 3 9 MR,HR COMBINLD ELUG EFF LUENT RADIAllON ([ NI RIF UGE L AST 3 9 MRiHR EXCEEDING EXCEEDING cf NYRIFUGE WEST 4.1 MHiHR TECH SPECS 10 X TECH SPECS r r DRYWELL . No . No . . _ i I)W AIRtOCK 419.1 R'HR DW L AUDER 381 O R/HR EPV PRIMARY SECONDARY pag,gggy'VI O (PU CONTROL CONTANMfNT CONT AMMENT RftfASE oo SIMUL ATOR F2m F3 = MENU F 4 = SPDS INPI FS= F6= f 1 - tLL AH CANC H ARDCOPY = CONSOLE = MODE = EVENT = i [ l
PMtSOS ULS & 1500 SELECT FUNC. KEY OR TURN- ON CODE 11H 9/96 E PMIS 05: RAD VALUES [ t ARM MSLSASIV BLMLDINGS REACTOR " FUEL POOL AREA 129.0 MR/HR MSL A RAD 31 MRMR EFF RAD MON A O.39 MRMR FUEL POOL AREA 12.3 MRMR HI MSL B RAD 32 MRMR EFF RAD MON B O.41 MR!HR NEW FUEL AREA 1.1 MRMR MSL C RAD 33 MRMR EFF NRML RNG iSOL UCl/SEC RWCU PRECOAT 14.0 MRMR MSL D RAD 32 MR/HR FLOW 4.69E + 04 CFM RWCU StuDGE OSH OSH SKID HEALTH NRML ((3f)M TIPINDEX OSH OSH UOutDS , itP DRIVE OSH OSH TURBINE CRD/HCU SOUTH OSH OSH RW EFF MON 2.39E + OS UC1/CC EFF NRML RNG 2.43E + 0i UCl/SEC I CRDIHCU NORTH 11.7 MRMR SW EFF MON 2.1 CPS EFF HIGH RNG O.OOE 4 00 UCl/SEC HPCI PUMP ROOM 3.2 URMR REC MON 11.3 CPS FLOW 140000 CFM RHR ROOM SW OSH OSH SKID HEALTH - NRML 74 No,mel RHR ROOM NW OSH OSH SJAE SKID HEALTH HIGH f ^ Normal RCIC/CS ROOM NE OSH OSH CS ROOM SE OSH OSH SJAE A RAD 0 MR/HR AOG/RW FfiONT ST ANDARD 8.9 MRMR SJAE B RAD 0MRMR ' EFF NRML RANGE 1.04E + 02 UC1/SEC TURB MEZZ CORR O.1 MR/HR SJAE A FLOW. 50 CFM EFF HIGH RNG ISOL UCl/SEC TURB BSMT CORR 0.1 MRiHR SJAE B FLOW 49 CFM FLOW 36000 CFM RFP ARE A O.9 MR/HR SKID HEALTH - NRML $1 Normel ' COND PUMP ARE A O.1 MRMR ERP SKID HEALTH HIGH E;. l Normal CONTROL ROOM 0.0 MR/HR CONT CORR GRADE O.2 MRMR EFF NRML RNG 2.39E + 0S UCI/SEC MPF
~
RW CONTROt ROOM O.O MR/HR EFF HIGH RNG 2.39E + 0S UCl/SEC EFF PART 1.00E 12 UCl/SEC RW PUMP ROOM S.0 MRMR FLOW 3.36E 4 03 CFM EFF GAS 4.40E 01 UCl/SEC 2.1 MR/HR HEALTH NRML Normel RW BASEMENT ' DEMIN Vtv HOOM 1.4 MRiHR HEALTH HIGH Normai HW CONV Al'>l t 0 3 MR HR IORUS ARE A O O MR,HR RW L AB 3 9 MR<HR COMBINLD HL DG LI F LUENT RADIAllON CENIRif UGE t AST 3,9 MR,HR EXCEEDING EXCEEDING CENTRIFUGE WEST 4.1 MR'HR TECH SPECS 10 X TECH SPECS DRYWEtt ; x.. No- ( l No ;m . DW AIRLOCK 419.1 RMR ' DW L ADDER 381.0 R/HR i mpy PRIMARY SECONDARY o j LPU RADIOAC frVE CONTgot CONTAkMENT CONTANMfNT pflfASE SIMUL AT OR 00 . F 1 - CLE AR F2a F3 = MENU F 4 = SPOS INPT FS = F6=
- CANC HARDCOPY = CONSOLE = MODE = EVENT = !
i I
PMtSus XLS 1515 SELECT FUNC. KEY OR TURN- ON CODE 11/19/96 E PMIS 05: RAD VALUES I ARM MSL/MstV gustogggs REACTOR FUEL POOL AREA 129.0 MR/HR MSL A RAD 31 MR/HR EFF RAD MON A O.39 MR/HR FUEL POOL AREA 12.3 MR/HR HI MSL B RAD 32 MR/HR EFF RAD MON B O.41 MR/HR NEW FUEL AREA 1.1 MR/HR MSL C RAD 33 MR/HR EFF NRML RNG ISOL UCllSEC RWCU PRECOAT 14.0 MR!HR MSL D RAD 32 MR/HR FLOW 4.69E + 04 CFM RWCU SLUDGE OSH OSH SKID HEALTH - NRML MENormel TIP tNDEX OSH OSH LIQUIDS TIP ORIVE OSH OSH TURDINE CRDiHCU SOUTH CSH OSH RW EFF MON 2.04E + OS UCI/CC EFF NRML RNG 2.43E + 01 UCl/SEC CRD/HCU NORTH 11.7 MR/HR SW EFF MON 2.1 CPS EFF HIGH RNG O.OOE + 00 UCl/SEC HPCI PUMP ROOM 3.2 MR/HR REC MON 11.3 CPS FLOW 140000 CFM RHR ROOM SW OSH OSH SKID HEALTH - NRML & M ' L Normal HHR ROOM NW OSH OSH SJAE SKID HEALTH HIGH h 4 1 Normel RCIC/CS ROOM NE OSH OSH CS ROOM SE OSH OSH SJAE A RAD 0 MR'HP AOG/RW F RONT St AtJDARD 8.9 MR/HR SJAE B RAD 0 MR/HR EFF NRML RANGE 1.04E + O2 UCl/SEC TURB MFll CORR O.1 MR/HR SJAE A FLOW SO CFM EFF HIGH RNG ISOL UCl/SEC TUI.B BSMT CORR O.1 MR/HR _SJAE B FLOW 49 CFM FLOW 36000 CFM ' RF P AHf A O 9 MRTHR SKID HEALTH NRML[. _ Normet LOND PUMP ARE A O.1 MR!HR ERP SKID HEALTH HIGH R + ; Normal CONTROL ROOM O O MR/HR CONT CORR GRADE O.O MRiHR EFF NRML RNG 2.04E + OS UCl/SEC M.PF RW CONT ROL ROOM O O MR!HR EFF HIGH RNG 2.04E + OS UCl/SEC EFF PART 1.OOE 12 UCt/SEC RW PUMP ROOM O.O MR/HR FLOW 3.36E + 03 CFM EFF GAS 4 40E 01 UCl/SEC RW BASE ME Ni 2.1 MR;HR HEALTH NRML i
' Norinei DEMIN VtV ROOM 14 MR
vill be used by Controllers in the field (plant) to provide radiological conditions to Emergency
~ Response Organization (ERO) personnel dispatched to survey, repair, troubleshoot, etc., in the plant during the scenario. These sheets are location and time dependent. Certain operational assumptions were made (for example number and location of systems / pumps / pipes recirculating :
reactor coolant). These assumptions are based upon educated best guess. There is operational discretion in regards to some of these decisions. Following the isolation of the leak into the reactor building, the concentrations in the building will decrease. Both trains of Standby Gas Treatment are assumed to remain running to both r maintain the reactor building at a negative pressure, and ensure an elevated, monitored release path. Thus a known volume will be exhausted from the reactor building for the duration of the exercise. '
- The maximum release rate at the Elevated Release Point (ERP) will be just over one curie per i second (noble gas). This is a very realistic release rate for this postulated accident.
l The ERP release path monitors are calibrated to measure noble gases. Thus, the off-site dose
- assessment programs used during emergencies effectively calculum the other release components
. and associated dose contribution based upon factors which include: time since reactor shutdown, core degradation status, holdup (plateout) in a building, filtering mechanisms such as Standby i Gas Treatment, and scrubbing (if the release were released through water).
Because this release ('seen' at the ERP) has been held up in the reactor building, has been
- . filtered by SBGT, and was not the result of severe core damage, fuel uncovery, or gross .
overheat, the vast majority of this release is noble gases. Although some noble gases decay to , particulates, the very low release rate concentrations would make these very small hence no
' deposition of particulates downwind is postulated.
Field monitoring team data sheets, provided to the downwind survey team Controllers, will allow them to provide raw data to the survey teams. The team may then relay these findings back to the Emergency Operations' Facility personnel. . Rmliological Data Generatium Pave Sa r:. EXER SECT 7-11.'WPS 4
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Source Term Core inventory CNS Core Gap release CNS Prim. Coolant Gap coolant Nuclide Fuel Damage Total Curies in Ci/MWe (Ci) Inventory (Cl) fraction Invent. (CC) concentration (uCi/cc) Fraction RCS Kr-85 5.60E+02 4.48E+05 0.05 2.00E+08 112 0.0365 Kr-85m 2.40E+04 1.92E+07 8.18E+ 02 0.05 2.00E+08 4800 0.0365 3.50E+04 Kr-87 4.70E+ 04 3.76E+07 0.05 2.00E+08 9400 : 0.0365 6.86E+04 Xe-133 1.70E+05 1.36E+08 0.05 2.00E+08 34000 Xe-133m 0.0365 2.48E+05 6.00E+03 4.80E+06 0.05 2.00E+08 1200 Xe-135 0.0365 8.76E+03 3.40E+04 2.72E+07 0.05 2.00E+08 6800 l-131 0.0365 4.96E+04 8.50E+04 6.80E+07 - 0.05 2.00E+08 17000 1-133 0.0365 1.24 E + 05 1.70E+ 05 1.36E+08 0.05 2.00E+08 34000 i 0.0365 2.48E+05 l-135 1.50E+05 1.20E+08 0.05 2.00E+08 30000 ! Cs-134 0.0365 2.19E+05 7.50E+03 6.00E+06 0.05 2.00E+08 1500 0.0365 1.10E4 04 Cs-137 3.00E+03 2.40E+06 0.05 2.00E+08 600 0.0365 4.38E + 03 Sr-90 3.70E+03 2.96E+06 0 2.00E+08 0 0.0365 0 00E+00 Np-239 1.64 E + 06 1.31 E+ 09 0 2.00E+ 08 0 0.0365 0 00E+00 ! P t i Radwloxiad Ihur.: Generation Page 8-3 C:..1EXERISEC77-II. WPS I i __ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - - - - - ------ ---- - --~
(Cors invent)(Gap Frac )(Fuel damage frac.)(1E6)(1.ege((4 01 rm))/(Coolant volume) Time 1115 1120 1125 1130 1135 1140- 1145 1150 1855 Nuclide 0 5 10 15 20 25 30 35 40 i Kr-85 Normal - 2.13E-01 6.28E-01 1.23E+00 2.02E+00 2.98E+00 4.10E+00 4.10E+00 4.10E+00 Kr-85m Normal 9.13E+ 00 2.69E+01 5.29E+01 8.66E+01 1.28E+02 1.76E+02 1.76E+02 1.76E+02 Kr-87 Normal 1.79E+01 5.27E+01 1.04E+02 1.70E+02 2.50E+02 3.44E+02 3.44E+02 3.44E+02 Xe-133 Normal 6.46E+ 01 1.91E+02 3.75E+02 6.14E+02 9.05E+02 1.25E+03 1.25E+03 1.25E+03 Xe-133m Normal 2.28E+00 6.73E+00 1.32E+01 2.17E+01 3.19E+01 4.40E+01 4.40E+01 4.40E+01 Xe-135 Normal 1.29E+01 3.81E+01 7.49E+01 1.23E+02 1.81E+02 2.49E+02 2.49E+02 2.49E+02 2 1131 Normal 3.23E+01 9.53E+01 1.87E+02 3.07E+02 4.52E+02 6.23E+02 6.23E+02 6.23E+02 $ l-133 Normal 6.46E+01 1.91 E+02 3.75E+02 6.14E+02 9.05E+02 1.25E+03 1.25E+03 1.25E+03 51
- l-135 Normal 5.70E+01 1.68E+02 3.31E+02 5.41E+02 7.98E+02 1.10E+03 1.10E+03 1.10E+03 k I Cs-134 Normal 2.85E+00 8.41E+00 1.65E+01 2.71E+01 3.99E+01 5.50E+01 5.50E+01 5.50E+01 k Cs-137 Normal 1.14E+00 3.36E+00 6.61E+00 1.08E+01 1.60E+01 2.20E+01 2.20E+01 2.20E+01 Sr.90 Normal 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 k Np-239 Normal 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 >
g
?. '(Cool Actmty @12 00)emp"((-6 OSE.4)(tune)) . .~
Q l Time l
^
l ~ C I 1200 1205 1210 1215 1220 1225 1230 1235 1240 1245 l m Nuclide 45 5 10 15 20 25 30 35 40 45 A Kr.85 4.10E+ 00 4.091093 4.078737 4.066417 4.054135 4.04189 4.029681 4.029681 4.029681 4.029681 -- Kr.85m 1.76E+02 175.3326 174.803 174.275 173.7486 173.2238 172.7006 172.7006 172.7006 172.7006 Kr.87 3.44E+02 343.3596 342.3225 341.2886 340.2577 339.23 338.2054 338.2054 338.2054 338 2054 $ Xe.133 1.25E+03 1241.939 43.83314 1238.188 43.70075 1234.448 43.56875 1230.719 1227.002 43.43716 43.305 % 1223 2 % 43.17516 1223.296 43.17516 1223 296 43.17516 1223 296 13.17516 O Xe-133m 4.40E+01 Xe-135 2.49E+02 248.3878 247.6376 246.8896 246.1439 245.4004 244.6592 244.6592 244.6592 244 6592 h O l-131 6.23E+02 620.9695 619.094 617.224 615.3597 613.5011 611.6481 611.6481 611.6481 611.6481 I-133 1.2SE+ 03 1241.939 1238.188 1234.448 1230.719 1227.002 1223.296 1223.296 1223.296 1223.2 % l l-135 1.10E+03 1095.829 1092.519 1089.219 1085.929 1082.649 1079.379 1079.379 1079.379 1079.379 Cs-134 5.50E+01 54.79143 54.62594 54.46094 54.29645 54.13245 53.96895 53.96895 53.96895 53.96895 I Cs-137 2.20E+01 21.91657 21.85037 21.78438 21.71858 21.65298 21.58758 21.58758 21.58758 21.58758 Sr-90 0.00E+00 0 0 0 0 0 0 0 0 0 [ Np-239 0.00E+00 0 0 0 0 0 0 0 0 0 t [ Radiological Data Generarium pay g.4 t C:. . lEXERtSECI'7 II WPS l I i i 2 i f
Leak rata (cc/ min) 121.000 volomo cf Rx o ing 9.53E+09 SBGT Vol. (cc/ min) 1.00E+08 Removal constant 1.05E-02 l Time 1200 1205 1210 1215 1220 1225 l 1230 1235 1240 INuchde 0 5 1250 1255 10 15 20 25 30 1300~ 5 10 15 Kr-85 0 0.000254 0.000495 0.000723 0.00094 0.001146 0.001341 20 25 Kr-85m 0.001272 0.001207 0.001146 0.001087 0.001032 0 0.010877 0.021197 0.030991 0.040283 0.049101 0.057468 Kr-87 0.05453 0.051743 0.049098 0.046589 0.044208 0 0.0213 0.041512 0.06069 0.078888 0.096156 0.112541 0.106789 0.10133 0.096151 0.091237 0.086573 Xe-133 0 0.077043 0.150148 0.219517 0.285339 0.347798 0.407064 0.386257 0.366515 0.347781 0.330005 0.313137 Xe-133m 0 0.002719 0.005299 0.007748 0.010071 0.012275 0.014367 0.013633 0.012936 0.012275 0.011647 0.011052 Xe-135 0 0.015409 0.03003 0.043903 0.057068 0.06956 0.081413 0.077251 0.073303 l-131 0 0.038522 0.075074 0.109758 0.069556 0.066001 0.062627 0.14267 0.173899 0.203532 0.193129 1133 0.183257 0.17389 0.165002 0 0.077043 0.150148 0.219517 0.285339 0.347798 0.156568 0.407064 0.386257 0.366515 t-135 0 0.347781 0.330005 0.067979 0.132484 0.193691 0.25177 0.306881 0.359174 0 313137 0.340815 0.323395 0.306865 Cs-134 0 0.003399 0.006624 0.009685 0.012589 0.29118 0 276297 0.015344 0.017959 0.017041 0.01617 Cs-137 0 0.015343 0.014559 0.013815 0.00136 0.00265 0.003874 0.005035 0.006138 0.007183 0.006816 0.0064S8 0.006137 Sr-90 0 0 0 0 0 0 0.005824 0 005526 0 0 0 No-239 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 l Time 1305 1310 1315 1320 1325 1330 1335 1340 1345 1350 i Ntclide 30 35 1355 1400 40 45 50 55 60 65 70 75 80 Kr-85 0 000979 0.000929 0.030881 0.000836 0.000793 0.000753 85 0.000714 0.000678 0.000643 0.00061 Kr-85m 0041948 0.039804 0.037769 0.635839 0.034007 0 000579 0 00055 0.032269 0.030619 0.029054 0.027569 Kr-87 0 082148 0.077949 0.073960'r 0.6/0184 0.066597 0.02616 0.024823 0 023554 0.063193 0.059963 0.056898 0 05399 Xe-133 0 297131 0.05123 0 048612 0 046127 0.281944 0 2675331 0.253858 0.240883 0.228571 0 216888 0 205802 0 195283 0.185301 0.17583 Xe-133m 0 010487 0.009951 0.009442 0.00896 0.008502 0.008067 0.007655 0 166842 0.007264 0.006892 0.00654 Xe- 135 0 059426 0.056389 0.053507 0.050772 0.048177 0 006206 0.005889 0.045714 0.043378 0.04116 0.039057 I-131 0.03706 0.035166 0 033368 0 148566 0.140972 0.133766 0.126929 0.120441 0.114285 0.108444 0.102901 i 0.097641 0.092651 0.087915 1-133 0.297131 0.281944 0.267533 0.253858 0.240883 0.228571 0.216888 0.083421 0.205802 0.195283 0.185301 0.17583 0.166842 1-135 0.262175 0.248774 0.236059 0.223993 0.212544 0.20168 0.191371 0.18159 0.172308 0.163501 0.155144 Cs-134 0.013109 0.012439 0.011803 0.0112 0.010627 0.010084 0.009569 0.147214 0.009079 0.008615 0.008175 Cs-137 0.005243 0.004975 0.004721 0.00448 0.004251 0.007757 0.007361 0.004034 0.003827 0.003632 0.003446 i Sr-90 0.00327 0 003103 0.002944 0 0 0 0 0 0 0 0 0 0 0 ,Np-239 0 0 0 0 0 0 0 0 0 0 0 0 0 Ra.twlogical Data Gem ration Page 8-5 C:. .tEXER\ SECT 7-11.WP5 Reactor Building Activity (uCi/cc)
- . - . . - - . - . - . ~ - . - . . - - - . - - - - - - - - . . - - . - . . . - . . - - - - . . - . . . - - -
Time == , 1405 1410 1415 1430 1435 1440 1445 1450 1455 1500 1510 1520 Nuclide 90 95 100 105 110 115 120 125 130 135 140 145 ; Kr-85 0.000522 0.000495 0.00047 0.000446 0.000423 0.000401 0.000381 0.000361 0.000343 0.000325 0.000309 0.000293
~I Kr-85m 0.02235 0.021208 0.020124 0.019095 0.018119 0.017193 0.016314 0.01548 0.01466s 0.013938 0.013226 0.01255 !
