ML17328A679
ML17328A679 | |
Person / Time | |
---|---|
Site: | Cook |
Issue date: | 04/30/1990 |
From: | INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
To: | |
Shared Package | |
ML17328A678 | List: |
References | |
AEP:NRC:0965T, AEP:NRC:965T, NUDOCS 9004300227 | |
Download: ML17328A679 (576) | |
Text
{{#Wiki_filter:Donald C. Cook Nuclear Plant 1990 Annual Emergency Preparedness Exercise April, 1990 900430ADOCK 90042~
~0003i'5 PDR pDC F
TABLE OF CONTENTS Introduction Exercise Objective Conduct of Exercise Controllers/Observers Information Off-site Agency Participation Exercise Narrative Summary (Basic Sequence of Events) Exercise Messages A. Plant Data Curves B. Controller Messages C. Thermocouple Data D. Exhibit A Data Radiation Data A. In-Plant Radiation Data B~ On-site Radiation Monitoring Teams Data C. Dose Projection Data D. Meteorological Data E. RMS Data F. Plume Exposure Data ERE-90
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE INTRODUCTION In the interest of verifying that the health and safety of Plant staff, Plant visitors and the general public are protected in the event of an accident at the Cook Nuclear Plant, the Indiana Michigan Power Company conducts an annual emergency response exercise. In accordance with the schedule prescribed by the Nuclear Regulatory Commission (NRC) and the Federal Emergency Management Agency (FEMA), the 1990 emergency exercise will be conducted as an off-hours, unannounced exercise with participation by both State and County agencies. Evercise events will begin at approximately 0100 on April 3, 1990 initiating the mobilization of Cook Nuclear Plant, American Electric Power Service Corporation (AEPSC) and Indiana Michigan Power Company (I&M) personnel. The scenario will'rogress in order to facilitate activation of State and County emergency organizations prior to 0400. Exercise termination is expected to take place at approximately 0900 on April 3, 1990. The intent of the exercise is to demonstrate that these various emergency response organizations (EROs) are adequately trained to implement their corresponding emergency plans and procedures from their respective emergency response facilities (ERFs). It will also serve to demonstrate their ability to effectively coordinate their activities. This scenario will prove particularly challenging to the TSC Plant Evaluation Team as well as control room operators to properly prioritize the multiple failures to determine which one is key to getting the plant under control in the quickest and safest manner. It will likewise force them to develop a well coordinated repair and recovery effort to minimize release time. The exercise will be evaluated by assigned observers from AEPSC, the Cook Nuclear Plant, the NRC and FEMA. A critique will be conducted by the NRC following the exercise to identify any licensee response deficiencies. This will be held in the Plant Manager's conference room critique on April 4 at 1400 hours. A subsequent critique will be conducted by FEMA to identify any offsite agency deficiencies. This latter critique will be held at the on April at hours. Licensee deficiencies identified in the critique will be documented with subsequent resolution being the .responsibility of the Plant and AEPSC Emergency Planning Coordinators. ERE-90 l-l
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE INTRODUCTION (CONTINUED) This manual has been prepared to assist exercise Controllers and Observers in the conduct and evaluation of the exercise. This manual contains all information and data necessary to conduct the exercise in a coordinated and efficient manner in the event the simulator becomes unusable. Although the use of the simulator will provide the opportunity for more free-play, it is important to remember that the timeline in Section VI may not track with the exercise activities as closely as it has with the more artificial, closely controlled timelines used in past exercises.
/
Finally, given that the players response should be candid and spontaneous to affect a valid evaluation, this manual must be treated as confidential material. Potential players shall not have prior knowledge of the scenario material in this manual . ERE-90 1-2
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE II. EXERCISE OBJECTIVES The exercise objectives dictate the scope of the scenario. The objectives for this exercise were developed based upon the Donald C. Cook Nuclear Plant Emergency Plan Administrative Manual, and FEMA Guidance Memorandum EX-3. Situations will be presented in the scenario to prompt the desired player response for each objective. Where appropriate, specific objectives and criteria for adequate demonstration have been included in the exercise messages for Controller/Observer use. ERE-90 2-1
DONALD C. COOK NUCLEAR PIANT 1990 EMERGENCY PREPAREDNESS EXERCISE OBJECTIVES OBJECTIVE A. OVERALL LICENSEE OBJECTIVES A-1 Demonstrate the ability of the emergency response organization to implement DCCNP Emergency Plan Px'ocedures, the IMPCo Emergency Response Manual and the AEPSC Emergency Response Manual. A-2 Demonstx'ate the ability to establish emergency management command and control, and maintain continuity of this function for the duration of the postulated event. A-3 Demonstrate the ability to establish communications and information flow between DCCNP emergency response facilities and participating offsite agencies. A-4 Demonstrate the ability to designate subsequent shifts of the emergency response organization. A-5 Demonstrate the ability to notify and mobilize off-duty personnel during non-working hours B. CONTROL ROOM OBJECTIVES B-1 Demonstrate the ability to recognize symptoms and parameters indicative of degrading plant conditions and to classify degraded conditions as emergencies. B-2 Demonstxate the ability to initiate notification of off-site authorities and plant personnel. B-3 Demonstrate communications and information flow to and from the Technical Support Center. B-4 Demonstrate the ability to transfer emergency authorities and responsibilities from the on-shift emergency organization to the DCCNP emergency response organization. B-5 Demonstrate the ability to implement site assembly and accountability during off-hours (i,e., 1700-0600). C. TECHNICAL SUPPORT CENTER OBJECTIVES C-1 Demonstrate the ability to activate the facility within one hour of declaration of an emergency requiring facility acti vation. ERE-90 2.2
OBJECTIVE C.'ECHNICAL SUPPORT CENTER OBJECTIVES (cont'd.) C-2 Demonstrate the ability to provide analytical, assistance and operational guidance to the Control Room.
~ C-3 Demonstrate the ability to coordinate on-site activities in response to the emergency.
C-4 Demonstrate the ability to establish and maintain hard copy communications vith the EOF and verbal communications vith the EOF, OSA, IAG, ENC and/or JPIC. C-5 Demonstrate the ability to provt.de analytical radiological assistance to the OSA and Control Room, C-6 Demonstrate the ability to obtai.n data from the OTSC/PSSD system, C-7 Demonstrate the ability to request emergency response teams from the OSA. C-8 Demonstrate the ability to desi.gnate a second shift for TSC operation. C-9 Demonstrate the ability to evaluate the results of TSC/OSA habi.tability surveys and assess the need to evacuate these faciliti.es. C-10 Demonstrate the ability to recognize degrading plant conditions and classify plant conditions as an emergency. C-11 Demonstrate the ability to evaluate site evacuation routes and determine an appropriate route based on indi.cated radiological and meteorological conditions. C-12 Demonstrate emergency the acti.ons required to be taken in the TSC involves a breach of the reactor coolant system. if the C-13 Demonstrate the ability to determine the level of core damage based on plant parameters provided. C-14 Demonstrate the ability to process personnel dose extension request. C-15 Demonstrate the ability to assess the need for, and process request for potassium iodide administration. ERE-90 2.3
OBJECTIVE D. OPERhTIONS SThGINC AREh OBJECTIVES D-1 Demonstrate the ability to activate the facility within one hour of declaration of an emergency requiring facility activation. D-2 'emonstrate the ability to assemble, brief and dispatch the following emergency response team(s}:
- a. Damage Contx'ol Team
- b. Post Accident Sampling Team C ~ On-site Radiation Monitoring Team
- d. Off-site Radiation Monitoring Team D-3 Demonstrate the ability to designate a second shift for OSA operation.
D-4 Each emergency response team assembled and dispatched shall demonstrate the following actions as applicable to the team type and mission: a ~ Assembly of tools/equipment.
- b. Preoperation checks of equipment and communications devices.
C. Performance of appropriate radiological precautions. d, Performance or simulation of team mission.
- e. Post-mission debriefing and radiological controls.
ability
'-5 Demonstrate the to provide emergency radiological support. As a minimum the following activities should be demonstrated:
a, Establishment of emergency dosimetry and exposure tracking system. b, Establishment of emergency control points.
- c. Performance of habitability surveys prescribed by procedure.
- d. Analysis of radiological conditions to be encountered by emergency response teams.
- e. Specification of radiological contxols and precautions for emergency response teams.
D-6 Demonstrate the ability to perform offsite radio3.ogical monitoring. As a minimum, two teams should be dispatched and direct radiation monitoring as well as airborne radioactivity analysis should be demonstrated. ERE-90 2.4
OBJECTIVE D OPRhTZONS SThGING hREh OBJECTIVES (cont d ) D-7 Demonstrate the ability to implement damage control activities in accordance with applicable Emergency Plan Procedures.
. D-8 Demonstrate the ability to perform onsite radiological monitoring in accordance with applicable Emergency Plan Procedures. This monitoring should include direct radiation surveys and analysis. of airborne radioactivity samples.
D-9 Demonstrate the ability to obtain post accident samples from the RSC Loop and complete appropriate chemical and isotopic analysis within three hours of the sample request. D-10 Demonstrate the ability to obtain radiological base data required to evaluate the release level from the secondary plant during a steam generator tube rupture. D-11 Demonstrate the ability to respond to a contaminated person. Included in this demonstration, personnel decontamination"shall be simulated. D-12 Demonstrate the actions required for an individual to exceed the exposure limits of 10CFR20. Included in this demonstration should be a discussion of post exposure actions and limitations. D-13 Demonstrate the actions required to administer potassium iodide. This demonstration should include a discussion of the follow-up actions associated with KI administration. D-14 Demonstrate a shift turnover. D-15 Demonstrate the ability to obtain environmental samples in accordance with applicable Emergency Plan Procedures. The following samples should be obtained:
- a. Vegetation
- b. Soil E. EMERGENCY OPERhTIONS PhCILITY OBJECTIVES E-l Demonstrate the ability to activate the facility within one hour of declaration of an emergency requiring facility activation.
ERE-90 2.5
OBJECTIVE E. EMERGENCY OPERATIONS FACILITY OBJECTIVES (cont'd.) E-2 Demonstrate the ability to establish overall command and control of the DCCNP emergency response within one hour of declaration of a site area emergency or general 'emergency, as applicable. E-3 Demonstrate the ability to establish and maintain effective emergency communications with. each of the following agencies and facilities: a ~ State of Michigan
- b. Berrien County c ~ NRC
- d. Technical Support Center
- e. Joint Public Information
- f. Initial Assessment Group E-4 Demonstrate the ability to establish and maintain hard copy data transmission and reception with each of the following faci'lities:
- a. Technical Support Center
- b. Joint Public Information Center
- c. State of Michigan EOC E-5 Demonstrate the ability to direct Offsite Radiation Monitoring Teams in order to determine the geographical location and radiological magnitude of the postulated plume.
E-6 Demonstrate the ability to designate a second shift for EOF operation. E-7 Demonstrate the ability to develop protective action recommendations based on projected dose and/or core and containment status. E-8 Demonstrate the ability to update the State of Michigan on the status of the emergency at 15 minute intervals. E-9 Demonstrate the ability to respond to inquiries from the TSC, JPIC, IAG and State of Michigan in a timely manner. E-10 Demonstrate emergency de-escalation and termination. E-11 Demonstrate the ability to project the magnitude of offsite dose using the Dose Assessment Program and the IBM Personal Computer. E-12 Demonstrate corporate augmentation of the EOF staff. ERE-90 2.6
OBJ ECTIVE (cont '. I EMERGENCY OPERhTIONS FhCZLXTT OBJECTIVES ) E-13 Demonstrate 'recovery planning associ'ated with emergency termination. E-14 Demonstrate the ability to take compensatory action in the event of a failure of the Meteorological Data Terminal. F. PUBLXC hFFhXRS OBJECTIVES F-1 Demonstrate activation of the Joint Public Information Center. F-2 Demonstrate the ability to conduct media briefings. F-3 Demonstrate the ability to respond to actual or simulated inquiries from media representptives. F-4 Demonstrate the ability of rumor control personnel 'to respond to simulated inquires from the general public. F-5 Demonstrate the ability to monitor media transmissions and respond to inaccurate information being transmitted by the media. F-6 Demonstrate the ability to designate subsequent shifts for JPIC operations. F-7 Demonstrate coordination of news announcement content with State and County representatives. ERE-90 2.7
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE III. CONDUCT OF THE EXERCISE A. EXERCISE PLAYER INFORMATION This exercise is intended to satisfy the requirements for an annual emergency response exercise to demonstrate the readiness of the Plant to respond to an abnormal Plant condition. The following information should be understood by all players prior to initiation of the exercise. It should be understood that the circumstances simulated for this exercise are unrealistic in certain aspects, which should not be construed as flaws in the scenario. Moreover, it is due to the reliable design and construction of nuclear power facilities that require unrealistic assumptions to be made in order to generate conditions that will affect the general public. Thus, in order to obtain a sequence of events that will result in a significant radiological hazard to the general public, the exercise scenario must contain an incredible Plant condition, an unlikely series of equipment failures, or an improbable sequence of events coupled with equipment failure. 2 ~ The purpose of the exercise is to demonstrate actual integrated emergency response capabilities, including the use of facilities. Personnelemergency equipment and knowledge and familiarity with the Emergency Plan and Procedures a'e the primary aspect of the evaluation. Demonstration of detailed knowledge of plant systems, equipment and operation is of secondary importance for purposes of this evaluation. Although knowledge of the plant is not being evaluated, system evaluations should not be eliminated from discussions during the exercise since this contributes to the realism of the response.
- 3. All emergency communications that relate to the exercise shall be identified as part of the drill. Verbal communications should be initiated and closed by the statement, "this is a drill".
Exercise extreme care to ensure that individuals who may overhear 'or observe exercise activities are not misled into believing that an actual emergency exists. ERE-90 3-1
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE CONDUCT OF TEE EXERCISE (CONTINUED) 4, Manipulation of any plant operating system, valves, breakers or controls in response to this exercise are to be simulated. There are to be no alternation of plant equipment, systems or circuits in response to this exercise.
- 5. Any motor vehicle response to this exercise, whether it be ambulance, fire fighting equipment, security or field monitoring vehicle should observe all normal motor vehicle operating laws including posted speed limits, stop lights/signs, one-way streets, etc.
- 6. Should any on-site security actions be required in response to this exercise, exercise participants are to cooperate as directed, and security representatives are to be prudent and tolerant in their actions.
7 4 Participants should inject as much realism into the exercise as is compatible with the safe performance of the exercise.
.8. Play out all actions, as much as possible, in accordance with the Emergency Plan Procedures.
Unless specifically instruc'ted by the controller, you should not simulate your actions. If instructed to simulate an activity, tell the observer/controller how and when you would actually perform the activity.
- 9. Periodically speak out loud, verbalizing your key actions and decisions to the controller and federal evaluator. This may seem artificial, but it will assist in the evaluation process and is to your benefit.
- 10. If ever in doubt, ask your controller for clarification. The controller will not provide prompting or coaching information.
Periodically the controller may issue messages or instructions designed to initiate response actions. You must accept these messages immedi a t e1y. ERE-90 3-2
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE III . CONDUCT OF THE EXERCISE ( CONTINUED )
- 12. You must not accept any messages or instructions from federal evaluators. If they desire to initiate some action, they must work through the controller.
- 13. If entering radiologically controlled areas, observe all ~ules and procedures governing access and egress. Do not enter high radiation areas for purpose of exercise response. Follow normal ALARA principles and guidelines.
- 14. Utilize status boaids, log books, three-part message forms, etc., as much as possible to document and record your actions, instructions and reports to co-players.
REKMBER PUT IT IN WRITING ERE-90 3-3
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE IV. CONTROLLERS/OBSERVERS INFORMATION The Controller/Observer group is essential to the successful implementation of the exercise. Controllers are responsible for ensuring the scenario proceeds on schedule by disseminating timely information and maintaining scenario integrity. Observers are responsible for observing, documenting and analyzing players actions. Observers may assume the function of Controller if identified inthe scenario or directed by the facilities lead controller. A. Control Room
- 1. Control Room Lead Controller R. Stephens
- 2. Control Room Observer I. Flee twood
- 3. EOP Controller G. Arent
- 4. EOP Observer D. Draper B. Technical Su ort Center
- 1. Exercise Lead Controller M. Barfelz
- 2. TSC Observer R. Ptacek
- 3. Radiological Controller B. Jepkema C. Operations Sta in Area
- 1. OSA Lead Controller
- 2. I&C Controller G. Griffin T. Walsh
- 3. DCT Controller T. Johnson
- 4. DCT Controller J. Moline
- 5. DCT Controller D. Londot
- 6. DCT Controller W. Lee
- 7. RRT/Onsite RMT Controller H. Springer
- 8. RRT/Onstie RMT Controller D. Gallagher
- 9. RP Lead Controller K. Scherer
- 10. Offsite RMT Controller (Counting) M. Schafer
- 11. Offsite RMT Controller (Survey) J. Paris
- 12. Offsite RMT Controller (Survey) J. Hoss
- 13. PASS Team Controller G. Cook D~ Emer enc Ooerations Facilit
- 1. EOF Lead Controller R. Heydenburg
- 2. Communications Observer K. Umphrey
- 3. Environmental Assessment Controller D. Noble E. Joint Public Information Center
- 1. JPIC Lead Controller K. Pinkowski ERE-90 4-1
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE IV. CONTROLLERS/OBSERVERS INFORMATION (CONTINUED) Controller/Observer Functions Controllers and Observers are utilized in this exercise to provide exercise information to the participants and to observe players response. In doing so, the Controllers and Observers should allow players to make, and correct, their own mistakes, while the Controller or Observer identifies the items to improve Plant emergency response capability. However, situations may arise where complete freedom of player response and success of the overall exercise are conflicting objectives. In such cases, the Controller or Observer must ensure proper conti'nuity of the scenario, while identifying problem areas in sufficient detail to allow corrections. Generally, the following rules apply to control of the exercise:
- l. Keep the reaction and emergency response going according to the time element established in the scenario.
- 2. Provide command messages to key personnel as a mechanism to prevent deviation from the scenario.
- 3. Observe player procedural discipline.
- 4. Provide prepared input data to players to stimulate response actions.
- 5. Observe and critique the participants actions, procedure effectiveness, equipment capability and general emergency response.
Exercise Controller Observer Instructions Each Controller/Observer shall participate in exercise briefings and critiques scheduled as follows: Exercise Walkthrough March 30, 1990, 0800 Location to be announced Exercise Facility Critique Immediately upon exercise termination in each emergency response facility NRC Critique April 4, 1990, 1400 Plant Managers Conference Room ERE-90 4-2
EPAM ATTACHMENT-5D DCCNP ERE-CI 1 DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE CHECKLIST NO. 1 APPLICABLE STATION: CONTROL ROOM DATE OF EXERCISE: T1ME INITIATED: EVAI UATORS ASS IGNED: LEAD CONTROI LER: CR OBSERVER: EOP CONTROLLER: A. EMERGENCY CLASSIFICATION SCENARIO PROJECTED ACTUAL CLASSIFICATION ECC EAL TIME ECC EAL TIME UNUSUAL KG2PZ ALERT SITE AREA EMERG. GENERAL EMERG. NOTIFICATIONS YES NO N~A
- 1. Were the State and County notified within 15 minutes of emergency declaration?
(Attach completed EXHIBIT-B of PMP 2080 EPP.106)
- 2. Was the NRC notified promptly following State/County notification?
- 3. Was Security notified of the declaration?
- 4. Was the STA notified and in the Control Room within 10 minutes?
- 5. Was PMP 2080 EPP.107, Notification of Plant Personnel, implemented within twenty minutes of declaration?
Page 1 of 5 Rev. 0
EPAM ATTACHMENT-5D DCCNP ERE"CI 1 C. I COMMUN CAT IONG YES NO N~A Were the State and County provided 15 minute updates using the Nuclear Plant Accident Notification Form? (attach copies of completed forms)
- 2. Was communication with the TSC established within one hour of the emergency declaration?
D. PROCEDUKK COMPLIANCE 1 ~ Were one or more of the following implementing procedures referred to as appropriate for the classification?
- a. PMP 2080 EPP.102, Unusual Event
- b. PMP 2080 EPP.103, Alert
- c. PMP 2080 EPP.104, Site Area Emergency
- d. PMP 2080 EPP.105, General Emergency Compliance was judged to be adequate/inadequate (if inadequate, comments identify deficiencies section}.
in the
- 2. Was PMP 2080 EPP.108, Initial Dose Assessment, implemented?
- a. Were results consistent with scenario px'ojections?
- b. Was a protective action recom-mendation developed based on projected dose?
- c. Was the State notified of dose projection results and/or pro-tective action recommendation within 15 minutes?
Compliance was judged to be adequate/inadequate inaequate, identify deficiencies in the comments (if section). Page 2 of 5 Rev. 0
EPACT ATTACiBKNT-5D DCCNP ERE-CL 1 YES NO ~NA Mere any of the following EPPs imp lemented?
- a. PMP 2080 EPP.109, .Fire Emergency Guidelines
- b. PMP 2080 EPP.110, Toxic Gas Release Guidelines
- c. PMP 2080 EPP.111, Natural Emergency Guidelines
- d. PMP 2080 EPP.112, Personnel Injury
- e. PMP 2080 EPP.113, Transportation Accident Involving Radioactive Naterial Compliance was judged to be; (list as appropriate)
ADE UATE INADE UATE (If inadequate, identify deficiencies section). in comment GENERAL ITENS
- 1. Emergency kits in the Control Room were adequately equipped?
- 2. Turnover from SS to oncoming SEC was thorough and documented.
- 3. Communications and interface with the TSC was adequate.
TSC support of Control Room activities was adequate?
- 5. Operator .familiarity with plant procedures (abnormal and EOP's) was adequate?
Page 3 of 5 Rev. 0
Pl EPAM ATTACHMENT"5D DCCNP ERE-CI l YES NO ~NA
- 6. Was the OTSC/PSSD system utilized?
F. SC NARIO DEFICIENCIES The following deficiencies in scenario content were noted: Page 4 of 5 Rev. 0
EPAM ATTACHMENT-5D DCCNP ERE-CL 1 G. COMMENTS COMMENT CHECKLE ST 'OMMENT NO REFERENCE Paqe 5 of 5 Rev. 0
EPAM ATTACHMENT-SE DCCNP ERE - CL 2 DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE CHECKLIST NO. 2 APPLICABLE STATION: TSC LEAD CONTROLLER DATE QZ EXERCISE: TIME INITIATED: EVALUATOR: A. ACTIVATION
- 1. Were each of the followirig actions completed?
YES NO N~A
- a. Turn on lights
- b. Turn on CAM
- c. Turn on ARM
- d. Unlock supply cabinets
- e. Turn on remote TV monitors
- f. Prepare OTSC/PSSD
- g. Prepare RDDS
- h. Update TSC STAFF status board
- i. Establish communications
- j. SEC turnover completed
- k. TSC staff briefed
- l. PMP 2081 EPP.101, EXHIBIT-B criteria satisfied 2 ~ Was the TSC operational within one hour, of the emergency declaration?
Page 1 of 5
EP AM ATTACHMENT-SE DCCNP ERE Cf 2 GENERAf OPERATION YES NO N~A
- 1. Did the Technical .Director establish and maintain command and control of TSC activities?
Did the Technical Director consdier and/or direct implementation of the zollowing EPP's when appropriate?
- a. PMP 2081 EPP.102, TSC Emergency Communications
- b. PMP 2081 EPP.106, On-site Radio-logical Assessment c ~ PMP 2081 EPP.103, Evacuation of Plant Personnel
- d. PMP 2081 EPP.216, Barring of the PABX
- 3. Did the Technical Director, in coordination with the PET, maintain an awareness of emergency conditions and assess the need for re-classification of the emergency periodically?
- 4. Did the TSC respond to Control Room requests in a timely manner?
- 5. Were emergency response teams requested in accordance with step 4.6 of PMP 2081 EPP.101?
- 6. Was the TSC ventilation system operated in accordance with section 4.8 of PMP 2081 EPP.101?
If appropriate, was TSC evacuation evaluated in accordance with section 4.9 of PMP 2081 EPP.101?
- 8. Was the OTSC/PSSD utilized by the TSC staff?
- 9. Werc subsequent shift(s) designated in accordance with section 4.10 of PMP 2081 EPP.3.01?
- 10. Did the Technical Director periodically brief the TSC staff on emergency conditions? (A minimum of once per hour is adequate).
I Page 2 of 5
EPAN ATTACHNENT-5E DCCNP ERE - CI 2 C. P~~VT EVAIUATION TEAN YES NO N/A P Mere all members of the PET aware of emergency conditions at all times?
- 2. Did the PET-Opertions and STA personnel follow Control Room progress in the EOPs?
- 3. Did the PET-Chemistry and Nuclear personnel assess the core status continually?
- 4. Did the PET evaluate overall plant conditions and develop appropriate mitigating and/or corrective actions?
- 5. Mas interface of the PET with the Control Room and IAG adequate?
- 0. GENERAI ITEMS Mere materials and equipment in the TSC adequate to facilitate an effective emergency response?
Were communications and interface with the OSA adequate?
- 3. Were communications and interface with the EOF adequate?
If the postulated events had actually occurred, would the actions taken by the TSC been adequate to protect the health and safety of plant personnel and the general public? Page 3 of 5
EP AM ATTACHMENT"SE DCCNP ERE - CL 2 E. SCENARIO DEFICIENCIES The following deficienc es xn'cenario content w'ere noted: Page 4 oZ 5
QN EPAM ATTACHMENT-5E DCCNP ERE - Cl 2 COMMENTS COUNT CHECKI I ST COMMENT j REFERENCE NO Page 5 of 5
EPAM ATTACHMENT-5F DCCNP ERE - CL 3 DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE CHECKLIST NO. 3 APPLICABLZ STATION: TSC COMMUNICATIONS OBSERVER DATE OF EXERCISE: TIME INITIATED: EVALUATOR: A. ACTIVATION YES NO ~NA
- 1. Were the following positions staffed within one hour of emergency declaration?
- a. TSC Administrative Coordinator
- b. TSC Boardwriter
- c. Telecopy Operator
- d. OSA Communicator
- e. IAG Communicator
- f. Public Affairs Liaison
,g. Runners (2)
If these positions were not staffed, was compensatory action taken to ensure the function was performed?
- 2. Did the Boardwriter establish communications with the Control Room and initiate status board update on arrival?
B. GENERAL COMMUNICATIONS ACTIVITIES
- 1. Did the Administrative Coordinator implement PMP 2081 EPP.102, TSC Emergency Communications?
Page 1 of 4
EPAM ATTACHNENT-5F DCCNP ERE - CL 3 YES NO ~NA ~ ~ Did each communicator follow the general guidance provided in the respective attachment of PNP 2081 EPP.102?
- a. Boardwriter - Attachment 2
- b. Telecopy Operator-Attachment 3
- c. TSC Runner-Attachment 4
- d. TAG Communicator-Attachment 6
- e. TSC OSA Communicator-Attachment 6
- f. Pub. Affairs liaison-Attachment 8 Was document transmission completed in accordance with Attachment 1 of PMP 2081 EPP.102?
- 4. Did each of the following communicators appear familiar with applicable EPP's and communications equipment?
- a. Boardwriter.
- b. IAG Communicator
- c. OSA Communicator
- d. TSC Scribe
- e. Public Affairs Liaison
- f. TSC Runners
- g. Telecopy Operator
- 5. Were inquiries received by communicators from other facilities documented and processed in a timely manner?
Page 2 of 4
V
EPAM ATTACHMENT-5F DCCNP ERE- Cf 3 C . COMMUNICATIONS E UIPMENT Document the operability of the following communications equipment. Spot-check telephones and document operability xn OTHER section. It may be necessary to question communicatois on equipment operability. E UIPMENT OPERABf E INOPERABEZ PROBIZN NOTED TEIECOPIER
-PHOTO COPY MACHINE TEST TEIL HEADSET OSA COMM. PHONE IAG COMM. PHONE P.A. fIAISON PHONE TECH.C DIR. PHONE RADIOS TV MONITORS OTSC PSSD TERMS RDDS TERM INAf PMNT PAGE OTHER:
Page 3 of 4
0 I ~ .
')r
EPAM ATTACHMENT-5F DCCNP ERE - CL 3 D. COMMENTS Oi~NT CHECKS I ST COMMENT NO. REFERENCE Page 4 of 4
EPAM ATTACHMENT"5G DCCNP ERE - CL 4 DONALD CD COOK NUCLEAR PLANT EMERGENCY RESPONSE'EXERCISE CHECKLIST HO. 4 APPI.ICABLE STATION: TSC RADIOLOGICAI. CONTROI,LER DATE OF EXERCISE: TIME INITIATED: EVAI UATOR: A. ACTIVATION YES NO ~iV A Was the position o f Radiological Assessment Coordinator staffed within one hour of emergency declaration?
- 2. Was the RDDS system prepared for operation (i.e. energized and appropriate program loaded)?
- 3. Were the TSC CAN and ARM energized and verified to be in proper working order?
B. RAC IMMEDIATE ACTIONS Did the RAC conduct a review of RDDS monitor .indications in accordance with step 4.4.2 of PNP 2081 EPP.106?
- 2. Did the RAC conduct a review of Westinghouse radiation monitor indications in accordance with step 4.4.3 of PMP 2081 EPP.106?
RAC SUBSE UENT ACTIONS Was the necessity for site evacuation based on site radiological conditions evaluated?
- a. If evacuation from item 1 was directed, PMP 2081 EPP.103 implemented?
was
- b. Were the provisions of PMP 2081 EPP.103 followed for implementation of the evacuation?
2 ~ Did the RAC provide adequate support to the RPD in determining adequate response team protective actions? Page 1 of 4
EPAÃ ATTACHMENT-SG DCCNP ERE - CL 4 YES NO N~A
- 3. Were appropriate correction factors applied to post-accident samples in accordance with steps 4.5.7 and 4.5.9 of PMP 2081 EPP.106?
K! DETERMINATION
- 1. Was KI considered for application to an emergency response team?
- 2. Was Section 4 tion, compliance with PMP 2081 EPP.106, Potassium Iodide Determina-adequate?
- 3. Was EXHIBIT-B of-PMP 2081 EPP.106 completed?
VOIUNTARY OVER-EXPOSURES
- 1. Was EXHIBIT-D of PMP 2081 EPP.106, completed?
- 2. Was compliance with PMP 2081 EPP.106, Section 4.7, Voluntary Over>>Exposure, adequate?
3, Did the SEC approve the over-exposure request? ALTERNATE RELEASE LEVEL DETERMINATIONS
- 1. Was compliance with PMP 2081 EPP.107 adequate?
- 2. Were calculated results in close proximity to scenario predictions?
SCENARIO PREDICTIONS CAI CULATED RESULTS Page 2 of 4
EP AM ATTACHMENT"SC DCCNP ERE "CI 4 G. GENERAI ITEMS YES NO N~A
- 1. Did the RAC provide adequate support to each of the following groups?
- a. Plant Evaluation Team
- b. OSA-Radiation Protection Director
- c. . EOF-Environmental Assessment Director
- 2. Did the following procedures provide adequate information to the RAC for performance of activities?
- a. PMP 2081 EPP.101, TSC Activation S Operation
- b. PMP 2081 EPP.103, Evacuation of Plant Personnel c ~ PMP 2081 EPP.106, On-site Radiological Assessment,
- 3. Mere adequate supplies, equipment and reference documentation available to perform the RAC function'?
H. SCENARIO DEFICIENCIES
.The following deficiencies in scenario content were noted:
Page 3 of 4
'f EPAM ATTACHMENT-SG DCCNP ERE - CL 4 COMMENTS COMMENT
'AO.
CHECKS 1 ST REFERENCE
'OMMENT
( II Page 4 of 4
EPAN ATTACHE:NT-SH DCCNP ERE -CL 5 DONALD C. COOK NUCLEAR PLANT EiiERGENCY RESPONSE EXERCISE CHECKI IST NO. 5 APPLICABLE STATION: OSA LEAD CONTROILER DATE OF EXERCISE: TIME INITIATED: EVALUATOR: A. ACTIVATION YES NO ~NA
- 1. Was the OSA operational within one =
hour of the emergency declaration?
- 2. Were each of the following activities completed?
- a. Turn on North and South Classroom lights
- b. Arrange tables and chairs
- c. Establish communications
- d. UnLock cabinets and offices
- e. Control points established at North and South access points
- f. PMP 2081 EPP.201, EXHIBIT-B criteria satisfied B. GENERAL OPERATION Did the OSA Manager establish and maintain command and control of OSA activities?
- 2. Did the OSA Manager consider and/or direct implementation of the following EPP's when
- a. PMP 2081 EPP.202, Operation of the Operations
'Staging Area Page 1 of 4
EPAM ATTAVPKNT-5H DCCNP ERE -CL 5 YES NO N~A
- b. PMP 2081 EPP.203, Activation of Emergency Response Teams
- c. PMP 2081 EPP.208, Emergency Radiation Protection Did the OSA Manager maintain an awareness of emergency conditions and brief the OSA staff at least once per hour?
Merc thc following records maintained accurately and expeditiously?
- a. Classroom Board
- b. OSA Manager Office Status Board
- c. OSA Manager Log If the Nuclear Emergency Alarm sounded, vere the OSA staff badge numbers and color recorded?
Were subsequent shifts designated in accordance with PMP 2081 EPP.202, Step 4.5.5? Did the OSA Manager complete PMP 2081 EPP.203, EXHIBIT-D and provide a copy to the RPD and the Ski'Lls Supervisor? Did the OSA Manager provide a copy of EXHIBIT-E of PMP 2081 EPP.203 to the SkilLs Supervisor. Mere team briefings adequate to establish the team objective, communications, procedures and methods,and equipment involved? Did the OSA Manager notify thc facility that requested the team upon dispatch? Page 2 of 4
c,r Ai'1 ATTACeZNT-5H DCCNP ERE -CG 5 C. GENERAI ITENS YES NO N~A
- 1. Were material and equipment in the OSA, adequate to facil'itate an effective emergency response?
- 2. Were communications and interface with the TSC adequate?
- 3. Were Communications and interface with dispatched teams adequate.
- 4. If the postulated events had actually occurred, would the actions taken by the OSA have been adequate to protect the health and safety of plant personnel and the general public?