Kr-87 0.043769 0.041532 0.039409 0.037395 0.035484 0.03367 0.031949 0.030316 0.028766 0.027296 0.025901 0.024577 ' Xe-133 0.158315 0.150223 0.142544 0.135258 0.128345 0.121785 0.11556 0.109653 0.104048 0.09873 0.093684 0.088895 Xe-133m 0.005588 0.005302 0.005031 0.004774 0.00453 0.004298 0.004079 0.00387 0.003672 0.003485 0.003306 0 003137 I Xe-135 0.031663 0.030045 0.028509 0.027052 0.025669 0.024357 0.023112 0.021931 0.02081 0.019746 0.018737 0.017779 [ t-131 - 0.079157 0.075111 0.071272 0.067629 0.064172 0.060892 0.05778 0.054827 0.052024 0.049365 0.046842 0.044448 t-133 0.158315 0.150223 0.142544 0.135258 0.128345 0.121785 0.11556 0.109653 0.104048 0.09873 0.093684 0.088895 l l-135 0.139689 0.132549 0.125774 0.119346 0.113245 0.107457 0.101965 0.096753 0.091807 0.087115 0.082662 0.078437 - Cs-134 0.006984 0.006627 0.006289 0.005967 0.005662 0.005373 0.005098 0.004838 0.00459 0.004356 0.004133 0.003922 i Cs-137 0.002794 0.002651 0.002515 0.002387 0.002265 0.002149 0.002039 0.001935 0.001836 0.001742 0.001653 0.001569 : Sr-90 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Npy. 9 0 I 1525 1530 1535 1540 1545 ! Nuclide 150 155 160 165 170 ; Kr-85 0 000278 0.000264 0.00025 0.000237 0.000225 , Kr-85m 0.011908 0.0113 0.010722 0.010174 0.009654 t Kr-87 0.023321 0.022129 0.020998 0.019924 0.018906 Xe-133 0 084352 0 08004 0.075949 0.072067 0.068383 0.002S44 0.002414 l(coolard Act @30mmXLeam rWe)/(Rn tutd voi p,enmai i Xe-133m 0002977 0.002825 0.002681 Xe-135 '001687 0.016008 0.01519 0.0144?3 0.013677 I " '" '" "P'" "**' *d 5'*'* H'*n t-131 0 042176 0.04002 0.037974 0.036033 0.034192 l(Rm Building Act @t2 30)(ewp*((Removal ConstantMT my 0 084352 0.08004 0.075949 0.072067 0.068383 l 1133 I-135 0.074428 0.070624 0.067014 0.063588 0.060338 Cs-134 0.003721 0.003531 0.003351 0.003179 0.003017 , Cs-137 0.001489 0.001412 0.00134 0.001272 0.001207 Sr-90 0 0 -0 0 0 Np-239 0 0 0 0 0 ; lhliolos:i.nl Data Gencnuion - page g.g C:. .tEXERtSEC77-II. WP5 9 t
Release out the ERP(Ci/sec) ((RWwino-RW )(2E8).(RB ,m.RB v)(1EE)E300 l Time l 1200 1205 1210 1215 1220 1225 1230 1235 1240 1245 Nuclide 0 5 10 15 20 25 30 5 10 15 Kr-85 0 200.8361 587.9557 954.088 1300.309 1627.641 1937.053 2177.245 2065.959 Kr-85m 1960.361 0 8607.262 25198.1 40889.49 55727.55 69756.06 83016.55 93310.52 88541.11 Kr.87 0 84015 48 16855.89 49346.28 80075.24 109133.1 136605.6 162574.1 182733.1 173393 164530.3 Xe.133 0 60968.11 178486.5 289633.9 394736.8 494105.4 588033.9 660949.5 627166.2 595109.6 Xe-133m 0 2151.816 6299.525 10222.37 13931.89 17439.01 20754.14 23327.63 22135.28 Xe.135 0 21003.87 12193.62 35697.31 57926.77 78947.36 98821.08 117606.8 132189.9 125433.2 119021.9 0 0.100978 0.295614 0.479702 0.653777 0.818355 0.973922 1.094688 1.038735 0.985642 l Time
]
l 1250 1255 1300 1305 1310 1315 1320 1325 1330 1335 j Nuclide H 20 25 30 35 40 45 50 55 60 65 ) Kr-85 1860.161 1765.082 1674.862 1589 255 1508 G23 1430.943 1357.802 1288.4 1222.546 1160 058 Kr.85m 79721.17 75646.35 71779.82 68110.91 04629.54 61326.11 58191.53 55217.16 52394.83 49716.76 Kr.87 156120.6 148140.8 140568.8 133383.9 126566.2 120097 113958.4 108133.6 102606.5 97361 98 Xe-133 564691.6 535828.3 508440.4 482452.3 457792.6 434393.3 412190 391121.6 371130.1 352160 4 Xe-133m 19930.29 18911.59 17944.95 17027.73 16157.38 15331.53 14547.88 13804.29 13098.71 12429.19 Xe-135 112938.3 107165.7 101688.1 96490.46 91558.51 86878.65 82438 78224.32 74226.01 70432.07 0.935262 0.887458 0.842097 0.799055 0.758212 0.719457 0.682684 0.647789 0.614679 0.58326 i Radiorni,alData Genenaion Page 8-7 C:. 1EXERtSEC17-II. WP5 i t
Ralsase out the ERP(Ci/sec) . i
==
Time 1340 1345 1350 1355 1400 1405 1410 1415 1420 ' 1425 Nuclide 70 75 80 85 90 95 100 105 1!O 115 Kr-85 1100.763 1044.5 991.1118 940.4528 892.3831 846.7704 803.4892 762.4202 723 4504 686.4724 Kr-85m 47175.57 44764.27 42476.22 40305.12 38244.99 36290.16 34435.25 32675.15 M 005.02 29420 25 Kr-87 92385.49 87663.36 83182.6 78930.86 74896.44 71068.23 67435.7 63988.84 60718.16 57614.65
.Xe.133 334160.3 317080.2 300873.2 285494.6 270902 257055.3 243916.4 231449 219618.9 208393.4 Xe-133m 11793.89 11191.07 10619.05 10076.28 9561.247 9072.54 8608.813 8168.788 7751.254 7355.062 Xe-135 66832.06 63416.05 60174.64 57098.92 54180.4 51411.06 48783.27 46289.8 43923.77 41678.68 0.553448 0.525159 0.498317 0.472846 0.448677 0.42574# 0.403983 0.383334 0.363741 0.345149 l Time l
l 1430 1435 1440 1445 1450 1455 1500 1505 1510 1515 l IIuclide ] 120 125 130 135 140 145 150 155 160 165 ] i Kr-85 651.3845 618.0901 586.4975 556.5196 528.0741 501.0224 475.4705 451.1676 428.1069 406 2249 Kr-85m 27916.48 26489.58 25135.61 23850.84 22631.75- 21474.96 20377.31 19335.75 18347 44 17409 64 Kr.87 54669.77 51875.42 49223.89 46707.9 44320.5 42055.13 39905.56 37865.85 35930 4 34093.88 Xe-133 197741.7 187634.5 178043.9 168943.5 160308.2 152114.3 144339.2 136961.6 129961 123318.3 i Xe-133m 6979.12 6622.394 6283.901 5962.71 5657.936 536E.741 5094.326 4833.938 4586.86 4352 41 Xe-135 39548.35 37526.9 35608.77 33788.69 32061.64 30422.86 28867.85 27392.32 25992.21 24663.66 0.327507 0.310767 0.2S4883 0.27981 0.265508 0.251937 0.23906 0.226841 0.215246 0.204244 l Time l l 1520 1525 1530 1535 1540 1545 1550 1555 1600 1605 l Nuclide lj 170 175 180 185 190 195 200 205 210 215 { Kr-85 385.4614 365.7592 347.0641 329.3245 312.4916 296.5191 281.363 266.9816 253 3353 240.3865 Kr-85m 16519.78 15675.4 14874.17 14113.91 13392.5 12707.96 12058.42 11442.07 10857.23 10302.28 32351.23 30697.65 29128.59 27639.73 26226.97 24886.43 23614.4 22407.39 ' Kr-87 21262.07 20175.3 Xe-133 117015.1 111034.1 105358.7 99973.5 94863.52 90014.73 85413.78 81048 76905.37 72974.48 Xe-133m 4129.944 3918.849 3718.544 3528.476 3348.124 3176.991 3014.604 2860.518 2714.307 2575.57 Xe-135 23403.02 22206.81 21071.75 19994.7 18972.7 18002.95 17082.76 16209.6 15381.07 14594.9 I 0.193805 0.183899 0.174499 0.16558 0.157116 0.149086 0.141465 0.134235 0.127373 0.120863 i Radioloercal Data Generarios Page 8-8 C:. .\ EXER \ SECT 7-l1.WP5 t
i exerc i i l Time 1615 1630 1645 1700 1715 1730 1745 1800 1815 1830 ' Nuclide 225 240 255 270 285 300 315 330 345 360 Kr-85 222.2701 195.059 166.6514 142.381 121.6452 103.9293 88.7935 75.86199 64.81377 55.37456 i Kr-85m 9525.861 8359.67 7142.203 6102.042 5213.367 4454.114 3805.436 3251.228 2777.733 2373.196 Kr-87 18654.81 16371.02 13986.81 11949.83 10209.51 8722.64 7462.311 6366.988 5439.727 4647.508 Xe-133 67474.85 59214.33 50590.6 43222.8 36928.01 31549.97 26955.17 23029.53 19675.61 16810.13 ; Xe-133m 2381.465 2089.917 1785.551 1525.511 1303.342 1113.528 951.3589 812.807 694.4332 593.2989 ' Xe-135 13494.97 11842.87 10118.12 8644.56 7385.603 6309.995 5391.034 4605.906 3935.121 3362.027 0.111754 0.098073 0.08379 0.071587 0.061161 0.052254 0.044644 0.038142 0.032587 0.027842 [ 33.52627 29.42186 25.13698 21.47614 18.34844 15.67625 13.39323 11.4427 9.776231 8.352462 l Time l l 1845 1900 1915 1930 1945 2000 l Nuclide ll 375 390 405 420 435 450 j ; Kr-85 47.31004 40.42001 34.53341 29.50411 25.20726 21.53618 Kr-85m 2027.573 1732.286 1480.003 1264.462 1080.311 922.979 Kr-87 3970.664 3392.394 2898.34 2476.238 2115.609 1807.501 Xe-133 14361.98 12270.36 10483.36 8956.605 7652.203 6537.768 Xe-133m 506.8933 433.0715 370.0008 316.1155 270.0777 230.7448 Xe-135 2872.396 2454.072 2096.671 1791.321 1530.441 1307.554 0.023787 0.020323 0.017363 0.014834 0.012674 0.010828 i 7.136044 6.096781 5.208871 4.450273 3.802154 3.248425 0 0 0 0 Total = 6965.139 Radiologiad Data Genciatiem huge 8-9 C:. .\ EXER \ SECT 7-II.WP5 l t i I
l l I ! REACTOR building ventilation / dispersion after HPCI steam line break. i l to the Elevated Release Point (ERP)Y 1001' Elevation 0% (no associated duct) l 1 l l
/\/\/\/ l 976' Elevation 0% SBGT l mm ,
l (shine from duct only) (shine only; 958' Elevation 0% l l (shine from duct only) 931' Elevation 0% I l (shine from duct only) 903' Elevation 8%
/. (for gama, beta, (plus duct shine) iodine) 4 ^ ^n 100 % TORUS AREA 92 %
GENERAL (for (HPCI steam line break (for gamma, QUADS release) is in this area) beta iodine) QUADS I I RadiologicalData Generation Page 8-10 C:. . tEXER\ SECT 711. WP5
At the termination of the exercise a ' time-jump' will occur for the sole purpose of demonstration of the recovery, re-entry, relocation objective by off-site agencies. A half-hour delay will allow Controllers from the station to reach County EOCs. Demonstration of this objective effectively
' requires'some radioactive deposition. Data for this objective's demonstration will be generated using the same accident sequence, but postulating the additional failure of Standby Gas l
l Treatment. Data will be provided to designated EOF and County EOC personnel as ifit were collected 24 hours ago. A mock DOE serpentine fly-over map will be provided. Isotopic sample results will also be provided assuming reasonable sampling points from the fly-over map. The above data is NOT included in the scenario package for all Controllers, but only this l submittal and a limited number of copies to be used by Controllers and Evaluators involved with l the recovery, re-entry, relocation objective for off-site agencies. l i l \ i l l l l I l l l l l l I Radiological Data Generation Page 8-11 C:. .\ EXER \ SECT 7-11.WP5
. .-- . _ = . . .- ., .. - -- . . . .-
4 t i Radmap { i Location / Description l S enario name number Admin. Bida. 903' (Ist floor) 8135 Admin. Blda. 918' (2nd floor) !8136 Admin. Bida. 932' (3rd floor) 8 l-37 , Ausniented Radweste 903' i8.1 18 j _Ausmented Radweste 918',929' 8119 Ausmented Radweste Basement 8117 Aux Boiler Rooen 8.l.30 Cable Sorsedisu Room C-918' 8.l.33
- Condenser Area 903' 8.1 25 Control Bida. 903' 8.1 32
- Control Bids. Rosement 8.1-3 i Control Room / Computer Room C-932' 8.l-34 Comdors.903'.918' 8.1 17 Critical Switchaear Rooma 8.1-38 Diesel Generator Rooma 8.1 30 Electric Shop 8.1-27 Emera. Cond. Storsae tc. Room 8142 Heater Bay 18,1 25 HPCI Room 1813 1 & C Shop 18.I.2 7 Igake Bada. 18.1 41 MPF 903' !8120 MPF Menanine !8.12I Off ass Building :8 l-42 PA Perimeter (Northeast) i.146 8
PA Perimeter (Northwest) 81.s7 PA Perimeter (Overview) 8 1-43 PA Perimeter (Southeast) 8 l 84 PA Perimeter (Southwes0 '8.1 is Radweste 903' ;8.1 14 Radwaste 918' hl I.l$ Radweste 934' 18.1 16 l
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Area: [ Time: 800 815 830 845 900 915 930 945 1000 '1015 11030 '1045 1100 1115 1130 1145 A AS Rt Ab 3 -1 8 si ( C D E Area: Time: 1200 1215 1230 1245 1300 1315 1330 !1345 1400 1415 1430 1445 i1500 '1515 1530 1545 A A$ RG bb i ', B = ( c ~ D E RP map number PP-/o4,/S Cable Spreading Room, Control Bldg. 918' A I N ! l f 8 E B
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! Area: Tame: 800 815 830 1 845 900 915 930 1 945 1000 1015 1050 1045 1100 1115 1130 1145 A B C D E r l Area. Trne' 1200 1215 1230 1245 1300 1315 1330 1345 11400 1415 1430 1445 15(X) 8515 1530 1545 l l l A \ 8 ) c 1 l O . E RP map number. $ f Ykh PA Perimeter (Overview) I 666 / Mb /0 ATF D /M A P
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l s 7.82 10.20 2.66 2.57 I l ! ARM #15 ARM #16 ARM #17 ARM #18 ARM #19 AR M J20 TB Frnt Std TB Mezz TB Bnmt Cort RFP Area Cond Pmp Cont Rm. l l l 143.00 0.12 0.06 11.00 l 0.I1 0.05 l 1 Power 1 ARM #21 ARM #22 ARM #23 ARM #24 l . Supply . Con. corr 903 RW C/R RW Pmp Rm RW F N i l 0.25 0.02 5.06 2.06 ARM #25 ARM #26 ARM #27 ARM #28 ARM #29 ARM #30 Demin Viv Rm RW Conv Torus Area RW Lab Ceninf E Ce nt n f.W i l 1.91 0.31 0.21 0.03 3.90 4.10 l l MSL*A* 467 mrihr in Contamment High range l MSL'B" 428 mr/hr Monitors MSL"C' 483 mrihr AIRLOCK l .07 E + 01 MSL "D" 389 mrbr LADDER 9.70 E - 00 Remihr Rem. hr Page S.2.- 1 i
__ . . .._ - _ _ . . _ - - . . _ -~ _ ._. . _ . . _ . J ' MIMICl .XLS ARMS 11/19/96 l TIM E 4 0815 2
- Power ARM #1 ARM #2 ARM #3 ARM #4 N -' Supply Fuel Pool Fuel Pmi New Fuel RWCU.Precoat 129.00 1.22 l 0.05 6.80 ARM #5 ARM #6 ARM #7 ARM #8 ARM #9 ARM #10 RWCU Sludge T1P Index TIP Dnse HCU South HCU Nor9i HPCIRm 4
0.70 28.60 1.86 0.96 3.60 0.I8 Power ARM #11 ARM #12 ARM #13 ARM #14
, Supply RHR-SW RHR NW RCIC/CS-N E C/S-SE l
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l 7.82 10.20 2.66 2.57 . l l ARM #15 ARM #16 ARM #17 ARM #18 ARM #19 ARM #20 J TB Frnt Std TB Mez2 TB Bsme Corr RFP Area Cond Pmp Cont Rm . 143.00 0.12 0.06 11.00 0.1I 0.05
~ Power ARM #21 ARM #22 ARM #23 ARM #24
' Supply Cons Corr 903 RW CiR RW Pmp Rm RW Bsmi l 0:25 0.02 5.06 2.% l ARM #25 ARM #26 ARM #27 ARM #28 ARM #29 ARM #30 Demin Viv Rm RW Conv Torus Area PW Lah Ceninf E Centnf W l.91 0.31 0.21 0.03 3.90 4.10 MSL*A* 467 mrlhr in-Containment High range MSL*B* 428 mr/hr Monitors MSL*C' 483 mr/hr AIRLOCK 1.07E + 01 MSL*D* 389 mrehr LADDER 9. 70 E - 00 Rem /hr Rem hr Page 8.2.- 2
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l MIMICl.XLS l ARMS 11/19/96 l TIME 0830
; Power ARM #1 ARM #2 ARM #3 ARM #4 x Supply Fuel Pool Fuel Pimu New Fuel RWCU.Precoat 129.00 1.22 0.05 6.80 ARM #5 ARM #6 ARM #7 ARM #8 ARM #9 ARM #10 RWCU Sludge TIP Index TIP Dnve HCU South HCU Nonh HPCI Rm
- 0.70 <
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- 0. 2'5 0.02 *,. 06 2.06 I
ARM #25 ARM #26 ARM #27 ARM #28 ARM #29 ARM #30 l Dermn Viv Rm RW Conv Torus Area RW Lab Ce nin f. E Centnf w ! I.91 0.31 0.21 0.03 3.90 ' 4.10 MSL*A* 467 mr/hr in Containment High range MSL*B* 428 mr hr Momtors MSL*C* 483 mr hr AIRLOCK 1.07 E - 01 MSL *D* 389 mr'hr LADDER 9. 70E - 00 Remihr Rem hr Page S.2.- 3 i
MIMICl.XLS ARMS !I/19/96 l TIME j 0845 e . Power ARM #1 ARM #2 ARM #3 ARM #4
; Supply Fuel Pool Fuel Pmi New Fuel RWCU-Precoat i
129.00 1.22 0.05 6.80 J l ARM #5 ARM #6 ARM #7 ARM #8 I ARM #9 ARM #10 ! RWCU Sludge TIP Indea T1P Dnvc HCU South HCU North HPCI Rm
- 0.70 28.60 1.86 0.96 3.60 0.I8 Power ARM #11 ARM #12 ARM #13 ARM #14 J S,upply RHRSW RHR-NW RCIC/CS-NE C/$ SE 7.82 10.20 2.66 2.57 a
ARM #15 ARM #16 ARM #17 ARM #18 ARM #19 ARM #20 TB Frnt Std TB Meu TB Bsma Corr RFP Area Cond Pmp Cone Rm i 143.00 0.12 0.06 11.00 0.t1 0.05
- Power ARM #21 ARM #22 ARM #23 ARM #24 Supply - Cont Corr 903 RW C/R RW Pmp Rm RW Bsmi 0.'25 0.02 5.06 2.06 ARM #25 ARM #26 ARM #27 ARM #28 ARM #29 ARM #30 Demin Viv Rm RW Conv Torus Area RW Lab Ceninf E Ceninf W l.91 0.31 0.21 0.03 3.90 4.10 MSL*A" 467 mrihr in Contunment High range MSL *B* 428 mrihr Momtors MSL"C* 483 mrhr AIRLOCK 1.07 E - 01 MSL "D" 389 mr hr LADDER 9 70E - 00 Remihr Rem /hr Page 8.2.-4
l MIMICl.XLS ARMS 11/19 96 l TIME 0900 Power ARM #1 ARM #2 ARM #3 ARM #4 Supply Fuel Pool Fuel P.e! New Fuel RWCU Precoat 129.00 1.22 0.05 6.80
. ARM #5 ARM *6 ARM *7 ARM #8 ARM *9 ARM *10 RWCU Sludge TIP Indes TIP Dnve HCU South HCU Noah HPCIRm 0.70 28.60 1.86 0.96 3.60 0.18 Powtr ARM #11 ARM #12 ARM #13 ARM #14 Supply RHR 5W RHR NW RCIC/C5.NE C/5-SE 7.82 10.20 2.66 2.57 ARM #15 ARM #16 ARM #17 ARM #18 ARM #19 ARM #20 TB Frni Std TB Meu TB Bomt Corr RFP Area Cond Pmp Cont Rm l 142 00 0.12 0.06 I I .00 0.Ii 0.05 Power ARM #21 ARM #22 ARM #23 ARM #24 Supply Con Cort 903 RW C R RW Pmp Rm RW Bsmi l U.25 0.02 5.06 2.06 ARM #25 ARM #26 ARM #27 ARM #28 ARM #29 ARM #30 Demin Viv Rm RW Conv Torum Area RW Lab Ceninf E Centnf.W l.91 0.31 0.21 0.03 3.90 4.10 MSL*A* 467 mrrhr in Containment High range MSL~B" 428 mrihr Monitors MSL*C" 483 mr hr AIRLOCK l .07 E - 01 MSL"D* 389 mr hr LADDER 9."0E - 00 Remthr Rem > hr Page 5.2. 5
MIMICI.XLS ARMS 11/19 96 l TIME 0915 Power ARM #1 ARM #2 ARM #3 ARM #4 Supply Fus ! P<ut Fuel P.e4 New Fuel RWCU Precoat 129.00 1.22 0.05 6.80 l l ARM #5 ARM #6 ARM #7 ARM #8 ARM #9 ARM #10 RWCU Sludge TIP Index TIP Dnv4 HCU Souin HCU North HPCI Rm l I O.70 28.60 1.86 0.96 3.60 0.I8
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; Rem hr Page 5.2. 6
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l MIMICI.XLS ARMS 11/19790 l TIME ! 0930 i Power ARM #1 ARM #2 l ARM #3 ARM #4 Supply Fuel Pmi f New Fuel RWCU.Presoat Fuel Pool _ 129.00 1.22 0.05 6.80 ARAi #5 ARM #6 ARM #7 ARM #S ARM #9 ARM #10 RWCU $1udge TIP Inden TIP Drne HCU South HCU North H PCI Rm 0.70 28.60 1.86 0.95 3.60 0.18 I Power ARM #11 ARM #12 ARM #13 ' ARM #14 Supply RHRSW RHR NM RCIC/CS-N E C/5-SE l l 7.82 10.20 2.66 2.57 I l 1 l l ARM #15 ARM #16 ARM #17 ARMalsl ARM #19 ARM #20 ) TB Fmt $id TB Meu TB B.ma C.irr RFP Area l Cond Pme C. nr Rm i 143.00 0.12 _ 0.06 1l.00 0.I1 0.05 Power - ARM #21 ARM #22 ARM #23 ARM #24 Supply Cont Corr $U RW C.R RW Pmp Rm RW Bsmt l l l d.25 0.02 5,06 2.% ARM #25 ARM #26 ARM #27 ARM #25 ARM #29 ARM #30 Demm Viv Rm RW Cons Torus Ares RW Lao Cenirii.E Centni.W l.91 0.31 0.21 0.01 3 90 4.10 MSL*A' 467 mr hr in Containment High range MSL *B* 42S mr hr Monitors MSL'C" 4S3 mr hr AIRLOCK 1.07 E - 01 M S L " [,
- 359 mr hr LADDER 9. 'OE - 00 Rem hr Rem hr Page 8. 2. '
l
MIMICI..XLS ARMS 11/19,96 l TIME 0945 Power ARM #1 ARM #2 ARM #3 ARM #4 Supply Fuel Pml Fuel Pmt New Fuel RWCU.Pruoat I 129.00 1.22 0.05 6.80 l _ l ARM #5 ARM #6 ARM #7 ARM 88 ARM #9 ARM #10 RWCU Studre TIP laden TIP Dnve HCU South HCU North HPCIRm 0.70 28.60 1.86 0.96 3.60 0.I8 Power ARM #11 ARM #12 ARM #13 ARM #14 Supply R HR-SW RHR.NW RCIC/CS.NE CIS.S E 7.82 10.20 2.66 2.57 i ARM #15 ARM #16 ARM #17 ARM #lS ARM #19 ARM #20 TB Frnt Std T8 Men TB 8 nu C.irr RFP Area Cond Pme Cona Rm I43.00 0.12 0.06 l1.00 0.II 0.05 Power ARM #21 ARM #22 ARM #23 ARM #24
. Supply ^ Cont Corr 903 RW C/R RW Pme Rm RW Bsm 0'.25 0.02 5.06 2,06 ARM #25 ARM #26 ARM #27 ARM #25 ARM #29 ARM #30 Denun Vh Rm RW Conv Torus Area _
RW Lan Centnf E Ce nin f.W I.91 0.31 0.21 0.03 3.90 4.10 MSL*A* 467 mrchr In-Containment High range MSL*B* 428 mr hr Monitors MSL*C' 483 mr hr AIRLOCK 1.07 E -01 MSL*D* 3S9 mr hr LADDER a 'OE - v0 Rem 1.r Rem hr l Page s.2. 5 l
MIMICI .XLS ARMS 11/19/96 l TIME 1000 ARM #1 ARMa2 ARM #3 ARM #4 Power Fuel P. wit New Fuel RWCU Presoat Supply Fuel Piwil 1 129.00 1.22 0.05 6.80 i ARM #6 ARM #7 ARM #8 ARM #9 ARM #10 ARM #5 TIP Dnve HCU South HCU North HPCI Rm RWCU Studge TIP Inden 1.86 0.96 3.60 0.18 0.70 28.60 1 Power ARM #11 ARM #12 ARM #13 ARM #14 RHR SW RHR NW RCIC/CS NE C/5 SE Supply 7.82 10.20 2.66 2.57 ARM #17 ARM #16 ARM #19 ARM #20 ( ARM #15 ARM #16 Cond Pmp Coni Rm TB Fmt Std TB Ma.z TB B4mt Corr RFP Aru l 0.12 0.06 11.00 0.I1 0.05 l 143.00 Power - ARM #21 ARM #22 ARM #23 ARM #24 Cons Cort 903 RW C/R RW Pmp Rm RW Bsmt Supply d.25 0.02 5.06 2.06 ARM #26 ARM #27 ARM #26 ARM #29 ARM #30 ARM #25 Tonn Area RW Lah Cent nfs Centnf W Demin Viv Rm RW Con 0.31 0.21 0.03 3.90 4.10 l.91 MSL*A" 467 mrihr in-Containment High range MSL'B' 428 mr hr Momtors MSL "C" 483 mr hr AIRLOCK 1.07 E - 01 i MSL"D" 389 mr hr LADDER 9. 70E - 00 Rem hr Rem br Page s.2. 9
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MIMICl.XLS ARMS 11/19/96 l TIME e 1015 Power ARM #1 ARM #2 ARM #3 ARM #4 Supply Fuel Pool Fuel P+1 New Fuel RWCU.Precoat 129.00 1.22 1 0.05 6.80 ARM #5 ARM #6 ARM #7 ARM #8 ARM #9 ARM #10 RWCU Sludge TIP Index TIP Dnve HCU South HCU North HPCI Rm 0.70 28.60 1.86 0.96 3.60 0.18 Power ARM #11 ARM #12 ARM #13 ARM #14 l
- Supply RHR SW RHR.NW RCIC/CS.N E C/S-S E 7.82 10.20 2.66 2.57 l l
l ARM #15 ARM #16 ARM #17 ARM #18 ARM #19 ARM #20 TB Fmt Sid TB Mu.z TB Bsmi Carr RFP Area Cond Pmp Cont Rm. l l 143.00 0.12 0.06 11.00 0.I1 0.05 ! Power. ARM #21 ARM #22 ARM #23 ARM #24 ! Supply ConaCarr903 RW C/R RW Pmp Rm RW Bsmt l O'.25 0.02 5.06 2.06 ARM #25 ARM #26 ARM #27 SRM #25 ARM #29 ARM #30 Demin Viv Rm RW Cons Torum Ar.:a RW Lah Cemnf E Ceninf.W l.91 0.31 0.21 0.03 3.90 4.10 l l l MSL"A" 467 mr hr in-Containment High r.tnge MSL *B" 428 mr/hr Monitors ! MSL "C" 483 mrihr AIRLOCK 1.07 E - 01 MSL "D" 389 mrhr LADDER 9.70E - 00 Rem /hr Rem /hr Page S.2. 10
MIMICl.XLS ARMS ! l /19,96 l TIME 1030 Power ARM #1 ARMS 2 ARM #3 l ARM #4 Supply . Fuel Pool Fuel Pmi New Fuel RWCU.Precosi 129.00 1 22 0.05 6.80 ARM #5 ARM #6 ARM #7 ARM #8 ARM #9 ARM #10 RWCU Sludge TIP Index TIP Dnve HCU South HCU Nonh HPCIRm l 0.70 28.60 1.86 0.96 3.60 0.I8 t Power ARM #11 ARM #12 ARM #13 ARM #14 l l Supply RHR SW R HR.NW RCIC/CS.NE C/S SE I , 7.82 10.20 2.66 2.57 l l ARM #15 ARM #16 ARM #17 ARM #18 ARM #19 ARM #20 TB Frnt Std TB Mer2 TB B mi Corr RFP Area Cond Pmn Cont Rm , l 143.00 0.12 0.06 11.00 _ 0.11 l 0.05
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. Supply Cont Corr 903 RW C/R RW Pmp Rm RW Bsmi
)
0.25 0.02 5.06 2.06 ARM #25 ARM #26 ARM #27 ARM #28 ARM #29 ARM #30 __Demin Viv Rm RW Conv Torus Area RW Lah Cenirif F. Centri (.W l.91 0.31 0.21 0.03 3.90 4.10 l l MSL"A" 432 mr/hr In-Containment High rangi- ! MSL*B' 421 mr hr Momtors i MSL"C" 452 mr hr AIRLOCK 1.07E-01 j MSL"D" 373 mr hr LADDER 9 'UE - 00 Rem hr Rem hr Page 8.2. 1I
- _ _ . - . _ .a a , - .
MIMICl .XLS ARMS 11/19 <96 l TIM E 1045 i t Power ARM #1 ARM #2 ARM #3 ARM #4 Supply Fuel Pool Fuel Pml New Fuel RWCU-Precoas j 4 129.00 1.22 0.05 6.80 $ ARM #5 ARM #6 ARM #7 ARM #8 ARM #9 ARM #10 RWCU Sludge TIP Inden TIF Dnve HCU $nuth HCU North HPCI Rm 0.70 28.60 1.85 0.96 3.60 0.18 Power ARM #1l ARM #12 ARM #13 ARM #14 Supply RHRSW RHR Nw C/CS.N E Cis.S E 7.82 10.20 _ 2.66 2.57 ARM #15 ARM #16 ARM #17 ARM #18 ARM #19 ARM #20 TB Frnt Sid TB Men TR B4mt Carr RFP Area Cond Pmp Coni Rm _ 143.00 0.I1 0.06 10.00 0.1I 0.05 Power ARM #21 ARM #22 ARM #23 ARM #24
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- Coni Corr 903 RW C/R RW Pmp Rm RW Bsmt 0.25 0.02 5.06 2.06 ARM #25 ARM #26 ARM #27 ARM #2S ARM #29 ARM #30 Denun Viv Rm RW Conv Toru. Area RW Lab Ceninf E Ceninf.W l.91 0.31 0.21 0.03 3.90 4.10 l
l MSL*A" 299 mrrhr in-Containment High range MSL"B" 293 mrhr Monitors MSL'C- 302 mr hr AIRLOCK 9.6 8 E - 00 MSL'D- 280 mr hr LADDER R SOE - oo Rem br Rem hr Page 5.2.- 12
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MIMICl.XLS ARMS 11/19/96 l TIM E I100 Power ARM #1 ARM #2 ARM #3 ARM #4
. Supply Fuel Pool Fuel P ul New Fuel R WCU-Precoat 129.00 1.22 0.05 6.80 ARM #5 ARM #6 ARM #7 ARM #8 ARM #9 ARM #10 RWCU Studge TIP Index TIP Dnve HCU South HCU North HPCIRm 1
2.58 44.00 1.85 0.96 3.60 0.18 , Pour ARM #11 ARM #12 ARM #13 ARM #14
- Supply RHR SW RHR NW RCIC/CS.N E C/5 SE l 9.42 10.20 2.94 2.73 ARM #15 ARM #16 ARM #17 ARM #18 ARM #19 ARM #20 TB Frnt Sid TB Meu TB Bsmt Carr RFP Area Cand Pme Cont Rm.
I43.00 0.08 0.05 10.00 0.08 0.05 Power ARM #21 ARM #22 ARM #23 ARM #24
. Supply RW C R RW Pmp Rm RW Bsmt
_ Cont Carr 903 0.20 0.02 5.01 2.06 ARM #25 ARM #26 h ARM #27 ARM #28 ARM #29 ARM #30 Demin Viv Rm RW Conv Torus Area RW Lah Ce nin t'.E Ceninf W l.41 0.26 0.15 0.03 3.90 4.10 MSL " A" 299 mr.hr in Containment High range MSL "B" 293 mr<hr Momtors MSL"C" 302 mr hr AIRLOCK 9.68 E - 00 MSL "D" 280 mr hr LADDER S SOE -UU Rem br Page 8.2.- 13 l l I
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- A" 47 mr
l
!29.00 12.25 1.10 14.00 i l
l 1 ARM #5 ARM #6 ARM #7 ARM #8 ARM #9 ARM #10 RWCU Siudge TIP Indes TIP Drive HCU south HCU Nonh HPCIRm OFT.HIGli OFT-l!!Gil OFT lilGli OFT.IllGil hilow OSH OSH OSH OSH 11.70 3.15 Power ARM #11 ARM #12 ARM #13 ARM #14 Supply RHRSW RHR NW RCIC/CS.NE C/S SE OFT.lllGli OFT lilGII OtT lllGil OFT-lilGil OSH OSH OSH OSH ARM #15 ARM #16 ARM #17 ' ARM #18 ARM #19 ARM #20 TB Frnt $td TB Meu TB Bsmi Corr RFP Aru Cond Pmp Cont Rm t 8.90 0.07 0.05 0.97 0.06 0.05
. Power
- ARM #21 ARM #22 ARM #23 ARM #24 Supply Cont Corr 903 RW CiR RW Pmp Rm RW Bsmt 0.20 0.02 5.01 2 06 ARM #25 ARM #26 ARM #27 ARM #2S ARM #29 ARM #30 Demin Viv Rm RW Cons Torus Area RW L.th Centrif E Centni-W OFT lllGil 1.41 0.26 OSH 0.03 3.90 _ 4.10 MSL*A" 31 mrhr in Containment High range MSL*B" 32 mr hr Monitors MSL*C' 33 mr hr AIRLOCK 4.19E - 02 MSL "D" 32 mr hr LADDER 3 8IE-02 Rem hr Rem br Page s 2 - 20
i MIMICI.XLS ARMS ! I /19i96 l TIME 1300 Power ARM #1 ARM #2 ARM #3 ARM #4 Supply Fuel P.ut Fuel Pml New Fual RWCU Precos HEI) 129.00 12.25 1.10 14.00 l ARM #5 ARM #6 ARM #7 ARM #8 ARM #9 ARM #10 RWCU Sludge TIP Index TIP Drne HCU South HCU North HPCIRm OFT lilGil OFT il!Gil OIT lilGli OFT.llIGli Wilow OSH OSH OSH OSH I1.70 3.15 Power ARM #11 ARM #12 ARM #13 ' ARM #14 Supply RHR SW RHR NW RCIC/CS NE C/S SE OFT lllGli OFT.IllGli OFT illGil OFT-illCll OSH OSH OSH OSH RM .185 l l*TM#16 ARM #l7 ARM #tS ARM #19 ARM #20 TB Frnt Std d Alen TB B5nu C.wr RFP Area Cond Pmp cont Rm. j i 8.90 0.07 0.05 0.97 0.06 0.05 ;
^ Power ARM #21 ARM #22 ARM #23 ARM #24
; Supply Cc-t Car 903 RW C R RW Pmp Rm RW Bsm 0'.20 0.02 5.01 2.06 ARM #25 ARM #26 ARM #27 ARM #28 ARM #29 ARM #30 Demin Viv Rm RW Cons Toru. Area RW Lah _Centrit' E Ceninf W otT.illGli 1.41 0.26 OSH 0.03 3.90 4.10 MSL " A" 31 mrihr In Contamment High range MSL"B" 32 mrhr Momtors MSL*C- 33 mr hr AIRLOCK 4.19 E - 02 MSL"D- 32 mr hr LADDER 3.SIE -02 Rem hr Rem hr Page 5.2 - 2 I t
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MIMICI.XLS ARMS 1I/19 96 l TIME 1315 1 i ~ Power ARM #1 ARMa2 ARM #3 ARM #4 Supply Fuel Pool Fuel P.e. New Fuel RWCU Precoat K F.D
,'e 129.00 12.25 1.10 14.00 ARM #5 ARM #6 ARM #7 ARM #8 ARM #9 ARM #10 RWCU Sludge TIP Index TIP Dnve HCU S.wih HCU North HPCIRm OPT-HIGH OFF-IllGli OFF IIIGli OFF lllGli h41ow OSH OSH OSH OSH 11.70 3.15 Power ARM #11 ARMal2 ARM #13 ARM #14 l
. Supply RHRSW RHR.NW RCIC/CS-N E C/S SE
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MIMICI.XLS ARMS 11/19 96 l TIM E 1330 Power ARM #1 ARM #2 ARM #3 ARM #4 Supply Fuel Piwil Fuel P.iol New Fuel RWCU Precoat R F.D 129.00 12.25 1.10 14.00 ARM #5 ARM #6 ARM #7 ARM #8 ARM #9 ARM #10 RWCU Sludge TIP liJe TIP Drne HCU South HCU Nonh HPCIRm OFT.HICil OtT-li!Gil OtT illGli OtT-IllGil L.ilow OSH OSH l OSH OSH 11.70 3.15 Power ARMall ARM #12 ARM #13 ARM #14 Supply RHR 5W R H R.N W RCIC/CS NE C/S.$E OFT-illGil OFF IllGli OFT.lilGil OFT il!Gli , OSH OSH OSH OSH ARM #15 ARM #16 ARM #17 ARM #15 ARM #19 ARM #20 TB Frnt Sid TB Meu TB B*mi Corr RFP Area Cond Pme Cont Rm 8.90 0.07 0.05 0.95 0.06 0.05 Power ARM #21 ARM #22 ARM #23 ARM #24 Supply Cont Carr 90.1 RW C R RW Pmp Rm RW Bsm:
- 0. 2'O 0.02 5.01 2.06 ARM #25 ARM #26 ARM #27 ARM #25 ARM #29 ARM #30 Demin Viv Rm RW Cons Toru Arn RW Lab Cemrd E Cenin( W OtT illGil 1.41 0.26 OSH 0.03 3 90 4.10 MSL"A" 31 mr hr In Containment High range MSL *B" 32 mr hr Momtors i MSL"C" 33 mr hr AIRLOCK 4.19E - u:
j MSL"D" 32 mr hr LADDER 3 s t E - 02 Rem hr l Rem h-Page i 2. 23 ? l
l MIMICI .XLS ARMS 11/19'96 l TIM E 1345 i l l Power ARM #1 ARM #2 ARM #3 ARM #4 l Supply Fuel Pool Fuel P+1 New Fuel RWCU.Precoat MVU i 129.00 12.25 1.10 14.00 l l ARM #5 ARM #6 ARM #7 ARM #8 ARM #9 ARM #10 RWCU Sludge T!P Inden T!P Dnse HCU South HCU North HPCI Rm OFF tilGli OtT illGli OtT IllGli OFT-IllGli hilow OSH OSH - OSH j OSH 11.70 3.15 l l l l Power ARM #11 ARM #12 ARM #13 ARM #14 Supply RHR5W RHR NW RCICTCS NE C/S-S E OFT illGil Off lllGil OtT illGli OtT ll!Gli OSH OSH OSH OSH l l l ARM #15 ARM #16 ARM #17 ARMals ARM #19 ARM #20 ! TB Fmt Std TB Men TB B mi C..rr RFP Arn i Cond Pmn Cont Rm l i , 8.90 0.07 0.05 0.95 0.06 0.05 l l l
.m Powet ARM #21 ARM #22 ARM #23 ARM #24
. Supply Cont Corr 903 RW C R RW Pmp Rm RW Bsmi 0.20 0.02 5.01 2.%
! ARM #25 ARM #26 ARM #27 ARM #28 ARM #29 ARM #30 ! RW Cons Tann Are.1 R W Lan Caninf E Centnf W Demin Vlw. R.m t Ol't lllGil 1 l 1.41 0.26 OSH 0.03 3 90 4.10 MSL
- A" 31 mr hr in Cont.unment High range MSL"B" 32 mr hr Monitors l
l MSL"C" 33 mr hr AIRLOCK 4.19 E - 02 MSL'D' 32 mrhr LADDER 3 'I E - 02 Rem hr Rem br Page 5 2.- 24 l l
.. . . __ _ . . _ _ _ _ _ _ _ ~ _ _ _ . . _ _ _ _ . . .___ _ _ . _ . . _ _ . . . .