D. SCENARIO DEFICIENCIES The following deficiencies in scenario content were note&: Page 3 of 4
~ "t EPAN ATTACHMENT"SH DCCNP ERE -CL 5 COl'KZ2PZ CHECKLIST COMNENT NO. REFERENCE Page 4 of 4
EPAM ATTACHMENT-5 J DCCNP ERE - CL 6
'I DONALD C. COOK NUCIEAR PLANT EMERGENCY RESPONSE EXERCISE CHECKL'IST NO. 6 APPIICABLE STATION: DCT CONTROLIER DATE OF EXERCISE: TIME INITIATED:
EVAI UATORS ASS IGNED: ACTIVATION YES NO N~A Did thc RPD brief the 'DCT on protective measures?
- 2. Did the skills Supervisor brief the DCT on thc task method?
- 3. Merc the following forms completed for each team? (PMP 2081 EXHIBIT-D, Response Form EPP.203)?
Team Request
- b. EXHIBIT-E, Team Briefing Form Was EXHIBIT-F of PMP 2081 EPP.203 consulted for team staffing?
Has the OSA Manager's Log completed?
- 6. If applicable, PMP 2081 EPP.208?
did the RPD consult
- 7. Did the OSA Manager or Skills Supervisor notify the appropriate facility upon team dispatch'?
Page 1 of 4
EPAM ATTAVPKNT-5J DCCNP ERE - CI 6 B. GENERAL OPERATION YES NO ~NA Did the team inform the OSA of unexpected conditions during enroute, assignment performance, and egress activities?
- 2. Did the team update the OSA on assignment progress?
- 3. Did the team rcport, any injured personnel to the OSA?
- 4. Did the team carefully monitor radiological conditions at all times?
- 5. Were appropriate emergency actions performed for any of the following:
- a. Turn back dose rate
- b. Turn back dose
- c. Personnel contamination
- 6. was personal contamination monitoring performed in low count rate areas?
- 7. Were contaminated equipment and anti-C's properly disposed?
C. GENERAL I TEMS Were adequate supplies and equipment conveniently located for each team?
- 2. Were all briefings adequate?
- 3. Were all procedures adequate?
Did the OSA respond to the TSC and EOF requests in a timely manner? Page 2 of 4
EPAN ATTACHMENT-5J DCCNP ERE - CL 6 D. SCENARIO DEFICIENCIES 1 The following deficiencies in scenario content were noted Page 3 of 4
EPAN ATTACHNENT-5 J DCCNP ERE - CL 6 E. COf ÃE;NTS COMK&T CHECKLIST COMNENT iVO. RE. TERENCE Page 4 of 4
EPAM ATTACHMENT-5K DCCNP ERE - CL 7 DONALD C. COOK NUCLEAR LANT EMERGENCY RESPONSE EXERCISE CHECKLIST NO. 7 APPI ICABLE'TATION: REENTRY AND RESCUE TEAM DATE OF EXERCISE: TIME INITIATED: EVALUATORS ASS IGNED: A. ACTIVATION YES NO ~NA
- 1. Did the RPD brief the RRT on protective measures?
- 2. Did the Skills Supervisor brief the RRT on the task method?
3 ~ Mere the following forms completed for each team? (PMP 2081 EPP.203)
- a. EXHIBIT-D, Response Team Request Form
- b. EXHIBIT-E, Team Briefing Form
- 4. Was EXHIBIT-F of PMP 2081 EPP.203 consulted for team staffing?
- 5. Was the OSA Manager's Log completed?
- 6. If applicable, PMP 2081 EPP.208?
did the RPD consult
- 7. Did the OSA Manager or Skills Supervisor notify the appropriate facility upon team dispatch?
Page 1 of 4
EPAN ATTAC)PE2PZ-5K DCCNP ERE - CL 7 B. GENERAL OPERATION YES NO ~MA Did the team inform the OSA of un-expected conditions while enroute, during assignment performance, and egress?
- 2. Did the team update the OSA on assign>>
ment progress? 3 ~ Did the team report any. injured personnel to the OSA?
- 4. Did the team carefully monitor radiological conditions at all times?
- 5. Were appropriate Emergency Actions performed for any of the following:
- a. Turn back dose rate
- b. Turn back dose
- c. Personnel contamination
- 6. Was personal contamination monitoring performed in low count, rate areas?
- 7. Were contaminated equipment, and anti-C's properly disposed?
C. GENERAL I TENS Were adequate'supplies and equipment conventiently located for each team?
- 2. Were all briefings adequate?'ere
- 3. all procedures adequate?
Did the OSA respond to TSC and EOF requests in a timely manner'? Page 2 of 4
EPAN ATTACHMEÃZ-5K DCCNP ERE CI 7 D. SCENARIO DEFICIENCIES The following deficiencies in scenario content were noted: Page 3 of 4
EPAM ATTACHMENT-5K DCCNP ERE CI 7 C CKI IS CO REFERENCE Page 4 of 4
EPAM ATTACHMENT-5L DCCNP ERE- CI 8 DONALD C. COOK NUCI EAR PLANT, EMERGENCY RESPONSE EXERCISE CHECKLIST NO. 8 APPLICABLE STATION: ONSITE RMT CONTROILER OBSERVER DATE OF EXERCISE: TIME INITIATED: EVALUATOR: A. ACTIVATION YES NO N~A Did the RPD brief the RMT on protective measures?
- 2. Did the Skills Supervisor brief the RMT on the task method?
- 3. Were the following forms completed for each team? (PMP, 2081 EPP.203)
- a. EXHIBIT-D, Response Team Request Form
- b. EXHIBIT-E, Team Briefing Form Was EXHIBIT-F of PMP 2081 EPP.203 consulted for team staffing?
- 5. Was the OSA Manager's Log completed?
- 6. If applicable, did the RPD consult PMP 2081 EPP.208? (KI assessment or dose extension)
- 7. Did the OSA Manager or Skills Supexvisor notify the appropriate facility upon team dispatch?
Page 1 of 4
EPAM ATTACHMENT-5 I, DCCNP ERE - CI 8 B. GENERAI OPERATION YES NO N~A Did the team inform the OSA of unexpected conditions while enroute, during assignment performance and egress?
- 2. Did the team update the OSA on assignment progress?
- 3. Did the team report any injured personnel to the OSA?
- 4. Did the team carefully monitor radiological conditions at all times?
Were appropriate Emergency Actions performed for any of the following:
- a. Turn back dose rate
- b. Turn back dose
- c. Personnel contamination
- 6. Was personal contamination monitoring performed in low count rate areas?
- 7. Were contaminated equipmcnt and anti-C's properly disposed?
C. MISSION DETAIjs Answer each of the following questions as applicablc to thc mission.
- l. Was PMP 2081 EPP.210, Unit Vent Sampling, adequately implemented
- 2. Was PNP 2081 EPP.211, Secondary Systems Sampling ,
adequately implemented?
- 3. Was PMP 2081 EPP.212, Containmcnt Atmosphere Sampling, adequately implemented?
- 4. Were prescribed surveys performed and documented in accordance with normal RP procedures?
Page 2 of 4
~l EPAM ATTACHMENT 5I DCCNP ERE CI 8 D. GENERAZ ITEMS YES NO N~A
- 1. Were adequate supplies and equipment conveniently located for each 'team?
- 2. Were all briefings adeqaute?
- 3. Were all procedures adequate?
- 4. Did the OSA respond to TSC and EOF requests in a timely manner?
E. SCENARIO DEFICIENCIES The 'following deficiencies in scenario content were noted: Page 3 of 4
EPAM ATTACHMENT-5L DCCNP ERE - CL 8 . Comawrs COMMENT CHECKLIST COMMENT NQ. REFERENCE Page 4 of 4
EPAM ATTACEPG'NT - 5M DCCNP ERE CL 9 DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE CHECKLIST NO. 9 APPLICABLE STATION: POST ACCIDENT SAMPI ING TEAM CONT OBS DATE OF EXERCISE: TIME INITIATED: EVALUATOR: A. ACTIVATION YES NO Did the RPD brief the PAST on pro-tective measures? 2- Did the Skills Supervisor brief the PAST on the task method? 3 ~ Mere the following forms completed for each team? (PMP 2081 EPP.203)
- a. EXHIBIT-D, Response Team Request Form
- b. EXHIBIT-E, Team Briefing Form Was EXHIBIT-F of PMP 2081 EPP.203 consulted for team staffing?
- 5. Has the OSA Manager's Log completed?
- 6. If applicable, 2081 did the RPD consult PMP EPP.208? (KI assessment and dose extension).
7 Did the OSA Manager or Skills Super-visor notify the appropriate facility upon team dispatch? Page 1 of 4
EPAN ATI'ACHMENT - SM DCCNP ERE CL B. GENERAL OPERATION YES NO N~A
- 1. Did thc team inform the OSA of unexpected conditions while enroute, during assignment performance, and egress?
- 2. Did thc team update the OSA on assignment progress?
- 3. Did the team report any injured personnel to the OSA?
4; Did the team carefully monitor radio-logical conditions at all times?
- 5. Were appropriate Emergency Actions performed for any of thc following:
- a. Turn back dose rate
- b. Turn back dose
- c. Personnel contamination
- 6. Was pcrsonncl contamination monitoring performed in low count, rate areas?
- 7. Were contaminated equipment and anti-C's properly disposed?
C.- SANPLINQ ACTIVITY EVALUATION What form of sample was requested?
- a. RCS Loop
- b. CTNT Sump
- c. CTMT Atm.
- 2. Was the sample obtained in accordance with applicable Chemistry procedures'?
- 3. Was the technician familiar with the post-accident sampling system and its operation?
Page 2 of 4
EPAM ATTACHMENT - SM DCCNP ERE CI 9 YES NO ~NA
- 4. Werc sample results available within three hours of the request 'for sample?
REQUEST TIME: TIME RESULTS AVAI MBA:
- 5. Were dose rates evaluated in thc area of the sample panel periodically?
6.- Werc radiation surveys performed in the hot lab during sample analysis?
- 7. Did the technician analyzing thc sample practice adequate contamination control techniques?
- 8. Was sample analysis performed adequately?
SCENARIO DEFICENCIES The following deficiencies in scenario content were noted: Page 3 of 4
EPAM ATTACHMENT SM DCCNP ERE - CL 9 CHECKLIST COMM22iT RE FENCE Page 4 of 4
0 DCCNP ERE - CL 10 DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE CHECKLIST NO. 10 APPIICABLE STATION: EMERGENCY OPERATIONS FACIIITY- LEAD CONTROLIER DATE OF EXERCISE: TIME INITIATED: EVALUATOR: A. ACTIVATION Yes No N~ Were each of the following actions completed? a 4 North gate open
- b. EOF unlocked c Cook security notified
- d. Area radiation monitor on
- e. Lights on Copier on
- g. OTSC/PSSD operational
- h. RDDS and IBM terminal operational
- i. Chronological event board being updated 3 ~ EOF Manager briefing and staff briefing completed Time designated to establish EOF communications PMP 2081 EPP.301 EXHIBIT-A require-ments satisfied Page 1 of 4
DCCNP ERE - CI 10 Yes No N~
- 2. Was the EOF operational within one hour of the emergency declaration?
- B. GENERAZ OPERATION Did the EOF Manager establish and maintain command and control of EOF activities?
- 2. Did the EOF Manager consider and/or direct implementation of the following EPP's when appropriate?
- a. PMP 2081 EPP.303, Off-site Radiological Assessment
- b. PMP 2081 EPP.302, EOF Emergency Communications
- 3. Was the State Notification Form completed and transmitted every 15 minutes according to the requirements of PMP 2081 EPP.301, Section 4.6?
Did the SEC/Recovery Control Manager approve initial or changed Protective Action Recommendations?
- 5. Did the EOF Manager brief the EOF staff on emergency conditions at least once per hour?
- 6. Were subsequent shift(s) designated in accordance with PMP 2081 EPP.301, Section 4.7?
Page 2 of 4
Qt ii W x
DCCNP ERE - CI 10 C. GENERAI ITEMS Yes, No N~
- 1. Were materials and equipment in the EOF adequate to facilitate an effective emergency response?
- 2. Were communications and interface with the TSC adequate?
- 3. Were communications and interface with government agencies adequate?
If the postulated events had actually occurred, would the actions taken by the EOF been adequate to protect, the health and safety of plant personnel and the general public? D. INITIAL RECOVERY ACTIVITIES
- 1. Were any emergency radiation exposure limit controls terminated and 10CFR20 radiation control measures re-established?
- 2. Was a preliminary damage evaluation compiled and priority repairs identified for maintaining a safe shutdown condition?
- 3. Was a preliminary assessment made of the scope of decontamination and disposal requirements?
- 4. Was the status and disposition of the uneffected unit, examined?
E. SCENARIO DEFICIENCIES The following deficiencies in scenario co'ntent were noted: Page 3 of 4
DCCNP ERE - CL 10 F. COMMENTS COMMENT CHECKLIST COMMENT NO. REFERENCE Page 4 of 4
DCCNP ERE - CK 11 DONALD C. COOK NUCIEAR PLANT ENERGENCY RESPONSE EXERCISE CHECKLIST NO 11 APPLICABIE STATION: EOF CONNUNICATIONS OBSERVER DATE OF EXERCISE: Trm INITIATED: EVALUATOR: A. ACTIVATION Yes No N~A Were the following positions staffed within one hour of emergency declaration?
- a. EOF Communications Director
- b. EOF Boardwriter
- c. Telecopy Operator d, . EOF Scribe
- e. JP IC 'Communicator
- f. NRC HPN Communicator
- g. Runners (2)
- h. BCSD Communicator
- i. NSP Communicator
- j. NRC ENS Communicator If these positions were not staffed, action taken to ensure the function was compensatory was performed?
- 2. Did the Boardwriter establish communications with the Control Room and initiate status hoard update on arrival?
Page 1 of 4
0 DCCNP ERE - CI. 11 Yes No N/A DENEB'~~ COMMUNICATIONS ACTIVITIES
- 1. Did the Communications Director implement PMP 2081 EPP.10" TSC Emergency Communications?
- 2. Did each communicator follow the general guidance providec in the respective attachment of PMP 2081 EPP.302?
Board'writer - Attachment 2
- b. Telecopy Operator-Attachment 3 C. EOF Runner-Attachment 4
- d. BCSD Communicatox-Attachment 6
- e. AEPCS Communicator - Attachment S MSP Communicator-Attachment 7
- g. NRC ENS Communicator-Attachment 8 NRC HPN Communicator-Attachment. 9
- i. JP IC Communicator-Attachment 10
- j. EOF Scribe-Attachment 11
- 3. Was document transmission completed in accordance with Attachment 1 of PMP 2081 EPP.302?
Did each of the following communicators appear familiar with applicable EPP's and communications equipment?
- a. Boardwriter
- b. AEPSC Communicator
- c. MSP Communicator
- d. BCSD Communicator
- e. JPIC Communicator
- f. EOF Scribe Page 2 of 4
DCCNP ERE - CL 1'es No NjA
- g. NRC ENS Communicator
- h. NRC HPN Communicator i . Runners j .. Telecopy Operator
- 5. Were inquiries received by communicators from other facilities documented and processed in a timely manner?
- 6. Was the Nuclear Plant Accident Notification Form completed accurately every 15 minutes?
- 7. Was the Nuclear Plant Accident Notification Form transmitted to the .MSP every 15 minutes?
COMMUNICATIONS E UIPMENT Document the operability of the following communications equip-ment. Spot-check telephones and document operability in OTHER section. It may be necessary to question communicators on equipment operability. E UIPMENT PERABLE INOPERABIE PROBLEM NOTED TELECOPIER PHOTO-COPY MACHINE TEST-TELE HEADSET AEPSC COMM. PHONE BCSD COMM. PHONE MSP COMM. PHONE COMM. DIR. PHONE RADIOS JPIC COMM. PHONE OTSC SSD TERMS RDDS TERMINAL NRC ENS COMM. PHO NRC HPN COMM. PHO OTHER Page 3 of 4
J' DCCNP ERE - CL 13. ( D. CONNENTS Oi~&1ENT CHECKLIST CONMENT NO. REFERENCE Page 4 of 4
I DCCNP ERE - CL 12 DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE CHECKLIST NO. 12 APPLICABLE STATION: EOF ENVIRONMENTAI ASSESSMENT CONTROLLER DATE OF EXERCISE: TIME INITIATED: EVALUATOR: ACTIVATION Yes No N
- 1. Were the following positions staffed within one hour of emergency declaration?
- a. Environmental Assessment Director
- b. Environmental Assessment Coordinator
- 3. Was the EOF ARM energized and verified to be in proper working order?
B. IMMEDIATE ACTIONS
- 1. Did the EAD/EAC conduct a review of RDDS monitor indications in accordance with Step 4.4.4 of PMP 2081 EPP.303?
- 2. Was a meteorological forecast obtained in accordance with Step 4.4.1 of PMP 2081 EPP.303?
- 3. Was a dose projection performed in accordance with PMP 2081 EPP.304, Dose Projection?
- 4. Were Off-site Radiation Monitoring Teams requested from the OSA?
C. SUBSE UENT ACTIONS
- 1. Did the EAC provide adequate support to the EAD in determining adequate off-site dose projections and protective action recommendations?
Page 1 of 6
DCCNP ERE - CE 12 Yes No N
- 2. Was the State Notification Form completed and transmitted every 15 minutes in accordance with PMP 2081 EPP.303, Attachment 1?
- 3. Were Off-site RMT's dispatched to confirm off-site radiation levels' Did EAD turnover include the following?
- a. Verbal turnover
- b. PMP 2081 EPP.303, EXHIBIT-D, Off-site Radiological Assessment Turnover Checklist Was potassium iodide administration considered for Off-site RMT's in accordance with PMP 2081 EPP.212?
D. OFFSITE DOSE ASSESSMENT
- 1. Was a dose projection calculated in accordance with PMP 2081 EPP.304?
- 2. Did the EAC perform dose assessment in accordance with Section 4.5.3 of PMP 2081 EPP.303 for unmonitored releases?
- 3. Were the field teams prepositioned for possible escalation of classification?
- 4. Was the containment, EQCA sequence considered for dose projections?
- 5. Were dose calculations verified by field data?
- 6. Were dose projections recomputes for every change in meteorological or radiation release data?
Did the emergency DAP sign-on procedure work properly? Page 2 of 6
J 4T
%tv
DCCNP ERE - CI 12 Yes No
- 8. Were communications and interface with the Canton Computer Center effective?
- 9. Did dose assessment, personnel fill Accident Notification Form in accordance out the with EXHIBIT-A of PMP 2081 EPP.304?
- 10. Were calculated results in close proximity to scenario predictions?
I ME SCENARIO PREDICTIONS CAiCULATED RESUITS
- 11. Did a protective action recommendation notification of general accompany initial emergency?
- 12. Were release duration predictions properly incorporated into dose assessment?
FIELD MONITORING
- 1. Was FMT prepositioning performed in accordance with section 4.7.2 of PMP 2081 EPP.303?
- 2. Was the cc}unting team position'ed outside of the plume?
- 3. Was plume tracking planning effective?
Page 3 of 6
DCCNP ERE - CL 12 Yes No
- 4. Was plume definition performed in accordance with Section 4.7 of PMP 2081 EPP.303?
PROTECTIVE ACTION RECOMMENDATIONS
- 1. Was the dose-saving effectiveness of protective acions considered by the EAD?
- 2. Was a protective action recommended to the State within 15 minutes of general emergency declaration>
- 3. Was the Protective Action Worksheet (Attachment 1, PMP 2081 EPP.305) completed in accordance with section 4.4 of PMP 2081 EPP.305?
- 4. Was the basis for protective action recommendation included on the State Notification Form?
- 5. If applicable, was the Core/Containment Status Worksheet completed in accordance with Section 4.5 of PMP 2081 EPP.305?
)
GENERAL ITEMS Did the EAC provide adequate support to each of the following groups?
- a. Field Monitoring Teams
- b. OSA-Radiation Protection Director
- c. EOF-Environmental Assessment Director
- 2. Did the following procedures provide adequate information to the EAC for performance of activities?
a ~ PMP 2081 EPP.301, Activation and Operation of the Emergency Operation Facility
- b. PMP 2081 EPP.304, Off-site Radiological Assessment
- c. PMP 2081 EPP.305, Protective Action Recommendations
- 3. Were adequate supplies, equipment and reference 'documentat.
available to perform the EAC function'? Page 4 of 6
DCCNP ERE - CE, 12 H. SCENARIO DEFICIENCIES T1:e following deficienci'es in scenario content were noted: Page 5 of 6
1 P l
~ I I ~ o ~
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE OFF-SITE AGENCY PARTICIPATION This exercise will be an unannounced, off-hours exercise as required by NUREG-0654/FEMA-REP-l, Rev. 1 and will include partial participation by the State of Michigan and full participation by Berrien County.. ERE-90 5-1
DONALD .C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE NARRATIVE
SUMMARY
INITIAL CONDITIONS: Unit 2 at 100% Power RCS Boron = 61 ppm EOL 17,500 MWD/MTU Days on line = 184 Power History 100% for 20 days 55% for 2 days 100% for 32 days Emergency power out of service due to lightning strike 12 hours earlier ~ NRV-151 isolated due to leakby
~ NRV-152 isolated due to NMO-152 being stuck closed I
NARRAT VE: The simulated events take place at the Unit 2 end-of-cycle (17,500 MWD/MTU) and begin to unfold in the early hours of April 3, 1990. Shortly after 0100 with initial plant conditions basically unremarkable (with the exception of emergency power being out of service due to lightning) an acoustical monitoring system (DMIMS) alarm is received in the Unit 2 Control Room. The audible "clanging" sounds picked up in three different locations in the Reactor Coolant System (RCS) reasonable indicate the presence of multiple, loose, solid objects (" loose parts") in the RCS that could, and in fact do, prove to be damaging to the system. Almost simultaneous with that alarm number 4 reactor coolant pump begins to vibrate with ever increasing intensity until an alarm is received for that condition also. Shortly after 0130 secondary system radiation levels increase prompting a decision to begin a 10%/hr. controlled shutdown with a subsequent decision to declare an UNUSUAL EVENT at .approximately 0147. All necessary notifications are made. ERE-90 6-1
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE NARRATIVE
SUMMARY
(CONTINUED) The primary to secondary leakage rate continues to increase and at approximately 0208 the operators are aware that has become significant and'trip the unit at 0210. An ALERT it is immediately declared followed by'otification of emergency personnel. Upon unit trip, safety injection occurs, plus reserve feed trips resulting in loss of offsite power. AB diesel generator indicates an incomplete start but CD diesel does start and load. Shortly thereafter (0223) control air valve XCR-102 .will not open, effectively eliminating the ability to depressurize. When the TSC, OSA and EOF become operational, teams are dispatched to monitor onsite and offsite radiation levels (none as of yet) and coolant system activity; repair valve XCR-102 and AB diesel generator and; investigate reserve feed problems and a leaking 04 steam generator stop valve. At approximately 0445 a significant release starts because the f4 Power Operated Relief Valve (PORV) opens. An alarm is immediately received from the PORV radiation monitor. EOF dose assessment projections indicate Protective Action Recommendations (PAR) leading to a GENERAL EMERGENCY declaration. During the next two hours electrical power is restored and XCR-102 is repaired. The release rate decreases as the stuck open 44 PORV and restored equipment depressurizes the system. This diminishing release rate is such that ALERT level PARs are reached shortly after 0700 and recovery planning and operations can begin. The exercise will terminate at approximately 0800. ERE-90 6-2
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE 'EXERCISE NARRATIVE
SUMMARY
(CONTINUED) TIMELINE: REAL SCENARIO TIME TIME EVENT/CONDITION 0100 00:00 Initial Conditions 0115 00:15 DMIMS alarm and 424 RCP vibrations indicating above normal levels (2.4 mils ) 0117 00:17 f24 vibrations trending upwards-now at 2.7 mils. 0119 00:19 f24 vibration at 3.2 mils 0122 00:22 f24 vibrations at 5.0 mils. Call is placed to J.R. Sampson, OPS Superintendent informing him of the situation. 0127 00:27 424 vibration reach 7.0 mils and alarm is received. 0133 00:33 Steam Jet Air Ejector (SJAE), Gland Steam Leak-off (GSLO) and blowdown RMS alarms are received. Crew begins checking steam generator for signs of leakage. 0135 00:35 Lab sample of secondary side is requested. 0138 00:38 Operations Superintendent is called again and a decision is made to begin controlled shutdown at 10%/hr. unless the situation worsens. 0144 00 44 Increased shutdown rate initiated by indications of increasing primary to secondary leakage. 0147 00:47 SS declares UNUSUAL EVENT based on ECC-14 and 17. ERE-90 6-3
h DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE NARRATIVE
SUMMARY
(CONTINUED) REAL SCENARIO , TIME TIME EVENT CONDITION 0150 00'50 SS calls Unit 1 to request initial notifications be made and to call him back when they are completed. He also requests additional manpower from Unit l. 0156 00:56 Chem Lab reports that secondary samples have high activity. 0208 01:08 Leak rate now ~ 500 gpm. 0210 01:10 Unit manually tripped; safety injections started and 524 Reactor Coolant Pump is stopped. 0210 01:10 SS declares ALERT based ECC-14 and ECC-17. 0211 01:11 Blackout occurs, train B is lost and AB diesel fails to start. 0223 01:23 Control air valve XCR-102 fails to open resulting in loss of control air to containment. 0217 01:17 Emergency Response Organization call out begins. 0230 01:30 Contingency for declaring ALERT. 0313 02:13 All Emergency Response Facilities activated.'n-site 0320 02:20 and off-site radiation monitoring teams dispatched. 0330 02:30 PASS team dispatched. ERE-90 6-4
Ew DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE NARRATIVE
SUMMARY
(CONTINUED) REAL SCENARIO TIME TIME EVENT CONDITION 0345 02:45 Teams dispatched from OSA to: Repair XCR-102 Repair AB diesel Find out why 54 S/G stop valve is leaking 0445 03:45 g4 PORV opens. 0446 03:46 PORV radiation monitor MRA-2602 alarms. 0455 03:55 EOF declares GENERAL EMERGENCY based on site boundary dose projections. 0505 04:05 Team be dispatched to see closed. if PORV can 0515 04:15 Contingency EOF declares GENERAL EMERGENCY if not done at 0455. 0515 04:15 XCR-102 is repaired. 0532 04:32 PORV team encounters turn-back dose. I 0540 04:40 AB Diesel is restored. 0550 04 50 RHR is aligned. 0605 05:05 PASS Team returns with results. 0642 05:42 RHR is in service. 0656 05:56 Reserve power is restored. 0715 06:15 Dose projections indicate rad levels below alert PARs. De-escalate to ALERT. 0720 06:20 Begin recovery operations. 0800 07:00 TERMINATE EXERCISE. ERE-90 6-5
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE VII. EXERCISE MESSAGES AND PLANT DATA SHEETS A. PLANT DATA CURVES B. CONTROLLERS MESSAGES C. PLANT OPERATING DATA D. THERMOCOUPLE MAPS ERE-9 0
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE VII. A. PLANT DATA CURVES This section provides Control Room and TSC Controllers with selected primary and secondary plant parameters in graphic format. Controllers will provide time specific data upon request from participants. TABLE OF CONTENTS GRAPH PARAMETER Containment Temperature Containment Hydrogen Concentration RWST Level Source Range Indication 5 Intermediate Range Indication Containment Pressure Containment Sump Level Containment Level CTS Pump Status 10 RHR Spray Flow Safety Injection Pump Flow 12 Boron Injection Flow 13 Accumulator Pressure 14 RHR Injection Flow 15 Reactor Coolant Pump Status 16 Reactor Coolant System Pressure (WR) 17 Charging Flow 18 Pressurizer Liquid Temperature ERE-9 0
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE VI1. AD PLANT DATA CURVES CONTINUED GRAPH PARAMETER 19 Pressurizer Steam Temperature 20 Pressurizer Level 2 1/22/23 PRT Temperature, Level & Pressure 24/25 Pressurizer Heater Status 26 Letdown Flow 27 Saturation Margin F 28 T-HOT, Wide Range 29 T-COLD, Wide Range 30 Steam Generator Pressure 31 Steam Generator Level, (NR) 32 Steam Generator Level, (WR) 33 Steam Flow 34 Feed Flow 35 Auxiliary Feed Flow 36/38 Steam Flowpath, Atmos/Dump 37 Condensate Storage Tank Level Parameters not addressed graphically, but which to the scenario are given in appropriate messages.are significant ERE-9 0
CONTAINMENT TEMPERATURE VS. TIME CONTAINMENT TEMPERATURE F 120 100 90 80
?0 60 -
30 20 10 II! t II I >'l t" Il! I I II I !It t I I I I I t I I II t t It I 1:00 2:00 3:00 4:00 6:00 6:00 ?:00 8:00 Tl ME 3APR90 THIS IS A DRILL
CONTAINMENT H CONC. VS. TIME
% HY.DROGEN 2.75 2.6 2 .25 2
1.75 1.5 1.25 0.76 0.5 0.25 I/$ I />I%I/f'$C ~ Ilail/ I I iI I I I I I I I I I I I / 0 I I I I I I 100 200 3:00 400 500 600 700 800 Tl M E 3APR90 THIS IS A DRILL
REFUELING WATER STORAGE TANK (RWST) LE VE L VS. Tl ME RWST LEVEL % RWST LEVEL GAL X E+03 100 420 95 399 85 I 378 357 80
?5 70 t 336 315 294 65 273 60 252 55 231 50 210 45 189 40 168 35 147 30 Z 126 Z 105 20 T 84 157 63 10 42 5Z 21 0
II III'II II III II" I I I I II I II I I I I I I I I I 0 100 200 300 400 500 600 700 800 TIME 3APR90 THIS IS A DRILL
SOURCE RANGE VS. T!ME SOURCE RANGE IN LOG CPS 1000000 II 100000 10000 1000 II I I 100 lt 10 I I s I II II I I I I I I III I II lllli IIII> I I I ! 1:00 2:00 3:00 4:00 5:00 6:00 7:00 8:00 TIME 3APR90 THIS IS A DRILL
INTERMEDIATE POWER RANGE VS. TIME INTERMEDIATE POWER RANGE IN AMPS 1.000E -03 = L 1.000E -04 1.000E "05 = i 1.000E -06 I
=
1.000E-O? = l ~ I= 1.000E -08 = k ldll 1.000E -09 = 1.000E-10 = F 1.000E-11 =. L IllII t I II II i I II
.OOOE 12 I I I 1:00 2:00 3:00 4:00 5:00 6:00 ?:00 8:00 TIME 3APR90 THIS IS A DRILL
CONTAINMENT PRESSURE VS. TlME CONTAINMENT PRESSURE PSIG 0.9 0.8 0.7 0.6 0.6 0.4 0.3 0.2 0.1 "
>II'>I> I' I II I'<ll' II I I!I I ' >
I II I I II I! I I II I I II ' II 0 I ! I I I
~
1:00 2:00 3:00 4:00 6:00 6:00 7:00 8:00 TIM E 3APR90 THIS IS A DRILL
GONTAINMENT SUMP LEVEL VS. TIME CONTAINMENT SUMP LEVEL 100 90 80 70 60 50 40 30 T 20 0 l l l 3 t IIIlIlll I ( ill I It I lI l I l l l l l I I I ' I l if I I I ' i I I l < 5 I I I I I l 1:00 2:00 3:00 4:00 5:00 6:00 7:00 8:00 TIME 3APR90 THIS IS A DRILL
CONTAINMENT LEVEL VS. TIME CONTAINMENT LEVEL % 100 90 80 70 GO 30 20 (<< (< < I I 1:00 2:00 3:00 4:00 6:00 6:00 7:00 8:00 TIME 3APR90 THIS IS A DRILL
CTS PUMP STATUS VS. TIME PUMP. STATUS EAS OFF ON YYEST OFF I Ill<If<fluff<i I< I I I f l < If> 20 li00 Z;00 Si00 440 540 8(00 Ti00 Si00 TIME SAPAOO SAFETY INJECTION PUMP FLOW VS. TIME SOUTH Sl PUMP FLOW GPM 300 280 280 240 2ZO 200 IGLOO 180 180 140 120 100 80 80 40 20 0 140 2;00 %00 4i00 540 TABOO $ 00 TIME OAPRQO THIS IS A DRILL
BORON INJECTION FLOW VS. TIME . FLOW GPM 116 LOOP1 0 115 LOOP 2 0
/
115 LOOP 3 75 0 / 115 LOOP 4 P I < I I < I " * < I
'~'~
I I '~ I I I I I I I III I If II I I i I I I I 1:00 2:00 3:00 4:00 6:00 6:00 7:00 8:00 Tl M E 3APR90 THIS IS A DRILL 12
ACCUMULATOR PRESSURE VS. TIME ACCUMULATOR PRESSURE PSIG 700
~ ~ ~ ~ I I ~
TK1 AND TK3 600 500 400 300 200 100 TK2 AND TK4 ( I( ( (( ( (( '( ( ( I I I I I ( 1:00 2:00 3:00 4:00 5:00 6:00 7:00 8:00 TIME 3APR90 THIS Is A DRILL
RHR INJECTION FLOW VS. TIME EAST AND WEST FLOW GPM 1500 1000 500 I~ It I> I I II II II 0 I I I I I 1:00 2:00 3:00 4:00 5:00 6:00 7:00 8:00 Tl ME 3APR90 THIS IS A DRILL 44
REACTOR COOLANT PUMP STATUS VS. TIME REACTOR COOLANT PUMP STATUS OFF j ON 2 OFF I r i ~ ~ ~ ON t. OFF r r r r r r r r ir I r r 4 I OFF
~ I ' Ill I ' I > II I III I I I I I I I ' I I I I I I I 1:00 2:00 3:00 4:00 6:00 6:00 7:00 8:00 TIME NUMBER 1 NUMBER 2 NUMBER 3 NUMBER 4 3APR90 THIS IS A DRILL 16
REACTOR COOLANT SYSTEM PRESSURE (W.R.) VS. TIME R CS PRESSURE WIDE RANGE PS IG 2600 2400 ~ 2200 2000 1800 1600 1400 1200 1000 800 T 600 400 200 I I I I I 1:00 2:00 3:00 4:00 5:00 6:00 7:00 8:00 TIME 3APR90 THIS IS A DRILL 16
CHARGING FLOW VS. TlME CHARGING FLOW GP M 400 300 200 100 II IIIII II < I II 'I I I I I I I I I
'l00 200 300 400 600 600 700 800 Tl M E 3APR90 THIS IS A DRILL 17
PRESSURIZER LIQUID TEMPERATURE VS. TIME 0 PRESSURIZER LIQUID TEMP F 700 650 600 550 500 450 400 350 300 250 200 ~ 150 ~ 100 III IIIIIIIIIIII I I II I II I I I I I ' I II I I 1:00 2:00 3:00 4:00 5:00 6:00 7:00 8:00 TIME 3APR90 THIS IS A DRILL 18
PRESSURIZER STEAM TEMPERATURE VS. TIME 0 PRESSURIZER STEAM TEMP F 700 650 600 560 600 450 400 350 T 300 260 200 150 100 III I IIIIIII I I I I I I I I Ill I I 100 200 300 400 500 600 700 800 TIME 3APR90 THIS IS A DRILL 19
PRESSURIZER LEVEL VS. TIME PRESURIZER LEVEL % 110 100 ~
'0 80 70 60 40 30--
20 Ill!'I!a'III II'IIII! I I I I I I I I I I I I I 1:00 200 300 400 6:00 600 700 800 Tl M E SAPR90 THIS IS A DRILL 20
P RT TEMPERATURE VS. TIME 0 PRT TEMPERATURE F 150 140 130 120 100 90 80 70 60 I I I I 1:00 2:00 3:00 4:00 5:00 6:00 7:00 8:00 TIME 3APR90 THIS IS A DRILL 21
PRT LEVEL VS. TIME PRT LEVEI '/0 100 95 90 85 80 75'0 65) 60 55 50 45 40 35 30 25 20 15 10 5 I I II I I 'I II I II II I II I I I II II I IIIIIIIIIIIII I II 0 I I I I 1:0 0 2:00 3:00 4:00 5:00 6:00 7:00 8:00. TIME 3APR90 THIS IS A DRILL 22
PRT PRESSURE VS. TIME PRT PRESSURE PSIG
'to I II I I I II I ! II I I I I I I I I I I I II I IIIIIII>I 1:00 .2:00 3:00 4:00 5:00 6:00 7:00 8:00 T IM E 3APR90 THIS IS A DRILL 23
PRESSURIZER HEATER STATUS VS. TIME PRESSURIZER HEATER STATUS PZR CYCLING'TR'FF PZR BACKUP HTR I I I I OFF II I I I I I' I !IIIIIIII I I I I I I II I I I I I I I 1:00 2:00 3:00 4:00 6:00 6:00 7:00 8:00 TIM E 3APR90 THIS IS A DRILL 24/25
LETDOWN FLOW VS. TIME LETDOWN FLOW GP M 100 90 80 70 60 40 30 20
~ t I I I(t I Ill 1:00 2:00 3:00 4:00 5:00 6:00 7:00 8:00 TIME 3APR90 THIS IS A DRILL 26
SATURATION MARGIN VS. TIME 0 SATURATION MARGIN F 200 180 160 - 140
. 120 100 80 60 40 ~
20 I I11I II I II I tI I I I II I I I I I I I I I I I I II I I 1:00 2:00 3:00 4:00 5:00 6:00 7:00 8:00 TIME 3APR90 THIS IS A DRILL 27
WIDE RANGE THOT VS. TIME 0 HOT 700 650 600 550 g'00 LOOP 2/3 450 400 350 300 250 200 LOOP 1/4 100 50 T T-I I I I I I I II I 0 1:00 2:00 3:00 4:00 5:00 6:00 7:00 8:00 TIME 3APR90 THIS IS A DRILL 28
WIDE RANGE TCOLD VS. TIME 0 E G
?00 coL F 650 600 550 500 LOOP 2/3 450 400 350 300 250 200 150 LOOP" 4' 100 LOOP-1 I I I I I I r A I I I I I ( I 1:00 2:00 3:00 4:00 5:00 6:00 ?:00 8:00 TIME 3APR90 THIS IS A DRILL 29
STEAM GENERATOR PRESSURE VS. TIME STEAM GENERATOR PRESSURE PSIG 1100 1000 S/8 4 900 800 700 600 500 ....S/8 1/2/3 400 I-300L I I 200 I I I 100 r I I I I l I I I I I I I I I I I II I I I I 1:00 2:00 3:00 4:00 5:00 6:00 7:00 8:00 Tl M E 3APR90 THIS IS A DRILL 30
NARROW RANGE STEAM GENERATOR LEVEL VS. TIME NARROW RANGE STEAM GENERATOR LEVEL % 100 S/G 4 90 80 70 60 S/G 1/2/3 50 I I
~ I ~ ~
40 30 20 10 n 1 I>> >I ~ >I I II I I 11 1 I I III I I II Il lil 1:00 2:00 3:00 4:00 5:00 6:00 7:00 8:00 S/G 1/2/3 ~ S/G 4 SAP R90 THIS IS A DRILL 31
WIDE RANGE STEAM GENERATOR LEVEL VS. TIME WIDE RANGE STEAM GENERATOR LEVEL % 100 90 80 S/6 4 70 II I
~ I 60 S/G 1/2/3 50 40 30 20 II II I I II II I I I 1:00 2:00 3:00 4:00 5:00 6:00 7:00 8:00 TIME ~ S/G 1/2/3 = S/G 4 3APR90 THIS IS A DRILL 32
STEAM FLOW VS. TIME ST EAM F LOW L BS/HOUR E+03 4000 3000 2000
't 000 I II I I I I 0 I 1:00 2:00 3:00 4:00 6:00 6:00 ?:00 8:00 TIME 3APR90 THIS IS A DRILL 33
FEED FLOW VS. TIME FEED FLOW LBS/HR X E+03 4000 3600 3000 2600 2000 1500 -
't 000 500 I I I 0
1:00 2:00 3:00 4:00 5:00 6:00 ?:00 8:00 TlME SAPR90 THIS IS A DRILL 34
AUXILIARYFEED FLOW VS. TIME AUXILIARYFEED FLOV/ LBS/HR X E+03 200
't 80 't 60 't 20 LOOP 1/2/3 100 =
80 60 40 20 0
'.I'llLOOP 4 IS ZERO ~ ~
11 I I I I I I I I I I I < 1:00 2:00 3:00 4:00 5:00 6:00 7:00 8:00 TIME LOOP 4 LOOP 1 LOOP 2 LOOP 3 3APR90 THIS IS A DRILL 35
STEAM FLOWPATH VS. TIME STEAM GENERATOR STOP VALVES ATM OS STEAM DUMP COND OPEN I I I I I 41 CLOSE 0, OPEN 2 CLOSE OPEN 43 CLOSE OPEN 44 r ~ r r r r / r / r CLOSED IIIII I I III II I I I I I I I I I I I I I 2:00 3:00 4:00 6:00 6:00 7:00 8:00 T IM E STEAM DUMP ~ ~ STOP VLV 3 ~ STOP VLV STOP VLV 4 1 STOP VLV 2 3AP R90. THIS IS A DRILL 36/38
CON DE N SATE STO RAG E TANK LEVEL VS. TIME CST LEVEL % CST LEVEL FEET 100 30 90 27 80 70 2'1 60 18 50 15 40 12 30 20 -
'10 I I I II 0 I I I I 0
1:00 2:00 3:00 4:00 5:00 6:00 7:00 8:00 T IM E 3APR90 THIS IS A DRILL 37
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE VII. B. CONTROLLER MESSAGES The fol1 owing forms represent the means by which information required to prompt a response from players, and provide the Controller with general guidance, is provided. The messages are not given directly to players. This series is for Controllers only. These messages are available to continue exercise play in the event of simulator malfunction. Because of the additional free-play permitted and subsequent variance from a preplanned time line, it is possible that adjustments will have to be made in delivery times of controller messages from the times stated the messages are needed. if ERE-90
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: Time: 0045 MESSAGE FOR: Control Room This exercise is a full participation exercise by the Berrien County Sheriff's Department and a partial participation by the Michigan State Police. Phone numbers to be used during initial notification are: Michigan State Police Number used in PMP 2080 EPP.106, Exhibit B Berrien County Sheriff Number used in PMP 2080 EPP.106, Exhibit B NRC ENS to be announced NRC HPN to be announced CONTROLLER USE ONLY Establish the communication systems that are to be used AND NOT to be used during the exercise. Review basic rules of participation with the shift personnel. (See Section III, "Conduct of Exercise" )
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: Time: 0045 MESSAGE FOR: Control Room INITIAL CONDITIONS ~ 100% Power
~ NRV-151 isolated due ~ RCS CB 61 ppm to leakby ~ EOL 17<500 MD/MTU ~ NRV-152 isolated due to NMO-152 being stuck ~ Emergency power out of service closed. after being hit by lightning strike 12 hrs. earlier. ~ Days on line 184 ~ Power history for previous 30+ days 100% for 20 days 55% for 2 days 100% for 32 days CONTROLLER USE ONLY Give Control Room operators copies of Log Book, Turnover Book and Outage Buster Daily Update Sheet containing initial conditions.