I l MIMICl.XLS ARMS 11!!9/96 l TIME 1400 i ! I Power ARM #1 ARM #2 ARM #3 ARM #4 ) l Supply Fuel Pmi Fuel Pmi New Fuel RWCU Precoat l l , RI:D 129.00 12.25 1.10 14.00 l l l ARM #5 ARM #6 ARM #7 ARM #S ARM #9 ARM *10 RWCU Sludge TIP Inde n TIP Dnve HCU South HCU Nonh H PCI Rm oft illGli OFT IllGil OFT-lilGli OFT IllGil hilow OSH OSH OSH OSH l 11.70 3.15 I l 1 Power ARM #11 ARM #12 ARM #13 ARM #14
. Supply RHR SW RHR-NW RCIC/CS NE CIS SE OFT IllGil OFT illGli OFT il!Gli OFT IllGli OSH OSH OSH OSH i ARM #15 ARM #16 ARM #17 ARM #15 ARM #19 ARM #20 TB Frni Sid TB hien TB B,nu Carr . RFP Ara Cond Pmr _ Cont Rm 8.90 0.07 0.05 0.95 0.06 0.05 Power ARM #21 ARM #22 ARM #23 ARM #24 Supply - con Corr 903 RW C.R RW Pmp Ria RW Bsma 0'.20 0.02 5.01 2.06 ARM #15 ARM #26 ARM #27 ARMS 2s ARM #29 ARM #30 Demin Viv Rm RW cons Torus Area RW Lah Ceninf E Ceninf W OIT.lllGli 1.41 0.26 OSH 0.03 3.90 4.10 MSL"A* 31 mr< hr in Containment High range MSL*B" 32 mrhr Momtors MSL "C" 33 mr hr AIRLOCK 4.19 E - u MSL"Da 32 mrhr LADDER 3 SIE -02 Rem /hr Rem hr Page s.2. 25 l
l
_ _ _ . m . m __ m . . _ . _ _ . . . _ . _ _ . . . I MIMICl.XLS ARMS I i /19:96 l TIME I 1415
)
l I l ! Power ARM #1 ARM #2 ARM #3 ARM #4 Supply Fuel Po.4 Fuel P.*4 New Fuel RWCU Precoas j l RI'D l 129.00 12.25 !.10 14.00 l ARM #5 ARM #6 ARM #7 ARM #8 ARM #9 ARM #10 RWCU Sludge TIPIndex TIP Dme HCU South HCU North HPCI Rm OFT.HIGH OFT illGli OFT-illGil OFT IllGil huow i l OSH OSH OSH OSH I1.70 3.15 Power ARM #11 ARM #12 ARM #13 ARM #14 Supply RHRSW RHR NW RCIC/CS.N E C/S.SE l OFT illGli OtT illGil OFT lilGli OPT It!Gil OSH OSH OSH OSH l ? l i I l ARM #15 ARM #16 ARM #17 ARM #lS ARM #19 ARM #20 1 l TB Frnt Sid TB Men TB 8.mt Corr RFP Ara Cond Pme Cont Rm I l 8.90 0.07 0.05 0.94 1 0.06 0.05 l i Power ARM #21 ARM #22 ARM #23 ARM #24 Supply Cont Corr 903 RW C.R RW Pmp Rm _ RW Bamt l 0.20 0.02 5.01 2.06 ARM #25 ARM #26 ARM #27 ARM #25 ARM #29 ARM #30 Demen Viv Rm RW Cons _ Tonn Aru RW Lab Ce nin f. E Ceninf w Off IllGli I 1.41 0.26 OSH 0.03 3.90 4.10 MSL*A* 31 mr hr in Contammem High range MSL "B" 32 mrhr Momtors l MSL "C" 33 mr hr AIR LOCK 4.19 E - 02 MSL*D" 32 mr hr LADDER 3.51 E - 02 Rem:hr i Rem hr Page 32. 26 l i I
MIMICl.XLS ARMS 11/19 96 l TIM E 1430 Power ARM #1 ARM #2 ARM #3 l ARM #4 Supply Fuel P.ul Fuel P,iol New Fuel RWCU Pre: oat RI:1)
+ 129.00 12.25 1.10 14.00 ARM #5 ARM #6 ARM #7 ARM #8 ARM #9 ARM #10 RWCU Sludge TIP Inde HCU South HCU N. inh HPCI Rm TIP Dnve_
OtT IIIGli OtT il!Gli OFT illG I OtT-illGil hum OSH OSH OSH OSH I1.70 3.15 i Power ARM all ARM #12 ARM #13 ARM #14 j Supply RHR sw RhR NW RCICeCS NE C/S SE l OtT illGli OFT illGil OFT illGil OtT illGli OSH OSH OSH OSH ARM #15 ARM #16 ARM #17 ARM #18 ARM #19 ARM #20 TB Fmt Sid TB Meu TB Bsmi Corr RFP Area Conj Pme Cont Rm 1 J 8.90 0.07 0.05 0.93 0.06 0.05
' Power ARM #21 l ARM #22 ARM #23 ARM #24 Supply Cont Corr 903 RW C'R RW Pmp Rm RW Bsmt 0.20 0.02 5.01 2.06 ARM #25 ARM #26 ARM #27 ARM #28 ARM #29 ARM #30 Demin Vh Rm RW Cons Toru, Area RW Lah Ce nin f- E Ce nin t' W OF F.lilGil 1.41 0.26 OSH 0.03 3.90 4.10 MSL " A" 31 mrahr in-Containment High range MSL"B" 32 mr hr Monitors MSL "C" 33 r.e hr AIRLOCK 4.19 E - U2 MSL "D" 32 mr hr L -\ D D E R MIE u2 Remihr Rem'hr Page S 2. - 2'
MIMICI.XLS ARMS 11/19,96 l TIM E 1445 Power ARM #1 ARM #2 ARM #3 ARM #4 Supply Fuel Phal Fuel Paul New Fuel RWCU Precoat R F.D I29.00 12.25 1.10 14.00 ARM #5 ARM #6 ARM #7 ARM #8 ARM #9 ARM #10 RWCU Sludge TIP Inden TIP Dnve HCU South HCU Narth HPCI Rm OFF lilGil OFT IllGil OFT illGli OFT il!Gil Yellow OSH OSH OSH OSH I1.70 3.15 1 l i Power ARM #11 ARM #12 ARM #13 ARM #14 Supply . RHRSW RHR N% RCIC/CS NE C/5 SE OFT IIIGli OFT ilIGli OFT-IllGil OFT IllGli OSH OSH OSH OSH l 1 i l ARM #15 ARM #16 ARM #17 ARM #18 ARM #19 ARM #20
)
TB Fmt Sid TB Meu TB B mi Carr RFP Area Cand Pme Cant Rm. l l l 8.90 0.07 0.05 0.93 0.06 0.05 1 Power ARM #21 ARM #22 ARM #23 ARM #24
. Supply . Cont Corr 903 RW C R RW Pmp Rm RW Bsmt
- 0. 2'O 0.02 l 5.01 2.06 ARM #25 ARM #26 ARM #27 ARM #28 ARM #29 ARM #30 Demin Viv Rm RW Cans T.'re Ara RW Lab Ceninf E Ceninf W OFT lllGil 1.41 0.26 OSH 0.03 3.90 4.10 MSL"A" 31 mrehr in Containment High range MSL "B" 32 mr hr Monitors MSL"C* 33 mrhr AIRLOCK 4.14E -02 MSL"D* 32 mr hr LADDER 3plE-u2 Rem /hr Rem 'hr Page s.2. 2s
l MIMICI,XLS ARMS I1/19'96 l TIME 1500 l l Power ARM #1 ARM #2 ARM #3 ARM #4 l Supply Fuel Pool Fuel Pool New Fuel R WCU-Precost RED 129.00 l 12.25 1.10 14.00 l l i ARM #5 ARM #6 ARM #7 ARM #8 ARM #9 ARM #10 l I RWCU Sludge T!P Inden TIP Dnve HCU South HCU North HPCIRm oft.IIIGil OFT il!Gli OtT illGli OFT lllGli nunw OSH OSH OSH OSH I1.70 3.15 l l l Power ARM #11 ARM #12 ARM #13 ARM #14 l
! Supply R H R-SW RHR NW RCIC/CS.N E C/S SE OFT.lilGil OFT IllGli OtT.lilGit' OFT IllGli OSH OSH OSH OSH 1
l ARM #15 ARM #16 ARM #17 ARM #13 ARM #19 ARM #20 l l TB Frnt Sid TB Men TB B.nu corr RFP Aru Cond Pme Coni Rm. 8.90 0.07 0.05 0.90 0.06 0.05 l l l Power ARM #21 ARM #22 ARM #23 ARM #24
. Supply l Cont Corr 903 RW C R RW Pmp Rm RW Bsmt d.20 0.02 5.01 2.06 ARM #25 ARM #26 ARM #27 ARM #28 ARM #29 ARM #30 Demin Viv Rm RW Cony Torus Area R W Lab Cenini E Centni W OtT.lllGll 1.41 0.26 OSH 0.03 3.90 4.10 l MSL*A* 31 mrrhr in Containment High range MSL *B* 32 mrhr Monitors MSL*C" 33 mr hr AIRLOCK 4.19 E - 02 MSL *D* 32 mrhr LADDER 3.slE -02 Rem hr l
Rem hr l i Page S.2. 28
MIMICl.XLS ARMS 11/19 96 l TIM E 1515
^
Power ARM #l ARM #2 ARM #3 ARM #4 Supply Fuel Pool Fuel P. si New Fuel RWCU Precost RED 129.00 12.25 1.10 14.00 J l ARM #5 ARM #6 ARM #7 ARM #8 ARM #9 ARM #10 l RWCU Sludge TIP Inden TIP Dnse HCU South HCU Nonh i!PCI Rm OFT.IllGil OFF.!!!Gil OFF.lllGil OFF.IllGli h.uow l OSH OSH OSH OSH - 11.70 3.15 ( 1 1
~
Power ARM #ll ARM #12 ARM #13 ARM #14 Supply RHR SW RHR NW RCIC/CS NE Ci5 SE OFF IllGl! OFF illGli OFF.lllGli OFF illGli OSH OSH OSH OSH i l ARM #15 ARM #16 ARM #17 ARMvli ARM #19 ARM #20 l TB Frnt Sid TB Meu TB Buni C.irr RFP Arts Cond Pmr Coni Rm 8.90 0.07 0.05 0.90 0.06 0.05
' Power ARM #21 ARM #22 ARM #23 ARM #24
. Supply Cont Corr 903 RW C R RW Pmp Rm RW Bsmt 0.D5 0.05 0.05 2.06 ARM #25 ARM #26 ARM #27 ARM #28 ARM #29 ARM #30 RW Cons Torus Area RW L.ib Centni E 1 Cenini W Demin Viv Rm _
OFF lllGil 1.41 0.26 OSH 0.03 3.90 4.10 MSL"A" 31 rnr br in Containment High range mrhr Monitors MSL*B" 32 MSL*C' 33 mr hr AIRLOCK 4.19 E - 02 MSL"D- 32 mrhr LADDER 3 SIE-02 Rem hr Rem >hr Page 5 2. 3u
MIMICI.XLS l ! ARMS 11,19 90 l TIM E 1530
' Power ARM #1 ARMa2 ARM #3 ARM #4 Supply Fuel Pool Fuel P.i.9 New Fuel RwCU Precoat HVU 129.00 12.25 1.10 14.00 ARM #5 ARM #6 ARM #7 ARM #8 ARM #9 ARM #!O
! RWCU Sludge TIP Index TIP Drne HCU South HCU North HPCI Rm l l OFT il!Gli OFT illGli OFF IllGli OFF il!Gil hilow l l OSH OSH OSH OSH I1.70 3.15 l l Power ARM #11 ARM #12 ARM #13 ARM #14 l
' Supply RHRSW RHR NW RCIC/CS NE CIS-SE OtT illGli OF F IIIGil OFF illGil otT.IllGli
, OSH OSH OSH OSH I l ! l l l ARM #15 ARM #16 ARM #17 ARM #15 ARM #19 ARM #20 l i TB B.mi Corr RFP Are.s Cont Rm TB Frnt Std
]PMeu Cond Pme 8.90 0.07 0.05 0.90 0.06 0.05 j iPower ARM #21 ARM #22 ARM #23 ARM #24 Supply Coni Corr 903 RwCR Rw Pmp Rm RW Bsnu 0'.05 0.05 0.05 2.06 i ARM #25 ARM #26 ARM #27 ARMaS ARM #29 ARM #30 Dermn Viv Rm RW Cons Torm Area R W Lab Cenird E Cenird.w
[ OFT lllGil l 1.41 0.26 OSH 0.03 3 90 4.10 l MSL*A* 31 mr hr in Contamment High range MSL *B" 32 mrhr Momtors MSL "C" 33 mr hr AIRLOCK 4.19 E - 02
, MSL *D- 32 mr hr LADDER 3.SIE -02 Rem,hr
! Rem br Page S.2.- 31 1 i l l I i i
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1 MIMIC 1.XLS ARMS 11/19'96 l TIM E j 1545 j 1 Power ARMal ARM #2 ARM #3 ARM #4 > Supply Fuel Pool Fuel Pmi New Fuel RWCU Precoat RFD I29.00 12.25 1.10 14.00 ARM #5 ARM #6 ARM #7 ARM #8 ARM #9 ARM #10 l RWCU Sludge TIP Indes TIP Drne HCU South HCU North HPCIRm i Off.IllGli OtT illGli OtT IllGil OFT IllGil Yeuow OSH OSH OSH OSH I1.70 3.15 l Power ARM #11 ARM #12 ARM #13 ARM #14 Supply RHRSW RHR.NW RCICeCS-NE C/S SE . 1 OIT illGil Off-lllGil OIYelllGil OtY IllGil OSH OSH OSH OSH j ARM #15 ARM #16 ARM #1' ARM #15 ARM #19 ARM #20 l TB Frnt Std TB Mm TB B mi Corr RFP Aru Cond Pmp Coni Rm l 0.06 0.05 8.90 0.07 0.05 0.90 l Poweir . ARM #21 ARM #22 ARM #23 ARM #24
.' Supply Cont Corr 903 RW C/R RW Pmp Rm RW Bsmi 0.05 0.05 0.05 2.06 ARM #15 ARM #26 ARM #27 ARM *2S ARM #29 ARM #30 Demin Viv Rm RW Cons Toru. Aru RM L.ah Centn( E Ce nini.W OFT lllGil I.41 0.26 OSH 0.03 3.90 4.10 MSL*A" 3l mrehr in-Containmen! High range MSL "B" 32 mr hr Monitors MSL "C" 33 mrhr AIRLOCK 4.20E-02 MSL"D" 32 mr hr LADDER 182E - U2
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! 96 D%.'.X LS I i Time: 800 1 Of f Site Survey Sheets Centerline Data l for edees: use 109 t . Current plant release rate: 4.30E +00 uC /see N.G. radiation :mr/hr i mile 2 mile 5 mile 10 mile l l l Direct 3 feet closed 0.00 0.00 0.00 0.00 3 feet open 0.00 0.00 0.00 0.00 3 inch closed 0.00 0.00 0.00 0.00 3 inch open 0.00 0.00 0.00 0.00 l l E-140 readings: mr/hr f Gross lodine on Silver Zeolite cart: l Concentration: sample size I cu ft 5 cu tt 15 cu fi i mi 1.49E-20 1 mile 0.00 0.00 0.00 , 2mi 1.47E 20 2 mile 0.00 0.00 0.00 { 5 mi 6.75E-21 5 mile 0.00 0.00 0.00 10 mi 3.26E-21 10 mile 0.00 0.00 0.00 Controllet Only Don't divulge E 140 readings: mr/hr l on Particulate cart: sample size I cu ft 5 cu it 15 cu ft I mile 0.00 0.00 0.00 2 mile 0.00 0.00 0.00 5 mile 0.00 0.00 0.00
- 10. mile 0.00 0.00 0.00 l for DRD dose assignment use the followine:
Dose rate I mile 2 mile 5 mile 10 mile per minute 0.00 0.00 0.00 0.00 j in plume: mr l Dowmrind Surny Team CONTROLLER data Paec 9.1.! C:. .tEXER\SEC77-11.WP5 l l
96DW.X LS 1 Time. 815 Off Site Suney Sheets Centerline Data ' for edges: uw 10W Current plant release rate: 4.7 t E + 00 uC /sec N.G. [ Direct r1tdiation :mr/hr I mile 2 mile 5 mile 10 mile l 3 feet closed 0.00 0.00 0.00 0.00 3 feet open 0.00 0.00 0.00 0.00 3 inch closed 0.00 0.00 0.00 0.00 3 inch open 0.00 0.00 0.00 0.00 E 140 readings: mr/hr Gross lodine on Silver Zeolite eart: Concentration: sample size Icuft 5 cu it 15 cu ft i mi 1.64E-20 1 mile 0.00 0.00 0.00 2mi 1.47E-20 2 mile 0.00 0.00 0.00
$ mi 6.75E-21 5 mile 0.00 0.00 0.00 10 mi 3.26E-21 10 mile 0.00 0.00 0.00 Controller Only Don't divulge E-140 readings: mr/hr on Particulate cart:
sample size I cu ft 5 cu ft 15 cu ft I mile 0.00 0.00 0.00 2 mile 0.00 0.00 0.00 5 mile 0.00 0.00 0.00 10 mile 0.00 0.00 0.00 for DRD dose assignment use the following: Dose rate 1 mile 2 mile 5 mile 10 mile per minute 0.00 0.00 0.00 0.00 in plume: mr i Donnwand Surver Team CONTROLLER data Page 9.1 ^' C:. . tEXER\ SECT 7-11.WP5 l
... . . _ . ._~ ._. . - _ . .- - . . . - -
96 DW.X LS Time- 830 Off Site Survey Sheets Centerline Data for edges: use 10% Current plant release rate: 4.83E+ 00 uCi/>ee N.G. l Direct radiation :snr/hr 1 mile 2 male 5 mile 10 mile j i 3 feet closed 0.00 0.00 0.00 0.00 3 feet open 0.00 0.00 0.00 0.00 3 inch closed 0.00 0.00 0.00 0.00 3 inch open 0.00 0.00 0.00 0.00 E.I40 readings: mrthr
- Gross lodine on Silver Zeolite eart
- Concentration
- sample size Icuft 5 cu tt 15 cu ft i mi 1.68E-20 I mile 0.00 0.00 0.00 2mi 1.61E-20 2 mile 0.00 0.00 0.00 5 mi 6.75E-21 5 mile 0.00 0.00 0.00 10 mi 3.26E 21 10 mile 0.00 0.00 0.00 Controller Only Don't divulge E-140 readings: mr/hr l on Particulate cart: j sample size I cu ft 5 cu tt 15 cu ft I mile 0.00 0.00 0.00 2 mile 0.00 0.00 0.00 l 5 mile 0.00 0.00 0.00 10 mile 0.00 0.00 0.00 for DRD dose assignment use the following:
Dose rate i mile 2 mile 5 nule 10 nule per minute 0.00 0.00 0.00 0.00 in plume: mr ^ Downwind Survey Team CONTROLLER data Page 9. l-3 C:. . < EXER \SEC77-11. WP5
96DW.XLS I I Ti me - 8-15 Off Site Sursey Sheets Centerline Data for edges: uw 109 Current plant release rate: 4.32E+00 uCiiw N.G. [ Direct radiation :mr/hr i nule 2 mile 5 mile 10 mile l 3 feet closed 0.00 0.00 0.00 0.00 3 feet open 0.00 0.00 0.00 0.00 3 inch closed 0.00 0.00 0.00 0.00 3 inch open 0.00 0.00 0.00 0.00 E-140 reading <: mr/hr Gross lodine on Silver Zeolite eart: Concentration: sample siu !cuft 5 cu ft 15 cu ft 1 mi 1.50E-20 I mile 0.00 0.00 0.00 l 2mi 1.65E-20 2 mile 0.00 0.00 0.00 ' 5 mi f.75E-21 5 nule 0.00 0.ou 0.00 10 mi 3.26E-21 10 mile 0.00 0.00 0.00 j 1 Controller Only Don't divulge E 140 readings: mr/hr i on Particulate cart: sample siu 1 cu ft 5 cu it 15 cu ft I mile 0.00 0.00 0.00 2 mile 0.00 0.00 0.00 5 mile 0.00 0.00 0.00 10 mile 0.00 0.00 0.00 for DRD dose assignment use the following-Dose rate I mile 2 mile 5 mile 10 mile per minute 0.00 0.00 0.00 0.00 in plume: mr Downairud Surver Team CONTROLLER data Page 9.1-J C:. . tEXER \ SECT ~' I L WP5
l l 96DW.XLS l l l Tinw. 900 ( Off Site Suney Sheets Centerline Data for edges: use 10% Current plant release rate: 4.32E +00 uCi/wc N.G. l Direct radiation :mr/hr 1 mile 2 mile 5 mile 10 nule l 3 feet - closed 0.00 0.00 0.00 0.00 3 feet open 0.00 0.00 0.00 0.00 3 inch closed 0.00 0.00 0.00 0.00 3 inch open 0.00 0.00 0.00 0.00 E 140 readings: mr/hr Gross lodine on Silver Zeohte eart: Concentration: sample size Icuft 5 eu ti 15 cu ft I mi 1.50E-20 l mile 0.00 0.00 0.00 2mi 1.48E 20 2 mile 0.00 0.00 0.00 5 mi 6.75E-21 5 mile 0.00 0.00 0.00 10 mi 3.26E-21 10 nule 0.00 0.00 0.00 Controller Only Don't divulge E-140 readings: mr/hr on Particulate cart: sample siu ! cu ft 5 cu ft 15 cu ft I mile 0.00 0.00 0.00 2 mile 0.00 0.00 0.00
$ mile 0.00 0.00 0.00 10 mile 0.00 0.00 0.00 for DRD dose assignment use the following:
Dose rate 1 mile 2 mile 5 mile 10 mile per minute 0.00 0.00 0.00 0.00 in plume: mr Downwind Sunty Team CONTROLLER data Pa::e 9.1.9 C:. \ EXER tSECT7-II. WP5
. ~ . _ _ . . _ . _. .. .. _- _- . . . . - - . _ . _ - - .- .
96 DW.XLS Time. 915 Of f Site Surs ey Sheets Centerline Data for edees: use 10% Current plant release rate: 4.32E +00 uCusee N.G. [ Direct radiation :mr/hr i mile 2 mile 5 mile 10 mile l 3 feet closed 0.00 0.00 0.00 0.00 3 feet open 0.00 0.00 0.00 0.00 3 inch closed 0.00 0.00 0.00 0.00 3 inch open 0.00 0.00 0.00 0.00 E-140 readin p: mr<hr Gross lodine on Silver Zeolite eart: Concentration: sample size I cu ft 5 cu ti 15 cu et I mi 1.50E-20 i mile 0.00 0.00 0.00 2mi 1.48E-20 2 mile 0.00 0.00 0.00 l 5 mi 7.39E-21 5 mile 0.00 0.00 0.00 10 mi 3.26E-21 10 mile 0.00 0.00 0.00 Controller Only Don't divulge E 140 readings: mr/hr on Particulate cart: sample size I cu ft 5 cu tt 15 cu it I mile 0.00 0.00 0.00 2 mile 0.00 0.00 0.00 5 mile 0.00 0.00 0.00 10 mile 0.00 0.00 0.00 for DRD dose assignment use the following: Dose rate i mile 2 mile 5 mile 10 nule per minute 0.00 0.00 0.00 0.00 in plume: mr l i l l \ Downwind Survey Team CONTROLLER Jara Page 9.16 C ' EXER SECT 7-11.w!'! l l l
96DW.XLS Time: 930 Oft' Site Survey Sheets Centerline Data for edees: use 109 l l Current plant release rate: 4.32E+00 uCi/see N.G. l Direct radiation :mr/hr i mile 2 mile 5 mile 10 mile l l 3 feet closed 0.00 0.00 0.00 0.00 i 3 feet open 0.00 0.00 0.00 0.00 j 3 inch closed 0.00 0.00 0.00 0.00 3 inch open 0.00 0.00 0.00 0.00 E-140 readmp: mr/hr Gross lodine on Silver Zeohte art-. I Concentration: sample size I cu tt 5 cu tt 15 cu ft ) I mi 1.50E-20 i mile 0.00 0.00 0.00 2mi 1.48E-20 2 mile 0.00 0.00 0.00 5 mi 7.58 E-21 5 mile 0.00 0.00 0.00 10 mi 3.26E 21 10 mile 0.00 0.00 0.00 Controller Only Don't divulge E-140 readings: mr/hr on Particulate cart: sample size I cu ft 5 cu tt 15 cu ft I mile 0.00 0.00 0.00 2 mile 0,00 0.00 0.00 l 5 mile 0.00 0.00 0.00 10 mile 0.00 0.00 0.00 for DRD dose assignment use the followind: Dose rate i nule 2 mile 5 mile 10 nule per minute 0.00 G.00 0.00 0.00 in plume: mr Downumi Suncy Thom CONTROLLER data Page 9.1 ' C:. . \ EXER; SECT 7 II. V.'P5
96DW.X LS I l l l 1 Time: 945 Off Site Survey Sheets Centerline Data for edees: use 109 l Current p' ant release rate: 4.32E+00 uCi/see N.G. l l l radiation :mr/hr I mile 2 mile 5 mile 10 mile l l Direct 3 feet closed 0.00 0.00 0.00 0.00 l 3 feet open 0.00 0.00 0.00 0.00 3 inch closed 0.00 0.00 0.00 0.00 3 inch open 0.00 0.00 0.00 0.00 E-140 readmg<: mr/hr Gross lodine on Silver Zeolite eart: I l Concentration: sample size I cu ft 5 cu tt 15 cu ft I mi 1.50E 20 l' mile 0.00 0.00 0.00 2mi 1.48E-20 2 mile 0.00 0.00 0.00 5 mi 6.78E-21 5 mile 0.00 0.00 0.00 10 mi 3.26E-21 10 mile 0.00 0.00 0.00 j 1 l Controller Only Don't divulFe E 140 readmgs: mr/hr l on Particulate cart: sample size I cu ft 5 cu ft 15 cu ft I mile 0.00 0.00 0.00 2 mile 0.00 0.00 0.00 5 mile 0.00 0.00 0.00 10 mile 0.00 0.00 0.00 l l i for DRD dose assignment l use the following: Dose rate 1 mile 2 mile 5 mile 10 mile per minute 0.00 0.00 0.00 0.00 in plume: mr l l l l Downwind Survey Teant CONTROLLER data Pace 915 C: 1 EXER 1 SECT 7 il. H'PS
96 DW.XLS Time: 1000 Of f Site Survey Sheets Centerline Data for edges: use IOW Current plant release rate: 4.32E+00 uCi/see N.G. l l Direct radiation :mr/hr I mile 2 nule 5 mile 10 mile l 3 feet closed 0.00 0.00 0.00 0.00 l 3 feet open 0.00 0.00 0.00 0.00 l 3 inch closed 0.00 0.00 0.00 0.00 3 inch open 0.00 0.00 0.00 0.00 E-140 readings: mr/hr Gross lodine on Silver Zeolite eart: Concentration: sample size I cu t's 5 cu tt 15 cu ft I mi 1.50E 20 i mile 0.00 0.00 0.00 2mi 1.48E-20 2 mile 0.00 0.00 0.00 5 mi 6.78E-21 5 mile 0.00 0.00 0.00 10 mi 3.26E-21 10 mile 0.00 0.00 0.00 Controller Only Don't divulge E 140 readings: mr/hr on Particulate cart: sample size I cu ft 5 cu ft 15 cu ft 1 mile 0.00 0.00 0.00 2 mile 0.00 0.00 0.00 5 mile 0.00 0.00 0.00 10 mile 0.00 0.00 0.00 for DRD dose assignment use the following: Dose rate I mile 2 mile 5 mile 10 mile per minute 0.00 0.00 0.00 0.00 in plume: mr Downwimi Surwv Team CONTROLLER data Page 9.19 C:. ! EXER tSECT7-II. WP5
. . - . . ., . . . _ = - . ~ . - - - . ._ - . - . - . ... .~- . - .
96DW.XLS Time: 1015 Off Site Survey Sheets Centerline Data for edges: use 10% Current plant re. case rate: 4.32E +00 uCi/see N.G. radiation :mrlhr 1 mile 2 mile 5 mile 10 mile l l Direct 3 feet closed 0.00 0.00 0.00 0.00 3 feet open 0.00 0.00 0.00 0.00 3 inch closed 0.00 0.00 0.00 0.00 3 inch open 0.00 0.00 0.00 0.00 l l l E-140 readings. mrihr 1 Gross lodine on Silver Zeolite art Concentration: sample size I cu ft 5 cu tt 15 cu ft I mi 1.50E-20 1 mile 0.00 0.00 0.00 , j 2mi 1.48E-20 2 mile 0.00 0.00 0.00 l 5 mi 6.78E-21 5 mile 0.00 0.00 0.00 10 mi 3.57E-21 10 mile 0.00 0.00 0.00 Controller Only divulge E 140 readings: mr/hr _ Don't on Particulate cart: sample size I cu ft 5 cu ft 15 cu ft I mile 0.00 0.00 0.00 2 mile 0.00 0.00 0.00 5 mile 0.00 0.00 0.00 10 mile 0.00 0.00 0.00 l 1 for DRD dose assignment use the following: Dose rate 1 mile 2 mile 5 mile 10 mile per minute 0.00 0.00 0.00 0.00 in plume: mr Paec 9.1 10 C:. . (EXER \ SECT 7-II. WP5 l DownwinJ Surver Team CONTROLLER data l i
96DW.XLS Time 1030 Olf Site Survey Sheets Centerline Data for edges: use 109 Current plact release rate: 4.32E+00 uCi/we N.G. ht 3 feet radiation :mr/hr closed 1 mile 0.00 2 mile 0.00 5 mile 0.00 10 mile 0.00 l 3 feet open 0.00 0.00 0.00 0.00 3 inch closed 0.00 0.00 0.00 0.00 3 inch open 0.00 0.00 0 00 0.00 E-140 re dings: mrihr Gross lodine on Silver Zeolite art: Concentration: sample size I cu tt 5 cu tc 15 cu ft 1.50E-20 1 mile 0.00 0.00 0.00 I mi 2mi 1.48E-20 2 mile 0.00 0.00 0.00 5 mi 6.78E 21 5 mile 0.00 0.00 0.00 10 mi 3.66E 21 10 mile 0.00 0.00 0.00 Controller Only Don't divulge E-140 readings: mr/hr on Particulate cart: sample size I cu ft 5 cu ft 15 cu ft I mile 0.00 0.00 0.00 2 mile 0.00 0.00 0.00 5 mile 0.00 0.00 0.00 10 mile 0.00 0.00 0.00 for DRD dose assignment use the following: rate I mile 2 mile 5 mile 10 mile Dose per minute 0.00 0.00 0.00 0.00 in plume: mr I l l C .EXERiSEC77-11. WP5 ' Downwind Survey Team CONTROLLER dava Page 9.1-1l l
l l 96DW.XLS , Time 1015 Off Site Survey Sheets Centerline Data for edges: uw 10% Current plant release rate: 4.32E +00 uC see N.G. [Dirut radiation :mr/hr i mile 2 nule 5 mile 10 mile l 3 feet closed 0.00 0.00 0.00 0.00 3 feet open 0.00 0.00 0.00 0.00 l 3 inch closed 0.00 0.00 0 00 0.00 3 inch open 0.00 0.00 0.W 0.00 E-140 reading : mr/hr I Gross lodine on Silver Zeolite cart: Concentration: sample size I cu ft 5 cu rt 15 cu ft I mi 1.50E 20 t mile 0.00 0.00 0.00 2mi 1.48E-20 2 mile 0.00 0.00 0.00 5 mi 6.78E-21 5 mile 0.00 0.00 0.00 10 mi 3.27E-21 10 mile 0.00 0.00 0.00 Controller Only Don't divulge E-140 readings: mr/hr l on Particulate cart: sample size I cu ft 5 cu ft 15 cu ft I mile 0.00 0.00 0.00 l 2 mile 0.00 0.00 0.00 ! 5 mile 0.00 0,00 0.00 ! 10 mile 0.00 0.00 0.00 for DRD dose assignment use the following: Dose rate i mile 2 mile 5 mile 10 mile per minute 0.00 0.00 0.00 0.00 in plume: mr r r Downwind Survey Team CONTROLI.ER Jara Page 9.1-12 C:. . \EXERiSECT7-11. WP9 I r i
96Dw.XLS Time 1100 Off Site Survey Sheets s Centerline Data for edges: use 10% Current plant release . rate: 4.31E +00 uCi/see N.G. [ Direct radiation :mr/hr I nule 2 mile 5 nule 10 mile l 3 feet closed 0.00 0.00 0.00 0.00 3 feet open 0.00 0.00 0.00 0.00 3 inch closed 0.00 0.00 0.00 0.00 3 inch open 0.00 0.00 0.00 0.00 J E-140 readings: mrihr ; Gross lodine on Silver Zeolite eart: l Concentration: wmple size I cu ft 5 cu tt 15 cu t't l 1 mi 1.50E-20 1 mile 0.00 0.00 0.00 2mi 1.48 E-20 2 mile 0.00 0.00 0.00 5 mi 6.78E-21 5 mile 0.00 0 00 0.00 10 mi 3.27E-21 10 mile 0.00 0.00 0.00 Controller Only Don't div'ulce E-140 readings: mr/hr on Particulate cart: sample size I cu ft 5 cu t1 15 cu ft l t mile 0.00 0.00 0.00 2 mile 0.00 0.00 0.00 5 mile 0.00 0.00 0.00 10 mile 0.00 0.00 0.00 for DRD dose assignment use the following: Dose rate 1 mile 2 mile 5 nule 10 mile per minute 0.00 0.00 0.00 0.00 in plume: mr Downwund Survey Tearn CONTROLLER d<ua Page 9.1 l) C:. \ EXER!SL'CT7-11. WP5
l 96D)V.XLS f i Tinw. Ii15 Off Site Sun e.s Sheets . i 1 Centerline Data for edees: use 109 Current plant relea.w rate: 4.05E +00 uCow N.G. l Direct radiation :mr/hr i mile 2 mile 5 mile 10 mile l 3 feet closed 0.00 0.00 0.00 0.00 3 feet open 0.00 0.00 0.00 0.00 i 3 inch closed 0.00 0.00 0.00 0.00 3 inch open 0.00 0.00 0.00 0.00 i E-140 readings: mr/hr Gross lodine on Silver Zeolite eart: Concentration: umple size I cu ft 5 cu tt 15 cu ft I mi 1.41 E-20 1 mile 0.00 0.00 0.00 2mi 1.47E 20 2 mile 0.00 0.00 0.00 l 5 mi 6.78 E-21 5 mile 0.00 0.00 0.00 10 mi 3.27E-21 10 nule 0.00 0.00 0.00 Controller Only Don't divulge , E- 140 readings: mr/hr j on Particulate cart: l sample size I cu ft 5 cu ft 15 cu ft Irmle 0.00 0.00 0.00 l 1 2 mile 0.00 0.00 0.00 5 mile 0.00 0.00 0.00 10 mile 0.00 0.00 0.00 for DRD dose assignment use the foilowmg: Dose rate 1 mile 2 mile 5 nule 10 mile per minute 0.00 0.00 0.00 0.00 in plume: rar l l l Downwimi Sunry Dam CONTROLLER data Pa.:e 9 I-lJ . \ EXER aSECT7-1I. WP5
.. . . . - - . - _ _ - . - _ _ . . = . . - _ . - . _ . ~ . . - . . . _ - . - _ -__ -
96DW.X LS Time. I130 Off Site Sursey Sheets l Centerline Data for edees: use 109 ; l l Current plant release rate: 4.05E+00 uCi/see N.G. I 1 i l Direct radiation :mr/hr 1 mile 2 mile 5 nule l0 mile l 3 feet closed 0.00 0.00 0.00 0.00 3 feet open 0.00 0.00 0.00 0.00 l 3 inch closed 0.00 0.00 0.00 0.00 3 inch open 0.00 0.00 0.00 0.00 i l E 140 readmps: mr/hr l Gross lodine on Silver Zeolite eart: ! Concentration: sample size i cu ft 5 cu tt 15 cu ft I mi 1.41 E-20 I inile 0.00 0.00 0.00 2mi 1.38E 20 2 mile 0.00 0.00 0.00 i 5 mi 6.78E 21 5 mile 0.00 0.00 0.00 l 10 mi 3.27E-21 10 mile 0.00 0.00 0.00 Controller Only Don't divulge E 140 readmgs: mr/hr I on Particulate cart: sample size I cu ft 5 cu ft 15 cu ft I mile 0.00 0.00 0.00 l 2 mile 0.00 0.00 0.00 l l 0.00 l 5 mile 0.00 0.00 10 mile 0.00 0.00 0.00 l for DRD dose assignment use the following: l Dose rate 1 mile 2 mile 5 mile 10 mile per minute 0.00 0.00 0.00 0.'.X) l in plume: mr l l l l i Downwinal Sunn Team CONTROLLER data Paec 9.115 C. ' EXER SECT 7-11. WP! 1 -
~ . - . . . - ._.- . .-- . _ . . - . .. . .-. . . - , - .
1 l 96DW.XLS Time: 1145 Off Site Survey Sheets Centerline Data for edges: use 10% Current plant release rate: 8.00E-01 uQisee N.G. l l l Direct radiation :mr/hr i nule 2 mile 5 mile 10 mile l l 3 feet closed 0.00 0.00 0.00 0.00 3 feet open 0.00 0.00 0.00 0.00 [ 3 inch closed 0.00 0.00 .0.00 0.00 1 ! 3 inch open 0.00 0.00 0.00 0.00 i l l E-140 readings: mr/hr l Gross lodine on Silver Zeolite cart: Concentration: sample size I cu ft 5 cu it 15 cu ft I mi- 2.78E-21 1 mile 0.00 0.00 0.00 2mi 1.38E-20 2 mile 0.00 0.00 0.00 5 mi 6.78E 21 5 mile 0.00 0.00 0.00 10 mi- 3.27E 21 10 mile 0.00 0.00 0.00 Controller Only Don't divulge E-140 readings: mr/hr j on Particulate cart: sample size I cu ft 5 cu ft 15 cu ft I mile 0.00 0.00 0.00-2 mile 0.00 0.00 0.00 l 5 mile 0.00 0.00 0.00 10 mile 0.00 0.00 0.00 for DRD dose assignment use the following: Dose rate I mile 2 mile 5 mile 10 mile per minute 0.00 0.00 0.00 0.00 in plume: mr Paec 9.1-10 C:. . ! EXER:SEC77-1I. WP5 l Downwimi Surrn Taim CONTROL.LER data
96DW.XLS Time: 1200 Off Site Survey Sheets Centerline Data for edges: use IOM Current plant release rate: 6.00E-02 uC /see N.G. [ Direct radiation :mr/hr I mile 2 mile 5 mile 10 mile l 3 feet closed 0.00 0.00 0.00 0.00 3 feet open 0.00 0.00 0.00 0.00 3 inch closed 0.00 0.00 0.00 0.00 3 inch open 0.00 0.00 0.00 0.00 E 140 readmp: mrihr Gross Iodine on Silver Zeolite eart: Concentration: sample size I cu ft 5 cu tt 15 cu ft I mi 2.08E-22 1 mile 0.00 0.00 0.00 2mi 2.73E-21 2 mile 0.00 0.00 0.00 5 mi 6.76E-21 5 mile 0.00 0.00 0.00 10 mi 3.27E 21 10 mile 0.00 0.00 0.00 Controller Only Don't divulge E-140 readings: mr/hr on Particulate cart: sample size ! cu ft 5 'cu ft 15 cu ft I mile 0.00 0.00 0.00 2 mile 0.00 0.00 0.00 5 mile 0.00 0.00 0.00 10 mile 0.00 0.00 0.00 for DRD dose assignment use the following: Dose rate I mile 2 mile 5 mile 10 mile per minute 0.00 0.00 0.00 0.00 in plume: mr i Downwimi Sunxy Team CONTROLLER data Pat;c 9. l-l ~ C: . iEXER; SECT 7-II. WP5 l i
96DW.XLS l Time: 1215 Off Site Suney Sheets Centerline Data for edges: use 10 9 Current plant release rate: 5.28E + 04 uC /see N.G. l Direct radiation :mr/hr ! rmle 2 mile 5 nule 10 mile l 3 feet closed 0 10 0.00 0.00 0.00 3 feet open 0.20 0.00 0.00 0.00 3 inch closed 0.10 0.00 0.00 0.00 3 inch open 0.20 0.00 0.00 0.00 E-140 readings: mr hr Gross lodine on Silver Zeolite eart: i Concentration: sample size Icuft 5 cu it 15 cu ft I mi 1.83E 16 I mile 0.00 0.00 0.00 2mi 2.05E-22 2 mile 0.00 0.00 0.00 5 mi 6.35E-21 5 mile 0.00 0.00 0.00 10 mi 3.27E-21 10 mile 0.00 0.00 0.00 Controller Only ) Don't divulge E-140 readings: mr/hr on Particulate cart: sample size I cu ft 5 cu ft 15 cu ft I mile 0.00 0.00 0.00 2 mile 0.00 0.00 0.00
$ mile 0.00 0.00 0.00 10 mile 0.00 0.00 0.00 for DRD dose assignment use the following:
Dose rate I mile 2 nule 5 mile 10 mile per minute 0.02 0.00 0.00 0.00 in plume: mr l Dawnwon.1 Sung Tc.mo CONTROLLER data Page 91 15 C. ' EXER' SECT 7-II. WP5 l
l 96DW.XLS l Time: 1230 Of f Site Surves Sheets ! Centerline Data for edges: use 109 i Current plant release rate: 9.78E +05 uCalsee N.G. l Direct radiation :mr/hr i mile 2 mile 5 mile 10 mile l' l 3 feet closed 1.45 0.10 0.00 0.00 3 feet open 2.90 0.19 0.00 0.00 3 inch closed 1.45 0.10 0.00 0.00 3 inch open 2.90 0.19 0.00 0.00 l E 140 readmp: mrihr Gross lodine on Silver Zeolite Eart: Concentration: sample size I cu ft 5 eu tt 15 cu ft I mi 3.40E-15 'l mile 0.00 0.00 0.00 2mi 1.80E 16 2 mile 0.00 0.00 0.00 5 mi 6.35E-21 5 mile 0.00 0.00 0.00 10 mi 3.27E-21 10 mile 0.00 - 0.00 0.00 Controller Only Don't divulge E-140 readmgs: mr/hr on Particulate cart: sample size I cu ft 5'cu ft 15 cu ft I mile 0.00 0.00 0.00 2 mile 0.00 0.00 0.00 5 mile 0.00 0.00 0.00 10, mile 0.00 0.00 0.00 for DRD dose assignment use the following: Dose rate I mile 2 nule 5 mile 10 mile per minute 0.02 0.02 0.00 0.00 in plume: mr C EXER; SECT 711. WP5 l Dawnaind Suncv Team CONTROLLER d.ua Paee 9.1-19
l: I I 96DW.XLS 1 l ! I Time- 1245 Off Site Survey Sheets l Centerline Data ) I for edges: uw 109 ! Current plant release rate: 7.94E +05 uCieses N.G. l l l l Direct radiation :mr/hr i nule 2 mile 5 mile 10 mile l !. 3 feet closed 1.18 1.43 0.00 0.00 3 feet open 2.35 2.85 0.00 0.00 l 3 inch closed 1.18 1.43 0.00 0.00
- 3 inch open 2.35 2.85 0.00 0.00 I
l E 140 readinp: mr/hr , 1 Gross lodine on Silver Zeohte cart. Concentration: sample size I cu ft 5 cu :: 15 cu tt I mi 2.76E-15 I mile 0.00 0.00 0.00 l 2mi 3.34E 15 2 mile 0.00 0.00 0.00
$ mi 1.25E 21 5 mile 0.00 0.00 0.00 ;
10 mi 3.27E-21 10 mile 0.00 0.00 0.00 l Controller Only Don't divulge E 140 readings: mr/hr on Particulate cart: sample size I cu ft 5 cu ft 15 cu ft I mile 0.00 0.00 0.00
' 2 mile 0.00 0.00 0.00 5 mile 0.00 0.00 0.00 l 10 mile 0.00 0.00 0.00 l
1 i for DRD dose assignment use the following: Dose rate I mile 2 mile 5 mile 10 mile per minute 0.01 0.02 0.00 0.00 in plume: mr l l l i I i l Page 9.1-20 C:. EXER'. SECT 711. WP5 Downwini Survo Team CONTROLLER <!ata
-.. .- - - . = . . . _ . . -
l 96DW.XLS l l Tmw 1300 Off Site Survey Sheets l Centerline Data for edges: uw 109 I Current plant release rate: 5.51E +05 uCi see N.G. l l l l Direct radiation :mr/hr 1 mile 2 mile 5 mile 10 mile l 3 feet closed 0.82 1.16 0.00 0.00 3 feet open 1.63 2.31 0.00 0.00 l 3 inch closed 0.82 1.16 0.00 0.00 3 inch open 1.63 2.31 0.00 0.00 i l l E 140 reaJings: mrihr l Gross lodine on Silver Zeolite eart: Concentration: sample size Icutt 5 cu it 15 cu ft 1 mi 1.91E-15 I mile. 0.00 0.00 0.00 l l 2mi 2.71E-15 2 mile 0.00 0.00 0.00 l 5 mi 9.41 E-23 5 mile 0.00 0.00 0.00 10 mi 3.26E 21 10 mile 0.00 0.00 0.00 Controller Only Don't divulge E-140 readings: mr/hr on Particulate eart: sample size I cu ft 5 cu ft 15 cu ft j i mile 0.00 0.00 0.00 2 mile 0.00 0.00 0.00 5 mile 0.00 0.00 0.00 10 mile 0.00 0.00 0.00 l for DRD dose assignment use the following: l Dose rate I mile 2 mile 5 nule 10 nule per minute 0.01 0.01 0.00 0.00 in plume: nu i i i Downwind Survey Team CONTROLLER data Pa::e 9.1-:1 C: . ; EXER; SECT 7-11. WP5
96 DW..X LS Tune 1315 Off Site Suney Sheets I Centerline Data for edges: use 109r Current plant release rate: 3.82E + 05 uCue N G. ) l Direct radiation :mr/hr i mile 2 mile 5 mile 10 mile l l 3 feet closed 0.57 0.80 0.04 0.00 ) 3 feet open 1.13 1.61 0.09 0.00 3 inch closed 0.57 0.80 0.04 0.00 3 inch open 1.13 1.61 0.m 0.00 E 140 reaJings mrihr Gross lodine on Silver Zeohte eart: Concentration: sample size I cu tt 5 eu ti 15 cu ft I mi 1.33E-15 1 mile 0.00 0.00 0.00 2mi 1.88 E-15 2 mile 0.00 0.00 0.00 5 mi 8.28E 17 5 mile 0.00 0.00 0.00 10 mi 3.07E-21 10 mile 0.00 0 00 0.00 Controller Only Don't divulge E-140 readinp: mr/hr on Particulate cart: sample size I cu ft 5 cu ft 15 cu ft I mile 0.00 0.00 0.00 2 mile 0.00 0.00 0.00 5 mile 0.00 0.00 0.00 10 mile 0.00 0.00 0.00 1 for DRD dose assignment use the following: Dose rate I nule 2 mile 5 mile 10 mile per minute 0.00 0.01 0.01 0.00 in plume: mr I i l l l ! Downwimi Surn v Team CONTROLLER <!ata Pa;:e 9 l-2: C. . . tEXER : SECT 7-II. WP.* l l 1
l 96DW.X LS Time: 1330 l Off Site Survey Sheets Centerline Data for edges: use 109 Current plant release rate: 6.19E +05 uCi see N.G. l Direct radiation :mr/hr i mile '2 m.lj 5 nule 10 mile l 3 feet closed 0.61 1.05 0 65 0.00 3 feet open 1.22 2.10 1.30 0.00 3 inch closed 0.61 1.05 0.65 0.00 t 3 inch open 1.22 2.10 1 30 0.00 E 140 readinp: mr/hr Gross lodine on Silver Zeolite cart: l Concentration: sample size i eu ft 5 eu ti 15 cu ft l 1 mi 2.15E-15 I mile 0.00 0.00 0.00 l 2mi 2.46E 15 2 mile 0.00 0.00 0.00 , 5 mi 1.53E-15 5 mile 0.00 0.00 0.00 ' 10 mi 3.07E 21 10 mile 0.00 0.00 0.00 l l Controller Only Don't divulge E-140 readmp: mr/hr on Particulate cart: I sample size I cu it 5 eu tt 15 cu ft I mile 0.00 0.00 0.00 2 mile 0.00 0.00 0.00 5 mile 0.00 0.00 0.00 l 10 mile 0.00 0.00 0.00 ! for DRD dose assignment ! use the following: l Dose rate I mile 2 mile 5 mile 10 mile per. minute 0.01 0.01 0.01 0.00 l m plume: mr i ]
- Dou nwind Suruy Team CONTROLLER data Pace 9 I 'i C: iEXER;SEC77 l1 WP5 l
l 06DW.XLS Time: 1345 Off Site Survey Sheets Centerline Data for edces: use 109 Current plant release rate: 5.25E +05 uCi see .N.G . l Direct radiation :mr/hr I mile 2 mile 5 mile 10 mile l l 3 feet closed 0.52 0.60 0.66 0.00 , 3 feet open 1.04 1.20 1.32 0.00 l l 3 inch closed 0.52 0.60 0.66 0.00 3 inch open 1.04 1.20 1.32 0.00 1 l E 140 reading- mr/hr Gross lodine on Silver Zeolite cart. 1 Concentration: sample size Icutt 5 cu tt 15 cu ft l 1 mi 1.82E 15 I mile 0.00 0.00 0.00 l 2mi 2.1 IE-15 2 mile 0.00 0.00 0.00 ; 5 mi 1.55E-15 5 mile 0.00 0.00 0.00 l 10 mi 6.06E-22 10 mile 0.00 Olo 0.00 Controller Only Don't divulge E-140 readmps: mr/hr f on Particulate cart: sample size I cu ft 5 eu tt 15 cu ft I mile 0.00 0.00 0.00 2 nule 0.00 0.00 0.00 5 mile 0.00 0.00 0.00 10 mile 0.00 0.00 0.00 for DRD dose assignment use the following: Dose rate i nule 2 nule 5 tmle 10 mile per minute 0.01 0.01 0.01 0.00 in plume; mr Don naind Suna Team CONTR3LLER Jata P:a
- l :a C. EXER. SECT 7-11. WPS
I 96DW.XLS 1 l l l Time: 1400 < Off Site Survey Sheets l Centerline Data for edges: use 104 , l l Current . plant release rate: 4.48E + 05 uCi see N.G. l l Direct radiation :mr/hr Irmle 2 mile 5 rmle 10 nule l 3 feet closed 0.44 0.51 0.56 0.00 3 feet open 0.89 1.02 1.13 0.00 3 inch closed 0.44 0.51 0.56 0.00 3 inch open 0.89 1.02 ! . l .1 0.00 l l E 140 readinp: mr/hr l Gross lodine on Silver Zeolite cart: Concentration: sample size I cu 1: 5 cu it 15 cu ft I mi 1.56E-15 1 mile 0.00 0.00 0.00 2mi 1.79E-15 2 mile 0.00 0.00 0.00 j
$ mi 1.32E-15 5 mile 0.00 0.00 0.00 10 mi 4.54E-23 10 mile . 0.00 0 uo 0.00 Controller Only l Don't divulce E140 readmp: mr/hr on Particulate cart: .