NOTE: Other key Plant personnel would receive/know this information from the previous morning meeting. Give copy to TSC, EOF a OSA controllers to distribute.
, DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.:
Time: 0100 MESSAGE rOR: Control Room Conditions as displayed on panels start of exercise. CONTROLLER USE ONLY
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: Time: 0115 MESSAGE FOR: Control Room Annunciator 207, drop 90 alarms. Digital Metal Impact Monitor System activated. CONTROLLER USE ONLY USE OiNTY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: Time: 0115 MESSAGE FOR: Control Room PMP 2080 EPP.103, Exhibit A data CONTROLLER USE ONLY US" ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: Time: 0116 MESSAGE FOR: Control Room When operator checks DMIMS cabinet have tape available that has impact noise recorded on it. Play tape and tell operator these alarms are on Channels 760, 752, and 753. (Rx vessel lower primary and secondary detectors and 54 S/G primary detector on hot leg) CONTROLLER USE ONLY Provide only if operator responds to DMIMS cabinet.
DONAI D C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: Time: 0117 MESSAGE FOR: Control Room g4 RCP vibrations increasing upwards now at 2.7 mils. CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: Time: 0119 MESSAGE FOR: Control Room 44 RCP vibrations continue to slowly increase now at 3.2 mils. CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAiLS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: Time: 0122 MESSAGE FOR: Control Room 44 RCP vibrations continue to slowly increase now at 5.0 mils. CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAiLS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 10 Time: 0122 MESSAGE FOR: OPS Superintendent Have Control Room maintain Rx power at 100%. Tell them you will notify Performance to check DMIMS alarm and RCP vibration. CONTROLLER USE ONLY Give message to DMIMS alarm and OPS RCP Superintendent vibration. if notified by Control Room of
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCiSE MESSAGE Message No.: Time: 0127 MESSAGE FOR: Control Room Annunciator 207, Drop 52 alarms. RCP vibration high at 7.0 mils. Levels of f at 7. 0 mils. CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE, EXERCISE EXERCISE MESSAGE Message No.: 12 Time: 0130 MESSAGE FOR: Control Room RMS data Exhibit A data CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 13 Time: 0133 MESSAGE FOR: Control Room Radiation Monitor alarms. R-19 Steam Generator Blowdown Sample Flow SRA-2805 Low alarms SRA-2905 Steam Generator Blowdown Sample Valves close Steam Generator Blowdown Isolation Valves close Provide 0133 RMS Screen facsimile, and Exhibit A. CONTROLLER USE ONLY USE ONLY, IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: Time: 0138 MESSAGE FOR: OPS Superintendent (or alternate) Tell Control Room to begin a controlled shutdown at 10'/hr. unless other conditions develop which warrant an increased power reduction rate. CONTROLLER USE ONLY Give message to OPS Superintendent primary secondary leakage. if notified by Control Room of
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 15 Time: 0140 MESSAGE FOR: Control Room VCT level decreasing .5%/min. Pressurizer level constant Charging flow 97 gpm Letdown flow 75 gpm NOTE: Charging flow control is in automatic. CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE-EXERCISE EXERCISE MESSAGE Message No.: 16, Time: 0143 MESSAGE FOR: Control Room Steam Generator Blowdown Sample Flow Low alarms begin to clear and alarm one at a time as Chemistry Lab takes S/G blowdown samples. CONTROLLER USE ONLY Provide message only t requested S/G samples. if simulator fails AND if Control Room has
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 17 Time: 0145 MESSAGE FOR: . Control Room RMS data Exhibit A data CONTROLLER USE ONLY USE ONLY 1F SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 18 Time: . 0146 MESSAGE FOR: Control Room SRA-2807 alarm (Mid Range on GSLO) CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 19 Time: 0150 MESSAGE FOR: Control Room Contin enc Messa e DO NOT trip unit at this time. CONTROLLER USE ONLY Zn the event a decision is made at this point to trip the unit based on possible fuel damage this should be delayed until approximately 0210.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE'essage No.: 20 Time: 0155 MESSAGE FOR: Chemistry Technician Chemistry has taken S/G samples and calls the Control Room to let them know that its activity is "very high". CONTROLLER USE ONLY
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 21 Time: 0200 MESSAGE FOR: Control Room RMS screen Evhibit A data CONTROLLER USE ONLY USE ONLY. IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 22 Time: 0200 MESSAGE FOR: Control Room - Contin enc Messa e Declare UNUSUAL EVENT if not already declared due to: ECC 14 (U.E. 1) (Fission Product Barriers/Loss of Coolant) ECC 17 (U.E. 1) (Steam Generator Tube Rupture) CONTROLLER USE ONLY
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 23 Time: 0200 (or when SS calls to initiate PMP 2080 EPP.107 Call-out rocedure MESSAGE FOR: Security Don't call: Bill Burgess Doug Noble (Special telephone instructions) I.D. Fleetwood CONTROLLER USE ONLY Provide when SS calls initial call in.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 24 Time: 0210 MESSAGE FOR: Control Room Pressurizer pressure and pressurizer level decreasing rapidly. Pressurizer decreasing > 5%/min. (- 500 gpm leak) CONTROLLER USE ONLY Control Room should trip Rx and initiate SI. USE ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 25 Time: 0211 MESSAGE FOR: Control Room Contingency Conditions after Rx trip and SI.
~ AB D/G incomplete start ~ Reserve Feed trips, offsite power is lost ~ CD D/G starts and loads CONTROLLER USE ONLY Notify Control Room to trip Rx and initiate SI if not done at 0210 hrs.
USE ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 26 Time: 0215 MESSAGE FOR: Control Room RMS screen Evhibit A data CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 27 Time: 0221 MESSAGE FOR: AEO Local indication of g4 Steam Generator Stop is closed. Message dependent on dose rate. Gen. area 130 mR/hr Contact pi'pe 500 R/hr CONTROLLER USE ONLY Provide message only if AEO dispatched locally to steam generator.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: "28 Time: 0223 MESSAGE FOR: Control Room XCR-l02 will not open. CONTROLLER USE ONLY This results in the loss of control air to one of the air headers in containment. USE ONLY IF SIMULATOR FAILS'
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 29 Time: 0230 MESSAGE FOR: Control Room Contin enc Messa e Declare ALERT based on ECC-14 and ECC-17. CONTROLLER USE ONLY Provide message if action not already taken by now.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 30 Time: 0230 MESSAGE FOR: Control Room RMS screen Exhibit A data CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAII S.
DONAI D C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 31 Time: 0237 MESSAGE FOR: Control Room 'NRV-153 will not open. NOTE: NRV-151 and NRV-152 block closed due to loss of gower and. stuck closed valve. CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PIANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 32 Time: 0238 MESSAGE FOR: AEO XCR-102 does not move when operated from Control Room. Air can be heard and felt around the top of the diaphram housing. CONTROLLER USE ONLY Give AEO message only if sent to XCR-102 by Control Room. Dose rate 14 mR/hr general area. Dose rates due to 2R-19 sample lines.
DONAI D C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 33 Time: 0245 MESSAGE FOR: Control Room RMS screen Evhibit A data CONTROLZER USE ONLY USE ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONS EXERCISE EXERCISE MESSAGE Message No.: 34 Time: 0300 MESSAGE FOR: Control Room RMS screen Evhibit A data CONTROLLER USE ONLY USE ONLY IF'SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCiSE MESSAGE Message No.: 35 Time: 0305 MESSAGE FOR: Control Room IMO-120 and IMO-140 power cannot be restored due to blackout. CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 36 Time: 0313 MESSAGE FOR: Control Room TSC, OSA a EOF operational. CONTROLLER USE ONLY Time is contingent on alert declaration time.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCiSE MESSAGE Message No.: 37 Time: See below under "CONTROLLER USE ONZY" MESSAGE FOR: EOF Environmental Assessment Coordinator Forecast meteorological data is as follows: 8 Hr. Forecast 24 Hr. Forecast Wind Direction Variable Variable 324'-355'ariable 290'-325'ariable Nind Speed 5-10 mph 5-10 mph Diff. Temp. -0.7 to 2.0 1.0 to 2.0 Stability Class D-E Precipitation P None CONTROLLER USE ONLY Provide this data when actions are taken to obtain such data from Murray and Trettle. DO NOT allow the players to actually contact Murray and Trettle.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 38 Time: If PET recommends this action for an reason. MESSAGE FOR: PET Team No parts are to be taken from Unit One to repair any damaged equipment in Unit Two., CONTROLLER USE ONLY TSC Controller provides message if a decision is from Unit One to repair Unit Two equipment. made to take parts
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 39 Time: 0315 MESSAGE FOR: Control Room, TSC, EOF RMS data Exhibit A data CONTROILER USE ONLY USE ONLY IF SIMUZATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 40 Time: 0330 MESSAGE FOR: Control Room, TSC, EOF RMS data Evhibit A data CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: Time: 0345 MESSAGE FOR: Control Room, TSC, EOF RMS data Exhibit A data CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAIZ S.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: - 42 Time: When PAS Team at sam lin anel. MESSAGE FOR: One Member of PAS Team Two drops of the sample fall from the end of the needle and land on his/her anti-Cs just above the knee on the right leg. through and contaminates his/her leg. It soaks When frisked, the area reads 94,000 cpm. CONTROLLER USE ONLY
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 43 Time: 0345 MESSAGE FOR: Control Room, TSC, EOF RMS data Evhibit A data CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAILS.
r DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 44 Time: 0400 MESSAGE FOR: Control Room, TSC, EOF RMS data Exhibit A data CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 45 Time: 0405 (or when team arrives at Diesel whichever is latest MESSAGE FOR: AB Diesel Repair Team Governor-bar linkage broken (completely through) CONTROLLER USE ONLY Provide message to team when inspection of governor linkage is in progress. Do not allow parts to be taken from Unit One to repair Unit Two AB Diesel.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No'.: 46 Time: 0415 MESSAGE FOR: Control Room, TSC, EOF RMS data Evhibit A data CONTROLLER USE ONLY .USE ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE, E:EXERCISE MESSAGE Message No.: Time: 0430 MESSAGE FOR: Cont~ol Room, TSC, EOF RMS data Evhibit A data CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCiSE MESSAGE Message No.: 48 Time: 0445 (or when team arrives at XCR-102, whichever is later) MESSAGE FOR: XCR-102 Repair Team Air can be heard and felt around the. top of the diaphram housing. CONTROLLER USE ONLY Provide message to team when they arrive at valve. Dose rate 14 mR/hr general area. Dose rate due to 2R-19 sample line (80 mR/hr contact with sample line) .
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 49 Time: 0445 MESSAGE FOR: Control Room, TSC, EOF RMS data Evhibit A data CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PI ANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 50 Time: 0446 MESSAGE FOR: Control Room 44 S/G pressure decreasing rapidly, MRA-2602 high alarm (5.50 E+3 uCi/cc). CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAII S.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Me'ssage No.: 51 Time: 0450 MESSAGE FOR: EOF RMS data Evhibit A data CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 52 Time: 0500 MESSAGE FOR: Control Room, TSC, EOF RMS data Exhibit A data CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 53 Time: 0515 MESSAGE FOR: EOF - Contin enc Messa e Declare General Emergency ECC-19. CONTROLLER USE ONLY Provide at this time if not already declared.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 54 Time: 0515 MESSAGE FOR: XRC-102 Repair Team Contin enc Messa e XRC-102 is repaired. CONTROLLER USE ONLY IF it looks like simulated repairs will continue beyond 0525 then provide this message now so scenario stays on track.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 55 Time: 0515 MESSAGE FOR: Control Room, TSC, EOF RMS data Exhibit A data CONTROLLER USE ONLY USE ONLY 1F SIMULATOR FAILS.
.thA DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 56 Time: 0530 MESSAGE FOR: Control Room, TSC, EOF RMS data Exhibit A data CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 57 Time: 0532 (or when team ets within a rox. 1 foot from valve MESSAGE FOR: ¹4 PORV Team Team encounters 288 Rihr at 1 foot from valve. CONTROLLER USE ONLY
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 58 Time: 0540 MESSAGE FOR: AB Diesel Repair Team Contin enc Messa e AB diesel is repaired. CONTROLLER USE ONLY If it appears that simulated repairs will continue beyond 0545 provide this message now so scenario stays on track.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE I EXERCISE MESSAGE Message No.: 59 Time: 0545 MESSAGE FOR: Control Room, TSC, EOF RMS data Exhibit A data CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 60 Time: 0550 MESSAGE FOR: Control Room AEO reports that RHR is aligned. CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE. Message No.: 61 Time: 0600 MESSAGE FOR: Control Room, TSC, EOF RMS data Exhibit A data CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAILS'
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 62 Time: 0615 (or when new hi her turn back dose is rovided MESSAGE FOR: f4 PORV Team SCBA air bottles need changing (if not already, done). CONTROLLER USE ONLY Purpose of this message is to delay team so valve is not repaired.
DONAI D C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 63 Time: 0615 MESSAGE FOR: Control Room, TSC, EOF RMS data Evhibit a data CONTROLLER USE ONE Y USE ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: Time: 0630 MESSAGE FOR: Control Room, TSC, EOF RMS data Exhibit A data CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 65 Time: 0642 MESSAGE FOR: Control Room RHR is in service. CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 66 Time: 0645 MESSAGE FOR: Control Room, TSC, EOF RMS data Exhibit A data CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 67 Time: 0656 MESSAGE FOR:. Control Room Reserve Po~er is restored. CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 68 Time: 0700 MESSAGE FOR: Control Room, TSC, EOF. RMS data Exhibit A data CONTROLLER USE ONLY NOTE: At this point RMS data should be shoving low enough site boundary levels to justify de-escalating to ALERT level. USE ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 69 Time: 0715 MESSAGE FOR: Control Room, TSC, EOF RMS data Exhibit A data CONTROLLER USE ONLY USE ONLY IF SIMULATOR FAILS.
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE EXERCISE MESSAGE Message No.: 70 Time: 0730 MESSAGE FOR: Simulator Instructor Contin enc Messa e If PORV Rad. Monitor is reading greater than 1 pCi/cc at 0730 close 44 PORV to terminate exercise on time. CONTROLLER USE ONLY
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE VII. C. PLANT TECHNICAL DATA This section represents data as. a direct facsimile of the Technical Information Sheet in PMP 2080 EPP.103, Exhibit A. This time specific data will be provided by the Controller when appropriate. ERE-90
PHP 2080 EPP.1.03 EWIBIT A
."cuw cap w o<<<pioN spse I;oio Jo: 4 Da "a~4b 'RO pime CO Data Taken Bv Data Reviewed Bv NOT.
When redurdant indication exists, record most severe condition. RCS P. M~T~R
- 1. Containpent Temp.
- F 5. Intermediate Range 3. +E-0 A fPS 1 Cont. H, Concentration
- 6. Containment Pressure CO PSZG
- 3. EST Level * ? . Containment Sump Level*~~8 4I Source Range
- CPEi 8. Containment -Leve 1 *~~%
9. 10 CPS Pumps RHR Spray Flow Eas East*
- ON Q
/ ~F GPA West*
Esse S t* ON / ~ GP.t 11 Sl Flow Norah~a 'outh* GPH 11 ."low LPl* O GP.'i GPA'IT LP2+ 0 GPA LP 3* C) LP4* CO GP.".
'lKF~GPA GPA'P Accum Pressure LP2+~QG?.'f 3*~~>G LP4*~QQGP< ~
13 PH 1 '.4 RHR In)ect'on F'ow East+ C7 GPH Wes t* 0 *LP4 GP.'f
'5 RCP Status <<LPl QO.p/ OFF *LP2 l / OFF *LP3 / OFF OFF Q. RCS Pressure PSIG 22. PRT Level
- 17. Charging Flow GPA 23. PRT Pressure PSZG 18 PZR Liquid Temp. F 24. PZR Cycling Htrs. / OFF OFF 19
'l0 PZR Sceam Temp.
PZR Level O~ 25. 26. PZR Backup Htrs. Letdown Flow GPA
/
Ol PRT Temp. o~ 27. Sacuration Hargin oF F OOP Q +MPTZQS oo Looo ~oo Wide Range T Ho" op ~~o ( COF
~S F ;a O W de Range T Cold F F 30 S/G Pressure PSIG PSIG ?S G ll Sr'G N.R. Level O
S /G W.R. Les el I 33 Steam F'ow (pph X 10 ) ~~<~ ~+04~ Feed Flow (pph X 10 ) 35 eed Flow(oph 'i 10 3 36 wSPP Saaaus O / CLOSE P S CLOSE ~PC"O. OPE.. CLOSE 37 Level + I 8 * +~Ft ~ SE'ST 38 Steam Dump *ATMOS / COL U PLt~ PT ST% US AVAILABLE H / UNAVAILABLE AVAILABLE
+ / t:NAVAZFMBLE
- 39. Eas" ESW*
~ / 49. Eas" CCP>> /
- 40. West ESW*
East CCW* v
/ /
50. 51. West. CCP* TDAFP+ M
~ j /
- 42. West CCW+ v / 52. EM)AFP* v /
- 43. East CTS* W / 53. p"ESDAFP* ~
~ /
West CTS* 54. AB Diesel* /
- 45. North SZ+
- 46. South SI*
Y W
/ /
55. 56. CD Diesel* Normal Res.*
~~ / /
- 47. ""as- RKR*
~
v / 57. 12 EP* /
- 48. West R.'iR*
+ Data to be taken bv Control /
Room operator. Page 1 of 1 Revision 0
PNP 2080 EPP.1.03 EXHIBIT A v".CKV'A VFO!Lw&T ON Su.oT Unit Vo:)m! Oats~An) 0 TimeCl Data ;aken Bv Data Reviewed Bv
~v'0 Vhen redundant ind'cation exists, record mos" severe condition.
RCS D Q+LFZ'. Contai~ent Temp.
- 5. Intermediate Range 3A E-'4 A"IPS 1 Cont. H Concencracion
- 6. Con"ainment Ptessute~PSIG
- 3. RE~ST Level
- 3. Containment Sump Level* W i
) ~ Source Range
- CPV 8. Contaiomen= Level *~~a
- 9. CTS Pumps Eas
- ON / ~FF liest* OvI / ~FF 10 RHR Soray Flow East*~~GPN Ves e* GPN 11.. SI Flow Sot".he~GPV Soueh* GPN
) BIT:low I ~1+Q~GPN LP2+ CO GPN LP3* GPN LP4* (3 GPN essure LTsl~t~OGPN LP2+~OGPN L?43~~g7G?
1 3 Accum RI)X P Inject on Flow East+ CO GPN LP3* Ries c* PN C'PN N I 5. RCP Status <<IZ1(00'/ OFF *L?2 Oi / OFF +LP3 0 / OFF E~L?4 (OO)/ OFF
- 16. RCS Pressure NDS PS IG 22. PRT Level
- 17. Charging Flow GPN 23. PRT Pressure . PSIG 1S PZR Liquid Temp. OF 24. PZR Cycling Hers. / OFF 1.9 . PZR Steam emp. OF 25. PZR Backup Htrs, / OFF 20 PZR Level 26. Letdown Flow 7(o . GPN o
PRT Temp. 27. Saturation Nargin F %SSS LOOP ~MR KMI TERS ~Lo o Loon 2 ~Leo 3 Loot 4 0 Vide Range T Ho" 2o Vade Range E Co1.d F ~O F o~ F
- 30. S/G Pressure
%1 S/G 'A.R. Level, PSIG PS IG ++V? S IG PS IG S/G V.R. Level
3 3
Steam F'ow (pph X 10 ) C0
)
Feed Flow (pph X 10 ) 3 ) Aux. Feed Flow(pph X
- C)
- 36. VSIP Status 3 CST Level OPE. / CLOSE
- f CO s
'OPoV / CLOSE ~~+~Fc. ~OP=V CLOSE I'E'i CLOS E "-
3S. Steam Dump *ATNOS //VO~LiID E U ?NEWT STATUS AVAILABL. / L'.JAVAIIMLE AVAILABLE / L~AVAILABLE
- 39. Ease ESP* W / 49. Eas" CCP<< v
~ /
- 40. Ves" ESV*
East CC'+
- 42. Vest CCV+ ~~
V V"
/ / / '1. 50. Vest CCP*
TDAFP*
~<J)AFP+
v'
~M / /
- 43. East CTS* / 53. '444DAFP*
Vest CTS* ~5. vlorch SI+
~ ~ / /
54 AB Diesel*
- 55. CD Diese1.* ~v /
/
- 46. Sou-h SI* P / 50. Normal Res.* /
- 47. Ease RPZ*
S.;est R~q.~
~ / 37. 12 EP*
U
/
Data co be taken by Control Room operator. Page 1 of 1 Revision 0
P!iP 2080 EPP.103 E'(HIBIT A 1'" CHVS1'CA VFOR+4 IOV SHEET Unir So: D Dare~W90Pine D 5 Data Taken Bv Data Reviewed Bv VOTE t'hen redundant indication exists, record most severe condition. RCS PAR pe 3. E
- l. Contaigent Temp.
- Q .""
- 5. Intermediate Range ~E~A3iPS Cont. H Concentration
- 3 6 Conrainnenr Pressure~pSSG
- 3. R'<<ST Level
- 7. Containment Sump Level*
Source Range *
- 9. CTS Pumps East* ON / <<est* ON g ~FF 10 R.'R Spray Flow East* O GP i 3 est* C3 GP.'i 11 SI Flow North~ CO GPA ln BIT ."low LPl* (0 GP.i LP2+ CO GP.'i LP3* CD GP S LPae CO GPS l 3 Accum Pressure '1+Qg3GPH LP 2+~G P.'i LP3*isLs~CtGP33 LPa*~QGP.'i RE% Injection F'ow East+ .C GPS Mes t* D G P.'i
'5. SCP Srarus eLPL(OOP/ OFF *LP2 Oi / OFF *LP3 0 / OFF +lM4~ON / OFF LO ~ RCS Pressure ~~8. I'SIG 22. PRT Level 17 Charging Flow GP i 23. PRT Pressure PSIG lS PZR Liquid Temp. OF 24. PZR Cycling Htrs. 0 / OFF OFF
'19. 20. PZR Steam Temp. PZR Level --) (
- 25. PZR Backup Htrs.
- 26. Letdown Flow Oi /
GP.i
~
01 PRT Temp. 27. Saturation Margin~~ F VSSS LOOP 'tE ERS ~Lou L~oo 2 ~Loo 3 Loon 29
'<<ide Range T Hot Vide Range T Cold 4Oa &f0 'F 'F 4~" .59M'F o g~ oOF 30 S/G Pressure PSIG PSIG PSIG PSIG 01 S/G N.R. Level ~
R.% 33 S/G '<<.R. Level Stean Flow (pph X 10 ) 59.jg gv Feed L"low (pph 2 10 ) 35 Aux. Feed Flow(pph X 10 3
- C) 36 37 3S
.'iSIV CST Status Level Steam Dump OP 6 *62uQS + / l~ +LOSE //ÃD 3 OP ~Q Ft CLOSE ~OP;~< / CLOSE PY.'i QCLOSF STATisS 39. ~0. -ast ESP<<+ '<<est ESV+
vM AVAI~LE /
/ /
UNAVAILABLE 49. 50. East CCP+ Vest CCP* AVAILABLE 3
~ / UNAVAILABLE / / ~1. East CC'<<'* + / 51. TDAFP* ~ / ~2. Vest CCP<<+ v / 52. EmAFP* ~ / ~3. East CTS+ v / 53. PEAFP* ~ /
Vest CTS+
~5. North SI*
v v'
/ 54.
55. AB CD Diesel* Diesel* l
~ / / ~6. South SI* ~P / 5o. Vormal Res.* H /
East RKR*
~S. 'est Rm~ / 57. 12 E?+ /
v Data to be taken bv Control
/ Room operator. Page 1 of 1 Revision 0
PefP 2080 EPP'. 103
~'DiIBIT A T"-CHV iCA VFCRKATIOV SHEET s
Lnie Vo: 4 Date LI }0 Time DIM Data Taken Bv Data Reviewed Bv
~VO p
hen redundant 'ndicacion exists, record most severe condition. RCS 'cp+R+Nt Tt ~
- 1. Contai~ent Temp.
- F 5. Intermediate Range B.W E ~ A'fPS 2 Cont. H Concencracion
- 6. Containment Pressure~PSIC
- 3. Rt<<ST Level
- i 7. Containment Sump Level* W e Source Range
- CPV S. Containmen" Level 9.
10 CTS Pumps RHR Spray Flow East* East+ M ON /~P GP.'f Nest* Mes t* OV /C>~P GP.'f 11 SI Flow Voreh>> (~GP f 'outh* C) GPf s BIT Flow LP1* CO GPf LP2+ O GPN LP3* 0 GPA LP4* 0 GPLf '1 Accum Pressure LPI+~<gGP!f LP2~~~GP.'f LP3*~<~OGP f LP4>>~+~GP.'f 3 RHR RCP Inject on Flow Status>>LP1~OV / OFF East t 0*LP2 GPA
/ OFF Mes +LP3 t* /, OFF C) +LP4 GP.'f ~OiV. / OFF
- 16. RCS Pressure PSIG 22. PRT Level
- 17. Charging :low 23. PRT Pressure . PSIG 18 PZR Liquid Temp. F 24. PZR Cycling Htrs. / OFF
- 19. PZR Steam Temp. 25. PZR Backup Htrs. / OFF
'10 ?ZR Level e 26. Letdown Flow~t ~GPf o1 PRT Temp. o~ 27. Sacuraeion Lfargin~~ F VSSS 00>>AR KfET~RS ~Los l ~oo~ ~Leo 3 Loose a Vide Range T Hot ( o>." ~~o o 0 '3 3 << de Range T Cold L O oF 30 S/G P essure PSIG PSIG PSIG PSIG S/G V.R. Level 3o S/G 4'R'e~el 6 33 Steam F'ow (pph X 10 ) Feed .low (pph X 10 ) 35 Aux. Feed Flow(pph X +~) 36 37
!fS IV Status CST Level OP~ / CLOSE
- le~
P CLOSE Fc,.
~OP"=.(~CLOSE ~PEv~fCLOSE 38 Steam Dump *ALTOS /$ ~0~
ohI c'V~ tS AVAILABLE / LVeAVAILMLE 49. AVAILABLE
~ / I L~lAVA LABLE ~ // ~ /
- 39. East ESP* v" East CCP>>
- 40. <<es" ESP*
~
- 50. P<<ese CCP*
~ /
East CC'<<* / 51. TDAFP*
~ /
EefDAFP*
~ /
- 43. Ease CTS* v / 53. Vol)AFP*
~ /
Vest CTS* W / 54. AB Diesel* /
~~ '
North SI* W
~ / 55. CD Diesel* /
- 46. South SI*
~ / 56. Vormal Res.*
- 47. East RLiR+ / 57 ~ 12 EP* /
- 48. <<est RHR*
Data to be taken by V', / Control Room operator. Page 1 oE ion 0 'evis
PHP 2080 EPP.103 TUGBOAT A TcCHW CAL 4FOR<<TION SHEET Cuit Vo:~pa:a "f-& to Time Data Taken Bv Data Reviewed Bv VOT:-
'<<hen redundant indication exists, record most severe condition.
RCS ?AR. fcTE.
- 1. Concainpent Temp.
- Qo 5. intermediate Range &~K-4 LVPS
- 2. Cont. H Concentration
- 6. Containment Pressure PSIG
- 3. RWST Level
- 7. Concainment Sump Level*
Source Range
- CO CPS 8. Containment Level ~ CO 9, CTS Pumps Eas=* ON /~OFF Nests t*
ON /C)CB V
- 10. RHR Spray F'ow
- 11. Sl Plow 1.2. BIT Flow East*
Vor LPl* t-C3 GPA GPA GPA LP2+ C) GPA Wes
'ouch*
LP3* C) GP'A GP'A GPA LP4* C) GPA
- 13. Accum Pressure LP1.~<~PA LP2M<~OGP.'I LP3* OGPLI LP4>> G)<~OGPLI Injection Flow East+ C> West+ O GPA
'.dms -.
RIEL GPA smi +LP3 / OFF ~LP4 / OFF
~ ~ON -'6.
RCS Pressure 4 ~ 5 PSIG 22. PRT Level
- 17. Charging Flow GPA 23. PRT Pressure . PSIG
'S. Liquid / OFF 19. 20. PZR PZR PZR Temo. Steam Temp. Level
~i OF 24. PZR Cycling Hers.
- 25. PZR Backup Htrs.
- 26. Letdown Flow W4 . GPA
/ OFF PR<<emp oc 27. Saturation Margin~~ F
.SSSS LOOP >MR.4<E E7S ~Lao ~os o Loon 3 Loon 2S. Vide Range T Hoc 4CeO 'F 0
- 29. F<<'de Range T Co'd F C) F O F
- 30. S/G Pressure
- 31. S/G vt.R. Lev el
- 32. S/G W.R. Level
- 33. S-earn Flow (pp nX 10 }
- 34. Feed Flow (pph X 10 )
- 35. Aux. Feed Flow(pph X
I(~
M.'R ~ PSIG 9E.K ~ (nO.5 S
~W (0 PSIG +.S ~S~ I PSIG ~
sq.+X, 4~5 PS IG
- 36. VSSV Status
- 37. CST Level
*OPo / l~S CLOSE OPsV ~ / CLOSE ~OP <&Ft.
V CLOSE 0 c.'t CLOSE
- 38. Steam Dumo *ATAOS~/
U ~<E'VT STst 'S AVAI~LE / UNAVAILABLE AVAILABLE / UMVAITMBLE
- 39. East ESW* ~ / 49. East CCP+ ~W /
M 40, T<<est ESW* M / 50. West CCP* / East CC'<<*
~ / 51. TDAFP* H /
- 42. '<<est CC<<* / E%AFP* v /
- 43. East CTS*
West CTS* + // W 53. WLLDAFP* 54 AB Diesel*
~v' / ~ ~~ // /
- 45. North SI* 55. CD Diesel* R
- 46. South SI* 5o. LVormal Res.* v'
~ // /
- 47. ".as" RHR* 57. 12 EP+
- 48. Wes" R.LR.*
Daca co be taken by Control Room operator. Page 1 of 1 Revision 0
PMP 2080 EPP.'03 EWIBIT A T=CWV Ca ~VFORWaTTOV.S .EO. Cnie VO: ant Daae~RD Tine Data Taken Bv Data Reviewed By NOTE l hen redundant indication exists, record most severe condition. Contai~ent Temp.
- 5. Intermediate Range S. ~ ~ 4 AMPS Cont. H Concentration
- 6. Containment Pressure C) PSIG R'<<ST Level
- 7. Containment Sump Level+
Source Range
- CPM 8. Containment Level *~~5
- 9. CTS Pumps East* Oil West* 034 /~OF 10 Spray Flow East* 6) GPM
/COO'.'tR Wes t* O GPM
- 11. SI Flow North~~~GPM GPM 1". BIT Flow LP1+ 0 GPM LP'2* 0 GPM LP3* (0 GPV LPa* & GPV 13 Accum Pressure
'n LP19~)GPM LP2+Wt@GPM LP3a L~) GPN Lpa*~EQ G?N Rakk Inj ec" F'w ""as t+ 0 GPM West* D GPM 1
5 RCP Status ~LP1 QOQ'/ OFF *LP2 i / OFF *LP3 OFF *LPGA/ OFF LO. RCS Pressure PSIG 22. PRT Level
- 17. Charging Flow GPM 23. PRT Pressure . PSIG
- 18. PZR Liquid Temo. OF 24. PZR Cycling Htrs. / OFF
- 19. PZR Steam Temp.
'30 PZR Le~el --) OF 25. PZR Backup Htrs.
- 26. Letdown Flow 94 .S GPM 0 0 / OFF PRT Temp. 27. Saturation Margin . F 4SSS LOOT'ABA<ETERS ~Lao ~Lao Loon 33 ~Leo 28 "de Range T Ro- F 5RS DR5'=
'3 O '<< de Range T Cold F F 30 S/G Pressure PSIG PSIG PSIG PSIG Wl S/G H.R. Level 3<< S/G ".R. Level 33 Steam Flow (pph X 10 ) 0 CQ I Feed Flow (pph X 10 )
- 3.
- 0 auv. Feed ."Low(pph X
~
35 i 5 CO CO 36 37 MS IV Status CST Level
*OPEV / CLOSE OP 'V / CLOSE Ft. ~OP . / CLOSE ~OPE~vs /CLOSE 38 Steam Dump *ATMOS / iV " UIPM~XT STA AVAILABLE / UNAVAILABLE ~ //
AVAl'LABLE UNAVAILABLE
- 39. East ESW+
~0. West ESP' g // A9. East CCP>>
- 50. West CCP* < /
~l. East, CC'<<+ ~2. <<est CC'<<+
~ ~ / /
51
'2. TDAFP* ~mAFP* ~ / /
~33. East CTS* <~, West CTS*
~H / /
- 53. OAF P*
5 ~/ AB Diesel* W
'~ / /
~5. North SI* ~6. South SI*
~ ~ / /
- 55. CD Diesel*
- 56. Normal Res.* ~
d /
/
~/7. East RHR* / 57. 12 EP+ / ~8. '<<est RHR* Data to be taken
~0 by /
Control Room operators Page 1 of 1 Revision 0
PMP 2080 EPP 103 EXHIBIT A T"-CHN C VFOR~ATIOV1 H"-ET Uni t No: 4 Date 4-5-95 Time Data Taken By Data Reviewed Bv
~VO Vhen redundant indication exists, record most severe condition.
RCS o V ent Temp. c'ontai~s
- 5. Intermediate Range 1 5E ~C'AMPS Cont. H Concentration
- 6. Containment Pressure (3. PSIG RVST Level
- 7. Containment Sump Level+
Source Range
- CPM 8. Containment Level
- Q
- 9. CTS Pumps East* OVL Q(00 Vest* ON g 4B 10 REPS. Spray Flow Eas t* C) GPM Vest,* CO GPM 11 SI Flow Vorth>> CO GPM BIT Flow LPL* SOGPSS LP2* 5 GPK LP3*7 GPE LP'*~&CPS l3 Accum Pressure LP1 GPM LP2* GPM LP3* O GPM LP4*~L~OGPM r
RuZ Injection Flow East+ 5 GPM Vest* O GPM 15 RCP Status +LP1 ON / F *LP2 ON / ~Fr *LP3 ON / F +LP4 ON / ~F
- 16. RCS Pressure PSIG 22. PRT Level Charging Flow GPM 23. PRT Pressure . PSIG 18 PZR Liquid Temp. QCO 0
F 24. PZR Cycling Htrs. *ON / F
- 19. PZR Steam Temp. 25. PZR Backup Htrs. *ON /
'30 PZR Level F3 26. Letdown Flow CO GPM O~ 0
- 21. PRT Temp. 27. Saturation Margin F SSS 0 oAR .tE E S Loo I oo~$ Looo 33 ~Lo o
"=8 20 Vide Range T Hot V'de Range T Cold ++ oF oF 0
F ++~o F F 30 S/G Pressure PSIG PSTG PSIG ~s~PS IG 31 S/G N.R. Level 3'3 S/G V.R. Level 33 Steam Flow (pph X 10 ) 34 Feed Flow (pph X 10 ) 35 Aux. Feed Flow(pph X
- lo~ C3 36 37 MSIU Status CST Le~el
*OP / C S OP CLOSE .~ Po. ~GPSS P / CLOSE ~OPr,, /CLOSE 38 Steam Dump ATMOS /
UI~f VT T AUAILABLE / i%i'AUAILABLE AUAILABLE / I UNAUA TABLE
- 39. East ESV* / 49. East CCP>> /
- 40. Vest ESV* / 50. Vest CCP* /
- 41. East CCV* / 51. TDAFP* /
- 42. Vest CCV* / 52 E!KAFP* /
.43. East CTS* / '3. VMDAFP* ' Vest CTS* / 54. AB Diesel* /
- 45. North SI* 55. CD Diesel* /
- 46. South SI* / 56. LVormal Res.* /
- 47. East RKR* / 57. 12 EP* /
'8. Ves" RHR+ /
Data to be taken by Control Room operator: of Page 1 0
+
1'evt.saon
++ l1O ~~P ChCSI +
2 PMP 2080 EPP.103 EXHIBIT A ~ECLPq CA> ~NFOR4LQ'ION SHEET Uni" No: 4 Date~//07ime C)g Data Taken Bv Data Reviewed Bv
~QOT- '<<hen redundant indication exists, record most severe condition.
P <q 4 IoToR
- 1. Contai~ent Temp.
- l F 5. Intermediate Range 9.5E 1l AMPS Cont. H Concentration
- 6. Coneainmene Psessuse~MPSIG
- 3. Level
- 7. Containment Sump Level+~3-R'<<ST Source Range
- CPM 8. Containmen" Level *~)
- 9. CTS Pumps East* ON+(OOF Vest* ON /~F 10 ReLR .Spray Flow East* M GPM '<<es t+ C) GPM 11 SI Flow North>> g+ GPM 'outh* gQ GPM 3
3 BIT Flow Accum Pressure 'l LPL* GPN GPM LP"* LP2* GPN QGPM L?3* LP3* GPN GPM LP *CLC3 G?u LP4*~QGPM 1 RLSZ SCP Injec-S-a-us on F'ow
'LPL ON East+ /(SF'L?2 (0
ON GPM
/ ~ Vest* *LP3 ON / FF 0
eLPe GPM ON /~OFi 16 RCS Pressure 1 PS1G 22. PRT Level 17 Charging Flow GPM 23. PRT Pressure . PSIG 18 PZR Liquid Temp. OF 24. PZR Cycling Htrs. *ON / 19 '30 PZR Steam Temp. PZR Level OF 25. PZR Backup Htrs. *ON
- 26. Letdown Flow D
/
GPM FF PRT Temp. 27. Saturation Margin <zS. g F NS S S OO>> <RA<3'<ERS ~Los ~Loon Loon 3 ~oo 28 29 Vide Range T Hot
<<ide Range T Cold ++ oF F
oF f
+ ,~o 0 ~
30 S/G Pressure PSIG Q> PSIG PSIG J~O'RDPSPG
%1 S/G V.R. Level 3 S/G '<<.R. Level 33 Steam Flow (pph X 10 )
3 Feed Flow (pph X 10 ) 35 Aux. Feed Flow(pph X 1 3 36 37 MSIV CST Status Level
*OPE / +LOSE OPEN /+L~OE OPEN j CLOSE *OPEN, LOSr, 38 Steam Dumo +ATMOS / COND " UIo.'F.o'ST ST% / / UNAVAILABLE
- 39. East ESV+
- 40. '<<'est ESV*
AVAILABLE M
/
j UNAVAILABLE
- 49. East CCP+
- 50. Vest CCP*
~
AVAILABLE
/ /
- 41. East CCV* ~ /
/ 51. TDAFP* ~ ~ / /
- 42. Vest CCV+
East CTS* ~'
/
52 53 '3. E.iDAFP* VSSDAFP* AB Diesel* j
/
CTS*
~ 54. 'est
- 45. North SI*
- 46. South SI*
/ / W
- 55. CD Diesel*
- 56. Normal Res.*
~ / /
- 47. Eas" R!K+
- 48. Vest R'.tR*
~ / /
- 57. 12 EP* /
+ Data to be taken by Con-rol Room operator. Page 1 of 0 'evision
PMP 2080 EPP.103 E.'KIBIT A
"-CoV CA< NPOR.'L4T ON SNSv. Cnir NO: D De-e0-Q IO Tine 0 05 Data Taken By Data Reviewed Bv ~VO '<<hen redundant inde cation exists, record most severe condition.
RCS D +4fT 1'T
- 1. Contai~ent Temp.
- 5. Intermediate Range ME ll A'1PS Cont. H Concentration
- 6. Containment Pressure~~& PSIC
- 3. Rf ST Level
- 7. Containment Sumo Level*
Source Range
- CP N S. Con"einnenr Level
- i5 i 9.
'0 CTS Pumps RHR Spray Flow East* 04V East* Q~ M GPM Vilest* OV Ves t*
/d& GPM 1
1 SI: low North>> Q GPM South* O GPM BIT Flow LP1+ 9 ~CPM LP2+~GPM LP3+~- GP.'f LP4+ F GPM 1 3 Accum Pressure LP1+~QGPM LP2+~GPM LP3*~~GPM LP4* GPM R."Z. Inject on F'ow ""ast+ ~*L22 GPM 'Jes t* GPM 5 RCP Status <<LP1 ON / r ON / ~FF *LP3 ON / F eLP4 ON /~Pe 16 . RCS Pressure 15M.S PS IG 22. PRT Level E 1;. Charging Flow 23. PRT Preeenre~PSTG 18 PZR Liquid Temp.
- 19. PZR Steam Temp.
oF F
- 24. PZR Cycling Htrs. *ON
- 25. PZR Backup Htrs. *ON'/
/ F 30 PZR Level o Ol PRT Temp. F 27. Saturation Margin~P~~ F NSSS LOOP o<q.<fET~RS Looo Looo Loon 3 Looo ++ W+ ~o 30 'ide <<de Range T Ho" Range T Cold S/G Pressure o
0 PSIG oF 0 f PSIG
~40 ~~PSIG o 'P +~ o P
SIG
%1 S/G V.R. Level 3 S/G w.R. Level 33 Steam Flow (pph X 10 )
3 35 36 Feed Flow (oph X 10 ) Aux. Feed Flow(poh yL 10 3 )*
.'fSIV Status *OPEV /
CO LOS" *OP~V 0
/ LOS *OPEV / ~O ~LOSF) *OP V i LOSc.
3 T CST Level * *+~F".. 38 Steam Dump ATMOS / COND
" Uio'f~VT Sik S AVAI~LE j/ UVAVAILABLE AVAIL+LE / UVAVA LABLK 39 East ESw* v 49. East CCP+ r /
40 '<<'est ESP* / 50. ~iest CCP* / East CC<<* v j v j
~W 51 TDAFP*
42 3
<<est Eas t '<<est CTS*
CCV* CTS* ~~ /
/ / /
52 EMDAFP*
- 53. tNLLDAFP*
- 54. AB Diesel* .
~ / /
j North SI* v 55. CD Diesel* / ~O South SI* / v 56. Normal Res.* / 47 East R!fR* 57. 12 EP+ / 48 '<<est RLfR* Data to be taken -bv
/
Control Room operator Page 1 of 1 Revision 0
++ Ao porn~
PAP 2080 EP P . l.03 EXHIBIT A i T"-CHN CAL INFORMATION HEET Cnir Vo:~, Dare~d- C1Q p 6 me Data Taken Bv Data Reviewed Bv
~VO '<<hen redundane indication exists, record mos" severe condition.
RCS E3~>%3 n E, Q
- 1. Coneai~ent Temp.
- io9 F 5. Intermediate Range 4 %+ ~ '1 A".PS Cont. H Concentration
- 3. R'<<ST Level Source Range
'E?
CPV
- 6. Conrainmenn Pressure~~~p
- 7. Conrainmenr Sump Level*
- 8. Conrainmenr Le~el
- CD
~ ?SEG 3
- 9. CTS Pumps Ease* ON ~OF '<<est* ON L<QP) 10 RHR Spray F'low Ease* GPA Vest.* C0 GPA 11 SI Flow North~ C) GPH South* O GPA B'IT Flow LP1? CO GPA LP2+ ~ GPA 13 Accum Pressure LP1$ +Q GPA LP2*~GP.'f LP3*V~~GPA LP43'F~l~GPH s
Rw9. RCP Inject Status
- 16. RCS Pressure on 'low
<<LP1 ON Ease+ / 0 D +LP2 ON GP'A /
PSIG
~ t<<es *LP3
- 22. PRT Level e*
ON / F eL?6 GP'N OiV / ~r F"
- 17. Charging Flow GPA 23. PRT Pressure . PSIG 18 PZR Liquid Temp. oF o 24. PZR Cycling Hers. *ON /
l.9 20
. PZR Steam Temp.
PZR Level 0 25. PZR Backup Htrs. *ON
- 26. Letdown Flow C7 GPH 0
/ FF O '1 PRT Temp. 27. Saturation Hargin N. 7 F VSSS OOP PARAMETERS Loo oo 2 ~oo 3 oo '<<ide Range T Ho" ~+ o O QF +~t-) o ++ o F
20 <<ide Range T Cold F 0 F F ~+ 30 S/G Pressure PSIG PSIG PSLG (5 PSEG el S/G N.R. Level I J S/G <<.R. Level e. 33 Steam rlow (pph X 10 ) D CO 34 ."eed .".low (pph X 10 ) 35 Aux.."eed Flow(pph X 10 )* 36 37 ASIV Status CST Level.
*OPEN / OS *OPE V/ *W, LOS '*OPEN Ft. / ~LCD*OPEN;~LOS~
38 Steam Dump *ATLfOS / COND E UIPHE'VT ST WS AVAILABLE / O'NAVAILABLE AVAIL+LE / UNAVAIE~LE
- 39. East ESt6+ v / 49 Ease CCP>> v /
/ /
- 40. <<es" ESP+
- 41. Ease CC"*
- 42. '<<es CCV*
~ /
50 51 52 Vest TDAFP* EM)AFP* CCP*
~ ~ / /
- 43. East CTS* W / 53 'tviiDAFP* /
/ / '<<est CTS* ~5. Voreh SI+
46 . South SI*
~ / /
54 55 AB CD Diesel* Diesel.* Res.+, ~ /
/
- 47. Ease R.'Lq.*
- 48. '<<ese R.'LR*
~ / /
56 57 Vormal 12 EP* / Data eo be taken bv Control Room operator. Page 1 oc Revis ion
++ Ac pex~r 4c char4-0
PMP 2080 EPP.1.03 E.'fHIBIT A Co< CA ~FORE.A IO'1 SHoKT Uoi" 3o + Dooo Daca Taken By Daca Reviewed By
~VO E <<hen redundant indica" ion exists, record most severe condi" ion.
RCS
- 1. Contaiyent Temp.
- C) 5. Intermediate Range +.dK;" lf A".PS
'7 o Conc. H Concentration
- 6. Containment Pressure~~~PSIG
- 3. R<<ST Level
- 7. Containment Sump Level*
I Source Range
- 8. Containment Level. *
/~
CP.f o
- 9. CTS Pumps Ease* ON ~ West* ON /~P 10 RE% Spray Flow East*~) GP.'f West* C0 GPM 11 SI Flow North<<~~GPM South* CO GPM BIT Flow LPl* D GPM LP2* O GPM LP3* CO GPM LP4* W GP.f 13 Accum Pressure LP1+~GPM LP2*%SOGPM LP3*gg~ GPM LP4*~CGPM 1
1 16 g REX RCP RCS In]ect Seaeus Pressure on Flow
<<LP1 ON /
Ease+
~
Il"4R O
*LP2 ON GPM R PSIG /~r *LP3 West*
ON
- 22. PRT Level
/
CO F <<LP4 GPM ON /~ 17 Charging Flow ,\ GPM 23. PRT Pressure ~5. +PSIG 18 PZR Liquid Temp. F 24. PZR Cycling Htrs. *ON / 19
%0 PZR Steam Temp.
PZR Level F 25. PZR Backup Htrs
- 26. Lecdown Flow 5
*ON /
GPM OF 21 PRT Temp. P 27. Saturation Margin 7. Q F VSSS LOO oARAMETEqS ~oo 3 ~LO 0 ~ioo 3 iooo t lW'W 18 Vide Range T Hot 29 W de Range I Cold 30 S/G Pressure PSIG PSIG PSIG PSIG 31 3" S/G N.R. Level Level (. S/G W.%. 33 Steam Flow (pph X 10 ) 34 35 reed Flow (pph X 10 ) Aux. Peed Plow(pph X 10 )*
~).o
-36 37 MSIV CST Status Level.
*OPEN / CL *OPEN *MS / L r t. +OPEN / ~LOSi~OPEN /~O~Sr.
38 Steam Dump *A, .'fO / COND E UIPMEV> TATUS AVAILABLE / LNAVAILABLE AVAILABLE / UVAVAIUBLE
- 39. East ESW+ u / 49. Eas" CCP<< v /
/ /
- 40. Wesc
- 41. Ease CC'*
ESW+
~ /
50. 51. West CCP* TDAFP* /
- 42. <<est CC3<<*
'3. Ease C S* '<<es c CTS*
- 45. North SI+
~R /// /
52. 53. 54. 55. E.EAFP* ZiDAFP+ AB CD Diesel* Diesel*
/ / //
- 46. South SI* 56. Vormal Res.*
- 47. East RHR+ v / 57. 12 EP+
- 48. West RffR* /
Data to be taken by Control Room oper ator. ~ Page 1. o po~cr ~ Mal +
'Revision 0
PAP 2080 EPP.103 EXHIBIT A T"-C:-"4'CAL up03L'STTON 3 ..'S. Uni- 'So: om3 Date~OTLme Data Taken By Data Reviewed Bv VOTE
'<<hen redundant indication exists, record most severe condition.
R.CS PAR. <<TE.
- l. Contai~ent Temp.
- 0 S. intermediate Range ~E.'IlA !PS
- 2. Cont. H Concentration
- 6. Containment Pressure PSIG
- 3. Rg<<ST Level
- 7. Concainmenc Sump Level* e I
Source Range
- CP."f S, Contaiossenc Level
- C)
- 9. CTS Pumps Ease*
East* OAV West* Vest+ ON / ~OFF 10 RHR Sprav Flow GPN GPA 11 SI Flow Vorth>> C3 GPN 1 3 BIT Flow LP1* C0 GPN LP2* 0 GPA LP3+ CO GPRi LP4* H GP'A Accum Pressure LPle+~GPN LP2e&~OGPN LP3*~<~GPN LP4*MI(D GPN Rudl Knjec"'on .""lou aste Q GSN Des-* O GpN 15 RCP Status *Lol ON / OP *LP2 ON )~O *LP3 ON / OP *LP4 ON /(00) RCS Pressure PSIG 22. PRT Level 17 Charging Flow GPH 23. PRT Pressure 'Q~PSIG 18 PZR Liquid Temp. F 24. PZR Cycling Htrs. *ON / 19 PZR Steam Temp. F 25. PZR Backup Htrs. *ON / OF 20 PZR Level 26. Letdown Flow CO GPA ') 1 PRT Temp. =tao MSSS LOOTA%4~3'TERS ~Los 1 ~Leo Loon 3 ~oo
'3 g Vide Range T Hot W+ F gg"- &55 F + <<Q S<<ide Range T Cold P ~RD P 30 11 S/G Pressure S/G N.R. Le~el DW) PS IG PSIG PSIG ~PS IG 39 S/G <<'R'es el MBM~ ~)wK 6
33 Steam Flow (pph X 10 ) C) Feed Flow (pph X 10 ) 75 C3 33 Aux. Feed Flow(pph X 10 3 )* 36 ASIU S tatus *OPEN C 0 *OPEV
/ C OS *OPEN / ~LO~S *OP E'.1, L c 37 CST Level + Fe.,
38 Steam Dump *ASS / COLVD
" UIP.'SENT STATUS AVAiLABLE / UVAUAIT ABLE AVAILABLE / UVAVA TABLE
- 39. Ease ESV* v / 49. Ease CCP+ W /
- 40. Vest ESW* / 50. Vest CCP*. /
41. 42. East CC'<<* Vest CCV*
~ / /
- 51. TDAFP* ~
~ / /
- 43. Ease CTS*
Vest CTS*
~ / /
52. 53. EK)AFP* 4iLDAFP* Diesel*
/ /
- 45. North SI+
- 46. South SI*
~ / /
54. 55. 56. AB CD Diesel* LVozmal Res.*
~ / /
- 47. Eas" RHR*
- 48. <<es" RLtR*
~ / /
- 57. 12 EP+ /
Data to be taken bv Control Room operator. P.age 1 of 1
+ +'o ~~f- Revision 0
PNP 2080 EPP.103 E'.GiIBIT A T"-coH c. <<Fo<L<<aT ov sH ET Gnir Ho: A 'ate s1 DIGLOT<me 0885 Data Taken By Data Reviewed Bv VO'T'v
'%hen redurdan" indication exists, record most severe condition.
RCS PAR <M~T~ 1 Containment Temp. Cont. H Concentration *
- loI F 5.
6. Intermediate Range Gonrai<ssenr P-essnre O. I.4 'C-1 l ALPS Io& PSLG
- 3. EST Level
- 7. Containment Sump Level*
Source Range
- CP.i 8. Containment Level
- CO 9.
10 11 CTS Pumps . EHE SPray Fiow SI Flow East* OiV Eas"*SOPH / North<<W GP.'i
~ F<<est*
Vest+ OiV ~F GPA 1'3 BIT Flow LP1* CO GPEi LP2* (3 GPEi LP3* L) GPS LP4~ O GP~ 13 Accum Pressure LP1~~) GPN LP2*~GP.'i LP3*~~GPEi LP4*~) GP.'i 14 RFZ nject'on Flow East+ O GPEi Res t* CO GP.'i 15 RCP Status <<LP1 ON / 0 *LP2 OiV /('OFF, *LP3 ON / *LP4 ON /QFQ
- 16. RCS Pressure PSIG 22. PRT Level
- 17. Charging Flow CPS 23. PRT Pressure PSIG
- 18. PZR Lingui.d Temp. F 24. PZR Cycling Htrs. *ON /
]Q PZR Steam Temp. 20 PZR Level F 25. PZR Backup Htrs. Letdown Flow CO
*ON GPA / ~1'6.
b1 PRT Temp. F 27. Saturation 'Aargin~4~5 F NSSS LOOb bAR4<ETERS ~Loon ~oo~ Loon 3 MQ.l o o 28 30 Vide Range T Hot
'<<'de Range T Cold S/G Pressure J~PSIG F ~ED PSIG F W~ ~~PS F
IG
~~F ~PSLG
%1 S/G N.R. Level COND'oon
. I s S/G V.R. Level LaE. h.>
Steam F1ow (pph X 10 ) O 33 Feed Flow (pph X '0 )
)*
D R~ Z5 CO C3 ~) Aux. Feed Flow(pph X 10 O 33 3b 3
'F liSIV Status CST Level *OP V / CL SE *OPEN *~/ CLO .(gpr. <<OPEN /~~ *OPEN /QL Q>-
38 Steam Dumo *AT4IO / E UIPM~VT STATUS
- 39. East ESls* ~ // LTMVAILABLE 49.
AVAIT~L'E Eas" CCP<< AVAILABLE H
/ /
TUNAVAI &LE M // /
- 40. <<est ES4* 50. Vest CCP*
- 41. East CC<<+
<<est CCt<<+ /
51. 52. TDAFP* E fDAFP+ ,
~ ~ / /
- 43. East CTS* M / 53. 'tNSSDAFP+ /
/ / '<<est CTS*
- 45. North SI* ~ /
54. 55. AB CD Diesel* Diesel* ~ / 4b. Sou"h SI*
- 47. ">>as" RPZ*
- 48. est RHR*
3
~ / / /
56. 57. Normal Res.* 12 EP*
/ /
Data to be taken bv Control Room operator. Page 1 of 1 Revision 0
<< ~
PMP 2080 EPP.103 HKIBIT A T""CHiV CA VFORNTIOV SHEET Unit Vo: 4 Date) ~>/@Time Data Taken Bv Data Reviewed By VOTE Vhen redundant indication exists, record most severe condition. CS PKK 'N~TE.
- l.M~
- 1. Containpent Temp.
2. 3. Cont. H Concentration RVST Level
- t F 5. Intermediate Range
"* ----~NK
- 7. Containment Sump Level*
~ I A"fPS Source Range
- OO CPN S. Conte'".ment Level
- D
- 9. CTS Pumps 'East+ OiV /(00~) Nest* ON /~FF
- 10. RKR. Spray Flow East* CO GPM fN es t* CO GP.'f
- 11. SI Flow Vor tht'c~~GP.'f South* CO GPM Q GP.'f LP2* +
'. BIT Flow Accum RI23, Pressure Inject LP1~ LP1+~~Q GPM on F'ow East+ LP2+~GPM 0 GPM GP.f LP3* (0 Vest* GP.'f LP3*~L-~GPM LP4+~~GPM CO LP4+ CO GP.'I GPM LS. NCP Status *LPL ON /~OF+ *LP2 ON /(OOr) eLP3 ON /0 *Lpa ON /~r
'6. RCS Pressure 5 PSIG 22. PRT Level
- 17. Charging rlow GPM 23. PRT Pressure PSIG
- 18. PZR Liquid Temp. Q F 24. PZR Cycling Htrs. *ON / 0
- 19. PZR Steam Temp.
- 20. PZR r.evel -->
F 25. PZR Backup Htrs." *ON
- 26. Letdown Flow C) 'PM
/ OFF
- 21. PRT Temp, F 27. Saturation Margin ~~ r VSSS LOO>>ARAMETERS 'Loo Loo Looo 3 J too
- 28. Vf.de Range T Hot o~ o + o
- 29. V'de Range T Cold 0 OF + M F
- 30. S/G Pressure PSIG PSIG PSIG PSIG
- 1. S/G V. R. Lei el S
- 32. S/G V.R. Level
- 33. Steam Flow (pph X 10 )
34. 35. Feed Flow (ooh X 10 ) Auxr Feed Flow(poh X 10 3 )* E5 (~ CO
- 36. MSIU Status *OPEV CLOSE *OPLV
/ CLO E OPEV / CL S OPE.V, LO r.
- 37. CST Level , Ft.
- 38. Steam Dumo +ATMO / COLVD UIPM V T TUS AUAI~LE / UVLAUAILMLE AUAIIMLE / LVAUAILABLE
- 39. East ESV* v / 49 East CCP~ V /
- 40. Vest ESV* / 50 Piest CCP+ /
/
41. 42. 43. East Vest East CCV* CCV* CTS* ~ /
/ .51 53 TDAFP*
LIDAFP*
'tt ttDAFP* ~W ' / W /
Vest
- 45. Vorth SI*
- 46. South SI*
CTS*
~ / /
54 55 AB CD Diesel* Diesel' Vormal Res.*
/ /
~
- 7. East RHR~
- 48. '<<est RLIR*
~ / / 'C 12 EP* /
+ Data to be taken by Control Room operator. Page 1 of 1 Revision 0
PMP 2080 EPP.103 EXHIBIT A T"-C<V CA VFOR+4 ION S E~T Unit LVo:~ Date - - ime Data Taken By Data Reviewed By VOTE
<<hen redundant indication exists, record most severe condi "ion.
RCS Pg LFETE Contairuyent Temp.
- F 5. Intermedio-e Range ~I.55K-I ANPS Cont. H" Concentration
- 6. Containment Pressure~~PSIG
- 3. RWST Level
- 7. Containment Sump Level*
Source Range
- 9.