sample size Icuit 5 eu it 15 cu h I mile 0.00 0.00 0.00 j 2 mile 0.00 0.00 0.00 5 mile 0.00 0.00 0.00 10 mile 0.00 0.00 0.00 for DRD dose assignment use the following:
)
Dose rate I mile 2 mile 5 mile 10 mile l per minute 0.01 0.01 0.01 0.00 l m plume: mr i l l I i l I i l Dowm,m.I Surver Team CONTROLLER J.na P.; , 9 l-:! C: TEXER SECT 7-11. tLP! I
i 96DW XLS Time: 1415 l Off Site Survey Sheets I i Centerline Data for edges: use 109 Current plant release rate: 3.83E-05 uCi see N.G. l Direct radiation :mr/hr i mile 2 mile 5 nule 10 mile l 3 feet closed 0.38 0.44 0.48 0.19 3 feet open 0.76 0.87 0.96 0.39 3 inch closed 0.38 0.44 0.48 0.19 3 inch open 0.76 0.87 0.96 0.39 E 140 readinp: mr/hr Gross lodine on Silver Zeolite cart: Concentration: sample size Icuft 5euit 15 cu ft I mi. 1.33 E-15 I mile 0.00 0.00 0.00 2mi 1.53E-15 2 mile 0.00 0.00 0.00 5 mi 1.13E-15 5 mile 0.00 0.to 0.00 10 mi 3.63 E- 16 10 mile 0.00 vw 0.00 Controller Only Don't divulge E-140 readinp: mc/hr on Particulate cart: sample size I cu ft 5 cu tt 15 cu ft I mile 0.00 0.00 0.00 2 mile 0.00 0.00 0.00 5 mile 0.00 0.00 0.00 10 mile 0.00 0.00 0.00 for DRD dose assignment use the following: Dose rate I mile 2 nule 5 mile 10 mile per minute 0.01 0.01 v.00 0.01 in plume: mr Don nwnd Surny Te.um CONTROLLER d.t:.s P.ue e 91.:o r- EXER SECT 7-11. t\P3
96DW.XLS i i l Time: 1430 Off Site Survey Sheets i Centerline Data i for edges: use 107r i Current plant release rate: 3.28E +05 uCiiee N.G. }
, l Direct radiation :mr/hr . I nule 2 mile 5 mile 10 mile l I 3 feet closed 0.32 0.37 0.25 0.31 3 feet open 0.65 0.74 0.55 0.63 i 3 inch closed 0.32 0.37 0.2S 0.31 3 inch open. 0.65 0.74 0.55 0.63 i + E 140 reaJm; *: mr/hr Gross Iodine on Silver Zeohte cart:
Concentration: sample size I cu tt 5 eu tt 15 cu ft I mi 1.14 E-15 I mile 0.00 0.00 0.00 2nu 1.3 I E-15 2 mile 0.00 0.00 0.00 j 5 mi 9.71 E-16 5 mile 0.00 0.00 0.00 10 mi 7.38 E-16 10 mile 0.00 v uv 0.00 3 Controller Only l Don't -divulge E-140 readinp: mr/hr on Particulate cart: sample size ! cu ft 5 eu tt 15 cu ft I mile 0.00 0.00 0.00 2 mile 0.00 0.00 0.00 5 mile 0.00 0.00 0.00 10 mile 0.00 0.00 0.00 l l 1 1 for DRD dose assignment l use the following: Dose rate ! mile 2 mile 5 nule 10 mile per minute 0.00 0.01 0.00 0.01 in plume: mr l Downwond Sung Tearn CON 7 ROLLER stata Pa.:e Y l 2 7 C FXER SWlT*lI HPE
. _ _ , - _ . _ . . . . _ _ - - . . -- - _ _ - - ~ - _. - , . - --
i 96DW.XLS Time: 1445 Off Site Survey Sheets Centerline Data for edges: use 10Si Current plant release rate: 2.79E-05 uCi see N.G. , ) l Direct radiation :mr/hr I mile 2 mile 5 mile 10 mile l 3 feet closed 0.28 0.32 0.23 0.32 3 feet open 0.55 0.64 0.47 0.64 3 inch closed 0.28 0.32 0.23 0.32 3 inch open 0.55 0.64 04' O.64 1 1 E 140 reaJings: mr/hr Gross lodine on Silver Zeolite cart: Concentration:
~
sample size I cu tt
~
, 5 eu tt 15 cu tt I mi 9.69E-16 I mile 0.00 0.00 0.00 2mi 1.12E 15 2 mile 0.00 0.00 0.00 5 mi 8.24E 16 5 mile 0.00 0.00 0.00 10 mi 7.47E 16 10 mile 0,00 0 Ou 0.00 Controller Only l Don't divulge E-140 readings: mr/hr on Particulate cart: sample size Icuit 5 eu tt 15 cu it I mile 0.00 0.00 0.00 2 mile 0.00 0.00 0.00 5 mile 0.00 0.00 0.00
'10 mile 0.00 0.00 0.00 for DRD dose assignment i
use the following: ! Dose rate 1 mile 2 mile 5 mile 10 mile per minute 0.00 0.00 0.00 0.00 in plume: mr s D<nennin.f Survn Team CONTROLLER alma Pace 0 I-:9 r. -
' EXER SErlT-iI WP5
96DW.XLS Time: 1500 Off Site Survey Sheets Centerline Data for edges: use 109 Current plant release rate: 2.39E-05 uCi see N.G. [ Direct radiation :mr/hr 1 mde 2 nule 5 mile 10 mile j 3 feet closed 0.24 0.27 0.20 0.27 3 feet open 0.47 0.54 0.40 0.54 1 3 inch closed 0.24 0.27 0.20 0.27 3 inch open 0.47 0.54 0.40 0.54 E-140 readmps: mr/hr Gross lodine on Silver Zeolite cart: Concentration: sample size I cu ft 5 cu tt 15 cu tt 1 1 mi 8.30E-16 1 nule 0.00 0.00 0.00 2mi 9.53E-16 2 mile 0.00 0.00 0.00 ) 5 mi' 7.03E 16 5 mde 0.00 0.00 0.00 l 10 mi 6. 38 E-16 10 nule 0.00 0.00 0.00 Controller Only Don't divulge E-140 readmgs: mr/hr on Particulate cart: sample size ! cu It 5 cu tt 15 cu ft I mile 0.00 0.00 0.00 2 mile 0.00 0.00 0.00 5 mile 0.00 0.00 0.00 10 mile 0.00 0.00 0.00 for DRD dose assignment use the following: Dose rate I mile 2 mile 5 mile 10 mile 1 per minute 0.00 0.00 0.00 0.00 in plume; mr Downwmd Surns Team CONTROLLER Jata Page 9.129 C. ' EXER \SEC7711 Wi"
- - . . . _ - _ - . . .. - - . - - - . ~ . . . = -
06DW.XLS t l Time: 1515 Off Site Survey Sheets Centerline Data for edges: use 109 Curretit plant release rate: 2.04E -05 uCi .see N.G. l Direct radiation :rnr/hr i mile 2 mile 5 mile 10 mile l 3 feet closed 0.13 0.23 0.17 0.23 l 3 feet open 0.25 0.46 0.34 0.46 3 inch closed O.I3 0.23 0.I? 0.23 3 inch open 0.25 0.46 0.14 0.46 l E-140 readinp. mrihr Gross lodine on Silver Zeolite eart: Concentration: sample size I cu ft 5 eu tt 15 cu tt l 1 mi 7.09E-16 1 mile 0.00 0.00 0.00 i 2mi 8.16E.16 2 mile 0.00 0.00 0.00 5 mi 6.01 E- 16 5 mile 0.00 0.00 0.00 i 10 mi 5.44E 16 to mile ' O.00 Oh0 0.00
- Controller Only
! Don't divulge E 140 readinp: mr/hr on Particulate cart: l sample size Icuit 5 eu tt 15 cu ft I nule 0.00 0.00 0.00 l 2 mile 0.00 0.00 0.00 ! 5 mile 0.00 0.00 0.00 l 10 mile 0.00 0.00 0.00 l l
- for DRD dose u.a enment use the followmg
Dose rate i nule 2 mile 5 mile 10 mile l per minute 0.00 0.00 0.00 0.00 in plume: mr l l l l l i ! Downww.i Sunev Team CON 1RO!.LER d.t'.t P.tv ') l-30 C- . EXER SECT ~-11 %I" l
l 96DW.XLS l. l l l Time- 1530 1 Off Site Survey Sheets l Centerline Data ! for edees: use 109 l Current plant release rate: 1.75E,05 uCi .see N.G. l Direct radiation :mr/hr i mile 2 mile 5 mile 10 mile l 3 feet - closed 0.11 0.12 0.15 0.13 3 feet open 0.22 0.25 0.29 0.27 3 inch closed 0.11 0.12 0.15 0.13 3 inch open 0.22 0.25 0 20 0.27 I E-140 reaJmps: mr/hr Gress lodine on Silver Zeolite cart: Concentration: sample size Icutt 5 eu tt 15 cu ft I mi 0.00E + 00 1 mile 0.00 0.00 0.00 2mi 6.97E-16 2 mile 0.00 0.00 0.00 J 5 mi 5.15 E-16 5 mile 0.00 0.tv 0.00 j 10 mi 4.69E-16 10 mile .0.00 0 -) 0.00 Controller Only Don't divulce E-140 reaJings: mr/hr I I on Particulate cart: sample size Icuit 5 eu tt 15 cu ft I mile 0.00 0.00 0.00 2 mile 0.00 0.00 0.00 5 mile 0.00 0.00 0.00 10 mile 0.00 0.00 0.00 1 1 for DRD dose assignment use the followine: 10 mile
)
Dose rate i mile 2 nule 5 mile per minute 0.00 0.00 0W 0.00 in plume: mr l l l lL>>. ros u>;.! Suney Te.un CONTROL.l.ER <tara P te e ') 1-3i r . . EXER SIT 771I WP5
w,.. + u-. --- > x .u - - s.a n ..--..a a w 96DW.XLS Time: 1545 Off Site Survey Sheets Centerline Data for edges: use 109 Current plant release rate: 1.49E + 05 uCi See N.G. l Direct radiation :mr/hr I mile 2 mile 5 nule 10 mile l 3 feet closed 0.09 -0.11 0.12 0.11 3 feet open 0.18 0.21 0.25 0.23 3 inch closed 0.09 0.11 0.12 0.11 3 inch open 0.I8 0.21 0.25 0.23 E-140 readings: mr/hr Gross lodine on Silver Zeolite eart: Concentration: sample size I cu ft 5 eu ti 15 cu tt I mi 0.00E + 00 I mile 0.00 0.00 0.00 2mi 0.00E + 00 2 mile 0.00 0.00 0.00 5 mi 4.36E-16 5 mile 0.00 0.00 0.00 10 mi 3.98E-16 10 mile ').00 0.00 0.00 Cc., troller Only Don't divulge E 140 readings: mr/hr or Particulate cars: sample size I cu ft 5 eu it 15 cu it I mile 0.00 0.00 0.00 2 mile 0.00 0.00 0.00 5 mile 0.00 0.00 0.00 10 mile 0.00 0.00 0.00 for DRD dose assignment use the following: Dose rate 1 mile 2 mile 5 mile 10 mile per minute 0.00 0.00 U.co 0.00 in plume: mr Downwinst Sure.n iYn ' 3 (Rt II.i.ER .l.u.t l'a .- V I .C C. EXEICSECT71l Win l i l t i
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9.2 Recovery, Re-Entry, Relocation The following material is provided to allow an integrated demonstration of the offsite objective
- for Recovery, Re-entry, Relocation by State and County emergency response agencies, i At 1530 during the plume phase of the scenario, a failure of Standby Gas Treatment is l postulated. This failure will provide plausible causation for an increase in the radioiodine and l particulate fraction of the release. This release will be simulated to continue until 2000 on the day of the plume phase. However, due to the late failure of SBGT, the release rate (particularly of iodines and particulates (which would have either plated out or been absorbed by the SBGT l charcoal beds) will already have decreased significantly. Therefore,forpurposes ofdeposition l only the data which follows includes deposition data for a radioactive release mix which includes radioiodines and particulates as if they had been present from the initial release. Without this artificiality the quantity of materials deposited would be so small as to approach limits of detectability with field instrumentation.
l l 1 i 1 l I l l l l l l l i i Recmtry, Re-entry, Relocation data Page 9.2-1 C:. .\ EXER \ SECT 7-11.WPS l l
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l Recovery, Re-entry, Relocation data Page 9.2-2 C:. . \EXERtSEC T7-11. WP5
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l l l FLYOVER.XLS I -
, ! i
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i DOE Flyover i iDistance l Distance ) Sample point Time ! Sample Location !D/W meters lOff C/L l meters i(mi) I(mi) 1 1001 l -1 -1609 4' 6436 2 1002 M3 1 -1609 3 4827 3 1003 M2 -1 -1609 2 3218 ; l 4 1004 -1 -1609 1 1609 l' l 5 1005 Sta 59 -1 -1609 0 0 6 1006 -1 1609 1 1609 7 1007 Sta 56 -1 -1609 2 3218 8 1008 I 1- -1609 3 4827 9 1009 E3.5-1 -1: 16C9 4 6436 10 1010 Langdon -0.5! -804.5 4 6436 0 13 l$ 1013 E
-0.5 E5
-804.5 1
EU 1609 14 1014 -0.5- -804.5 0 0 ; 15 1015 M1 -0.5 -804.5 1 1609 16 1016 -0.5 -804.5 2 3218 17 1017 -0.5 : 804.5 3 4827 18 1018 -0.5 804.5 4 6436 l 19 1019 N4 _ 0 0 4 6436 l 20 1020 N3 0 0 3 4827 l 21 1021 N 2_ 0 0 2 3218 22 1022 N1 0 0 1 1609 23 1023 CNS 0 0 0 0 l 24 1024 0 0 1 1609 l 25 1025 0 0 2 3218 26 1026 0 0 3 4827 27 1027 0 0 4 6436 28 1028 0.5 804.5 4 6436 29 1029 E2.5 0.51 804.5 3 4827 30 1030 : 0.51 804.5 2 3218 31 1031 ! 0.51 804.5! 1, 1609 32 1032 i 0.5! 804.5l 0 0 33 1033.01 0.5j 16091 1 1609 34 1034lP2 O.Si 804.51 2 3218 35 1035 i 0.Si 804.5l 3 4827 36 1036 0.5, 804.5 4 6436 37 1037 i 1: 1609 4 6436 38 1038 P3 i 1: 1609i 3 4827 Correlation between flyover points and pre identified sampling points. an c,. ann,,. acicca, ion sa,a eaxc 9.2-3 c:. .nexcansac7Eii.wes
._ . .. - . . _ - . . - . . - - . . ~ . . _ - _ _ . . ~ _ _ _ - . _. . . . . -
FLYOVER.XLS 39 1039'P2 1- 1609I 2: 3218 40 1040iO1 1 1609i 1 1609 41 1041lA1 1 16091 0 0 42 1042iD2.5-1 1. 1609) 1- 1609 43 1043; 1 1609 2 3218 44 1044 i 11 1609 3 4827 ! 45 1045 1 1609 41 6436 ! 46 1046 Sta 71 1.5 2413.5 4j 6436 , l 47 1047 1.5 2413.5 3- 4827 l j 48 1048 C2 1.5 2413.5 2 3218 -{ l 49 1049 C2 1.5 2413.5 1 1609 50 1050 A1.5 1.5 2413.5 Oi 0 51 1051 1.5 2413.5 1! 1609 52 1052 O2 i 1.5 2413.5 2! 3218 53 1053 l 1.5 2413.5 3: 4827 54 1054 1 1.5 2413.5 6436 41 , 55 1055 Sta 84 i 2 3218 41 6436 56 1056 P4 2 3218 3 4827 57 1057 Q3 2 3218 2 3218 58 1058 Brownville-So. 2 3218 1 1609 59 1059 Mo. Bridge 2 3218 0 0 60 1100 Sta 87. 2 3218 1 1609 61 1101 2 3218 2 3218 62 1102 2 3218 3 4827 63 1103 2 3218 4 6436 64 1104 2.5 4022.5 4 6436 65 1105 Phelps City 2.5 4022.5 3 4827 l 66 1106 C3-1 2.5 4022.5 2 3218 l 67 1107 2.5 4022.5 1 1609 y.v 68 1108 A2.5-2 2.5 4022.5 0 0 Y 69 1109 Brownville-Cntr 2.5 4022.5 1 1609 70 1110 2.5 4022.5 2 3218 71 1111 2.5 4022.5 3 4827 I 72 1112 2.5 4022.5 4 6436 j 73 11131 i 3t 48271 4' 6436 74 1114 Q4 3: 4827i 3l 4827 75 1115 ' 3i 4827 2; 3218 76 1116 R3 i 3 4827 1l 1609 77 1117 Sta 85 . 3; 4827 0, 0 1 78 1118 i 3l 4827 il 1609 79 1119 B3 3! 4827 2j 3218 80 1120 C3-2 3i 4827 3 4827 81 1121 : 3l 4827 4 6436 Correlation between flyover points and pre-identified sampling points.