10 CTS Pumps Flow Res East*
"* GN /~0 Nest* ON / ~FF RKR Soray GPM 11 SI Flow North>> GPM 'outh* Q) GPM BIT Flow LP1+~> GPM LP2* GPM LP3+~) GPM LP4* C) GPM L?4s~G?N ~ ~ *LP4 13 accum Pressu."e L?1*Lc~GPN LP2e L?3e Ips~GPN ~
GPN Rw9, Inject on Flow East+ ~ GPM Gest* GPN "5 RCP Status *LP1 ON / *LP2 ON / *LP3 ON / OF ON /
- 16. RCS Pressure . 6 PSIG 22. PRT Level
- 17. Charging Flow GPM 23. PRT Pressure 9 . -K PSIG 1S PZR Liquid Temp. F 24. PZR Cycling Hers. *ON /
- 19. PZR Steam Temp. F 25. PZR Backup Htrs *OVL / FF
'30 PZR Level 26. Letdown Flow GPM 01 PRT Temp. 27. Saturation Margin~)~ F VSSS LOO0 AR<<ETERS ~Los L~oo Loon 3 Looo 4 2S. Wide Range T Ho" l5 'F o ~+ o 20 W'de Range T Cold +W F ~Q'F ~o
- 30. S/G Pressure 1.~PS IG PSIG PS,IG PSIG
- 31. S/G N.R. Le1 el S S/G W.R. Level
- 33. Steam Flow (pph X 10 ) C) 34 Feed Flow (pph X 10 )
- 35. Aux. Feed Flow(pph X 10 )*
CO CO ~) CO
- 30. MSIV Status 3
s CST Level
*OPEN / CL SE 1? *OP V *W / LO E Ft. *OP" V / CL S *OPEN /FALSE)
- 38. Steam Dumo *ATMOS / COLVD UI VT STATUS AVAI LE / UVAVAILABLE AVAIL+LE / tiVAVAIFMBLE
- 39. East ESW* v / 49. East CCP* v /
- 40. / /
41. West East ESW+ CCW* / PF 50. West CCP*
- 51. TDAFP* ~
~ /
- 42. West
- 43. "ast CTS*
CCW+ West CTS* ~5. North SI*. Sou-h SI* W v
/ / / /
I v 52. 53. 54. 55. 56. E%)AFP* tgiiDAFP* AB CD Diesel* Diesel* Normal Res.* v
/ / / / /
- 47. East R.'L%+ P / 57. 12 EP* /
- 48. <<est R R*
Data to be taken bv Control
/ Room operator. Page 1 of Revision 0
PNP 2080 EPP.103 EXHIBIT A T"-CLPV CA< VFORK TIOV SH>>ET Unic Ão:Q Ga"a~OP'me Data Taken Bv Data Reviewed Bv V~OT~
'<<hen redundant indication exists, record most severe condition.
RCS
- 1. ContainsJent Temp.
- C) F 5. Intermediate Range (.5E ~1 A.'fPS 1 Cont. H Concentrat'on
- 6. Containment Pressure O W PSIG
- 3. R<<ST Level
- 7. Concainmenc Sump Level*
Source Range
- CPS 8. Concainmenc Level e O i 9.
10 11 CTS Pumps 8388 Spray SI Flow Plou East* North>> 04V Pas-*~GP!i OF
& LP2* GP.'f '<<est+ '<<est*
ON /~ O GP GP f f BIT Flow LP1* CO GPA CO GP f LP3*~~GP f LP4+ CO GP.'f 13 Sccum P"assure 'oleg@GPli LP2*~G?v. LP3*Q~OGPli LPae~GPv. 'l 4 Roll& Inject'on .""'ow East+ C) GP!f '<<est* & GP.'f RCP Stat' *LP1 ON / 0 *LP2 ON / ~FF *LP3 ON j FF +LP4 ON /~OFF
- 16. RCS Pressure PSIG 22. PRT Level Charging Flow GP.'f 23. PRT Pressure . PSIG 18 PZR Liquid Temp. F 24. PZR Cycling Htrs. *ON / Ol"~
- 19. PZR Steam Temp. F 25. PZR Backup Hers, *ON ~ OF 10 PZR Level 26. Letdown Flow 0 GPf 71 PRT Temp. 27. Saturation fargin t Q%. f F VSSS 100P PAR<<ETERS ~
ooae, Looo Loon 3 28 19
'ide Range T Hot <<'de Range T CoLd ++ o ~o ..
0 0 OF 30 S/G Pressure PSIG PSIG ~~~~ SIG PSIG 31 S/G N.R. Le~el 9j S/G '<<.R. Level 4.Q a 3 33 35 4 Steam Flow (pph X 10 ) Feed Flow (pph 2 10 ) Aux. Feed Flow(pph X 10 3 )*~C) (~ ZO C) CO
/ " /
36 3
'3 .'fSIV Status CST Level *OPEN
- Q ) '+Q/
*OP< J LO Ft. *OPEN CLOS *0?EV LOS" 38 Steam Dump AT fO / COND U ~~fEVT ST% 'S AVAILABLE / LVAVAILABLE AVAIL+LE / i:VAVAILSLBLE
- 39. East ES<<*
'0. 'est v / 49. East CCP>> V / ESV+ / 50. '<<est CCP* / v East CC<<*
- 42. <<est CC'<<+
~ / /
51. 52. TDAFP* E.fDAFP*
/ /
- 43. East CTS*
Vest CTS*
+ / /
p 53. 54. t'LLDAFP* Diesel*
- 45. North SI*
- 46. South SI*
~ ! /
55. 56. AB CD Diesel* Normal Res.* v / v
- 47. East RKR*
- 48. P<<est R fR*
~ / /
- 57. 12 EP+
Data to be taken bv Control operator. Page 1 of 'oom
~~ rl~ p~~~ dark
PMP 2080 EPP.103 E!QiIBIT A sCHSV CAP VFOR<3TIOV SHsET Data Taken By Da a Reviewed Bv VOTE Vhen redundant indication exists, record mos" severe condition. RCS fsTE. 1 Containment Temp.
- 5. Intermediate Range 1 k~ I A"-PS
~
'3 Cont. H Concentration
- 6. Containment Pressure~C). <~PSIG
- 3. RVST Level
- 7. Couteiumeuc Sump Level*
Source Range
- CP.f S. Corteiomec- Level e C?
CTS Pumps East* ON 'j(00~ Ceet* ON /~OFF '0. RLSZ Spray Flow East+~~GPM Not th 'GPN Ves t* ~ GPM 1 3 SI Flow BIT Flow Accum pteeeu".e LPl* W Lpl~gG?N G?K LP2* (0 L?2D~G?v. GP '\. LP3* LP3* GPM GPN LP4* GP.t L?4*~OPS O GPM L6. R."3. RCP RCS Injection Stat s Pressure F~ ow Eas + .
+LPl ON, OFs O'PM +LP2 ON /A/3 PSIG FJes *LP3 t+
ON
- 22. PRT Level
/ OFF C> CPM DL?4 ON /~
1,. Charging Flow GPM 23. PRT Pressure . PSIG PZR Liquid Temp. F 24. PZR Cycling Htrs. *ON / 19 PZR Steam Temp. F 25. PZR Backup Htrs.~*ON / OF.
'30 PZR Level 26. Letdown Flow GPM PRT Temp. 27. Saturation Margin lb9 .3 F VSSS LOOo Ph<~fETERS Loo Loo ~Lot 3 l coo
- 28. Vide Range T Ho" W+ F oF W+ o
- 29. V'e Range T Co' F F F
- 30. S/G Pressure ~(~PSIG Q PSIG ~C3 PSLG ~~PS IG S/G N.R. Level MQJ ~
32..S/G '<<.R. Level
- 33. Steam Flow (pph X 10 )
~~Ps 3>>. Feed Flow (pph X 10 )
- 35. Aux. Feed Flow(pph X 10
~) CO )+,BC'6.
MSIV Status *OPEN *OPEV C OS *OPsN / CLOSE, +OPEN CLOS 3.. CST Level * ~
- 38. Steam Dump +A MO / COND UIPMsVT S 3LTUS AVAlLABLE W
/ UVAVAILMLE ~
AVAILABLE / v VAVAI ~LE
- 39. East ESV* / 49. Eas" CCP~/ /
/ >>'0. Vest ~l. East t
ESW* CC<<+ W /
/
50. 51. Vest TDAFP+ CCP*
~~ / / /
>>2 . ~3. East
'<<es CC<<+
C S* ~ / 52. 53. E.fDAFP+ ttttDAFP* /
/
Vest CTS* ~5. North SI~ >>6. South SI*
~ /
5a. 55. 5o. AB CD Diesel* Diese'* Vormal Res.+
~ / /
~7. Eas" RHR+ ~8. Ves" RELY+
~ / /
- 57. 12 EP* /
Data to be taken bv Control Room operator. Page 1 of 1 Revision 0 W~ po pcx
- t PMP 2080 EPP.103 EXHIBIT A T"-CHV'FCA "VFOR<3LTIOV SHEET Unit Vo: Q Date +- ~QQZime 05~
Data ;aken By Data Reviewed Bv
~VOT~
When redundant indicateon exists, record most severe condition. RCS Contai~ent Temp.
- F 5. Intermediate Range l .8 E-~ I AMPS Cont. H Concentracion
- 6. Containment Pressure O~~PSIG
- 3. RWST Level
- 7. Concainment Sump Level+
F Source Range
- CPM 8. Containment'evel
- Q
- 9. East* 'w'ceo* ON /~OFF 10 11 CTS Pumps RHR Spray SI Flow Flow East+~>
OV North~~) OF GPM GPM Wes t* ~ GPM BIT Flow LP1* C'PM LP2* D GPM LP3* O GPM LP4* CO GPM LP'~CO GPM LP3*t~o LP4*~GPN Accum Pressure 0LP2*~GPM 13 GPN F Rus Inj ecto on Flow Eas "+ GPM West* O RCP Status <<LP1 OV / OFF *L22 ON /4QFF eLP3 ON / e eLPL ON /(00~) LO. RCS Pressure PSIG 22. PRT Level
- 17. Charging Flow GPM 23. PRT Pressure . PSIG 18 PZR Liquid Temp. OF 24. PZR Cycling Htrs. *ON /
- 19. PZR Steam Temp. o~ 25. PZR Backup Htrs *ON / OFF
'30 PZR Level 26. Letdown Flow GPM PRT Temp. o~ 27. Saturation Margin~~(~ F VSSS LOO~ >ARK<ETERS Looo Loo ~Leo 3 Looo 28 Wide Range T Hot r ~%5 o r ++- o 2a W'e Range T Cold F O 0 o 0 30 %1 S/G Pressure S/G N.R. Le3 el PSIG PSIG CO PSIG ~~PS IG 3o S/G W.R. Level 33 Steam Flow (pph X 10 )
e rFeed rlow (pph X 10 ) 35 Aux ..Status eed r low(pph X 10 ) + 36 37 MSIV CST Level
*OPEV '+ / L SE *OPrV CL Ft. +OPEV / CLO *OPEN, CLOS 38 Steam Dump *ATMO COND U PMrV ST< 'S / UMVAILMLE /
- 39. East ESW* ~
AVAILABLE
/ /
- 49. East CCP>> ~
AVAI>~LE
/ /
t3NAVAILABLE
- 40. West ESW*
East CCW*
- 42. F<<est CCW*
~ / /
- 50. West CCP*
- 51. TDAFP*
E'.KAFP*
~ ~ / / "-ast CTS* ~ / /
52
- 53. WMDAFP*
'3.
- 54. AB Diesel*
/ /
West CTS*
- 45. North SI*
South SI*
~ / /
- 55. CD Diesel+
- 56. iVormal Res.*
~ / /
- 47. East RHR+
- 48. Wes" RHR+
~ / /
- 57. 12'P+ /
Data to be taken bv Control Room operator. Page 1 of 1 Revision 0
P.'fP 2080 EPP.103 E'GiIBIT A T""CLfiV~CAL VFOR TION SH"E -8rr. ~615 Data Taken By Data Reviewed Bv
~VOT~
When redu..dant indication exists, record most severe condition. RCS
- l. Contai~ent Temp.
- 5. Intermediate Range l D~ l ) A".PS Cont. H Concentration
- 6. Containment Pressure . PSIG
- 3. RWST Level
- 7. Containment Sump Levels 4 Source Range
- CpN 8. Contalrteen" Level e L5 l
- 9. East* ~ Neet* /~OFF 10 CTS Pumps RHR Spray Flow ON j(~O East*~~GPM Wes t*
ON
~C) GP.'f /:
11 SI Flow Nor th~~~GPM South* GPM
] '3 BIT Flow LP1* GPM LP2* C'PM -
LP3* g~GPM LP4~ C) GP.'f 3 Accum Pressure '1+ GPM LP2+~GPM LP 3*~i~GPM LP4~+~GPM
~
3 R~R Injection Flow East+ CO GPM West* W GPM
'5 RCP Status <<LPI ON / OF *L22 ON / *LP3 ON LPe ON /(IPrP
- 16. RCS Pressure PSIG 22. PRT Level
- 17. Charging Flow
'g. PZR Liquid
- 19. PZR Steam Temp.
- 20. PZR Level 2RT Temp ~
Temp.
~4 GP.'f 23. PRT Pressure <<~~PSIG
- 24. PZR Cycling Htrs. *ON
- 25. PZR Backup Htrs. *ON
- 26. Letdown Flow
- 27. Saturation Margin ~( g F C GPM
/ / FF VSSS LOOP AR<fETERS ~Loon Loon 3 Loon '3 g Wide Range T Hot o oF >4m") o ~~o ~~ o '39 Wide Range T Cold P 9c '-.
- 30. S/G Pressure PSIG PSIG PSIG PSIG
- 31. S/G N.R. Level S/G ".R. L h
Steam F'ow (pph X 10 ) cD Feed Flow (pph X 10 ) C0
- 35. Aux. Feed Flow(pph X 10 )+~M
- 36. MSIV Status
- 37. CST Level
*OPEV / C ac.
g
*OPEV / *~Q~F t CL *OPEN / CLOSc. OPEN . C OSc.
- 38. Steam Dump *A;.fOS / COND
" Ui~. ~VT STATUS r
- 39. East ESW*
AVAiLABLE
~ / /
LiLAVAILABLE
- 49. Eas" CCP~ ~
AVAILABLE /
/
VAILABL 40. 41. West ESW* East CCW* ~ /
/ /
50. 51. West CCP* TDAFP* ~
~ / /
42. 43.
<<est CCW+
East CTS* ~ // 52. 53. E<eDAFP+ f"LLDAFP*
/ / / 'reest CTS*
- 45. North SI*
South SI*
~ / /
54. 55. AB Diesel* CD Diesel* Normal Res.*
~ / / '7. as"
'48. West RHR* RELY* ~ // 56.
- 57. 12 EP+ /
Data to be taken bv Contro 1 Room operator. Page 1 of 0 'evision
PNP 2080 EPP. 103 E:QiIBIT A 7'"-CHV LC 'F RKKTIOVL SHEET Unit No:Q Date+~~QTime 055+ Data Taken Bv Data Reviewed Bv V~O
'<<hen redundant indication exists, record most severe condi"ion'.
. CS t3 gC'. Contai~ent Temp.
- 5. Intermediate Range ! . 1 4-) f AMPS Cont. H Concentration
- 6. Containment Pressure~~<~~PSIG
- 3. RP<<ST Level
- 7. Containment Sump Level+
Source Range
- CPN 8. Containment Level
- D
- 9. CTS Pumps Eas
- ON /~OFF Gest* ON /~OFF 10 RLLR Spray Flow East* CO GPN Mes t+ GPN 13 SI Flow Vot the GPN South* GPN 1'3 BIT Flow Accum Pressure
. LP1* 0 GPN LP2*
LP2*~G?N O GPN L>3* CO GPN LP4* LP4*~GPN
~ GPN LP1+Q~GPM LP3*LP~OGPN 2 I Rw& Injec" ion Flow East+ ~ GPN Mes t* ~ GPN 5 RCP Status *LP1 ON / *LP2 OiV /~O *LP3 ON / F *LP4 ON /~OF~
16, 7 RCS Pressure PSIG 22. PRT Level W '33 l Charging Flow GPN 23. PRT Pressure . PSIG 18 PZR Liquid Temp. OF 24. PZR
'ZR Cycling Htrs. *ON / OFF 19.
70 PZR Steam Temp. PZR Level O 25 Backup Htrs.
- 26. Letdown Flow W
*OVi GPN /
ol PRT Temp. 27. Saturation Margin~~ F SSS LOOP AR.~P.E>ERS ~Leo 1 ~Los 2 Loon 3 Loon "8
'7 o 'ide '<<a Range T Hot de Range T Cold ++ oF P ~aF go ~+ o 30 %1 S/G Pressure S/G V.R. Level O PSIG 0
PSIG ~~PS IG S/G '<<.R.. Level 3 33 Steam F'ow (pph X 10 )- 33 36 Feed Flow (pph X 10 ) etta. Feed FLon(pph NS IV S tatus X 10 3
*OPEN )*~ /
c'~ CLOS@, *OPEV / C OS *OPEN / OS *OPEN, CLOSE 37 CST Level
- 38 Steam Dump *A . / COiVD
~ U P<~VT STATUS
- 39. East ES3 * ~ ///
AVAILABLE L'LVAVA'ILABLE AVAILABLE / UVAVA F~LE
- 49. Eas" CCP~ v /
- 40. ;est ESV~ 50. <<est CCP* /
East CC<<*
- 42. P<<est CC'<<*
~ // 51. TDAFP*
52.'.fDAFP+
~W ' /
- 43. East CTS* Z / 53. '444DAFP* /
'<<est CTS* / v 54. AB Diesel* /
- 45. North SI* W / . 55. CD Diesel* 3
/
- 46. South SI* / 56. Normal Res.* /
- 47. ""as" RHR+ v / 5?. 12 EP* /
- 8. ~es: Rw~*
Data to,be taken b Control
/ Room operator. Page of y 1 1 Ao ~~~ 4c c.her+ Revision 0
PAP 2080 EPP. L03
, EXHIBIT A T"-c-'vvcA Ã 0!CvATYov 8H"-:--, Gni vo:Q! Gene+-3 )opine Data Taken Bv Data Reviewed Bv v'OTE Vhen redundant indication exists, record most severe condition.
RCS QQ +LPV Contai~ent Temp.
- F 5. Intermediate Range ~.C'+ <) A.'tPS 1 Cont. H Concentration * '3 6. Containment Pressure Q. ?SIG
- 3. RVST Level
- 7. Containment Sump Level*
4 Source Range
- D CP.'l 8. Coneelnnene Level *
- 9. CTS Pumps East* ON OF Vest* ON+ FF 10 RHR Spray Flow East* GPN Mes t* 23 GPA 11 SI Flow North~>>~GP.'f BIT Flow LPL* ~ GPA LP2+ D GP.'i LP3* D GPN LP4* CO GPN 13 Accum Pressure LPL+~GPA LPZ+~GP.'f LP3e lp'~GPN LP4*~GPN 15 e
RPZ, RCP Injection Status
- 16. RCS Pressure Flow
+LPL ON East+ / F ~ *LP2 ON GPA /
PSIG
~ 22. 'Pes *LP3 PRT t*
ON / Level
~ ~LP4 GP.'1 ON '3 /~
1/ . Charging Flow GP.'f 23. PRT Pressure . PSIG 18 PZR Liquid Temp. OF 24'. PZR Cycling Htrs. *ON / 0 lo ">0 PZR Steam Temp. PZR Level OF 25. PZR Backup Htrs *04N /
- 26. Letdown Flow GPLi 9~ '1 ~ PRT Temp. 27. Saturation 'Aargin &F 0 v SSS LO01'<R<METERS -ooo Looo L~oo 3 Loon 28 29 Vide Range V'e Range T Hot T'o }.d
~50 " F ~~0 o 30 S/G Pressure PSIG PSIG SAG 31 S/G N.R. Level 3o S/G V.R. Level 33 Steam F'ow (pph X 1.0 )
Feed Flow (pph X 10 ) CO 3o Aux. Feed Flow(pph X 10 3 )* 36 37
'ASIV Status CST Le~el *OPEN 'P / C *OPEN /
Ft.
*OPEN / CL SE *OPEN, CLOSE 38 Steam Dump *ATM / COND ~ UIPHENT STATUS / /
- 39. East ESV* ~M AVAILABLE
/
UNAVAILABLE
- 49. East CCP>> ~
AVAIL3LBLE
~ / /
UNAVAILABLE
- 40. '.vest ESV*
East CCV* ~
~ / / /
- 50. Vest CCP*
51.. TDAFP* ~
~ /
- 42. Vest CCV*
- 43. East CTS* ~
~ / /
52. 53. EM)AFP* 4iiDAFP+ ~
~ / / /
45. Vest CTS* North SI* South SI*
~ ~ / / >4.
55. AB CD Diesel* Diesel>> ~ /
/
46. 47. 48.
"=as" RPZ*
Vest R'.LR+ '
~ / / >o.
57. Normal Res.* 12 EP* / Data to be taken by Control Room operator. Page l. o Revision 0
'7 PNP 2080 EPP.103 E!KIBIT A T"-CHN~C iF R<KTION SHEE L t:ni" No: W Date~+H~QTime Data Taken Bv Daca Revi,ewed Bv
~LOT" t hen redundant indication exists, record mos" severe condition.
R.CS e3
~+3f 3. 'P 3 1 Contai~ent Temp.
- 0 F 5. Intermediate Range 1 >4 f l ALPS Cont. H Concentration * '33
- 6. Containment Pressure . PSIG 3 RVST Level
- Containment Sump Level*
I Source Range
- CPu ll. Con"element Level
- CO
""as-* Vest*
9; CTS Pumps
- 10. RM Spray Flow SI Flow East*
No st N~e
~ /(00~0 ON GP~f GP.f Ves South*
ON t* W
/~OF GPA'1.
GP f
- 12. BIT Flow LP1* O GP.'f LP2* O GP."f LP3* GPA LP4~ H GP".f
- 33. Accum Pressure LPLM~O CPM LP3*~GPN LP3eg~>GPN LP4*~GPN Rf3Z Inject'on
- 16. RCS Pressure Flow ="as-+
/ eao 'Gm CO GPA PSIG Ves t* D GPef '" " //sn '"-' /tev)
- 22. PRT Level
- 17. Charging Flow GPf 23. PRT Pressure . PSIG l.S. PZR Liquid Temp. F 24. PZR Cycling Hers. *ON /
SV / l.9. PZR Steam Temp. F 25. PZR Backup Htrs. *ON OF
- 20. PZR Level 26. Letdown Flow GP~f
- 21. PRT Temp. 27. Saturation Nargin~+)~ F NSSS LOO>> 'VPETERS ~Leo l ~coo ~oo 3 ~oo 28 Vide Range T Ho" S4 Q'-
/3 V de Range T Col.d ~C) &9& 'F 9 F F
~~
30 el 3 '3 33 33 S/G Pressure S/G N.R. Level S/G V.R. Level Steam Flow (pph X 10 ) Feed Flow (pph X 10 ) Aux. Feed Flow(pph X 10 )* CO'O PSIG I ) & PSIG llew 3PSI G PSIG 36 37
.'fSIV Status CST Level *OPEN + / CL SE *OPEN / CL Ft. *OPE.'i / LOS OPEN . CLOSc 38 Steam Dump *. MOS / COiND UI D'LP3. 3/iT STAWS AVAI~LE / LPNAVAILABLE AVAILP+LK / UNAVAI <BLE W / /
- 39. East ESV*
- 40. Vest ESV* ~ /
- 49. EaSt CCP3'C
- 50. Ves- CCP* /
<<l. East CCV+
~ //
v 51. TDAFP* /
/
- 42. Vest CCV*
- 43. East CTS*
Vest CTS*
~v / /
52. 53. 54., E'1DAFP+ friiDAFP* AB Diesel*
/ /
A /
- 45. North SI*
- 46. South SI* ~ /
/
55. 56. CD Diesel* Normal Res.*
- 47. East R.'Lq*
- 48. Vest RHR*
Data to be taken
~V bv Control / Room ooerato
- 57. 12 EP+
Page 1 ot 1 Revision 0
PNP 2080 EPP.103 EXHIBIT A
""C'FFLMiCA ~FORMATION SHEE'T Cuit No:~Oa"e~dFime Data Taken Bv Data Reviewed Bv -, ~NOT+ <<<<hen redundant ..dicacion exists, record mose severe condicion.
RCS '0Q 'Lgg. T3. 1 Contai~ent Temp.
- l 0 l F 3. Lntetmediate Range ~O E ilaNPF Cont. H Concencration
- 6. Containment Pressure C) Q PSIG
- 3. RF<<ST Level
- 7. Containment Sump Level*
Source Range
- CPN 8. Containment Level
- 33 9.
'0 CTS Pumps RHR Spray Flow East* Ease* ON ~OF GPN
'<<est*
Wes t* ON / ~FF GPN 11 SI Flow North>> GPN 'ouch* GP.i BIT. Flow LP1* ~ GPN LPR<< C3. GPR LP3* GPN LP4* (0 GPN 1 cecum essute LPL*~~GPN LP2<<~CPN LP3*~to LP4<<~GPN 1 3
~s RKR P
Inj ection Flow ""asc+ C'PS Wes c* C3GPM GPA 1i RCP Sea us *LPI ON /~OF *LP2 ON /~FF *LP3 ON / F *LPld ON /~OF 16 RCS Pressure PSIG 22. PRT Level 17 Charging Flow GPA 23. PRT Pressure , PSIG 18 PZR Liquid Temp. F 24. PZR Cycling Htrs. *ON / 19 ') 0 PZR Steam Temo. F 25. PZR Backup Htrs. *ON G GPRi 0
/ OF PZR Level ~ . 0 26. Letdown Flow O1 PRT Temp.
0 2?. Saturation Margin .& F SSS FOOP ARK E>ERS oo Loo ~Lao 3 ~Lao o
- 8. Wide Range T Hoc
~
F <<e Q V'de Range T Cold
- 30. S/G Pressure PSIG ~ o PSIG
~C '.-F PSIG 31 S/G N.R. Level ) S/G W.R. Level
- 33. Seeam FLow (pph X 10 ) CO 3w Feed Flow (pph X 10 ) CO
- 33. Aux. Feed Flow(pph X 10 3 )*
- 36. .'fSIV Status 3
s CST Level
*OPEN '+ / OS *OPEN *~~Fj CLOS c *OPEN / C OS *OPEN, CLOSE
- 38. Steam Dumo *ATMO / COND U 1'83'R STATUS
/ / ~~
AUAI LE UNAVAILABLE AUAILABLE UNAVA<LABL>>"
- 39. Ease ESW* /
/
- 49. East CCP* /
~0. West ESW* ~1. East CC<<* ~2. <<est CCW*
~V v / /
50. 51. 52. West CCP* TDAFP*
~%)AFP* ~M / / / / ~ /
~3. Ease CTS+ West CTS* V R /
- 53. WLLDAFP*
AB Diesel* ~
~ /
North SI*
+ //
v Diesel* / ~F5. 55. CD ~o. South SI+ 56. Normal Res.* , / ~7. Ease R.'K* A / 57. 12 EP+ / ~8. West R"IR+ R / Data co be taken bv Control Room operator. Page 1 of 1 Revx.saon 0
PfP 2080 EPP.103 EXHIBIT A 2"-cp3l c rpoRKKPLGN sN". o Unit No: Dace -Q-/opine Data Taken Bv Daca Reviewed By
~VOTE 'w'hen redundant indf.cation exists, record most severe conditi.on.
RCS LECT%'3 Contai~ent Temp.
- D F 5. Intermediate Range l. OE-1 l ALPS Cont. H Concentration
- 6. Containment Pressure~<~PSIG 3 RfN'ST Level
- 7. Containment Sump Level*~)
Source Range
- 9: CTS Pumps East* OiV (O~F Vest*
t* ON /(0+ 10 RHR Spray Flow East* GPA Vfes GP f 11 SI Flow North~>>) GPef 'outh* GP!f
~
BIT ."low LP1* CO GP!f LP2* 0 GPof LP3+~~GPLf LP4* GPLf 13 eccum pressure Lpletru~GSM Lp2e~GSN Lp3*~~GSN Lpe*~G?N 14 RKR Injection Flow East+ C) GP!f 'iest* CO GP.f SCP S"arus 'LP1 ON / 0 3 *LP2 ON /~v *LP3 ON / P eLPa ON /~P 16 RCS Pressure --) PSIG 22. PRT Level 17 Charging Flow GPf 23. PRT Pressure~<I,1-~PSIG 18 PZR Liquid Temp. F, 24. PZR Cycling Hers *OiV ~ / OF 19 PZR. Steam Temp. F 25. PZR Backup Htrs. ON 20 PZR Level 26. Letdown Flow G?.'f '31 PRT Temp. F 27. Saturation ifargin . F NSSS OOP 1'AR A.f3"<ERS Loo Looo 2 Loon 3 1 coo
'>>ide Range T Ho"
'3 0 0 7 de Range T Cold F r 30 S/G Pressure C0 PSIG O PSIG C) PSIG PSIG
'1 1 S/G N.R. Level '3 QQ 0 32 S/G 'R. L 1 ~ 3 33 Steam r'ow (pph X 10 ) CD C) CD 34 reed F1ow (pph X 10 ) CO
- 3) Aux. Feed Flow(pph X 10 }*
36 3w
.'fSIV Status CST Level *OPEN / CLOSE *OPEV C OS Fe *OPEV / CL Sr. OP V C OSc, 38 Steam Dump *ATMO / COiVD UIPLf~V ST31 PS AVAI LE / LVAVAILMLE 49. AVAIL&LE / LVAV31 LABL"
- 39. East
- 40. '<<est ESV*
ESfN'* ~
~ / /
50. East CCP>> Vest CCP*
~
M / Z /
~ ///
East CC"* 51. TDAFP* '. Vest CTS*
- 42. 'iest East CCV+
CTS* v
~W //
u / 52. 53. E.fDAFP* lNLLDAFP* ~~ //
- 45. North SI+
South SI* '
)4 55.
56. AB CD Diesel* Diesel* Vormal Res.*
~ /
- 7. East R~~* A / 57. 12 EP+ /
- 48. Vest RHR* H Data to be taken bv Control Room operator.
/ Page 1 of 1 Revision 0
PMP 2080 EPP . 103 EXHIBIT A poCwv Ca ?vno?Vap?pv Sms?n Gnic Vo:~Pace~3)-GLCtime dLo tS Data Taken Bv Data Reviewed Bv V~30 Vhen redundant indication exists, record mos" severe condition. RCS '0 3 vi T'cP
- l. Contaiyent 1
Temp.
- lH 5.
6. Intermediate Containment Pressure Range ), D+
~ ~ AMPS PSIG
- 3. RVST Level
- 7. Containment Sump Level*
4 Source Range CPM 8. Containment Level *
- 9. CTS Pumps East* ON /~OF Vest,* ON /NW 10 RHR Spray F'ow East* & GPM 11 SI. Flow North~~~GPM 11 BIT Flow Accum P"essuce LPl~ C GPM LP2* CO GPM Lol*~G?m L?2*KG?V LP3* ~
L?3eM<MGPN GPM LP4* L?4*~G?V n GPM
/~
1 14 Vwc Injeccion flow Gas "e GPV Gesc* GPM 3 RCP Sta us +LP1 ON / OrF *LP2 ON / ~F: *LP3 ON / F *LP4 ON
- 16. RCS Pressure &CO PSIG 22. PRT Level Qs
- 17. Charging Plow GPM 23. PRT Pressure PSIG 18 PZR Liquid Temp. F 24. PZR Cycli.ng Htrs. *ON /
- 19. PZR Steam Temp.
- 20. PZR Level
- 25. PZR Backup Htrs ~ON t< / F
- 26. Letdown Plow GPM 11 PRT Temp. 27. Saturation Margin U4 Q NSSS OO? ?AR<<E1'~MS oo Loo Loon 3 ~oo 4
~K) "
T Vide Range T Ho- F 0
- ~) o 0 0 1O V de Range T Cold ~X> F F 30 S/G Pressure C) PSIG O PSIG PSIG ~PS?G 31 S/G N.R. Level Qs 3> S/G V.%. Level 33 Steam Flow (pph X 10 ) CO CO Feed .= ow (pph X 10 ) CO 35 Aux. Feed Flow(pph X 10 )*
36 37 MSIV S tatus CST Level
*OPEN + / L SE, *OPEV / OS Ft. *OPEV / OS OPEN .~L3.~>j 38 Steam Dump *ATMO / COiVD " U PM~NT STA PS j// ~ / UNAVAIP~LE AVAILABLE UNAVAILABLE AVAILABLE
- 39. East ESV+ v
~ 49, East CCP~j /
- 40. Ves" ESV+
/
- 50. Vest CCP* ~
~ / /
41. 42. East CCV+ Vest CCV+ ~
~
v
/ /
51. 52. TDAFP* iDAFP*
~
4<< /
/
- 43. East C S*
Vest CTS* ~5. Nor h SI+
~~ / /
53. 54 55. VLLDAFP* AB Diesel* CD Diesel*
~ ~ / /
- 46. South SI* ~ / /
- 47. East RHR*
- 48. Ves- RW+
~~ / / Room operator.
56. 57. Vormal Res.* 12 EP* / Data to be taken bv Control Page 1 o" 1 Revision 0
PAP 2080 EPP.103 E'GiIBIT A TC2' VFOR ATION SH Gnic No: g Pace~+- -ROTIae Data Taken Bv Data Reviewed Bv
'.SOT" T
hen redundant ind'cation exists, record most severe condition. RCS PAR3L!6ETER 1 Containment Temp.,
- lo 5. Intermediate Range l.Ot=-l I A"fPS Cont. H Concentration 6. Goncainaenc Pressure~QS PSIG 3 R<<ST Le~el
- 7. Containment Sump Level*
s Source Range
- CP.'f 8. Containmen" Level *
- 9. CTS Pumps East* ON /(00 'iest* ON / ~FF 10 RHR Spray Flow East* W .GPA Mes t* GPA 11 SI Flow Nor th>> C3 GP!i South* ~ GPA
~
BIT rlow LP1* W GPA LP2+ ~ GP.'f LP3* CO GPN LP4+ GPN 13 Accum Pressure LP1*~GP'A LP2*~GP'A LP3*~3 GPH Lpa*~GPH RLSR Inject'on Flow East+~+~G?A Ves t* GPA 1 5 RCP Status +LP1 ON / ~F. *L22 ON / ~ri +LP3 ON / +LP4 ON / QQ
- 16. RCS Pressure I RQ PSIG 22. PRT Level
- 17. Charging Flow GP!i 23. PRT Pressure~PSIG
- 18. P R Liquid Temp. OF 0
- 24. PZR Cycling Htrs. *ON /
19 PZR Steam Temp.
'evel
- 23. PZR Backup Hers, *GN /
10 PZR 26. Lecdovn Flow GP.'I 0 '> 1 PRT Temp. 27. Sacuracion margin IR+, [ F VSSS 'OOP PARBL<ETERS Looo Loon 2 Loon 3 Loco oo 8 Vide Range
<<de Range T
T Hot Cold F ~C) r"
~S cR~
F 30 S/G Pressure PSIG ~C3 PSIG PSIG )~PS LG 31 S/G N.R. Level 3o S/G <<.R. Level 33 Steam F1ow (pph X 10 ) CO CO Feed Flow (pph X 10 ) 3 auy. Feed Flow(pph I 3 10 )*~M 36 37
<SIV Status CST Level *OPEV + / CL S" *OPEN /(MCL)S)Q +OPEN e ~~pc. / C OS *OPEN, LOS~
38 Steam Dumo +A~OS COVLD UIP'.SENT STATUS AVAILABLE j UNAVAILABLE
/
AVAILABLE / UNAVAILABLE
- 39. East. ESP* W M
- 49. East CCP+ v /t
- 40. 'west ESP+ / 50. Vest, CCP*
East v / M /
/
CC<<* 51. TDAFP*
- 42. <<est CC<<+ H / 52. E'.KAFP* v
- 43. East CTS* / 53. lPI6DAFP* ~ /
<<est CTS*
~5. North SI* gs v
/ /
54. 55. AB Diesel* CD Diesel>>
~ ~ / /
- 46. Sou h SI* ~ / 56. Normal Res.+' /
~ // /
- 47. East RuR* g 57. 12 EP+ .
- 48. <<est RHR*
Data to be taken bv Control Room operator. Page 1 of 0 'evision
PAP 2080 EPP.103 EXHIBIT A TECKl1'CA VFOR~ATION SHEE Un'c No:~Dace~6- IOPine Data iaken Bv Data Reviewed By VOTE
'<<hen redundant indication eziscs, record most severe conditi.on.
RCS PARANcTc Contairuyent Temp.
- F 5. Intermediate Range ) 6E-l ( ALPS Cont. H Concentrat'on
- 6. Containment Pressure . PS IG
- 3. Rf'ST Level
- 7. Containment Sump Level*
Source Range
- Cl CPN S. Concairasenc Level e D e 9.
10 CTS Pumps RNR Spray Floe East* OiV Passe~OPÃ
/~ Wesc*
Vies t* ON ~OFF CO GP!f 11 SI Flow Vorth~~) GP!f South* M GP'f 11 BIT Flow LP1* W GPf LP2* CO Gpq I>3+~) GPA LP4* CO GP'f 13 Accum Pressure LP1~) GPA LP2*~GP.'f LP3*~0 GPN LP4*~GPN In) ection <<es t* '5 RwaR
'RCP Status ~'l ON /Eas t+
Flow
*LP2 ON GP!f /(6Ppr +LP3 ON / F C)C) *LP4 GP'f ON /~Or
- 16. RCS Pressure --) PSIG 22. PRT Level 17 Charging Flow GPN 23. PRT Pressure PSIG 18 PZR Liquid Temp, F 24. PZR Cycling Htrs. *ON /
19. 40 PZR Steam Temp. PZR Level 0 F 25. PZR Backup Htrs. ~OLV
- 26. Letdown Flow
/
GP!f oc 0 PRT Temp. 27. Saturatf.on Nargin . + F VSSS LOO> PARAfETcRS ~Lao ~Lao Loao 3
'<<vide Range T Ho- ~gg o~~5 oP ~5 a ~g5a Za 30 31 '. 'de Range S/G Pressure S/G N.R. Level T Cold ~) D PSIG C>
PSIG e
~D ~C>
PSIG e
~~PSIG 3o S/G <<.R. Level ~ 95 33 Steam Flow (pph X 10 ) O CO C0'eed 34 .Clow (pph X 10 )
35 Aux. Feed Flow(pph X 10 )* 36 .'fSIV Status *OPEN / CLOSE OPEN / L S COPEN /~Eke. OPEN; L c. 3 I CST Level *~C3 e *~My=. 38 Steam Dump *A~a.fO / COiVD E UIP~fENT STATES
/ LVLAVAILMLE 39: "-as" ESw*
- 40. P<<est ESV*
~~
AVAILABLE
~ / /
49. 50. East CCP~ Viest CCP*
~~
AVAII&LE /
/ /
L VAVAI~~PLE
- 41. East CC<<* / 51. TDAFP* .M
~ /
V / /
- 42. <<est CCV*
- 43. East CTS*
'<<est CTS* ~ ~ / /
52. 53. E.fDAFP* wiiDAFP+ Diesel*
~ / /
- 45. North SI*
- 46. South SI*
v
+ / /
54. 55. AB CD Diesel*
- 56. iVormal Res.*
~ ~
v
/ /
- 47. Eas t'.'K+ i / 57. 12 EP+'
- 48. 'Vesa R.'6.+
Data to be taken Z / by Control Room operator. Page -1 of 1 Revision 0
P!fP 2080 EPP.1.03 EXHIBIT A
.".G}Lv Ga vFGRwaTTDR sR".RT Unit Ão:~oa-e~+ OTLne ORBAL Data Taken Bv Data Reviewed 3v ~VO When redundant indication exists, record mos" severe condition.
RCS PAfL urTE '
- 1. Contairugent Temp.
- 5. Intermediate Range ~.C)lc I l AiuPS 2 Cont. H Concentration
- 6. Containment Pressure O. PSIG
- 3. RWST Level
- 7. Containment Sump Level*
Source Range
- CP.'f 8. Containment Level *
- 9. CTS Pumps East* 04V /~+ Vest* ON j(OF~
10 R.'K Spray Flow East* C) GP.'f Wiese* ~ GPM 11 SI F1.ow North<<~) GPN 'outh* CO GPN 12 BIT Flow LPle L> GPA LP2* Ct GPR LP3* lO GPA LP4* C0 GPA 13 accun Pressure L~l+~GPR LP2e~GPR LP34~~~OGPA3 LP4*~CPA 14 R123. In~ ect'n Flow ""as "+~+~GPA Vie s t* GP!f 2 16 17 1.8 RCP RCS Status Pressure Charging Flow PZR Liquid Temp.
<<LP1 OiV /(5F) *L22 OiV / ~FF O
PSIG GP F f 22. 23. 24.
*LP3 PRT PRT PZR ON /
Level ~ *LP4 Pressure~5 9 .PSTG Cycling Htrs. *OLV / OiV /(fF) 19 PZR Steam Temp. OF 25. PZR Backup Hers *ON / OFF s30 PZR Level 26. Letdown Flow 0 GPRr.n
'31 e PRT Temp. F 27. saturation Marsin 'R p NSSS LOOP ARAuE>ERS Loon .~ ~Lao ~Leo 2 3 or MCX"OoF o oS Vide Range T Hot oF ~~ ~OGO M~
~ oo 30 Vide Range T Cold S/G Pressure F PSIG F PSIG
~W F PSTC ~O F
PS2G 31 S/G N.R. Level 3o S/G 4.R. Level 6 33 Seeam rlow (pph X 10 ) CO 34 Feed Flow (pph X 10 ) CO 35 Aux. Feed r low(pph X 10 )* 3 CO ~C) ~O 36 37
.'fSIV CST Status Level *OPEN / CL S *OPEN / CLOS Fe. *OPEN /~LC~Se. *OPEN CL S 38 Steam Dumo ATMOS / COiVD UI u VT STA AVAI LE / UVLAVAILABLE AVAILABLE / LVAVAILABLE
- 39. East ESW* / 49. East CCP* /
- 40. Vese ESW* v / 50. West CCP* /
East CCV* v / 51. TDAFP* /
- 42. Vest CCW* . v / 52. E.Q)AFP* /
- 43. East CTS* v / 53. t 44DAFP* /
- 44. Vest CTS*
- 45. North SI*
~~ / /
54. 55. AB Diesel* Diesel.*
//'
- 46. South SI*
- 47. East RHR*
~ ~ / /
56. 57. CD Normal Res 12 EP+
. *.~ /
- 48. Vest RKR+
Daea to be eaken bv Control Room operaeor. Page 1 of 1 Revision 0
PNP 2080 EPP.103 E.'QiIBIT A TDCKV CA VFOR.LWTIOV SH>ET Unit No: eo) Date 4 9" }QTLae QW+5 Data Taken Bv Data Reviewed Bv VOTE
'<<hen redundant indication exists, record most severe condi"ion.
RCS Contairugenc Temp.
- 0 F 5. Intermediate Range I.COE ~l ALPS Conc. H Concentration 6. Containment Pressure . PSIG RVST Le~el
- 7. Containment Sump Level*
Source Range
- CO CP~i 8. Containment Level
- 9. CTS Pumps Pae East*
*O"N /~OFF ~ Vest*
Vest* ON /C)~FF 10 RKR, Spray Flow GP i GPLi 11 SI Flow North~<< ~GPA GPA 12 BIT Flow LP1* W GP i LP2* ~ GP i LP3* M GPLi LP4+ ~ GP.'i 13 Accum Pressure LP1~~GPM LP2*~GPLi LP3*l+Q GPN LPa*~GPN 1 a RHR RCP Injection Status
- 16. RCS Pressure Flow
<<L21 ON East+ /~O. *LP2 D
ON G Phf
/
PSIG
~ 22.
Ves c* eLP3 ON PRT
/ ~*LPa Level GPN ON /~Or
- 17. Charging Flow 18 2ZR Liquid
- 19. PZR Steam Temp.
Temp. GPLi F F 23. 24. 25. PRT PZR PZR Pressure Cycling Htrs. Backup Hers.
*ON /~
PSIG
*ON /~OF~
'30 PZR Level 26. Letdown Flow DH GPM '31 PRT Temp. 0
- 27. Saturation Margin W0 F NSSS LOOP AR K<E ERS L~oo o ~Leo 2 ~oo 3 Loon
'<<ide Range T Hoc )RD 'F ~IO 28 29 V'de Range T Cold )RCD TU) ~ 'F F ~O'-. ~)C:3'F F 30 S/G Pressure PSIG C) PSIG CO 2SIG PSIG 31 S/G N.R. Level 3)) ) S/G V.R. Level W8 '5 0 g ~
6 33 Steam Flow (pph X 10 ) CO 35 36 Feed Flow (pph X 10 ) ana..".eaa Floe(pph X LO >* ASIV StatuS *02EV /
~
CL c *OP~V WO
/ +OPEN CD /~3~c. ~OPEN <~L)~SE 37 CST Level
- Fc.
38 Steam Dump ATeiOS COVD U Dhc'cQT S'Pg AVAILABLE F / i.VLAVAILMLE AVAIL&LE / uNAVAILABLE
- 39. East ESV+
+ / 49. East CCP+ v /
- 40. Vest ESV* / 50. Vest CCP* /
- 41. East CC'<<* y / 51. TDAFP* !
- 42. Vesc CCV* ' / 52. E iDAFP* /
- 43. East CTS* v
~ / 53. l"LLDAFP* / + // AB Diesel* /
Vest CTS* 54. ~5. North SI* 55. CD Diesel* /
- 46. South SI* . D/ / 56. Normal Res.* /
- 47. Eas" RLPR* v / 57. 12 EP*
- 48. P<<esc R.tR*
Data co be taken by NF / Control operator. Room 2age 1 oC 1 Revision 0
PMP 2080 EPP.103 EXHIBIT A ECHN CA VFOR.'QTION S EET Unit No; 4 Date~&- ~OTime OKXO Data Taken Bv Data Reviewed Bv VOTE
'<<hen redundan- indicacion exists, record most severe condicion.
RCS D LEYTE Q 1 2 Contaf.~ent Temp. Conc. H Concentration *
- lo F'. Intermediate Range
- 6. Containment Pressure COE ~~ AMPS PSIG 3 RVST Level
- 7. Containmenc Sump Level*
Source Range
- CPM 8. Containmen" Level
- 9.
10 CTS Pumps RHR Spray Flow East* Eas"+ OiV /~ GPA Nese* Mes t* ON /~OPE GPA 11 13 SI Flow BIT Flow iccuu Pressure North>> LP1* W LPieggC}GPN GPM GPM LP2+ ~ GPA LP2*~GPN LP3* LP3*~EO CO GPM GPN LP~/ + LP4*~GPN
~ GPM 15')
2
'5 16 RP3.
SGP RCS inject Pressure on F'ow Srarus:LPL ON /~
""ast+ 'I *LP2 GPA ON /+OP+
PSIG Gee
*LP3 ON
- 22. PRT Level
/
I
*LP4 ON,~OrE
] 'P Charging Flow GPA 23. PRT Pressure PSIG 1S PZR Liquid Temp. OF 24. PZR Cycling Hers. *ON / 19 '10 PZR Steam Temp. P>% Level OF Qj
- 25. PZR Backup Htrs. *ON
- 26. Letdown Flow S GPM
/
PRT Temp, F 27. Saturation Margin F VSSS P OO>>A<<WE1'ERS Loo L OD Loon 3 18 '30 Vide Range T Hot
<<ide Range T Cold )RCO 'F l~ " ~~o l~ '.= ~%5'F 0
30 S/G Pressure PSIG PSIG ~PSLG PSIG 39 33 1 S/G N.R. Level S/G ".R. Level Steam Flow'(pph X 10 )
'co ~Sl ~ CxO 3A Peed Flow (pph X 10 )
33 Aux. Peed Flow(pph X 10 3 )* O
/ /
36 3 38
'P ASIV Status CST Level Steam DumD *OPEN AT.fOS C OS COiVD *OPEN * +/ CLOS Ft. +OPEN CLOSe. *OPEV CLOSE < U DV~VT STATUS AVAILABLE / UVAVAII&LE AVAI LE / UVAVAILABLE
- 39. East ESVi*
~/0. 'west ESV*
~ ~ / /
L9. East CCP+
- 50. P<<est CCP* H
/ /
~1. East CC'<<+ v / 51. TDAFP* v / ~2. '<<est CCP<<* ~3. East CTS*
~v / /
52. 03. EMDAFP* ViiDAFP* ~ W /
/ '<<est CTS*
~5. North SI* ~
< / /
- 54. AB Diesel*
Diesel*
~ ~ / /
~o. South SI* ~7. Eas" R.'B*
~v / /
55. 56. 57. CD iVormal Res.* 12 EP*
~ / /
~8. Vest BR+ v' Data to be taken bv Control Room operator. Page 1 oe Revision 0
P'AP 2080 EPP. Ã EXHIBIT A TEC 2l CA VF QTION SH T'T Unie No: & Dace 4-S" t)Time l-)K ~S Data Takin Bv Daea Reviewed By
~VOT~
F<<hen redundant indication exiscs, .ecord most severe condition. RCS 1 Containpent Temp.
- 5. Intermediate Range l ~ ~~ ~ALPS Cone. H Concent acion
- 6. Containment Pressure 0. PSIG 3 R'<<ST Level *, 7. Containment Sump Level+
- 8. Containment Level *
/~
Source Range CPM
- 9. CTS Pumps Ease* OiV Vest+ ON /~OFF 10 RER Spray Flow Eas *~"GPE Res t* GPA 11 SI Flow Nor th~~~GPA 12 BIT Flow LP1+~GPAE LP2+ O GPA LP3* C0 GPA LP4+ M GPA 1
3 Accum Pressure 'l+~GPA LP2*~GPA L?3*CRL~GPN L?4*~G?E I RaL3. In]ection Flow Ease+ lECQ GPA West* GPN 15 RCP Status +LPl OV / 0 *LP2 ON /Q~ *LP3 ON / ~)*LP4 ON /+F~F
- 16. RCS Pressure PSIG 22. PRT Level Charging Flow GPA 23. PRT Pressure PSIG 1
8 PZR Liquid Temp. F 24. PZR Cycling Htrs. *ON /
- 19. PZR Steam Temp.
20 21. PZR Level PRT Temp. F P
- 26. Letdown Flow
- 27. Sartration Margin~& F
~
- 25. PZR Backup Htrs. *ON ~F=
GPA
/
NSSS 'OOE'SAR RFETKRS Loan 1 Los~ Loon 3 ~Leo l&o oF ~C) o qQ o 2S 20 30 Vide Range T Hoc 7<< de Range T Cold S/G Pressure F PSIG 0 PSIG
+g oF PSIG PS IG 31 S/G N.R. Level 3'3 S/G '<<'.R. Level MQ 33 Steam Flow (pph X 10 ) CO 3>> Feed Flow (ppn X 10 ) K'OP 3D Aux. Feed Flow(pph X 10 )*
36 .'fSIV Seatus *OPEN / CLOS" i 52'OPEN /(CLOStg *OPEN / CL S EV CLOS 3w CST Level + 57?
.~I Fe.
38 Steam Dump ATMOS / COND U ~'i""NT STATUS AVAI~LE /
~ UVAVAILDLBLE ~
AVAILABLE / t:VAVAILSLBLE 39. 40. Ease ESP* 7<<ese ES'lt* East CC'* ~v
/ / /
- 49. East CCP:
5G. Gest CCP* ~
~
v /
/ /
41.
- 42. 7<<est CC<<+ ~
~ / /
- 51. TDAFP*
- 52. E.'EAFP* ~
~ / /
- 43. East CTS*
'<<ese CTS* ~ ~ . /
- 53. '4LLDAFP*
- 54. AB Diesel* ~
~ / /
- 45. North SI*
- 46. South SI* ~ /
/ /
- 55. CD Diesel*
So. Eonsal Res.* /
- 7. Ease Rm~
- 48. t ese RM+
- Data eo be taken by ~W
/
Control Room operator.
- 57. 12 EP* /
Page 1 of 1 Revision 0
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE VII. D. THERMOCOUPLE MAPS ERE-9 0
DRl t.l. l)hTh COOK PLANT GRADED EXERCISE DR l I.l. DATA TllERMOCOUPLE DATA 0/3/'30 Time 0/60 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 C
t)BI I.I. I)ATA COOK PLANT GRADED EXERCISE OOI t.l. nATA TIIERIIOCOUPI.E DATA l)ate It/3/90 Time 0l~S 1 2 3 4 5 6 7 8 9 10 ll 12 13 14 15 0 C
COOK PLANT GRADED EXERC1SE DRl l.l. l)ATA TllEBNOCOUPLE DATA l)ate 0/3/~30 Time 0l 1 2 3 4 5 6 7 8 9 10 ll 12 13 14 15 0 C 90
DBll.l. DATA 1990 COOK PMNT GRADED EXERCISE DR I l.l. DATA TllEBHOCOUPI.E DATA Dq<e 4/3/~30 Time 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 Q C aro 457 J 457
t)B l t,l, t)hTA COOK PLANT GRADED EXERCISE DRt t t nhTA TttEfNOCOVPI.E DATA t)at e 4/3/'30 Time Q 0<~ 2 3 4 5 6 7 8 9 10 11 12 13 14 15 C ll r Q70 J
DRll.l. t)hrh 199~) COOK PI ANT GRADED EXERCISE DRl I,I. l)ATA T!IERNOCOUPLE DATA Date 4/3/90 Time 02 JQ 1 2 3 4 5 6 7 8 9 10 21 12 13 14 15 0 C Col Il go J 270 J N
liBl l.l. DhTh COOK PLANT GRADED EXERClSE DR I I,L l)ATA TllERMOCOUPLE DATA Date 4/3/90 Time 0230 1 2 3 4 5 6 7 8 9 1Q ll 12 13 14 15 0 C
l)H l l.l. DATA COOK PLANT GRADED EXERCISE DRl l.l. DATA TllEfNOCOUPl.E DATA Date 4f3/90 Time 0+~~ 1 2 3 i 5 6 7 8 9 10 11 12 13 '14 15 0, C ll o g.~O J 539 N
gc I)kl I.L l)ATA COOK PLANT GRADED EXERCISE DB I I.I. DATA TIIERHOCOUPI.E DATA t)a I. e 4/3/90 Time Og 0 C3 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 0 D 90
PR l l.l. DATA I 990 COOK PAINT GRADED EXERCISE PR l l.l. PA'l'A TllERHOCOUPI E DATA Date 4/3/90 Time D3 S 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 B
IJ 8 l I. L DATA COOK Pl ANT GRADED EXERC I SE DR I l.l. DATA THERHOCOUPI.E DATA Date a/3/90 Time D3 3 0 1 i 2 3 4 5 6 7 8 9 10 1'1 12 13 1.4 15 0
lK hl
DRl l.l. l)ATA COOK PLhNT GRADED EXERCLSE DRl l.l. DArA Tll ElNOCOU PI.E DATA t)etc 4/3/90 Time O3 ~S 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 0 ll o 9- JO J'
~ ' DB l l.l. l)A'TA COOK PLANT GRADED EXERCISE DR I l.l. DA l'A TllERNOCOUPLB DATA l)ate 4/3/90 Time 090~ 1 2 3 4 5 6 7 8 ' 10 ll 12 13 14 )5 0 C e's~ ll o
+70 J
l)Rll.l. l)nTA 19')~) COOK PLANT GRADED EXERCISE DRl l.l. nhrh TllERMOCOUP I.E DATA l)a l e 4/3/90 T i me 1 2 3 4 5 6 7 8 9 10 11 12 13 1 i 15 0 /
4 DRl l,L l)hTA COOK PLANT GRADED EXERCISE DB l l, l. l)ATA TllERHOCOUPLE DATA l)ate 0/3/90 Time 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 c9 C ll o J P UFO
4 kt 0
DBl l.l. l)hTh COOK Pl ANT GRADED EXERCISE DRl l.l. DATA TllEBMOCOUPI.E DATA t)al.c 4/3/90 Time 1 2 3 4 5 6 7 8 9 10 r1 12 13 14 15 . 0 C
4 DHll.l. l)ATA 4')')0 COOK PLANT GRADED EXERCISE DRlLl. DATA TllERHOCOUPLE DATA Dal.e . 4/3/90 Time D50O 1 2 3 4 5 6 7 8 9 10 11 12 13 Ii 15 0
l)B l l.l. t)ATA COOK PLANT GRADED EXERCISE D R I l.l. DATA TllERNOCOUPLE DATA l)ate 4/3/30 Time OS I + 1 2 3 4 5 6 1 8 9 10 11 12 13 14 15 0 387 ll a g7d J N
DRILL l)ATA 1990 COOK PLANT GRADED EXERCISE DRrl.l. DATA THERHOCOUPLE DATA l)a t a 4/3/90 Time 059 0 1 2 3 4 5 6, 7 8 9 10 11 12 13 14 15 C
I) B I I.I. I)ATA 19'30 COOK PLANT GRADED EXERCISE Dg l I.I. DA'I'A TIIEfNOCOU PI.E DATA Da t e 4/3/9O Time GS VX 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 C gyes J Pro
l)kl l.l. l)ATA COOK PLANT GRADED EXERCISE DR I l.l. DATA TllERHOCOUPI.E DATA f)~pe 4/3/90 - Time 04 00 1 2 3 4 5 6 7 8 9 10 kl 12 13 14 15 0 C G
II I)BI I.!. j)ATA .1'390 gOOK PLhNT GRADED EXERCISE DRi ~.~. DATA TllERHOCOUPI.E DATA t)a tc </3/OO Time 04~ 1 2, 3 4 5 6 7 8 D 9 10 11 12 13 14 15
1990 COOK PLMT GRADED EXERCISE DRt t.t. DATA TltF RHOCOU Pl.E DATA t>ate 4/3/90 Time (34 8Q 1 2 3 i 5 6 7 8 9 10 11 12 13 14 15 Q C
l)R l l.l. l)ATh COOK PIANT GRADED EXERCISE DR l l.l, DATA TllERNOCOUPI.E DATA l)a I e 4/3/90 T i me gg 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 c9 C 33/
l)RI I.I. I)ATA . COOK Pl ANT GRADED EXERCISE DR I I.I. DATA TIIEBHOCOUPt.E DATA Da I.c 4/3/90 Time D7 0 2 3 4 5 6 7 8 9 10 11 12 13 14 15 0
DVI l.l. I)nrh COOK Pl ANT GRADED EXERCISE DR l l,l, l)h'I'A TIIEfNOCOUPI.E DATA l)ale 0/3/90 Time 07 ~ + 1 2 3 4 5 6 7 8 9 10 %1 12 13 14 15 C II o 9o P,70 J N
~ 4t I)BI I.I. I)ATA I )9~) COOK PLANT GRADED EXERCISE DRI I.I. I)ATA TIIERHOCOUPLE DATA I)ale 0/3/90 Time 1 2 3 4 5 6 7 8 9 10 ll 12 13 14 15 D 2IQ 96 K
~ g I)illI.I. I)hTA COOK PLANT GRADED EXERCISE DBI l.l. I)ATA TIIERHOCOU PI.E DATA I)ate 4/3/90 Time 0~ ~5 1 2 3 4 5 6 7 8 9 1Q 11 12 13 14 15 2lO 2l f
+70 ll pit (
J Ql 5
I)BI l.l. l)ATA COOK PLANT GRADED EXERCISE DRll.l. DATA TIIERHOCOVPLE DATA l)at.c 0/3/90 Time d 800 2 3 4 5 6 7 8 9 10 11 12 13 14 15 O B C 2/0 4/0 pal
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE VIII. RADIATION DATA A. IN-PLANT RADIATION DA'7A B. . ON-SITE RADIATION MONITORING TEAMS DATA C. DOSE PROJECTION DATA D. METEOROLOGICAL DATA E. RMS DATA F. PLUME EXPOSURE DATA ERE-90
DONALD C. COOK NUCLEAR PLANT Ei41ERGENCY RESPONSE EXERCISE VIII. A. IN PLANT RADIATION DATA The following maps describe the radiological contamination levels and dose rates and the various areas of the plant pertinent to exercise activities for the times shown. These data are to be provided to the player only upon request. In addition to the maps emergency response facility habitability data is included along with contamination/ decontamination data for a contaminated player. ERE-90 SA-l
~ I RADIOLOGICAL AREA STATUS Sl-IEET MAP NO l67 FAUX I:[ QQR A A I I ATI N MK K PE/J~
~ EXTREME ~
RADlATION HIGH RADIATION DID' <ooo
~ $ NTdMI HIGH Rdd)IATION AT[ Qrc.a cLose rakes a +
DOSE
' DENOTES CONTACT / IS RDG.
RATES IN MR HR AT WAIST LEVEL 8 CONTAMINATION IN DPM /COCM SURVEYED BY TIME DAT E REVIEWED BY DATE l RWP USED: A K C /OOO // O~ ~/go 0 o ( DOO /
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+ DENOTES RATES IN MR HR CONTACT / I8 'DG AT WAIST LEVEL 6 CONTAMINATION IN Of% /LOCI SURVEYED BY DAT E REVIEWED BY 4 c (AO'aL. Pk 4f gqy-zan 0@ MsV- tol-w 0 U-2 Ql 0000d io mR./hr . Q~ iso ~A./hr Q~-935 Q Jhr Q t'O /
OO U-I
Rb,DIOLOGICAL AREA STATUS SI-IEET I' N 6I2'LJX. CLOOR MhP NQ 9 A A I I ATI RAOATIOf1 ~ HIGH RADIATI(N EXTREME HIGH RADIATICN NTAMI ATI O~ I I O 530 DOSE
+ DENOTES CONTACT / IS RDG.
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OO U-I
Rb,DIOLOGIGAL b,REb, STATUS Sl-ICCT MAP NO I:LQQFI 'R A A I I ATI I /WW RAOATQ0 HIGH RADIATI(N 053> ~5 cz EXTREME HIGH RADIATICN C NTAMI ATI DOSE
+ DENOTES CONTACT t I8 RDG RATES IN MR HR AT WAIST LEVEL 8 CONTAMINATION IN DPQ /COC SURVEYED BY TIME DATE REVIGYKD BY DATE ~co'd. Pk kW.
MR V->~3 0@ ~sV- to(-w 0 U-2 Ql 00 000 Qs 0 rnR/hr I 5 I m Rlhr t> Pggy i'O / 0 U-. I
'8 'I RAD(OLOGlCAL AREA STATUS Sl-lEET 4 ~'" 6I2'UX. PLQQR MhP NQ ~R A A I I ATI
~ RAOATQN HIGH RADIATICN EXTREME HIGH RADIATICN Q54( - 0 zo HAMI ATi DOSE ' DENOTES CCNTACT / 18 ROG RATES IN MR HR AT WAIST LEVEL 8 CONTAMINATION IN OPM /COCI SURVEYEO BY TIME DATE REVIEWED BY DATE 44O'al. Pk k4or gp,y-2.43 vsY- tol-w 0 U-2 p
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RADIOLOGICAL AREA STATUS Sl-IEET A 'I2'AUX. CLQOR MAP NO A A I I ATI RADATl00 ~ I::I HIGH R4DIATICN EXTREME HIGH MDIATICN gyral- QC I5 ~ C NTAMI ATI A
+ CeeTCS CCWrACT/ IS" each IMSE RATES IN MR HR AT VtAIST LEVEL 8 CONTAMINATION IN OPS /KNC SURVEVED BY TIME DATE REVIEWED BY DATE 0@ MsV- tol-%
0 U-2 OOOOO (? rnid/hr l 't ~Alba ( ~ R/hr@ l'O / OO U-I
Rb,DIOLOGICb,L b,RE@ STATUS Sl-I i' '12',UX. I:LQOR MAP Ng, A A l I ATI I /Wa
~ RADIATION HlGH PADlATICN EXTREME HlGH RADIATl(N OaIS 0630 HAMI ATI DOSE + DENOTES CONTACT / I8 RDG RATES IN MR HR AT WAIST LEVEL 8 CONTAMINATION IN OPM /COCh SURVEYED BY TIME DAT E WP USED: REVIEWED SY DATE A Kc 0@ MsV- to(-9 U-2 Oo ooooo <? rn R/hr l 2. m ql R/hr R/hr I 'O / OO U-I
I 40 RADIOLOGICAL AREA STATUS Sl-IEET i' N 6I2'UX. I:.LOOR I67 A A l l ATl ~ MATION HtGH PADIATICN EXTREME HlGH RADIATICN QQ3 l -O 4%5' NTDMI ATl DOSE DENOTES CONTACT / 18" ROG RATES IN MR HR AT WAIST LEVB. 6 CONTAMINATION IN OPM /COC SURVEYED BY TIME DAT K REVIEWED BY. MUHAM~ a4o'aL pk ACo MR V->~~ 0@ MGV- ta(-9 U-2 Oo ooooo (2. mR1hr 7,5 m Rlhr
~~ 2.~ R/h.@ I OO /
OO U-I
RbDIOLOGiCBL b,RE4 STATUS SPRAT I' 'l2'AUX. I:LOOR MAP NO 'R A 4 l I Al p /wa 2 RADATICjN HlGH RADIATICN EXTREME H(GH RAOIATICN ~C,~S - O10> NTAMI ATI DOSE
+ DENOTES CONTACT / I8 RDG.
RATES IN MR HR AT WAIST LEVEL 8 CONTAMINATION IN OPM /IOOCI SURVEYED BY TIME DAT E REVIEWED BY DATE A K! 04O'aL Pk k4o 0@ MSV- tol-9 0 U-2 ooooa (2.mR jhr S R/%. Rlh gl
/
OO OO U-I
4 RbDIOLOCICb,L bREA STbTUS Sl-IEET N 6I2'UX. CLQOR MAP NO 167 "R A A
~ RAQATlON I I ATI I'3~
HIGH RADIATICN EXTREME HlGH RADIATE ~PO I - 07 I5 I:I C NTAMI ATI
+ DENOTES CONTACT/ IS RDG DOSE RATES IN MR HR AT WAIST LEVEL 8 CONTAMINATION IN OP%I /COC SURVEYEO BY TIME OAT E RWP USED: REVIKV(ED BY OATE A
a4o'sL pkklo K'@ MGY- ta l-'t / 0 U-2 / ooooo Z gnR1hr 3 mR/hr Io R/hr I CI0
/
0 U-I
Rb,D(OL.OCJCAL b,RE@ STATUS SI-IECT I' 'I2'UX. FLOOR MAP NO 4 4 I I ATI RAOATION > HIGH RADIATICN - 07/0' EXTREME HIGH RM)IATICN CI P )I NTdMI GATI DOSE DENOTES CONTACT / l8 RDG RATES IN MR HR AT WAIST LEVEL 6 CONTAMINATION IN DPM /COCl SURYEYEO BY TIME DAT E REVIEWED BY DATE 4 K I 4o'sL Pk Pox 0@ MsV- tol-'t 0 U-2 /
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+ DENOTES CONTACT / I8 RDG RATES IN MR HR AT WAIST LEVB 8 CONTAMINATION IN DPQ /COC SURVE YFO BY TIME DAT E fKVIKNEO BY OATE A K 44O'2 pkkfor 0@
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(:I EXTREME C TATAMI ATI HIGH RADIATION QIOO ~ I~O 4 4 II Clima do+a ~4ca QS ~ cz 5I DOSE RATES IN MR
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S Rb,DIOLOCICb,L AREA STATUS SI-lkET
'i'~i '50'UX. I:LOOR MAP NO. I65 A A I I ATI N PE/~Z
~ ~
~ RADIATION HIGH RADIATION ~go - ldO 0 I:I
~ EXTREME HIGH RADIATION C NTAMI AT( Al
~ ~dec OOSE ' OENOTES CONTACT / I8 ROG.
RATES IN MR HR AT WAIST LEVEL 8 CONTAMINATION IN OPM /lOOCh', SURVEYED BY TIME DAT E WP USED: REVIEWED SY DATE gazoo A
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DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE VIII. A. IN PLANT RADIATION DATA (CONTINUED CONTROL ROOM OSA/TSC HABITABILITYCHECKS TIME DOSE RATE (mR h 0330 ( 2 0345 2 0400 2 0415 2 0430 ( 2 0445 ( 2 0500 ( 2 0515 S 2 0530 2 0545 2 0600 2
...(1615 2 0630 5 2 '0645 ( 2 0700 ( 2 0715 ( 2 0730 ( 2 0745 2 0800 2 All air sample results are (MDA.