- Recovery, Re-erary, Relocation data Page 9.2-4 C
- . .\ EXER \SEC77-11.WPS t
t , l -- ; I FLYOVER.XLS l 82' 1122: 1 3.5' 5631.5l 4! 6436 l 83 1123 i 3.5 , 5631.5: 3' 4827 84: 1124;B3.5-2 ! 3.5 5631.5 2- 3218 85; 1125'83.5-1 ! 3.5~ 5631.5l 1! 1609
,, 86, 1126 ' A3 1 3.5: 5631.5, O. 0
, 87 1127 3.5 5631.5 1 1609 88 1128 R4 3.5 5631.5 2 3218 l l 89 1129 Sta 67 3.5 5631.5 3 4827 90 1130 QS 3.5 5631.5 4 6436 i 91 1131 4 6436 4 6436 l 92 1132 4 6436 3 4827 93 1133 4- 6436 2 3218
- 94. 1134' 4; 6436 1 1609 j l + 95i 1135'A4 4' 6436 0 0 96 1136; 41 6436 1 1609 l l 6436 3218 97 11371 4! 2 l l 981 1138 C4 41 6436 3 4827 l 99 1139 C5 4l 6436 4 6436 100 1140 4.5 7240.5 4 6436 1 101 1141 4.5 7240.5 3 4827 l 102 1142 B4-5 4.5 7240.5 2 3218 l 103 1143 Sta 86 4.5 7240.5 1 1609 l 104 1144 4.5 7240.5 0 0 1 105 1145 4.5 7240.5 1 1609 l 106 1146 R5 4.5 7240.5 2 3218 107 1147 4.5 7240.5 3 4827 108 1148 4.5 7240.5 4 6436
. 109 1149 5 8045 4 6436 i 110 1150 R6A 5 8045 3 4827 111 1151 5 8045 2 3218 l
! 112 1152 5 8045 1 1609 l w 113 1153 AS 5 8045 0 0 l 114 1154 5 8045 1 1609 115 1155 5 8045 2 3218 116 1156 B5.5-2 5 8045l 3 4827 117 1157' ! 5! 8045i 4i 6436 118 1158iC7 5.Si 8849.51 4; 6436 119 1159, i 5.5j 8849.5l 3! 4827 120i 1200 !B 5.5-1 I 5.51 8849.Si 2! 3218 1211 1201 iB5.5-1 1 5.Si 8849.5' 1l 1609 122l 1202! l 5.di 8849.5 0 0 123 1203! l 5.51 8849.5! 1 1609 124 1204: i 5.Si 8849.51 2' 3218 Correlation between flyover points and pre-identified sampling points. 1 Recmery, Re-entry, Relocation data Page 9.2 5 C:. .\ EXER \SEC77-11.WP5 l
l FLYOVER.XLS I l 125i 1205= 5.5: 8849.5 3l 4827 5.5; 8849.5 6436 126i 1206l _ __ 6 9654 4l 41 6436 i 127 12071 A 128: 12081R7 6 9654i 3; 4827 ! 129l 1209!R6-B 6 9654! 2! 3218 I 3x 130 1210 6, 9654 1 1609 l 131 1211 61 9654 0 0 132 1212 6 9654 1 1609 133 1213 6 9654 2 3218 , 134 1214 6 9654 3 4827 1 135 1215 61 9654 4 6436 f 136 1216 Brickyard Hill-SW 6.Si 10458.5 4 6436 137 1217 B7-2 1 6.5' 10458.5 3 4827 l 138l 12181 I 6.5 10458.5 2 3218 l 1391 1219 6.5 10458.5 1 1609 140i 1220 i 6.5, 10458.5 0 0
' 1609 141 1221 6.Si 10458.5 1 l
142 1222 . 6.5I 10458.5 2 3218 l 143 1223 6.5! 10458.5 3 4827 144 1224 6.5 ! 10458.5 4 6436
, 145 1225 R8 73 11263 4 6436 f i 146 1226 7; 11263 3 4827 j 147 1227 7' 11263 .
2 3218 ; 148 1228 7 11263 1 1609 149 1229 7 11263 0 0 f 150 1230 B7-1 7 11263 1 1609 , 151 1231 B7-1 71 11263 2 3218 152 1232 Brickyard Hill-SW 7 11263 3 4827 153 1233 Brickyard Hill-Cntr 7 11263 4 6436 , 154 1234 Brickyard Hill-Cntr 7.5 12067.5 4 6436 l 155 1235 Brickyard Hiu-West 7.5 12067.5 3 4827 l 156 1236 7.5 12067.5 2 3218 I 157 1237 7.5- 12067.5 1 1609 7.54 12067.5 0 0 158 1238 A7 159 1239 A7 7.5l 12067.5 1 1609 1601 1240 i 7.5! 12067.5' 2 3218 l 4827
! 7.5! 12067.5 3 4 161l 1241 162l 1242 Peru-SE i
7.5! 12067.5 4 6436 1243 R9 i 12872 4 6436 jv 163' ' 8l 12872 3 4827 y< 164 1244 Peru-boat ramp 8. 165, 1245 8: 12872 2 3218 1246 A8-1 8! 12872 1 1609 166i Bi 12872 0 0 1671 12471 Correlation between flyover points and pre identified sampling points. ( Recovery, Re-entry, Relocation data Pace 9.2-6 C:. .\ EXER \SEC17-II.WPS h
1 l l l FLYOVER.XLS n 168' 12481_A_8 2, Watson _ [ 8 _ _128721 1! 1609
> 1691 1249!B8-1 8 12872! y 3218 1701 1250!B8-2 -
3 12872 31 4827 171 1251 ' B8-3 3 12872: 4' 6436 172' 1252iBrickyard Hill NE F 13676.5 4! 6436 173' 1253 Brickyard Hill-NW S.5_ 13676.5 3 4827 174 1254 8.Si 13676.5 2 3218 175 1255 Watson-North. 8.5 13676.5 1 1609 176 1256 8.5 13676.5 0 0 177 1257 8.5l 13676.5 1 1609 178 1258 8.5! 13676.5 2 3218 v 179 1259 Peru-boat dock 8.51 13676.5 3 4827 180 1300 R9 8.5 13676.5 4 6436 181 1301 9 14481 4 6436 l 182 1302i 9' 14481 3 4827 183 1303' I 9- 14481 2 3218 184 1304i j 9' 14481 1 1609 185 1305 l 9 14481 0 0 l 186 1306 9 14481 1 1609 l 187 1307 9 14481 2 3218 188 1308 Brickyard Hill-NW 9. 14481 3 4827 189 1309 Brickyard Hill-NE 9! 14481 4 6436 190 1310 9.5 15285.5 4 6436 l
-191 1311 B10-1 9.5 15285.5 3 4827 l 192 1312 9.5 15285.5 2 3218 l 193 1313 A9-3 9.5 15285.5 1 1609 194 1314 9.5 15285.5 0 0 195 1315 A9-2 9.5 15285.5 1 1609 196 1316 A9-1 9.5 15285.5 2 3218 l 197 1317 9.5_ 15285.5 3 4827 l
198 1318 9.5l 15285.5 4 6436 199 1319 10i 16090 4 6436 200 1320 10! 16090 3 4827 201 1321 10I 16090 2 3218 202 1322l A10-1 i 10i 16090 1 1609 203 1323 ! 10. 16090 0 0 204 1324 A10-2 ! 10 i 16090 1 1609 205 1325 l 10i 16090 2 3218 206 1326, i 10! 16090i 3 4827 207 13271 i 10; 16090! 4 6436 l Correlation between flyover points and pre-identified sampling points. Recowry, Re-entry, Relocation data Page 9.2-7 C:. 1 EXER \ SECT 7-11. WP5
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i 1 Recovery, Re-entry, Relocation data Page 9.2-8 C:. .tEXER\ SECT 7-11.WP5 l i - . _ . - -
exoffsite Release out the ERP(Ci/sec) l Time 1200 1205 1210 1215 1220 1225 1230 1235 1240 1245 Nuclide 0 5 10 15 20 25 30 5 10 15 l-131 0 30484.05334 89243.274 144816.9315 197368.4008 247052.7046 294016.9403 330474 7474 _ 313583.086 297554.8134 1-133 0 60968.10668 178486.548 289633.863 394736.8016 494105.4093 588033.8806 660949.4949 627166.172 595109.6269 t-135 0 53795.38825 157488.1306 255559.2909 348297.1779 435975.3611 518853.424 583190.7308 653381.9165 525096.7296 Cs-134 0 2689.769412 7874.40653 12777.96454 17414.8589 21798.76806 25942.6712 29159.53654 27669.09582 26254.83648 Cs-137 0 1075.907765 3149.762612 5111.185818 6965.943558 8719.507223 10377.06848 11663.81462 11067.63833 10501.93459 0 0.149013225 0.436242122 0.707899236 0.964783183 1.20765175 1.437223985 1.615438324 1.532867909 1.454517941 44.70396763 130.8726365 212.3697707 289.4349549 362.2955251 431.1671954 484.6314973 459.8603726 436.3553823 l Time l 1250 1255 1300 1305 1310 1315 1320 1325 1330 1335 Nuclide 20 25 30 35 40 45 50 55 60 65 l-131 282345.8 267914.168 254220.1855 241226.1478 228896.2786 217196.6299 206094.9891 195560.79 185565.0288 176080.1842 1-133 564691.6 535828.336 508440.3709 482452.2957 457792.5572 <34393.2598 412189.9782 391121.5801 371130.0577 352160.3684 1-135 498257.29 472789.7082 448623.8567 425693.202 403934.6093 383288.1704 363697.0396 345107.2765 327467.6979 310729.7368 Cs-134 24912.865 23639.48541 22431.19283 21284.6601 20196.73046 19164.40852 18184.85198 17255.36383 16373.3849 15536.48684 Cs-137 9965.1459 9455.794165 8972.477134 8513.864041 8078.692186 7665.763409 7273.940792 6902.145531 6549.353959 6214.594736 1.3801727 1.309627492 1.242688083 1.17917017 1.118898868 1.061708232 1.0074408 0.955947156 0.907085523 0.860721371 414.05181 392.8882475 372.8064249 353.7510509 335.6696603 318.5124696 302.2322399 286.7841468 272.125657 258.2164113 Recovery. Re-erary. Relocation data Page 9.2-9 C:. .\ EXER \SEC77-11.WP5
e::offsite l Time j l 1340 l 1345 l 1350 l 1355 1400 l 1405 1410 1415 l l 1420 l 1425 l Nuclide 70 75 80 85 90 95 100 105 110 115 1-131 167080.14 158540.1207 150436.6088 142747.2943 135451.0062 128527.6556 121958.1805 115724.493 109809.43 104196.7055 1-133 334160.28 317080.2414 300873.2177 285494.5887 270902.0125 257055.3113 243916.361 231448.986 219618.86 208393.411 1-135 294847.31 279776.6836 265476.3685 251906.99 239031.1875 226813.51 215220.3185 204219.6935 193781.347 183876.5391 Cs-134 14742.365 13988.83418 13273.81843 12595.3495 11951.55937 11340.6755 10761.01592 10210.98468 9689.067352 9193.826954 Cs-137 5896.9462 5595.533673 5309.527371 5038.1398 4780.62375 4536.270199 4304.40637 4084.393871 3875.626941 3677.530782 0.816727 0.774981414 0.735369541 0.697782362 0.662116389 0.628273423 0.596160282 0.565683551 0.536774331 0.509338013 l Time { l 1430 1435 1440 1445 1450 1455 1500 1505 1510 1515 l Nuclide 120 125 130 135 140 145 150 155 160 165 l 1-131 98870.866 93817.24777 89021.93678 84471.73006 80154.09951 76057.15739 72169.62358 68480.79454 64980.51379 61659.14401 l-133 197741.73 187634.4955 178043.8736 168943.4601 160308.199 152114.3148 144339.2472 136961.5891 129961.0276 123318.288 l-135 174478 165559.849 157097.5355 149067.7589 141448.4109 134218.513 127358.1593 120848.4609 114671.4949 108810.2541 Cs-134 8723.8999 8277.99245 7854.876775 7453.387946 7072.420545 6710.925652 6367.907963 6042.423047 5733.574746 5440.512706 i Cs-137 l 3489.56 3311.19698 3141.95071 2981.355179 2828.968218 2684.370261 2547.163185 2416.969219 2293.429898 2176.205083 0.4833041 0.458600782 0.435160173 0.412917692 0.391812098 0.371785281 0.352782101 0.334750237 0.317640041 0.301404404 l Time j j 1520 1525 1530 1535 1540 1545 1550 1555 1600 1605 l Nuclide 170 175 180 185 190 195 200 205 210 215 l-131 58507.54 55517.02584 52679.36634 49986.74905 47431.76036 45007.36562 42706.88975 40523.99884 38452.68273 36487.23846 I-133 117015.08 111034.0517 105358.7327 99973.49809 94863.52071 90014.73124 85413.7795 81047.99763 76905.36546 72974.47692 1-135 103248.6 97971.22206 92963.58766 88211.91008 83703.10651 79424.76286 75365.09956 71512.93913 67857.6754 64389.24434 CS-134 5162.43 4898.561103 4648.179383 4410.595504 4185.155326 3971.238143 3768.254978 3575.646956 3392.88377 3219.462217 Cs-137 2064.972 1959.424441 1859.271753 1764.238202 1674.06213 1588.495257 1507.301991 1430.258783 1357.153508 1287.784887 0.2859986 0.271380285 0.257509138 0.244346991 0.231857605 0.220006593 0.208761326 0.198090841 0.187965761 0.178358207 Recovery. Re-entiv. Relocation data Page 9.2-10 C:. .\ EXER \SEC77-11.WP5
exoffsite l Time l 1615 1630 1645 1700 1715 1730 1745 1800 1815 1830 [Nuclide 225 240 255 270 285 300 315 330 345 360 'l-131 33737.425 29607.16302 25295.30068 21611.39978 18464.00667 15774.98661 13477.5841 11514.7656- 9837.803705 8405.067468 t-133 67474.851 59214.32604 50590.60135 43222.79955 36928.01333 31549.97323 26955.1682 23029.5312 19675.60741 16810.13494 l-135 59536.633 52247.93474 44638.7659 38137.76431 32583.54118 27838.21167 23783.97194 20320.17459 17360.83007 14832.472 Cs-134 2976.8317 2612.396737 2231.938295 1906.888216 1629.177059 1391.910584 1189.198597 1016.008729 868.0415034 741.6236001 Cs-137 1190.7327 1044.958695 892.775318 762.7552863 651.6708236 556.7642335 475.6794389 406.4034917 347.2166013 296.64944 0.1649165 0.144726779 0.123649382 0.105641607 0.090256409 0.077111846 0.065881602 0.056286884 0.048089499 0.041085947 l Time j l 18:45 19:00 19:15 19:30 19:45 20:00 [ Nuchde 375 390 405 420 435 l 450 1-131 7180.9889 6135.179959 5241.678227 4478.302319 3826.101258l 3268.884009 t-133 14361.978 12270.35992 10483.35645 8956.604638 7652.202516l 6537.768017 l-135 12672.333 10826.78816 9250.020401 7902.886445 6751.943396l 5768.618839 Cs-134 633.61667 541.3394082 462.50102 395.1443223 337.5971698l 288.4309419 lCs-137 253.44667 216.5357633 185.000408 158.0577289 135.0388679l 115.3723768 0.0351024 0.029990203 0.025622557 0.021890995 0.018702883 0.015979074 Total = 10917.46355 Reanerv Re-entry, Relocation data Page 9.2-11 C:. .\EXERISEC77-11.WP5
24 hours after accident no decay Distance 1-131 l-133 1-135 Cs-134 Cs-137 Total ci/m2 725 5.70E-07 1.14 E-06 1.01 E-06 2.51E-09 1.01 E-09 2.72E-06 1050 1.05E-05 2.09E-05 1.85E-05 4.61 E-08 1.85E-08 4.99E-05 1609 4.76E-05 9.52E-05 8.40E-05 2.10E-07 8.40E-08 2.27E-04 2625 7.56E-05 1.51 E-04 1.33E-04 3.33E-07 1.33E-07 3.61E-04 3219 7.35E-05 1.47E-04 1.30E-04 3.24E-07 1.30E-07 3.51 E-04 8047 3.12E-05 6.23E-05 5.50E-05 1.37E-07 5.50E-08 1.49E-04 16090 1.16E-05 2.32E-05 2.05E-05 5.11 E-08 2.05E-08 5.53E-05 l l Decay Corrected Activity 24 hrs later . Time = 24 Total Total dpm Total dpm Dose Rate Distance 1-131 1-133 1-135 Cs-134 Cs-137 Total ci/m2 uCi/m2 per cm2 per 100cm2 mrem /hr 725 5.23E-07 5.12E-07 8.00E-08 2.51E-09 1.01 E-09 1.12E-06 1.12 248.31 2.48E+04 0.004 1050 9.59E-06 9.40E-06 1,47E-06 4.61E-08 1.84E 2.05E-05 20.52 4556.27 4.56E+05 0.068
/ 1609 4.37E-05 4.28E-05 6.68E-06 2.10E-07 8.40E-08 9.34 E-05 93.44 20742.70 2.07E+06 0.309 2625 6.94 E-05 6.80E-05 1.06E-05 3.33E-07 1.33E-07 1.48E-04 148.41 32947.38 3.29E+06 0.491 2 3219 6.74 E-05 6.61 E-05 1.03E-05 3.24E-07 1.30E-07 1.44 E-04 144.31 32037.93 3.20E+06 0.477 5 8047 2.86E-05 2.80E-05 4.37E-06 1.37E-07 5.50E-08 6.12E-05 61.17 13580.05 1.36E+06 0.202
;{} 16090 1.06E-05 1.04 E-05 1.63E-06 5.11 E-08 2.05E-08 2.28E-05 22.75 5051.09 5.05E+05 0.075 100m off center 500 m off center 1000 m off center 1500 m off center dpm/100cm2 Dose Rate dpm/100cm2 Dose Rate dpm/100 cm2 Dose Rate dpm/100cm2 Dose Rate Distance 725 5.14E+03 7.65E-04 1.95E-13 2.90E-20 9.43E-65 1.40E-71 2.81E-150 4.19E-157 1050 2.03E+05 3.03E-02 7.88E-04 1.17E-10 4.08E-30 6.08E-37 6.34E-74 9.44E-81
/ 1609 1.43E+06 2.13E-01 1.84E+02 2.73E-05 1.27E-10 1.89E-17 6.90E-31 1.03E-37 '
2625 2.82E+06 4.21 E-01 6.97E+ 04 1.04E-02 6.62E-01 9.85E-08 2.81 E-09 4.19E-16 c2. 3219 2.88E+06 4.29E-01 2.23E+05 3.31 E-02 7.45E+01 1.11 E-05 1.20E-04 1.79E-11 f!8047 1.33E+06 1.98E-01 8.16E+05 1.21 E-01 1.77E+05 2.63E-02 1.38E+04 2.06E-03 jo 16090 5.02E+05 7.48E-02 4.37E+05 6.50E-02 2.82E+05 4.20E-02 1.36E+05 2.03E-02 Rewrery. Re-entry Relocation data Page 9.2-12 C:... \ EXER \ SECT 7-!!. WP5
_ _ _ _ . - . _ . _ ... _- - -~ _ .- _ _ _ .. __ _ . _ . ._. . _ _ _ . JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE Message _1_ Controller making call Issued at _7 a.m. (time) Received by l I live in Plattsmouth heard you went off line this morning because ice is clogging your plant. Where is Omaha getting it's power from now? Is there any chance oflosing that power? l ' 1 I i l l
RESPONSE
l l l [ Joint information Center (JIC) Paec 10-1 C . EXER'. SECT 7-1I WP5 i l l
l. I r JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE Message _2 Controller making call ! Issued at _7:10 a.m. (time) Received by I was wondering, with Fort Calhoun down, if you are experiencing similar problems with ice i getting into your plant Does that cause an emergency? l l 1 RESPONSE: l l l l l I l l l l Joint bifonnation Center U!O Paee 10-: C . EXER'. SECT 7-11 \\*PS
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i l l l JOINT INFORMATION CENTER L RUMOR CONTROL MESSAGE 1 Message _3_ Controller making call i 1 Issued at _7.15 a.m. (time) Received by I live in Shubert and we get our electricity from your plant is there a chance of any power i
- lines going down in this area? I have some sows in my farrowing house and want to have my l l back-up generator ready.
1 l l l I r 1 i RESPONSE: i ? l I l t v l Jo. ort Infonnation Center rJIC Page 10.4 C . EXER SECT 7 Il WP5
JOINT INFORMATION CENTER i I l- RUMOR CONTROL MESSAGE i-( l Message _4_ Controller making call Issued at _8 a m. (time) Received by i l I heard that ice was gettmg into your plant and freezing up the pipes. If those pipes break, i- ' how much radiation willleak out? l l l I RESPONSE: 1 l l l l I l l l l l I I I Joint Infonnatwn Center tJICs Pace 10 J C EXER SECT'" il \VPS
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i JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE l l Message _5_ Controller making call l
- l. Issued 'at _8 a.m (time) l l' )
Received by l 1 live in Northeastern Kansas and am calling about some information about ice jamming your power plant. That happened at Wolf Creek nuclear plant last year One of the things they didn't do is alert the public. Have you alerted the public? l l t
RESPONSE
i Joint intirrmatum Center (JICs Page 10-! C EXER SECT 7-Il WP5 l
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i JOINT INFORMATION CENTER l RUMOR CONTROL MESSAGE j l Message _6_ Controller making call ! Issued at _8:10 p.m. (time) - ! l Received by l I heard there was an emergency shutdown of your plant Are we supposed to start evacuating? i
RESPONSE
i. l i ( Joint Information Center tJIC Page 10-h C EXER SECT 7-11.WPS i i i t l
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l l JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE Message _7_ Controller making call Issued at _8 05 a.m. (time) Received by . l This is William Poplar in Aurora We have several lines down out here and I understand that Cooper is the only plant operating. I thought that new transmission line you built was supposed to help in this situation That's what you told us Didn't you guys see this coming' 1 1 1 > 1 l RESPONSE: ) l 1 l l 4 Joint Inn >rmation Center tJICs Paer 10-7 C EXER SECT 7-11.WP! 1 i I
l l JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE l Message _8_ Controller making call l l t Issued at -8:10 a m. (time) Received by 1 l This is John Thompson from Nebraska City. I understand that Ft Calhoun shut down this l morning because ofice on the Missouri River What happens if all the power plants go down' l l \ i i I
RESPONSE
1 l l l l l l i i n l l i i i Jannt Informanon Center UICs Paee 10-X C. . EXER SECT 7-II %P3 l l i
l l JOINT INFORhiATION CENTER RUMOR CONTROL afESSAGE l Message _9_ Controller making call Issued at _8:45 a.m. (time) Received by I understand the line from Nebraska City has gone down. I was about to head out to visit my sister out of town, but now I don't want to leave because if the power goes out, the food in our freezer may go bad. How soon do you think you'll have that repa: red and have the electricity supply stable again? l
RESPONSE
I 1 l l Joint intkurmation Center tJICs Page 10 9 C. EXER!SEC&ll WP5 l
l [ [ r i JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE 1 Message _10_ Controller making call Issued at _8:55 a.m. (time) l Received by ,. We've heard that high winds and ice have knocked out a Ict oflines in western Nebraska, and caused your plant in North Platte to shut down With the storm moving east, what are you doing to keep Cooper on line' l l l
RESPONSE
l l l l l l l l l l t I I i> 1 l .Jomt Inthemanon Center tJICs
. Paee 10-10 C EXER SECT 7-Il WP!
l l l w- r , - . , - ,. --
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JOINT INFORMATION CENTER RUM'OR CONTROL MESSAGE Message _11_ . Controller making call l Issued at _8:55 a.m. (time) l Received by I heard that you've called out several area fire departments to the plant. What part of the plant is on fire?