All smears ~ 100 ncpm. ERE-90 SA-2
PERSONNEL CONTAMINATIONREPO SECTION A NAME: COMPANY: DEPT: REPORT NO.: ssw: DATE: TIME: RWP NO.: ACAD NO.: SUPERVISOR: RP TECHNICIAN: SECTION 8 INSTRUMENT USED: PROBE: INSTRUMENT SERIAL NO.: BKGD: LOCATION OF CONTAMINATIONON BODY (DESCRIBE, OUTLINE ON BODY) CONTAMINATIONLEVEL If applicable, Count Rate with probe adapter attached: ccpm 0 1cm adapter C3 5cm adapter (Use No. to reference drawing if more than one area) Count Rate (ccpm) Decon Count Rate (ccpm) No. Time Before Decon Method(s) After Decon 23,400 9 360 3 740 1 500 500
< 100 Decon Methods: A Wash D Tape Lift G Scrub B Shower E Sweating H Other C Launder F Weak Chemical Solution ERE-90 RA-3
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE VIII. A. IN PLANT RADIATION DATA (CONTINUED POST ACCIDENT SAMPLING RESULTS Total Dilution (PAS panel + Extra Dilution) 1/1000000 After PAS panel dilution sample reads 580 mR. ISOTOPE ACTIVITY ( pCi/ml ) Kr-85M 3.38E-3 Kr-87 6.71E-3 Kr-88 8.79E-3 Xe-131M 9.64E-5 Xe-133 3.05E-3 Xe-133M 4.23E-3 Xe-135 5.75E-3 I-131 2.05E-2 I-132 4.88E-2 I-133 4.12E-2 I-134 2.87E-3 I-135 6.37E-2 Rb-88 1.22E-4 Cs-134 3.55E-4 Cs-137 1.69E-3 Te-129 1.01E-4 Te-132 2.06E-4 Ba-140 1.22E-4 La-140 9.81E-6 La-142 7.87E-6 Pr-144 4.21E-5 ERE-90 8A-4
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE VIII. B. ON SITE RADIATION DATA 1.0 OUT-OF-PLANT AREA The onsite, out-of-plant radiological conditions are attributed to the release from the steam generator safety valve. The release through the steam jet air ejectors and gland leakoff systems do not contribute to the offsite radiological conditions because of the limited time the pathway exists and the low flow rate associated with the systems. Therefore, onsite, out-of-plant conditions prior to 0446 will be normal. Table I provides the controller with out-of-plant radiation conditions in the form of time specific dose rate, airborne and contamination data. Figures 1 through 5 provide the basic plume definition for the time period 0446 to 0730. ERE-90 8B-1
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE ON-SITE, OUT OF PLANT RADIOLOGICAL CONDITIONS TO 100'F CONTAINMENT TABLE I Air Sam les ontamina t z.on Particulate Iodine Levels Time DR CPM pCi/cc c m pCi/cc c m 0100-0115 0116-0130 0131-0145 0146-0200 0201-0215 0215-0230 0231-0245 0246-0300 0301-0315 k 0316-0330
- 0331-0345 0346-0400 0401-0415
- 0416-0430 0431-0445 0446-0500 4.15E3 1.88E4 2.99E-7 OSH 30,000 0501-0515 4.16E3 1.88E4 2.99E-7 OSH 60,000 0516-0530 2.84E3 5.14E3 2.05E-7 OSH 91,230 0531-0545 1.72E3 7.75E3 1.23E-7 6.74E5 2.69E-5 100,108 0546-0600 1.07E3 7.22E3 1.15E-7 6.39E5 2.51E-5 101,340 0601-0615 591 2.68E3 4.27E-8 2.34E5 9.32E-6 210,000 0616-0630 375'46 1.70E3 2.70E-8 1.48E5 5.89E-6 210,950 0631-0645 1.11E3 1.77E-8 9.67E4 3.85E-6 215,234 0646-0700 139 628 1.00E-8 5.48E4 2.18E-6 215,500 0701-0715 83 377 6.01E-9 3.29E4 1.31E-6 215,750 0716-0730 58 261 4.15E-9 2.27E4 9.04E-7 215,750 0731-0745 28 130 2.07E-9 1.13E4 4.52R-7 215,850 0746-0800 32 215,850 0801-0815 28 215,850 0816-0830 28 215'50 0831-0846 28 215,850 DRgpp= Dose rate in mR/hr within 100 feet of Containment OSH = Off scale high
- 1) Radiological conditions are extreme due to the release rate and the stability class of E. Conditions decrease dramatically as readings are observed off centerline of the plume.
ERE-90 8B-2
Cl a+4 t. o5'/5 1. po'IGURE Plume, Width =
GSL4- o( l5 FIGURE 2. Plume WlcLWh "
~20
O4I4 - 07(g R.use Mid& FIGURE 3.
-po
~-ttg o T3o N
Plume Qictfg PO'IGURE 4.
=
0 J
oT I- l>~~ FIGURE 5.
PHP 2081 EPP.2I4 EXhIB IT-A Type of Sample Pecan TaJckag SampLes Before@a +ects Dire&cas-Dist eca-sq. ft. i ae~ San+1 Aftes. S Radf.@tlat Beadiay 9 fan 27.5 mR/hr HacKatice Reah~ 8 tea 1 aNteC' mR/hr 9 I aates: NeaeheL CorxKthmss Ot."ws. Ccm)erLtss " These dose rates are applicable within Site Boundary after the plume has'assed (0730) or moved. If samples are collected . during the release, then, dose rat~s will equal the DAP generated dose rate for the Site Boundary at the time of interest. Dose rate should be increased proportional if samples are collected clos'er to the Plant than Site Boundary (.6 miles),
* ~ As read Page 1 of 1 Revision 0
PAP 2081 EP~.ZI4 EXHIBIT-A ~ of Saa@e Ve etation Date: Tfme Person Ta1dng Sample: tucatiaa: Reference ~oct: Directive: Distance:
~. ft.
After S Radiation BeMLnp 8 Tcn 36 R~~ Re~~ 0 l~
- 27.5 mR/hr 5 1 meter I Neatdmr CorxKtices:
These dose, rates are applicable within Site Boundary after the plume has passed (0730) or moved. If samples are collected during the release, then, dose rates will equal the DAP generated dose rate for the Site Boundary .at the time of interest. Dose rate should be increased proportional if samples are collected closer to the Plant than Site Boundary (.6 miles).
- As read Page 1 of 1 Revision 0
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE VIII. C. DOSE PROJECTION DATA. This section is intended to serve as a base reference for the Environmental Assessment Controller to determine the validity of dose projections performed by the players. It is not anticipated that the players will obtain the exact results contained in this scenario due to variance in the assumptions and operator actions in the simulator. The section consists of actual DAP printouts used to determine offsite radiological data and data. The assumptions applied in the scenario dose projections are as follows:
- 1. RELEASE DURATION: Started at 0430, ran with 8.0 hours and decreased at 0.25 hou thereafter.
2 . VALVE POSITION: Assumed 50.5% resulting in maximum flow.
- 3. COOLANT ACTIVITY: Selected failed fuel gap activity.
- 4. TIME OF SHUTDOWN: Assumed 0210.
- 5. IODINE CONCENTRATION: Applied default value of E-3 Noble Gas reading.
At the initial onset of the event a radiological release is initiated through SRA-2800, Gland Steam Leak Off Monitor and SRA-2900, Steam Jet Air Ejector Monitor. This pathway will cease at approximately 0210 when Safety Injection is initiated which isolates the pathway. No further release will take place until the one noted above at 0430. ERE-90 8C-1
Il 0 0
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE VIII. C. DOSE PROJECTION DATA (CONTINUED Scenario predictions of dose projection results are given in the following table. The definition and units associated with tabulated dose projection parameters are as follows: DRwb Whole body dose rate in mrem/h. Dwb Whole body dose in mrem. This is the projected dose, not the integrated dose. DRthy Thyroid dose rate in mrem/h. Dthy Thyroid dose in mrem. This is the projected dose, not the integrated dose. Average gamma energy in MeV. qng Noble gas release rate in Ci/s. qi - Iodine 131 equivalent release rate in Ci/s. EAL Classification mandated by dose. In addition to the dose projection data, this section also provides meteorology data and forecast. This data should be provided only after the player has successfully demonstrated the ability to obtain it. ERE-90 8C-2
- ~
" ..<<*<<>>* NUeLEAR PLANT ACCIDENT NOTIFICATION>>**>>>>>> DAP RcPORT PAGE 1 OF 2 RECORDFR REC. REC.
NAME TITLE TIME Ol:AS DATE c\/E PLANT COMMUNICATOR NAME TITLE TEL NO.
- 2. PLANT NAME/UNIT 2A. PLANT MESSAGE NO.
- 3. CLASS OF EHERGENCY A. UNUSUAL EVENT B. ALERT C. SITE AREA EMERGENCY D. GENERAL EHERGENCY E. THIS CLASSIFICATION DECLARED AT: TIHE DATE
- 4. DESCRIPTION OF EVENT/INITIATING CONDITION
- 5. PROGNOSIS A. STABLE B. ESCALATING C. DE-ESCALATING D. TERHINATING
- 6. PLANT EMERGENCY RESPONSE ACTIONS UNDERWAY A. OFF-SITE ASSISTANCE PREY. REQUESTED: YES NO B. FIRE C. POLICE D. AHBULANCE E. HOSPITAL F. OTHER G. SITE EVACUATION: YES NO LIHITED H. ON-SITE RH TEAMS DISPATCHED: YES NO TIHE I. OFF-SITE RM TEAMS DISPATCHED: YES NO TIHE
- 7. RELEASE INFORHATION AD POTENTIAL REL. YES NO B. ACTUAL REL. YES NO C. REL. TIHE D. AIRBORNE E. WATERBORNE F. SURFACE SPILL G. POTENTIAL RELEASE DURATION MRS
- 8. HETEOROLOGI GAL DATA A. STABILITY CLASS F BASED ON 1 .06 T(DEG C)/ 50.0 Z(H) OR SIGHA THETA (D)
- 8. WIND SPEED, MPH 5. 0 C. WIND DIRECTION, DEG, FROH 338. TO 158.
D. DOWNWIND SECTOR(S) GHJ E. PRECIPITATION RADIOLOGICAL RELEASE DATA A. EST IHATED MEASURED B. EFF. POINTS 8 HEIGHT GROUND RELEASE C. NOBLE GAS REL. RATE, CI/SEC 4.05E -04 E. AVERAGE ENERGY/DIS., E.MEV 2. 06E-01 E. EQUIV I-131 REL. RATE, CI/SEC 4.0 5E-07 F. PARTICULATES, CI/SEC 0. OOE+00 ~
- 10. CALCULATED OFF-SITE DOSE DISTANCE S.B. 2 HI. 5 HI. 10 MI.
A. WB GAMMA DOSE RATE, HREH/HR A1. 3.20E-03 A2. 1.08E-03 A3. 4.59E-04 A4. 2.01E-04 B. WB GAMMA DOSE, MREM 81. 2.56E-02 82. S.63E-03 83. 3.68E-03 84. 1.60E-03 C. CT GAMMA DOSE RATE, HREH/HR Ci 1.96E-01 C2. 3.18E-02 C3. 1.00E-02 C4. 4.25E-03 D. CT GAHMA DOSE, MREM D1. 1.57E+00 D2. 2.54E-01 D3. S.03E-C2 D4. 3.40E-02 E. SECTOR(S) AFFECTED E1. ALL E2. 8-K E3. GMJ E4. GHJ F. ADDITIONAL DATA
- 11. MEASURED OFF-SITE DOSE RATES DISTANCE S.B. HI. HI ~ MI.
A . WB GAHMA DOSE RATE, HREH/HR Al. A2. A3. A4 B. CT GAMMA DOSE RATE, HREH/HR'. 81. 82. 83. 84. SECTOR(S) AFFECTED C1. C2. C3. C4. D. ADDITIONAL DATA
- 12. PROTECTION ACTION REC. SECTOR(S) MILES "A. NONE 8-K 2 5 10 B. IN-PLACE SHELTERING C. EVACUATION D. KI DISTRIBUTION E. CONTAHINATION CONTROL OTHER ESTIHATE- OF CONTAHINATED AREA A. IN-PLANT SQ. FT;
- 8. ON-SITE SQ. HI.
C. OFF-SITE SQ. MI.
- 14. ADDITIONAL INFORHATION
*<<***>>**NUCLEAR PLANT ACCIDENT NOTIFICATION ~<<>>*>~*~ DAP REPORT, PAGE 1 OF 2 RECORDER REC. REC.
NAME TITLE TIHE 02: 00 DATE I~RE
.,PLANT COHMUNICATOR NAHE TITLE , TEL NO.
- 2. PLANT NAME/UNIT 2A. PLANT HESSAGE NO.
- 3. CLASS OF EHERGENCY A. UNUSUAL EVENT B. ALERT C. SITE AREA EMERGENCY D. GENERAL EMERGENCY E. THIS CLASSIFICATION DECLARED AT: TIHE DATE
- 4. DESCRIPTION OF EVENT/INITIATING CONDITION
- 5. PROGNOSIS A. STABLE B. ESCALATING C. DE-ESCALATING D. TERHINATING
- 6. PLANT EMERGENCY RESPONSE ACTIONS UNDERWAY 4
A. OFF-SITE ASSISTANCE PREY. REQUESTED: YES NO B. FIRE C. POLICE D. AMBULANCE E. HOSPITAL F. OTHER G. SITE EVACUATION: YES NO LIHITED H. ON-SITE RH TEAMS DISPATCHED: YES NO TIHE I. OFF-SITE RM TEAHS DISPATCHED: YES NO TIHE
- 7. RELEASE INFORMATION A. POTENTIAL REL. YES NO B. ACTUAL REL. YES NO C ~ REL. TIME D. AIRBORNE E. WATERBORNE F. SURFACE SPILL G. POTENTIAL RELEASE DURATION HRS
- 8. HETEOROLOGICAL DATA A. STABILITY CLASS F BASED ON 1.11 T(DEG C)/ 50.0 Z(H) OR SIGMA THETA (0)
B. WIND SPEED, HPH 5. 0 C. WIND DIRECTION, DEG, FROM 338. TO 158. D. DOWNWIND SECTOR(S) GHJ E. PRECIPITATION RADIOLOGICAL RELEASE DATA A. ESTIMATED HEASURED B. EFF. POINTS & HEIGHT GROUND RELEASE C. NOBLE GAS REL. RATE, CI/SEC 1.00E -01 E. AVERAGE ENERGY/DIS., E.HEV 2. 06E-01 E. EQUIV I-131 REL. RATE, CI/SEC 1. 0 OE-04 F. PARTICULATES, CI/SEC 0. 00E+00
- 10. CALCULATED OFF-SITE DOSE DISTANCE S. B. 2 HI. 5 MI. 10 MI.
A. WB GAHMA DOSE RATE, MREH/HR A1. 7. 90E-01 A2. 2. 67E-01 A3. 1. 14E-01 A4. 4. 96E-02 B. WB GAMMA DOSE, MREH B1. 6.12E+00 B2. 2.07E+00 B3. 8.80E-01 B4. 3.84E-01 C. CT GAMMA DOSE RATE, MREH/HR C1. 4.85E+01 C2. 7.85E+00 C3. 2.48E+00 C4. 1.05E+00 D. CT GAMMA DOSE, HREH 01. 3.76E+02 D2. 6.09E+01 03. 1.92E401 04. 8.14E400 E. SECTOR(S) AFFECTED El. ALL E2. B-K E3. GHJ E4. GHJ F. ADDITIONAL DATA
- 11. MEASURED OFF-SITE DOSE RATES DISTANCE S.B. MI. HI. HI.
A. WB GAMHA OOSE RATE, MREH/HR A1. A2. A3. A4. B. CT GAMMA DOSE RATE, MREM/HR B1. B2. B3. B4. C. SECTOR(S) AFFECTED C1. C2. C3. C4. D. ADDITIONAL DATA
- 12. PROTECTION ACTION REC. SECTOR(S) MILES A ~ NONE B-K 2 5 10 B. IN-PLACE SHELTERING C. EVACUATION
- 0. KI DISTRIBUTION E. CONTAMINATION CONTROL F. OTHER ESTIHATE OF CONTAMINATED AREA A. IN-PLANT SQ. FT.
B. ON-SITE SQ. HI. C. OFF-SITE SQ. HI.
- 14. ADDITIONAL INFORHATION
>>>>>>**>> NUCLEAR PLANT ACCIDENT NOTIFICATION **>~~***>* DAP REPORT, PAGE 1 OF 2 RECORDER REC. REC.
NAME TITLE TIME 04: 45, DATE LINE PLANT COMMUNICATOR NAME TITLE TEL NO. PLANT NAHE/UNIT 2A. PLANT HESSAGE NO..
- 3. CLASS OF EHERGENCY A. UNUSUAL EVENT B. ALERT C. SITE AREA EHERGENCY g 0. GENERAL EHERGENCY E. THIS CLASSIFICATION DECLARED AT: TIME DATE
- 4. DESCRIPTION OF EVENT/INITIATING CONDITION
- 5. PROGNOSIS A. STABLE B. ESCALATING C. DE-ESCALATING 0. TERMINATING
- 6. PLANT EHERGENCY RESPONSE ACTIONS UNDERWAY A ~ OFF-SITE ASSISTANCE PREY. REQUESTED: YES NO B. FIRE C. POLICE D. AMBULANCE E. HOSPITAL F. OTHER G. SITE EVACUATION: YES NO LIMITED H. ON-SITE RM TEAHS DISPATCHED: YES NO TIHE I. OFF-SITE RM TEAMS DISPATCHED: YES NO TIME
- 7. RELEASE INFORMATION A. POTENTIAL REL. YES NO B. ACTUAL REL. YES NO C. REL. TIME
- 0. AIRBORNE E. WATERBORNE F. SURFACE SPILL G. POTENTIAL RELEASE DURATION HRS
- 8. HETEOROLOGICAL DATA A. STABILITY CLASS E BASED ON .39 T(OEG C)/ 50.0 Z(H) OR SIGMA THETA (D)
B. WINO SPEED, HPH 5. 5 C. WIND DIRECTION, DEG, FROH 351. TO 171.
- 0. DOWNWIND SECTOR(S) HJK E. PRECIPITATION RADIOLOGICAL RELEASE DATA A. ESTIHATED MEASURED B. EFF POINTS 1k HEIGHT GROUND RELEASE C. NOBLE GAS REL. RATE, CI/SEC 1.36E +02 E. AVERAGE ENERGY/DIS., E.HEV 1. 17E-01 E. EQUIV I-131 REL. RATE, CI/SEC 1. 3 6E-01 F. PARTICULATES, CI/SEC O,OOE+00
- 10. CALCULATED OFF-SITE DOSE DISTANCE S.B. 2 MI. 5 HI. 10 MI.
A. WB GAMHA DOSE RATE, HREH/HR A1. 4.62E+02 A2. 1.13E+02 A3. 4.37E+01 A4. 1.92E+01 B. WB GAHMA DOSE, MREH B1. 3.70E+03 82. 9.0SE+02 B3. 3.50E+02 B4. 1.53E+02 C. CT GAHMA DOSE RATE, MREH/HR C1. 3.92E+04 C2. 4.48E+03 C3. 1.29E+03 C4. 5.17E+02
- 0. CT GAHMA DOSE, HREH D1. 3.13E+05 02. 3.59E+04 03. 1.04E+04 D4. 4,14E+03 E. SECTOR(S) AFFECTED E1. ALL E2. B-K, E3. HJK E4. HJK F. ADDITIONAL DATA
- 11. MEASURED OFF-SITE DOSE RATES DISTANCE S.B. HI. HI. MI.
A. WB GAHHA DOSE RATE, MREH/HR A1. A2. A3. A4.
'B. CT GAHMA DOSE RATE, HREH/HR 81. 82. B3. B4.
C. SECTOR(S) AFFECTED C1. C2. C3. C4.
- 0. ADDITIONAL DATA 12 PROTECTION ACTION REC.
~ SECTOR(S) MILES AD NONE B-K 10 B. IN-PLACE SHELTERING HJK C. EVACUATION B-K
- 0. KI DISTRIBUTION E. CONTAMINATION CONTROL F. OTHER
- 3. ESTIHATE OF CONTAMINATED AREA A. IN-PLANT SQ. FT.
B. ON-SITE SQ. MI. C. OFF-SITE SQ. MI.
- 14. ADDITIONAL INFORMATION
**<<**<<*>NUCLEAR PLANT ACCIDENT NOTIFICATION *>*>**~*>* DAP REPORT, PAGE 1 OF 2 RECORDER REC. REC.
NAME TITLE TIME 0~ '00 DATE LINE PLANT COMMUNICATOR NAHE TITLE TEL NO. PLANT NAHE/UNIT 2A. PLANT HESSAGE NO.
- 3. CLASS OF EMERGENCY A. UNUSUAL EVENT B. ALERT C. SITE AREA EHERGENCY g D. GENERAL EHERGENCY E. THIS CLASSIFICATION DECLARED AT: TIME DATE
- 4. DESCRIPTION OF EVENT/INITIATING CONDITION
- 5. PROGNOSIS A. STABLE B. ESCALATING C. DE-ESCALATING D. TERHINATING
- 6. PLANT EMERGENCY RESPONSE ACTIONS UNDERWAY A. OFF-SITE ASSISTANCE PREY. REQUESTED: YES NO B. FIRE C. POLICE D. AMBULANCE E. HOSPITAL F. OTHER G. SITE EVACUATION: YES NO LIHITED H. ON-SITE RM TEAHS DISPATCHED: YES NO TIME I. OFF-SITE RM TEAMS DISPATCHED: YES NO TIHE
- 7. RELEASE INFORMATION A. POTENTIAL REL. YES NO B. ACTUAL REL. YES NO C. REL ~ TIHE D. AIRBORNE E. WATERBORNE F. SURFACE SPILL G. POTENTIAL RELEASE DURATION HRS
- 8. HETEOROLOGICAL DATA A. STABILITY CLASS E BASED ON .44 T(DEG C)/ 50.0 Z(H) OR SIGHA THETA (D)
B. WIND SPEED, MPH 5. 5 C. WIND DIRECTION, DEG, FROM 351. TO 171. D. DOWNWIND SECTOR(S) HJK E. PRECIPITATION RADIOLOGICAL RELEASE DATA A. ESTIMATED MEASURED B. EFF. POINTS 8 HEIGHT GROUND RELEASE C. NOBLE GAS REL. RATE, CI/SEC 1.36E +02 E. AVERAGE ENERGY/DIS., E.HEV 1. 13E-01 E. EQUIV I-131 REL. RATE, CI/SEC 1. 3 6E-01 F. PARTICULATES, CI/SEC 0. OOE+00
- 10. CALCULATED OFF-SITE DOSE DISTANCE S. B. 2 MI. 5 MI. 10 MI.
A. WB GAMHA DOSE RATE, HREH/HR . A1. 4.45E+02 A2. 1.09E+02 A3. 4.21E+01 A4. 1.84E+01 B. WB GAHMA DOSE, HREM 81. 3.45E+03 82. 8.46E+02 83. 3.26E+02 84. 1.43E+02 C. CT GAMHA DOSE RATE, MREM/HR C1. 3.91E+04 C2. 4.47E+03 C3. 1.29E+03 C4. 5. 16E+02 D. CT GAMMA DOSE, HREM D1. 3.03E+05 D2. 3.46E+04 D3. 1.00E+04 D4. 4,00E+03 E. SECTOR(S) AFFECTED E1. ALL E2. 8-K E3. HJK E4. HJK F. ADDITIONAL DATA
- 11. MEASURED OFF-SITE DOSE RATES DISTANCE S. B. HI. HI.
A. WB GAMMA DOSE RATE, MREH/HR A1. A2. A3. A4. B. CT GAHMA DOSE RATE, MREM/HR 81. 82. 83. 84 C. SECTOR(S) AFFECTED Ci. C2. C3. '4. D. ADDITIONAL DATA
- 12. PROTECTION ACTION REC. SECTOR(S) HILES A. NONE 8-K 10 B. IN-PLACE SHELTERING ~HJK C. EVACUATION 8-K D. KI DISTRIBUTION E. CONTAMINATION CONTROL F.~ OTHER
~ ESTIHATE OF CONTAHINATED AREA A. IN-PLANT SQ. FT ~
B. ON-SITE SQ. MI. C. OFF-SITE SQ. MI.
- 14. ADDITIONAL INFORMATION
***~>>~<<* NUCLEAR PLANT ACCIDENT NOTIFICATION wwww~wcwww DAP REPORT, PAGE 1 OF 2 RECORDER NAME LINE TITLE REC.
TIME 'AT REC. E PLANT COMMUNICATOR NAHE TITLE TEL NO. PLANT NAME/UNIT 2A. PLANT MESSAGE NO.
- 3. CLASS OF EHERGENCY A. UNUSUAL EVENT B. ALERT C. SITE AREA EHERGENCY w D. GENERAL EHERGENCY E. THIS CLASSIFICATION DECLARED AT: TIHE DATE
- 4. DESCRIPTION OF EVENT/INITIATING CONDITION
- 5. PROGNOSIS A. STABLE B. ESCALATING C. DE-ESCALATING D. TERMINATING
- 6. PLANT EMERGENCY RESPONSE ACTIONS UNDERWAY A. OFF-SITE ASSISTANCE PREY. REQUESTED: YES NO B. FIRE C. POLICE D. AMBULANCE E. HOSPITAL F. OTHER G. SITE EVACUATION: YES NO LIMITED H. ON-SITE RM TEAHS DISPATCHED: YES NO TIME I. OFF-SITE RM TEAMS DISPATCHED'ES NO TIME
- 7. RELEASE INFORMATION A. POTENTIAL REL.. YES NO B. ACTUAL REL. YES NO C. REL. TIHE D. AIRBORNE E. WATERBORNE F. SURFACE SPILL G. POTENTIAL RELEASE DURATION HRS
- 8. METEOROLOGICAL DATA A. STABILITY CLASS E BASED ON .50 T(DEG C)/ 50.0 Z(H) OR SIGMA THETA (D)
B. 'WIND SPEED, HPH ., 5.2 C. WIND DIRECTION, DEG, FROH 352. TO 172. D. DOWNWIND SECTOR(S) HJK E. PRECIPITATION RADIOLOGICAL RELEASE DATA A. ESTIMATED HEASURED B. EFF. POINTS 8 HEIGHT GROUND RELEASE C. NOBLE GAS REL. RATE, CI/SEC 8.62E +01 E. AVERAGE ENERGY/DIS., E.HEV 1.09E-01 E. EQUIV I-131 REL. RATE, CI/SEC 8.6 2E-02 F. PARTICULATES, CI/SEC 0. OOE+00
- 10. CALCULATED OFF-SITE DOSE DISTANCE S. B. 2 MI. 5 MI. 10 MI.
A. WB GAMMA DOSE RATE, HREH/HR A1. 2.89E+02 A2. 7.08E+01 A3. 2.73E+01 A4. 1.20E+01 BE WB GAMMA'OSE, MREH B1. 2.18E+03 B2. 5.35E+02 B3. 2.06E+02 B4. 9.03E+01 C. CT GAHMA DOSE RATE, MREM/HR C1. 2.62E+04 C2. 3.00E+03 C3. 8.66E+02 C4. 3.46E+02 D. CT GAHHA DOSE, MREH '. D1. 1.98E+05 D2. 2.26E404 D3. 6.54E+03 D4. 2.61E+03 SECTOR(S) AFFECTED E1. ALL E2. B-K E3. HJK E4. HJK F. ADDITIONAL DATA
- 11. HEASURED OFF-SITE DOSE RATES DISTANCE S.B. MI. Mj.
A. WB GAHHA DOSE RATE, MREH/HR A1. A2. A3. A4. B. CT GAHHA DOSE RATE, HREH/HR B1. B2. B3. B4. C. SECTOR(S) AFFECTED C1. C2. C3. C4. D. ADDITIONAL DATA
- 12. PROTECTION ACTION REC ~ SECTOR(S) HILES A. NONE B-K 10
- HJK 2 5 C. EVACUATION D. KI DISTRIBUTION E. CONTAHINATION CONTROL F. OTHER ESTIHATE OF CONTAMINATED AREA AD IN-PLANT SQ. FT.
B. ON-SITE SQ. MI. C. OFF-SITE SQ. HI.
- 14. ADDITIONAL INFORMATION
~ .
<**>4<<~*~ NUCLEAR PLANT ACCIDENT NOTIFICATION *~*<*****~ DAP REPORT, PAGE 1 OF 2 RECORDER REC. REC.
NAHE TITLE TIHE 05: ~0 DATE LINE
- 1. PLANT COMMUNICATOR NAHE TITLE TEL NO.
.'PLANT NAHE/UNIT 2A. PLANT HESSAGE NO.
- 3. CLASS OF EMERGENCY A. UNUSUAL EVENT B. ALERT C. SITE AREA EMERGENCY X D. GENERAL EMERGENCY E. THIS CLASSIFICATICN DECLARED AT: TIHE DATE
- 4. DESCRIPTION OF EVENT/INITIATING CONDITION
- 5. PROGNOSIS A. STABLE B. ESCALATING C. DE-ESCALATING D. TERHINATING
- 6. PLANT EMERGENCY RESPONSE ACTIONS UNDERWAY A. OFF-SITE ASSISTANCE PREY. REQUESTED: YES NO B. FIRE C. POLICE D. AHBULANCE E. HOSPITAL F. OTHER G. SITE EVACUATION: YES NO LIMITED H. ON-SITE RM TEAHS DISPATCHED: YES NO TIHE I. OFF-SITE RH TEAMS DISPATCHED: YES NO TIME
- 7. RELEASE INFORMATION A POTENTIAL REL.
~ YES NO B. ACTUAL REL. YES NO C. REL. TIME D. AIRBORNE E. WATERBORNE F. SURFACE SPILL G. POTENTIAL RELEASE DURATION HRS
- 8. METEOROLOGICAL DATA A. STABILITY CLASS E BASED ON .44 T(DEG C)/ 50.0 Z(H) OR SIGMA THETA (D)
B. WIND SPEED, HPH 5. 2 C. WIND DIRECTION, DEG, FROH 353. TO 173. D. DOWNWIND SECTOR(S) HJK E. PRECIPITATION RADIOLOGICAL RELEASE DATA A. ESTIMATED MEASURED B. EFF. POINTS 8 HEIGHT GROUND RELEASE C. NOBLE GAS REL. RATE, CI/SEC 5.16E +01 E. AVERAGE ENERGY/DIS., E. HEV 1. 05E-01 E. EQUIV I-,131 REL. RATE, CI/SEC 5. 1 6E-02 F. PARTICULATES CI/SEC 0. 00E~OO
- 10. CALCULATED OFF-SITE DOSE DISTANCE S.B. '
MI. 5 MI. 10 HI. A. WB GAMHA DOSE RATE, HREM/HR A1. 1.67E+02 A2. 4.10E+01 A3. 1.58E+01 A4. 6.92E+00 B. WB GAMMA DOSE, MREM B1. 1.21E+03 B2. 2.97E+02 B3. 1.15E+02 B4. 5.02E+01 C. CT GAMHA DOSE RATE, HREM/HR C1. 1.57E+04 C2. 1.79E+03 C3. 5.18E+02 C4. 2.07E+02 D. CT GAMHA DOSE, MREM D1. 1.14E+05 D2. 1.30E+04 D3. 3.76E+03 D4. 1.50E+03 E. SECTOR(S) AFFECTED E1. ALL E2. B-K E3. HJK E4. HJK F. ADDITIONAL DATA
- 11. HEASURED OFF-SITE DOSE RATES DISTANCE S.B. HI. HI. HI.
'A. WB GAHMA DOSE RATE, MREH/HR A1. A2. AS. A4.
B. CT GAMMA DOSE RATE, HREM/HR B1. B2 ~ B3. B4. C. SECTOR(S) AFFECTED C1. C2. C3. C4. D. ADDITIONAL DATA
- 12. PROTECTION ACTION REC. SECTOR(S) HILES A. NONE B-K 5 10 B. IN-PLACE SHELTERING B-K C. EVACUATION D. KI DISTRIBUTION E. CONTAHINATION CONTROL F. OTHER ESTIHATE OF CONTAHINATED .AREA A. IN-PLANT SQ. FT.
B. ON-SITE SQ. MI. C. OFF-SITE SQ. HI.
- 14. ADDITIONAL INFORMATION
't I
<<*<<*******NUCLEAR PLANT ACCIDENT NOTIFICATION <<*****<<**<< DAP REPORT, PAGE 1 OF 2 RECORDER REC. REC.
NAHE TITLE TIME 0>.: 4> DATE LINE
' PLANT COHMUNICATOR NAME TITLE TEL NO.
PLANT NAHE/UNIT 2A. PLANT HESSAGE NO.
- 3. CLASS OF EMERGENCY A. UNUSUAL EVENT B. ALERT C. SITE AREA EMERGENCY g D. GENERAL EMERGENCY E. THIS CLASSIFICATION DECLARED AT: TIME DATE
- 4. DESCRIPTION OF EVENT/INITIATING CONDITION
- 5. PROGNOSIS A. STABLE B. ESCALATING C. DE-ESCALATING D. TERHINATING
- 6. PLANT EHERGENCY RESPONSE ACTIONS UNDERWAY A. OFF-SITE ASSISTANCE PREY. REQUESTED: YES NO B. FIRE C. POLICE D. AHBULANCE E. HOSPITAL F. OTHER G. SITE EVACUATION: YES NO LIHITED H. ON-SITE RH TEAMS DISPATCHED: YES NO TIME I. OFF-SITE RM TEAHS DISPATCHED: YES NO TIHE
- 7. RELEASE INFORHATION A. POTENTIAL REL. YES NO B. ACTUAL REL. YES NO C. REL. TIME D. AIRBORNE E. WATERBORNE F. SURFACE SPILL G. POTENTIAL RELEASE DURATION HRS
- 8. HETEOROLOGICAL DATA A. STABILITY CLASS E BASED ON 44 T(DEG C)/ 50.0 Z(M) OR SIGMA THETA (D)
B. WIND SPEED, MPH 5. 1 C. WIND DIRECTION, DEG, FROM 352. TO 172. D. DOWNWIND SECTOR(S) HJK E. PRECIPITATION RADIOLOGICAL RELEASE DATA A.- ESTIMATED MEASURED B. EFF. POINTS 8 HEIGHT GROUND RELEASE C. NOBLE GAS REL. RATE, CI/SEC 3. 18E +01 E. AVERAGE ENERGY/DIS ~, E.MEV 1.02E-01 E. EQUIV I-131 REL. RATE, CI/SEC 3.1 8E-02 F. PARTICULATES, CI/SEC 0. 00E+00
- 10. CALCULATED OFF-SITE DOSE DISTANCE S.B. 2 HI. 5 MI ~ 10 MI.