RESPONSE
! Jov;t Inforntation Center IJICs Page Ith! .' C:. EXER SECT 7 II. nPS l
JOINT INFORMATION CENTER . RUMOR CONTROL MESSAGE Message _12 Controller makinc call Issued at _9 a.m. (time) Received by I heard you guys have a big fire over there Are we supposed to get out of town? RESPONSEi I 1 Joint information Center tJICs Paee ISI: C. EXER' SECT 7 Il WP5
i l l l l JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE Message _13_ Controller making call Issued at (time) Received by l l
RESPONSE
1 i Jannt Information Center 'llCs Pace 10-l.1 C EXER SECT 7-Il WP! l
JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE - Message _14_ Controller making call Issued at _9 a.m. (time) Received by l 1 heard that there's a fire in the generators that are used for back up and keep the safety l systems nanning at the plant. Does this mean that you don't have any safety systems working? Is there radiation coming from Cooper now' 1 l 1 l RESPONSE: l l I l l 1 l l I l Joint Information Center UIC) Paee liki.I C EXER SECT 7 l1 \\'PS l ! I l
JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE Message _15_ Controller making call Issued at _o 10 a m- (time) Received by l This is Patricia Ott and the radio said you have something going on at your plant. I live in Watson and that's within that 10 mile plant area. I lost that calendar book you gave me. Am I supposed to be doing something?
RESPONSE
l r i i Joint Information Center (JICI pagejtht! C EXER' SECT 71I WP3 l
JOINT INFORMATION CENTER Rt rMOR CONTROL MESSAGE Message _16_ Controller making call Issued at _9:15 a m. (time) l Received by l l Ilive in Brownville and saw a bunch ofsmoke coming from over by Cooper I also heard the l fire sirens. I knew this was going to happen. I never liked that plant. You guys don't know l what you're doing. It's dangerous. Dangerous. Do you know how many people died at Chernobyl? Now you're going to kill all of us Who do you think you are? t i l
RESPONSE
l l l l Jomt Information Center IJICs Paee 10-16 C. EXER'. SECT 71 IMP 3 l l
i i JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE ! Message _17_ Controller making call Issued at _9.20 a m (time} Received by . I heard that when all the power lines went down, the power backed up the lines and blew up your plant. I live in Rock Port. Are we supposed to get out of here? Or is the radiation already all over the place? Should I go to my basement and bring some food down there? 9 l s j i RESPONSE: l t 1 i ; l I i I I l Joint Information Center (JICs Page 10-17 C: . EXER'. SECT 7-Il WPS
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! 1 JOINT INFORMATION CENTER l , RUMOR CONTROL MESSAGE l Message _18_ Controller making call Issued at 9:25a.m (time) 1 Received by I heard there were three people in the room and the fuel sprayed all over them and started on
. fire. Are they all right?
i
RESPONSE
l l l l i l l l Joint Information Center 'JICS Page itkl8 C. EXER SECT 7 li \\'PS
JOINT INFORMATION CENTER , RUMOR CONTROL MESSAGE 1 j Message _19_ . Controller making call l Issued at 9!25 (time) Received by l l ! l l Someone told me that one of the guys in the fire is dead My cousin works there. What's the !
- name of the guy who died? l l
RESPONSE
l l l l l i j Jorn: Infi>rmation Center (JICs Pace 10-19 C EXER
- SECT 7-1I WPS
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1 a 4 i
; JOINT INFORMATION CENTER RUMOP CONTROL MESSAGE Message _20 Controller makinc call Issued at _9:30 a.m. (time) 1 Received by 4
My husband is a volunteer firefighter. He got a call and he's on his way to your plant. I'm very worried about him. Are you going to make him go into any radioactive areas? 1 i 1
RESPONSE
a Jennt Information Center tJICs Page 10.'O C. . EXER' SECT 7-Il WPS J
5 JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE Message _21_ Controller makin'g call Issued at _9.35 a m. (time) Received by I heard some information about the fire at your plant. Is this related to the problems earlier this year that you identified with your plant's fire safety program' I thought you hired a bunch of people to watch for that. Don't you hire quality people? l l l I l 1 RESPONSE: ) l l Joint Information Center tJICr Paee1021 C EXER' SECT 7 Il \\P.S
4 t a i l JOINT INFORMATION CENTER l RUMOR CONTROL MESSAGE i Message 22 Controller makinc call I
- Issued at 10 a m - (time) 1
- Received by i
i I heard someone fellin the river trying break up some ice and got sucked unoer I di'in't believe that, j-but wanted to check with you guys. 1 l ) i
- j l
RESPONSE
] 4 Joint infi>rmatwn Center (JICI Paer lik:: C EXER' SECT 7-1I WP!
JOINT INFORA!ATION CENTER RUMOR CONTROL MESSAGE Message _23_ Controller making call l Issued at !0.15 a m _ (time)- Received by - I live in St. Joe and heard on TV that Nebraska has a lot of power lines down and that a couple ofyour plants have shut down because of this. Does this arTect the electricity you're sending from your plant to Missouri?
RESPONSE
Joint Information Cemer IJIC; Page 104) C EXER' SECT 7 II WPS
l l JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE Message _24_ Controller making call Issued at _10.20 a.m. (time) Received by I heard that three people were killed there this morning My uncle works there and I don't know if he's okay. What are their names?
RESPONSE
JOINT INFORMATION CENTEst RUMOR CONTROL MESSAGE Message 24 Controller making call
- Issued at (time)
Received by
RESPONSE
I JOINT INFOIO1 ATION CENTER l l
- l. Joint Injistmatwn Center tJICs Page 101 t C. . ~ EXER' SECT 711. WP3
l t RUMOR CONTROL MESSAGE Message _25 Controller makine call l l-Issued at _11 a.m. (time) Received by I heard that all of NPPD's power plants have shut down because all of your power lines are down. My mother is on an in-home respirator. How long before we run out of electricity' l'm going to have to get her to the hospital. 1
RESPONSE
JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE - l Message _25_ Controller making call Issued at (time) Received by 1 I
RESPONSE
Joint Informatwn Center IJIC) Paer in .'! C EXER SECT 7 Il WP5
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i l JOINT INFORMATION CENTER ) l RUMOR CONTROL MESSAGE
- l. I Message _26_ Controller making call l
I Issued at _11 a m (time) j Received by I live in Watson and I don't have a radio that works My power went out and I don't have any batteries My phone lines are still working and my uncle called from Omaha and said that both nuclear plants are having problems and Cooper is on fire. He said that they showed black
'~
smoke coming from the plant. So that's why I called. I'm sorry to bother you, but I just want to know what's going on and ifI'm in danger.
RESPONSE
1 Jennt Information Center *)lC) Pate 10-:n C EXER SECW11 WPS
JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE i i l Message _27_ Controller making call l-
- issued at- 11-05 a m (time) ;
t I \ Received by l l
\
l l 1 I I understand that you evacuated all your employees and sent them home, but there are people unaccounted for. How many are there? i l
RESPONSE
I Jenn* Informatwn Center (JICs Pate ite:7 C EXER'5ECTill nPS
~.- ~
r..w e-, w ,m.e ,
.,-r. m , - - v - t f
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l
+
l JOINT.INFORMATION CENTER ; RUMOR CONTROL MESSAGE l 1 Message _28_ Controller making call l 1 Issued at ,_I 1:10 a m (time) I 1 1 Received by l I was calling to check into a rumor. Someone said that we have to leave our homes because you have nuclear fuelleaking and burning. I haven't heard anything on the radio. Can you tell me what's going on? : l l i
RESPONSE
I l hunt Intbrmatwn Center IJICs Pa:e in .?R C EXER SECT 7-Il WP5 l
l I JOINT INFORMATION CENTER l RUMOR CONTROL MESSAGE l l Message _29_ Controller making call
. Issued at _11:15 a.m. (time)
Received by I'm a temporary painter and my buddyjust called and said that the plant is in bad shape. I was wondering ifI'm supposed to come to work this anernoon. l l l l
RESPONSE
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_ _ . _ _ _ _ _ . _ _ _ _ _._ .._.__-_-..___._m _ _ _ - . _ . - _ . . . . . _ . - - . _ _ . . - JOINT INFORMATION CENTER . I RUMOR CONTROL MESSAGE ! l Message _30_ Controller making call Issued at i1:20 a m (time) l Received by { I was in the grocery store and someone said we have to leave our homes. Where do we go' Wejust moved here a month ago and I don't know what to do I didn't even know there was i a nuclear plant near here. I don't really know anyone here. What do I do? I have a preschool 1 aged daughter and son. Do I take a lot of clothes? Which way can I drive' i l
RESPONSE
10:1.1 fnfinimation Center tJIC, Page 10 30 C EXER SECT ~ iI WP5
i i JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE Message _31_ Controller making call Issued at _11:30 a m. (time) l Received by I l l Someone said your plant was on fire, but that you're still putting out power. I just was l wondering how long you can do that. I run a day care and have a bunch of kids here. I just don't want to lose power now and have to find some way to keep them all warm. My car's not big enough to put them all in and go somewhere. Besides, if there's no power, where can we go? I RESPONSE: i l l - Joint Information Center (JICI Paer 10-31 C- EXER' SECT 7 Il WP.9 l
l i JOINT INFORMATION CENTER - RUMOR CONTROL MESSAGE Message _32_ Controller making call Issued at _11:45 a.m. (time) Received by l
.Ijust heard from a friend that you guys had a fire and ice is freezing up your plant. I told him he was crazy, but I wanted to check just the same. Is that true?
RESPONSE
i I l l 1 I lsnnt lotformation Center IJICs Paer 10-3.' C ' EXER' SECT 7 il WP.4 l l 1
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JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE Message _33_ Controller making call Issued at _11.45 a.m. (time) Received by I live between Auburn and Brownville and have this wire laying across my driveway in front ofmy house. I was wondering ifyou guys are going to make us evacuate. Because if you are, I want the electric people to come out here ar. move this wire But otherwise I'm not going out. The weather's too bad And so I won't bother them with it Are we going to evacuate?
RESPONSE
Joint Informatwn Center rJICr Paee Irk.U C. EXER' SECT 7 Il WPS
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JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE Message _34_ Controller making call Issued at _11:55 a m. (time) Received by i 1 I l On the radio, they said theyjust got some information that there's a potential for a release of l radiation. What's that mean, a potential? Has there actually been a release or is there going to be or not? l l l l 1 1 l l RESPONSE: l l i ? Jomt informatwn Center UICI Paee 1n34 C. EXER SECT 71I WP3 i
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i Message 35 Controller making call j issued at _12:10 p.m (time) l Received by i I i This is Sue Baker from Stella I heard that you are evacuatinu some areas around the plant. Does that include Stella? i i. i ! RESPONSE: l i i 1 l' e J i Jov t Informanon Center tJICr Page Ith .15 C. EXER SECT ~ 1I WP!
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l l l JOINT INFORMATION CENTER l RUMOR CONTROL MESSAGE Message _36_ Controller making call
. Issued at _12.20 p m (time) i l
Received by l This is Lydia Swanson. I'm 79 years old. I don't drive, but my granddaughter in Omaha called and said that you are evacuating the area around the plant. I live in Brownville and I don't see very wel! Do you have someone who can pick me up and take me to where i need to go?
RESPONSE
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RESPONSE
l hnnt Infarrnanon Center IJICI Pagein!7 C EXER SECTKil WPS l
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! JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE Message '38 Controller makinc call Issued at _12:50 p.m. (time) Received by I just heard on the radio that you are evacuating everyone from around the plant I called earlier and you said that you weren't. What's going on? l I l i l i t l=
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l l. JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE 9 Message '39 Controller making call issued at _12:55 p m (time) Received by . l I was wondering ifit's okay to go outside. Do we have to wear any special clothes? Our car is in the attache,d garage and I can get to it without going outside Can I run ti:e heater' Or : l will that pull the radioactive air in? l l RESPONSE: , I l , l l l J<nnt Informanon Center ilici Pace 10-39 C EXER SECT'-il WP5
I l JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE Message _40 Controller makinc call issued at _l:00 p m. (time) Received by My teenage son and his friends just left here and said they were going to go to the nuclear plant and see what's happening for themselves. I'm really worried about them, but they said that it's no big deal. They read about it in school. Are they in danger'
RESPONSE
Joint inlannatwn Center IJIC) Paee 10-.10 C. EXER SECT 7-Il WPS
l l l I l JOINT INFORMATION CENTER 1 RUMOR CONTROL MESSAGE l l ,. Message _41_ Controller making call l l l ! Issued at _l:05 p.m. (time) ! l l Received by ! This is Donna Johnson from Hamburg My nephew works there and my neighbor told me she ! heard that someone or a few people died in that fire earlier. Do you have any information? His ! parents live in Florida and I wanted to call them i don't think they've heard anything about l l it yet. I just want to make sure he's all right before I call.
RESPONSE
l I i Joint Informatwn Center (JIC, Pace liksi C ' EXER SECT 7-1I WP5 i
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JOINT INFORMATION CENTER l_ RUMOR CONTROL MESSAGE
. Message _42_ Controller making call l
l Issued at _l:10 p.m (time) l Received by The wind is blowing toward my house from your plant. Am I supposed to get out'
RESPONSE
1 1 l l ! I f Joint Information Center IJICt Pate 10-92 C. .. EXER SECT 7-Il WPS l
l JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE Message _43_ Controller making call Issued at _l.15 p m. (time) Received by
- This is Steve Ginsberg from Fairfax, Missouri l'd like to speak with someone who can give l me some information about the emergency at your nuclear power plant. I understand there
- have been several injuries and the public is being evacuated I used to live in Michigan near l a nuclear plant and they were always doing drills to test for things like this Is that what this is? Or is it real9 s
RESPONSE
1 l l l I I l Jr i u irrformation Center tJIC, race 10-43 C EXER SECWll WPS l 1 1 I
. v- = JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE Message _44_ Controller making call issued at ,_l:30 p.m. (time)
' Received by I was one of those fire watches you had there and heard that you're having a fire now. Are , you going to be hiring extra help again' l'm available to work e
?
RESPONSE
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JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE l Message _45_ Controller making call Issued at _l:30 p m Oime) Received by My little boy was out in the yard playing and he ate some snow Now I hear that there's radiation all over the place from your plant; I'm really worried He said he doesn't feel so good. Should I bring him to the hospital' l
RESPONSE
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JOINT INFORMATION CENTER , ! ~ RUMOR CONTROL MESSAGE Message _46_ Controller mr'%g call l Issued at _l:35 p.m (time) t Received by ) i i 1 I'm headed from Omaha to Kansas City on 1-29 and I heard on the radio that there's radiation I coming from your plant. I want to know ifit's okay to keep dnymg or is the radiation j blowing over to the interstate? Should I turn around' ; i
RESPONSE
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3 JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE Message _47_ Controller making call e Issued at 1:40 p m._ (time) Received by This is Margaret Learink and I am trying to get out of my house like the radio said My car ! won't stan because of the cold Can you send someone to get me' 1 l l
RESPONSE
l l l i l L Jarnt Infarnration Center tJIC. l' age its-J' t' EXER SIN T*-1I ti"I'!
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l JOINT IN.v0RMATION CENTER RUMOR CONTROL MESSAGE Message _48_ Controller making call Issued at _145 p m (time) Received by I know that the radio said that no one was dead, but are you guys just covering up' I heard that three people died in the fire there this morning. l I RESPONSE 1 l l l l l I I l ! i. 1 l l l Jamt Ini>rmatum t ' enter <JR 's - Pace Io-.h t' EXER SEc T-11 I11'.4 i t- _ _ ,,, , , ,.y-- -- , , . - - - _
P JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE Message _49_, Controller making call Issued at _,1:50 p m (time) Received by This is Lisa Worthington and me and my kids are going to leave town We're not going to the place where the radio said. We're going to my brother's place in Kansas City instead 1 just wanted to check in. l l
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P l [ j Jennt inti>rmation Center tJICo l' age Ituu t' IGER .4Et T~-11 IIP.4 i l t r -
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! RUMOR CONTROL MESSAGE i i Message _50 Controller makinu call . i
. Issued at _l:55 p.m (time)
I Received by i l l l 1. l l 1 was packing to leave and wanted to bring my dog with me. but she's been running around i l outside in the snow and now she's all wet. I live about seven and a half miles from the plant l Has the radiation gotten this far yet? I don't want to b-ing her if she has radiation on her Should I bring her to the vet' ? l l 1 l l RESPONSE. i l i I ( l l i
- Janit Inkrmation l' enter -ejit'o PaceIn-!n ** EXER set T~-11 If TS l
_._._.m.. 1 i JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE 1 i Message _51_ Controller making call l 1
-1 Issued at I:55 p.m. (time) 1 Received by I I farm in that 10-mile radius of your plant. My cows are out in this right now. The government's been coming up with all these reasons to put cattle farmers out of business. like l
this mad cow disease. This is just one more thing that you're doing to get rid of cattle farmers.
RESPONSE
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' JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE Message _52_ Controller making call Issued at _2 p m. (time)
Received by l We get power from your plant and our electricity is out Someone told me the plant blew up and there's radiation spraying out. Just how bad is it? RESPONSE. l l l 1 l l l
.lomt informatum t ' enter t.llCi Pace 10-5.' < EVER SECT ~-11 IVP.4 L
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i JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE j Message _53_ Controller making call 5
- Issued at _2-05 p m (time) 1 . Received by s
l 1 got a call from somebody who knows somebody who is related to someone who works there and he said that three people were killed there this morning Were they employees or the fire fighters from the area? i f 1 ' i-j RESPONSE: 1 1 J 4 4 1 i i-4 1 1 1 1 i l 4 i f i 4. Jomt Infi>rnsattum Center tJIC, l'.teeIto!? t' 131?R NB T*-1! It1'5 4 d
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4 i i- JOINT INFORMATION CENTER , RUMOR CONTROL MESSAGE } Message _54_ Controller making call i.
' Issued at 2::0 p m _ (time)
- Received by i l'm a registered nurse, but I don't have ajob right now I heard that there have been some j injuries and am willing to come to the plant and help out. Do you need extra help?
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l JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE Message _S5_ Controller making call l Issued at _2:25 p m. (time) Received by - This is Matthew Morrison in Lincoln. I've been following that lawsuit about how you guys don't run that place very well and it raises our electric bills in Lincoln How much do you estimate the damage to your nuclear plant is going to cost us this time' RESPONSE-. t Joint Inliormatann t ' enter <JK'r l' age it).55 1:XER SEC T-lI II1'5
JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE Message _56 Controller makinu call . Issued at _2:30 p.m. (time) Received by I was going to evacuate. Someone told me I should bring food and everything J can carry with me because we probably won't be allowed back for weeks or months How long are we going to be gone from our homes? l
RESPONSE
1 1 l l Joint informatuur Center <JIC. l'aec I(I .46 t' 13ER S/3 T*.II If1'.<
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JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE Message _57_ Controller making call issued at 2:40 p.m _ (time) Received by i I have to get out and feed my livestock. I can't just leave them out there. I have a lot invested ! in them. Ifl give them food and water, are they going to get radiation poisoning? i l l l l RESPONSE: l l I i l
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JOINT INFORMATION CENTER l - RUMOR CONTROL MESSAGE
' Message - 58 Controller makinc call l
Issued at _2-40 p m. (time) Received by I live in St. Joe and am supposed to catch a plane from Kansas City to Milwaukee, but I heard l that there is radiation coming from your nuclear plant is that going to affect the flight patterns for airplanes or can the radiation get into the planes' i l l l l 1 1 1
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l l lI JOINT INFORMATION CENTER ) RUMOR CONTROL MESSAGE ) i Message _59_ Controller making call issued at _2 40 p m (time) Received by l This is Sue Cramer in Stella. I heard on TV that the National Weather Senice says it s going ' to snow even more. Is that going to bring the radiation to the ground faster? And what happens then when the snow melts? I know in Chernobyl all the trees are still covered with radiation. Are we going to be able to even live around here' I l l l l l l l 1 RESPONSE: i l 1 t Jennt Informatom t ' enter <Jll's l'aee Itt-!9 t' 1 3l R S B '1 ~ 11 Ill'! l
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1 1 JOINT INFORMATION CENTER RUMOR CONTROL MESSAGE Message _60_ Controller making call Issued at _3 p.m. (time) Received by I have some people out in my field walking around with these meters I was going to go out and talk with them, but I was afraid I'd get radiation on me What's going on?
RESPONSE
l Ionns infarmarsem Center uJit ', l'aec 10 6H ' ' 13ER SB T'-lI Ifl'.' I
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