A. WB GAMHA DOSE RATE, HREH/HR A1. 1.02E+02 A2. 2.50E+01 A3. 9.63E+00 A4. 4.22E+00 B. WB GAMMA DOSE, HREH- B1. 7.13E+02 B2. 1.75E+02 B3. 6.74E+01 B4. 2.95E+01 C. CT GAMMA DOSE RATE, MREM/HR C1. 9.87E+03 C2. 1,13E+03 C3. 3.26E+02 C4. 1.30E+02 D. CT GAMMA DOSE, MREH D1. 6.91Et04 D2. 7.90E403 D3. 2.28E+03 D4. 9.12E+02 E. SECTOR(S) AFFECTED E1. ALL E2. B-K E3. HJK E4. HJK F. ADDITIONAL DATA
- 11. HEASURED OFF-SITE DOSE RATES DISTANCE S. B. HI. MI.
A. WB GAHMA DOSE RATE, MREM/HR A1. A2. A3. A4. ~ B. CT GAHMA DOSE RATE, MREH/HR B1. B2. B3. B4. C. SECTOR(S) AFFECTED C1. C2. C3. C4. D. ADDITIONAL DATA
- 12. PROTECTION ACTION REC. SECTOR(S) HILES A. NONE B-K 5 10 B. IN-PLACE SHELTERING B-K C. EVACUATION D. KI DISTRIBUTION E. CONTAHINATION CONTROL F. OTHER
~ ~ ESTIHATE OF CONTAHINATED AREA A. IN-PLANT SQ. FT.
B. ON-,SITE SQ. HI. C. OFF-SITE SQ. HI.
- 14. ADDITIONAL INFORMATION
<~>~~~~*>> NUCLEAR PLANT ACCIDENT NOTIFICATION *>>*<*>>** DAP REPORT, PAGE 1 OF 2 RECORDER REC. REC.
NAME TITLE TIME ~06: DATE LINE
- 1. PLANT COMMUNICATOR NAHE TITLE TEL NO.
PLANT NAHE/UNIT 2A. PLANT MESSAGE NO.
~ CLASS OF EMERGENCY A ~ UNUSUAL EVENT 8, ALERT C SITE AREA EMERGENCY g 0 GENERAL EMERGENCY E. THIS CLASSIFICATION DECLARED AT: TIME DATE
- 4. DESCRIPTION OF EVENT/INITIATING CONDITION
- 5. PROGNOSIS A. STABLE B. ESCALATING C. DE-ESCALATING D. TERHINATING
- 6. PLANT EHERGENCY RESPONSE ACTIONS UNDERWAY A. OFF-SITE ASSISTANCE PREY. REQUESTED: YES NO B. FIRE C. POLICE 0. AMBULANCE E. HOSPITAL F. OTHER G. SITE EVACUATION: YES NO LIHITED H. ON-SITE RH TEAHS DISPATCHED: YES NO TIME
. I. OFF-SITE RM TEAHS DISPATCHED: YES NO TIME
- 7. RELEASE INFORMATION A. 'POTENTIAL REL. YES NO B. ACTUAL REL. YES NO C. REL. TIME
- 0. AIRBORNE E. WATERBORNE F ~ SURFACE SPILL G. POTENTIAL RELEASE DURATION HRS
- 8. METEOROLOGICAL DATA B. WIND SPEED, HPH
- 0. DOWNWIND SECTOR(S)
A. STABILITY CLASS E BASED ON 8 HJK
.44 T(DEG C)/ 50.0 Z(M) OR C. WINO DIRECTION, OEG, FROM 353. TO 173.
E. PRECIPITATION SIGMA THETA (0) RADIOLOGICAL RELEASE DATA f A. STIHATEO MEASURED 8. EFF. POINTS 8 HEIGHT GROUND RELEASE C. NOBLE GAS REL. RATE, CI/SEC 1.95E +01 E. AVERAGE ENERGY/DIS., E.MEV 9. 90E-02 E. EQUIV I-131 REL. RATE, CI/SEC 1. 9 5E-02 F. PARTICULATES, CI/SEC 0. OOE+00
- 10. CALCULATED OFF-SITE DOSE DISTANCE S.B. 2 MI. 5 HI ~ 10 HI ~
A. WB GAHHA DOSE RATE, HREH/HR A1. 5.33E+01 A2. 1.31E+01 A3. 5.04E+00 A4. 2.21E+00 B. WB GAHMA DOSE, MREH 81. 3.60E+02 82. 8.82E+01 83. 3.40E+01 84. 1.49E+01 C. CT GAMMA DOSE RATE, MREH/HR C1. 5.32E+03 C2. 6.09E+02 C3. 1.76E+02 C4. 7.03E+01
- 0. CT GAMHA DOSE, MREH 01. 3.59E+04 D2. 4.11E+03 03. 1.19E+03 04. 4.74E+02 E. SECTOR(S) AFFECTED E1. ALL E2. 8-K E3. HJK E4. HJK F. ADDITIONAL DATA
- 11. MEASURED OFF-SITE DOSE RATES DISTANCE S.B. iiI. HI. 81.
A. WB GAMMA DOSE RATE, HREM/HR A1., A2. A3. A4. B. CT GAMMA DOSE RATE, MREH/HR 81. 82. 83. 84. C. SECTOR(S) AFFECTED C1. C2. C3. C4.
- 0. ADDITIONAL DATA
- 12. PROTECTION ACTION REC. SECTOR(S) MILES A. NONE 8-K 2 5 10 B. IN-PLACE SHELTERING C. EVACUATION D. KI DISTRIBUTION E. CONTAMINATION CONTROL F. OTHER
- 13. EST IHATE OF CONTAMINATED AREA A. IN-PLANT SQ. FT.
B. ON-SITE SQ. MI. C. OFF-SITE SQ. HI.
- 14. ADDITIONAL INFORMATION P
~****~<<**NUCLEAR PLANT ACCIDENT NOTIFICATION ~****44~44 DAP REPORT, PAGE 1 OF 2 RECORDER NAHE TITLE TIHE 06:15 DATE LINE PLANT COMMUNICATOR NAME TITLE TEL NO.
Pl ANT NAHE/UNIT 2A. PLANT HESSAGE NO.
~ CLASS OF EHERGENCY A.~ UNUSUAL EVENT B. ALERT C. SITE AREA EMERGENCY g D. GENERAL EMERGENCY E. THIS CLASSIFICATIDN DECLARED AT: TINE DATE
- 4. DESCRIPTION OF EVENT/INITIATING CONDITION
- 5. PROGNOSIS .
A. STABLE B. ESCALATING C. OE-ESCALATING 0. TERHINATING
- 6. PLANT EMERGENCY RESPONSE ACTIONS UNDERWAY A. OFF-SITE ASSISTANCE PREY. REQUESTED: YES NO B. FIRE C. POLICE D. AHBULANCE E. HOSPITAL F. OTHER G. SITE EVACUATION: YES NO LIHITED H. ON-SITE RH TEAHS DISPATCHED: YES NO TIHE I. OFF-SITE RM TEAMS DISPATCHED: YES NO TINE
- 7. RELEASE INFORMATION A. POTENTIAL REL. YES NO B. ACTUAL REL. YES NO C. REL. TIME
- 0. AIRBORNE E. WATERBORNE F. SURFACE SPILL G. POTENTIAL RELEASE DURATION HRS
- 8. HETEOROLOGICAL DATA A. STABILITY CLASS E BASED ON .44 T(OEG C)/ 50.0 Z(H) OR SIGHA THETA (0)
B. WIND SPEED, HPH 5.5 WIND DIRECTION, OEG, FROH 351. TO 171. D. DOWNWIND SECTOR(S) HJK E. PRECIPITATION
- 4. RADIOLOGICAL RELEASE DATA A. ESTIMATED HEASURED B. EFF. POINTS It HEIGHT GROUND RELEASE C. NOBLE GAS REL. RATE, CI/SEC 1.22E +01 E. AVERAGE ENERGY/DIS., E.HEV 9.61E-02 E ~ EQUIV I-131 REL. RATE, CI/SEC 1.2 2E-02 F. PARTICULATES, CI/SEC 0. OOE+00
- 10. CALCULATED OFF-SITE DOSE DISTANCE S.B. 2 HI. 5 MI. 10 MI.
A. WB GAMMA DOSE RATE, MREM/HR A1. 3.40E+01 A2. 8.34E+00 A3. 3.21E+00 A4. 1.41E+00 B. WB GAMMA DOSE, MREM B1. 2.21E+02 B2. 5.42E+01 B3. 2.09E+01 B4. 9.15E+00 C. CT GAMHA DOSE RATE, MREM/HR C1. 3.50E+03 C2. 4.00E+02 C3. 1.16E+02 C4. 4.62E+01
- 0. CT GAMMA DOSE, MREM 01 ~ 2 27E+04 02 ~ 2 60E+03 03
~ 7 51E+02 04. 3 00E+02 ~ ~
E. SECTOR(S) AFFECTED E1. ALL E2. B-K E3. HJK E4. HJK F. ADDITIONAL DATA
- 11. HEASURED OFF-SITE DOSE RATES DISTANCE S.B. MI NI. NI.
A. WB GAMMA DOSE RATE, MREH/HR A1. A2. A3. A4. B. CT GAMHA DOSE RATE, HREH/HR B1. B2. B3. B4. C. SECTOR(S) AFFECTED C1. C2. C3. C4.
- 0. ADDITIONAL DATA
- 12. PROTECTION ACTION REC. SECTOR(S) HILES A. NONE B-K 2 5 10 B. IN-PLACE SHELTERING C ~ EVACUATION O. KI DISTRIBUTION E. CONTAHINATION CONTROL t
F. OTHER
- 13. ESTIHATE OF CONTAHINATED AREA A. IN-PLANT SQ. FT.
8 ON-SITE
~ SQ. HI.
C. OFF-SITE SQ. MI ~
- 14. ADDITIONAL INFORHATION
~*<<>>~>>> NUCLEAR PLANT ACCIDENT NOTIFICATION wwwwwwwcct DAP REPORT) PAGE 1 OF 2 RECORDER REC. REC.
NAME TITLE TIHE ~QO DATE LINE PLANT COMMUNICATOR NAHE TITLE TEL NO. PLANT NAME/UNIT 2A. PLANT HESSAGE NO.
~ CLASS OF EMERGENCY A. UNUSUAL EVENT ~ B. ALERT C. SITE AREA EMERGENCY X D. GENERAL EMERGENCY E. THIS CLASSIFICATION DECLARED AT: TIME
- 4. DESCRIPTION OF EVENT/INITIATING CONDITION
- 5. PROGNOSIS A. STABLE B. ESCALATING . C. DE-ESCALATING D. TERHINATING
- 6. PLANT EMERGENCY RESPONSE ACTIONS UNDERWAY A OFF-SITE ASSISTANCE PREY. REQUESTED:
~ YES NO B. FIRE C. POLICE D. AHBULANCE E. HOSPITAL F. OTHER . G. SITE EVACUATION: YES NO LIMITED H. ON-SITE RM TEAHS DISPATCHED: YES NO TIHE I. OFF-SITE RH TEAMS DISPATCHED: YES NO TIHE
- 7. RELEASE INFORHATION A. POTENTIAL REL. YES NO B. ACTUAL REL. YES NO C ~ REL. TIME D. AIRBORNE E. WATERBORNE F. SURFACE SPILL G. POTENTIAL RELEASE DURATION HRS
- 8. METEOROLOGICAL DATA A. STABILITY CLASS E BASED ON .50 T(DEG C)/ 50.0 Z(H) OR SIGHA THETA (D)
B. WIND SPEED, HPH 5.6 C. WIND DIRECTION, DEG, FROH 347. TO 167. D. DOWNWIND SECTOR(S) GHJ E. PRECIPITATION RADIOLOGICAL RELEASE DATA A. ESTIHATED MEASURED B. EFF. POINTS 8 HEIGHT GROUND RELEASE C. NOBLE GAS REL. RATE, CI/SEC 7.52E +00 E. AVERAGE ENERGY/DIS., E.MEV 9. 33E-02 E. EQUIV I-131 REL. RATE, CI/SEC 7. 5 2E-03 F. PARTICULATES CI/SEC 0. 00E+00
- 10. CALCULATED OFF-SITE DOSE DISTANCE S. B. 2 HI. 5 MI. 10 HI.
A. WB GAMMA DOSE RATE, MREM/HR A1. 2.00E+01 A2. 4.92E+00 A3. 1.89E+00 A4. 8.30E-01 B. WB GAHMA DOSE, MREH B1. 1.25E+02 B2. 3.07E+01 B3. 1.18E+01 B4. 5.19E+00 C. CT GAMMA DOSE RATE, MREH/HR C1. 2.12E+03 C2. 2.43E+02 C3. 7 01E+01 C4. 2.80E+01
~
D. CT GAHMA DOSE, MREM D1. 1.33E+04 D2. 1.52E+03 D3. 4.38E+02 D4. 1.75E+02 E. SECTOR(S) AFFECTED E1. ALL E2. B-K E3. GHJ E4. GHJ F. ADDITIONAL DATA
- 11. HEASURED OFF-SITE DOSE RATES DISTANCE S. B. MI. MI. MI.
A. WB GAHHA DOSE RATE, HREM/HR A1. A2. A3. A4. B. CT GAMMA DOSE RATE, MREH/HR C. SECTOR(S) AFFECTED D. ADDITIONAL DATA B1. C1. B2. C2. B3. C3. '4 B4 ~
~
- 12. PROTECTION ACTION REC. SECTOR(S) MILES A. NONE B-K 2 5 10 B. IN-PLACE SHELTERING C. EVACUATION D. KI DISTRIBUTION E. CONTAHINATION CONTROL F. OTHER
- 13. ESTIHATE OF CONTAMINATED AREA A. IN-PLANT SQ. FT.
B. ON-SITE SQ. HI. C. OFF-SITE SQ. MI.
- 14. ADDITIONAL INFORHATION
><<<<><<>~ NUCLEAR PLANT ACCIDENT NOTIFICATION *<I**>*~** DAP REPORT, PAGE 1 OF 2 RECORDER REC. REC.
NAHE TITLE TIHE 06: 45 DAT LINE
- 1. PLANT COMMUNICATOR NAME TITLE TEL NO.
PLANT NAME/UNIT 2A. PLANT HESSAGE NO. CLASS OF EMERGENCY A. UNUSUAL EVENT B. ALERT g C. SITE AREA EMERGENCY D. GENERAL EMERGENCY E. THIS CLASSIFICATION OECLAREO AT: TIME DATE
- 4. DESCRIPTION OF EVENT/INITIATING CONDITION
- 5. PROGNOSIS A. STABLE B. ESCALATING C. OE-ESCALATING D. TERHINATING
- 6. PLANT EMERGENCY RESPONSE ACTIONS UNDERWAY A. OFF-SITE ASSISTANCE PREY. REQUESTED: YES NO B. FIRE C. POLICE D. AHBULANCE E. HOSPITAL F. OTHER G. SITE EVACUATION: YES NO LIHITED H. ON-SITE RH TEAMS DISPATCHED: YES NO TIHE I. OFF-SITE RM TEAHS DISPATCHED: YES NO TIHE
- 7. RELEASE INfORMATION A. POTENTIAL REL. YES NO B. ACTUAL REL. YES NO C. REL. TIME 0 ~ AIRBORNE E. WATERBORNE F. SURFACE SPILL G. POTENTIAL RELEASE DURATION HRS
- 8. METEOROLOGICAL DATA A. STABILITY CLASS E BASED ON 50 T(OEG C)/ 50.0 Z(H) OR SIGHA THETA (0)
B. WIND SPEED, HPH 6. 2 C WIND OIRECTION2 DEG2 FROH 347. TO 167.
- 0. DOWNWIND SECTOR(S) GHJ E. PRECIPITATION RADIOLOGICAL RELEASE DATA A. ESTIMATED MEASURED B. EFF. POINTS 5 HEIGHT GROUND RELEASE C. NOBLE GAS REL. RATE, CI/SEC 4. 60E +00 E. AVERAGE ENERGY/DIS., E.MEV 9. 08E-02 E. EQUIV I-131 REL. RATE, CI/SEC 4. 6 OE-03 F. PARTICULATES, CI/SEC 0. OOE+00
- 10. CALCULATED OFF-SITE DOSE DISTANCE S ~ B. 2 HI. 5 HI. 10 HI.
A. WB GAMHA DOSE RATE, HREM/HR A1. 1.08E+01 A2. 2.64E+00 A3. 1.02E+00 A4. 4.45E-01
- 8. WB GAMMA DOSE, HREH 81. 6. 45E+01 82. 1. 58E+01 83 ~ 6. 10E+00 84. 2. 67E+00 C. CT GAMMA DOSE RATE, MREH/HR C1. 1.17E+03 C2. 1.34E+02 C3. 3.87E+01 C4. 1.55E+01
- 0. CT GAMHA DOSE, HREH 01. 7.03E+03 02. 8.04E+02 03. 2.32E+02 04. 9,2SE+01 E. SECTOR(S) AFFECTED E1. ALL E2. 8-K E3. GHJ E4. GHJ F. ADDITIONAL DATA 11 ~ MEASURED OFF-SITE DOSE RATES DISTANCE S. B. HI . MI. MI.
A. WB GAHHA DOSE RATE, MREH/HR A1. A2. A3. A4. B. CT GAMMA DOSE RATE, MREH/HR 81. 82. 83. 84 C. SECTOR(S) AFFECTED C1. C2. C3. C4.
- 0. ADDITIONAL DATA
- 12. PROTECTION ACTION REC. SECTOR(S) MILES A. NONE 8-K 2 5 10 B. IN-PLACE SHELTERING C ~ EVACUATION
- 0. KI DISTRIBUTION E. CONTAHINATION CONTROL F. OTHER 8 ON-SITE
~ 'Q.
- 13. ESTIHATE OF CONTAHINATED AREA A. IN-PLANT FT.
SQ. HI. C. OFF-SITE SQ. HI.
- 14. ADDITIONAL INFORMATION
*>><<<<*~* NUCLEAR PLANT ACCIDENT NOTIFICATION <*~~*~<*~* DAP REPORT, PAGE 1 OF 2 RECORDER REC. REC.
NAME TITLE TIME 07: 00 DATE LINE PLANT COMMUNICATOR NAME TITLE TEL NO. PLANT NAME/UNIT 2A. PLANT MESSAGE NO. CLASS OF EHERGENCY A. UNUSUAL EVENT B. ALERT Q C. SITE AREA EMERGENCY 0. GENERAL EHERGENCY E. THIS CLASSIFICATION DECLARED AT: TIME DATE
- 4. DESCRIPTION OF EVENT/INITIATING CONDITION
- 5. PROGNOSIS A. STABLE B. ESCALATING C. OE-ESCALATING 0. TERMINATING
- 6. PLANT EMERGENCY RESPONSE ACTIONS UNDERWAY A. OFF-SITE ASSISTANCE PREY. REQUES TED: YES NO B. FIRE C. POLICE 0. AHBULANCE E. HOSPITAL F. OTHER G. SITE EVACUATION: YES NO LIMITED H. ON-SITE RM TEAMS DISPATCHED: YES NO TIME I. OFF-SITE RM TEAHS DISPATCHED: YES NO TIHE
- 7. RELEASE 'INFORMATION A. POTENTIAL REL. YES NO B. ACTUAL REL. YES NO C. REL. TIHE D. AIRBORNE E. WATERBORNE F. SURFACE SPILL G. POTENTIAL RELEASE DURATION HRS
- 8. HETEOROLOGICAL DATA A. STABILITY CLASS E BASED ON .22 T(DEG C)/ 50.0 Z(M) OR SIGHA THETA (0)
B. WINO SPEED, HPH 6.2 C~ WIND DIRECTION, OEG, FROH 347. TO 167.
- 0. DOWNWIND SECTOR(S) GHJ E. PRECIPITATION RADIOLOGICAL RELEASE DATA A. ESTIMATED HEASUREO B. EFF. POINTS 8 HEIGHT GROUND RELEASE C. NOBLE GAS REL. RATE, CI/SEC 2. 90E +00 E. AVERAGE ENERGY/DIS., E.MEV 8. 83E-02 E. EQUIV I-131 REL. RATE, CI/SEC 2. 9 OE-03 F. PARTICULATES, CI/SEC O,OOE+00
- 10. CALCULATED OFF-SITE DOSE DISTANCE S. B. 2 MI. 5 MI. 10 HI.
A. WB GAMMA DOSE RATE, MREH/HR Al. 6. 59E+00 A2. 1. 62E+00 A3. 6. 23E-01 A4. 2. 73E-01 B. WB GAHMA DOSE, MREH Bl. 3.'79E+01 B2. 9. 30E+00 B3. 3. 58E+00 B4. 1. 57E+00 C. CT GAMMA DOSE RATE, HREM/HR Cl. 7.38E+02 C2. 8.45E+01 C3. 2.44E+01 C4. 9.75E+00
- 0. CT GAHMA DOSE, MREM 01. 4.24E+03 02. 4.86E+02 03. 1.40E+02 04. 5,61E+01 E. SECTOR(S) AFFECTED El. ALL E2. B-K E3. GHJ E4. GHJ F. ADDITIONAL DATA
- 11. MEASURED OFF-SITE DOSE RATES DISTANCE S.B. MI. HI.
A. WB GAMMA DOSE RATE, MREH/HR Al . A2. A3. A4. B. CT GAMHA DOSE RATE, HREH/HR Bl ~ B2. B3. B4. C. SECTOR(S) AFFECTED Cl . C2. C3. C4.
- 0. ADDITIONAL DATA
- 12. PROTECTION ACTION REC. SECTOR(S) MILES A. NONE B-K 2 5 10 B. IN-PLACE SHELTERING C. EVACUATION
- 0. KI DISTRIBUTION E. CONTAMINATION CONTROL F. OTHER
- 13. ESTIHATE OF CONTAHINATED AREA A. IN-PLANT SQ. FT.
B. ON-SITE SQ. HI. C. OFF-SITE SQ. MI.
- 14. ADDITIONAL INFORMATION
i~<>>>><<* NUCLEAR PLANT ACCIDENT NOTIFICATION ~*>*~***>* DAP REPORT, PAGE 1 OF 2 RECORDER REC. REC. NAME TITLE TIME 07 '> DATE LINE
- 1. PLANT COMMUNICATOR NAME TITLE TEL NO.
PLANT NAME/UNIT 2A. PLANT MESSAGE NO. CLASS OF EMERGENCY A. UNUSUAL EVENT B. ALERT Q C. SITE AREA EMERGENCY D. GENERAL EMERGENCY E. THIS CLASSIFICATION DECLARED AT: TIME DATE
- 4. DESCRIPTION OF EVENT/INITIATING CONDITION
- 5. PROGNOSIS A. STABLE B. ESCALATING C. DE-ESCALATING D. TERMINATING
- 6. PLANT EMERGENCY RESPONSE ACTIONS UNDERWAY A. OFF-SITE ASSISTANCE PREY. REQUES TED: YES NO B. FIRE C. POLICE D. AMBULANCE E. HOSPITAL F. OTHER G. SITE EVACUATION: YES NO LIMITED H. ON-SITE RM TEAMS DISPATCHED: YES NO TIME I. OFF-SITE RM TEAMS DISPATCHED: YES NO TIME
- 7. RELEASE INFORMATION A. POTENTIAL REL. YES NO B. ACTUAL REL. YES NO C. REL. TIME D. AIRBORNE E. WATERBORNE F. SURFACE SPILL G. POTENTIAL RELEASE DURATION HRS
- 8. METEOROLOGICAL DATA A. STABILITY CLASS E BASED ON 28 T(DEG C)/ 50.0 Z(M) OR SIGMA THETA (D)
B. WIND SPEED~ MPH 6. 0 C. WIND DIRECTION, DEG, FROM 347. TO 167. D. DOWNWIND SECTOR(S) GHJ, E. PRECIPITATION RADIOLOGICAL RELEASE DATA A. ESTIMATED MEASURED B. EFF. POINTS 8 HEIGHT GROUND RELEASE C. NOBLE GAS REL. RATE, CI/SEC 1.81E +00 E. AVERAGE ENERGY/DIS., E.MEV 8. 60E-02 E. EQUIV I-131 REL. RATE, CI/SEC 1. 8 1E-03 F. PARTICULATES, CI/SEC 0. 00E+00
- 10. CALCULATED OFF-SITE DOSE DISTANCE S.B. 2 MI. 5 MI. 10 MI.
A. WB GAMMA DOSE RATE, MREM/HR Al. 4.14E+00 A2. 1.02E+00 A3. 3.91E-01 A4. 1.71E"01 B. WB GAMMA DOSE, MREM Bl. 2.28E+01 B2. 5.58E+00 B3. 2.15E400 B4. 9.42E-01 C. CT GAMMA DOSE RATE, MREM/HR Cl. 4.76E+02 C2. 5.44E+01 C3. 1.57E+01 C4. 6.28&00 D. CT GAMMA DOSE, MREM Dl. 2.62E+03 D2. 2.99E+02 D3. 8.64E+01 D4. 3.45&01 E. SECTOR(S) AFFECTED El. ALL f2. B-K f3. GHJ E4. GHJ F. ADDITIONAL DATA
- 11. MEASURED OFF-SITE DOSE RATES DISTANCE S.B. MI. MI . HI.
A. WB GAMMA DOSE RATE, MREM/HR Al. A2. A3. A4. B. CT GAMMA DOSE RATE, MREM/HR Bl . B2. B3. B4. C. SECTOR(S) AFFECTED Cl . C2. C3. C4. D. ADDITIONAL DATA
- 12. PROTECTION ACTION REC. SECTOR(S) MILES A. NONE B-K 2 5 10 B. IN-PLACE SHELTERING C.'VACUATION D. KI DISTRIBUTION E. CONTAMINATION CONTROL F. OTHER
- 13. ESTIMATE OF CONTAMINATED AREA Aji'N-PLANT SQ. FT.
B. ON-SITE SQ. MI. C. OFF-SITE SQ. MI.
- 14. 'ADDITIONAL INFORMATION
'><~~w~~~<~ NUCLEAR PLANT ACCIDENT NOTIFICATION ~~>>**~**~ DAP REPORT, PAGE 1 OF 2 RECORDER REC. REC. NAME ~ TITLE TIME 07: 30 DATE PLANT COHMUNICATOR NAME TITLE TEL NO.
~ PLANT NAME/UNIT 2A. PLANT MESSAGE NO.
- 3. CLASS OF EHERGENCY A. UNUSUAL EVENT g B. ALERT C. SITE AREA EHERGENCY D. GENERAL EMERGENCY E. THIS CLASSIFICATION DECLARED AT: TIME DATE
- 4. DESCRIPTION OF EVENT/INITIATING CONDITION
- 5. PROGNOSIS A. STABLE B. ESCALATING C. DE-ESCALATING D. TERHINATING
- 6. PLANT EHERGENCY RESPONSE ACTIONS UNDERWAY A. OFF-SITE ASSISTANCE PREY. REQUESTED: YES NO B. FIRE C. POLICE D. AHBULANCE E. HOSPITAL F. OTHER G. SITE EVACUATION: YES NO LIHITED H. ON-SITE RH TEAHS DISPATCHED'ES NO TIHE I. OFF-SITE RM TEAHS DISPATCHED: YES NO TIHE,
- 7. RELEASE INFORMATION A. POTENTIAL REL. YES NO B. ACTUAL REL. YES NO C. REL. TIME D. AIRBORNE E. WATERBORNE F. SURFACE SPILL G. POTENTIAL RELEASE DURATION HRS
- 8. HETEOROLOGICAL DATA A. STABILITY CLASS E BASED ON .06 T(DEG C)/ 50.0 Z(M) OR SIGHA THETA (0)
B. WIND SPEED, HPH 5. 9 C. WIND DIRECTION, DEG, FROH 3 '7. TO 167. D. DOWNWIND SECTOR(S) GHJ E. PRECIPITATION RADIOLOGICAL RELEASE DATA A. ESTIMATED HEASURED B. EFF. POINTS 8 HEIGHT GROUND RELEASE
~
C. NOBLE GAS REL. RATE, CI/SEC 1. 08E +00 E. AVERAGE ENERGY/DIS., E.HEV 8. 18E-02 E. EQUIV I-131 REL. RATE, CI/SEC 1. 0 8E-03 F. PARTICULATES CI/SEC 0. OOE+00
- 10. CALCULATED OFF-SITE DOSE DISTANCE S.B. 2 HI. 5 MI. 10 MI.
A. WB GAMMA DOSE RATE, MREH/HR Al. 2.39E+00 A2. 5.86E-01 A3. 2.26E-01 A4. 9,90E-02 B. WB GAMHA DOSE, HREH Bl. 1.25E+01 B2. 3.08E+00 B3. 1.19E+00 B4. 5,20E-01 C. CT GAMMA DOSE RATE, MREH/HR Cl. 2.89E+02 C2. 3. 31E+01 C3. 9.54E+00 C4. 3,81E+00 D. CT GAMMA DOSE, MREH Dl. 1.52E+03 D2. 1.74E+02 D3. 5.01E+01 04. 2.00E+01 E. SECTOR(S) AFFECTED El. ALL E2. B-K E3. GHJ E4. GHJ F. ADDITIONAL DATA
- 11. HEASURED OFF-SITE DOSE RATES DISTANCE S.B. HI . MI. MI.
A ~ WB GAHHA DOSE RATE) HREM/HR Al . A2. A3. A4. B. CT GAHHA DOSE RATE, MREH/HR Bl . B2. B3 ~ B4. C. SECTOR(S) AFFECTED Cl. C2. C3. C4.
- 0. ADDITIONAL DATA
- 12. PROTECTION ACTION REC. SECTOR(S) HILES A. NONE B-K 2 5 10 B. IN-Pl ACE SHELTERING C. EVACUATION D. KI DISTRIBUTION E. CONTAMINATION CONTROL F. OTHER ESTIMATE OF CONTAMINATED AREA A. IN-PLANT SQ. FT.
B. ON-SITE SQ. HI. C. OFF-SITE SQ. MI.
- 14. ADDITIONAL INFORMATION
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE VIII. D. METEOROLOGICAL
SUMMARY
The meteorlogical conditions are standard for early morning inwi April which the exception of wind directionwith weather forecast predict a low pressure system approaching possible showers in the late afternoon. 10m WIND TIME DIRECTION(mph) DIRECTION DT STABILITY CLASS PREC. 0100 5.2 324 0.7 NONE 0115 5.1 325 1.5 NONE 0130 5.1 328 1.4 NONE 0145 5.0 338 1.9 NONE 0200 5.0 338 2.0 NONE 0215 5.0 338 1.9 NONE 0230 5.1 328 1.4 NONE 0245 5.1 325 1 ~ 5 NONE 0300 5.2 324 0.7 0315 5.2 330 0.7 NONE 0330 5.2 330 0.7 NONE 0345 5.3 346 0.7 NONE 0400 5.5 351 0.7 NONE 0415 5.5 351 0.7 NONE 0430 5.5 351 0.7 NONE 0445 5.5 351 0.8 iVONE 0500 5.2 352 0.9 NONE 051S 5.2 353 0.8 NONE 0530 5.1 352 0.8 NONE 0545 5.8 353 0.8 NONE 0600 5.5 351 0.8 NONE 0615 5.6 347 0.9 NON" 0630 6.2 347 0 ' NOiVE 0645 6.2 347 0.4 NONE 0700 6.0 347 0.5 ViOVi" 0715 6.0 350 0.6 ViOViE 0730 5.9 347 0.6 NOiVE 0745 5.9 347 0.6 NONE 0800 5.9 335 -O.l NONE 0815 6.5 340 -0.2 NONE 0830 7.6 340 -0.1 NONE 0845 7.6 340 -0.1 NONE 0900 7.7 340 -0.3 NONE 0915 8.0 340 -0.4 NONE 0930 8.6 -0.4 NONE 0945 8.6 350 -0.5 ViON = 1000 8.4 350 -0.5 NONE ERE-90 8D-2
DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE VIII. E. RMS DATA Radiation monitor data displayed by the Eberline RMS terminal will be driven by the simulator computer in accordance with simulated plant parameters during the exercise. The attached sheets however, are reasonable facsimiles of the RMS radiation monitor channel displays at the times shown on each sheet. These are provided solely for use in the event of simulator or simulated RMS data display failure during the exercise. ERE-90 SE-1
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pl Ol II <<Lr I lr4I III ~ I) rlflC arr a r 'I r 'IVle OAII VV"I
0133 ~TATllg . AQR-AA PW 298) Unit 2 Elf)uthta t A+4tent nnTn A? 5 Q I R R IS AIIIP Iil I 925&3 2.33E-BQ7 uCI 925-95 2.33E-997 uCI/CC 925-97 2.33E-997 u CI/cc 4185-It(5 2.33h.-ldltl/ ul'I/cc Iieet J C'I te U ~ J JlI ee ee ~ I On At ll OQV~ 4ol II I V~R -a>> ear-reS it r I /rr 928-92 3.9QE-BQS uCl/cc 927-Qf 3.QQE+999 uCI/CC 927 "92 3.99E-QQB uCl/cc
~ e % 80 eeee ee QC0 OJ t ( I'C ROID ul I et T,ue elec te ~ AU W a na ~ ~ r Oil ti < '+t tin earJ el . ne 'ue ~
OO'.I II I i Ii Uc tee I BZB -l 9 ) . 92E+99 j CFH 929 "95 8.83E-993 uCI/CC ItlÃJ-lf/ /.21L-Ndl ul'I/cc II2~-ibad 7.8~E-993 uilrcc n~o
~ ot H in& ~ ~ ~ ~
ac v ee&If. J.nnn Parcaltt ct hl tt alarIa 2 9 I!IIit ApR-f}P %to tIle. MnrmIIl l hr2tti An: $ li I AI2P 4 PAQV T. I )P P%t ~~ ~weeeeW
~ . OI. o OI 0 hAC')hht I I Ieetl I I Il Ill eel ~ V r VVUe Wl U'A 0I I lt gi it@I III ~ ~
Ii hhE)AA<
~ VVC VVUe
sTATIIQ . A7R-AI'1 PIP 29BI Un 1 t 2 Eff Iuante 0140 L4Q AJ n CITA A>C-At R R t F-AAP rrrt 825 W3 2. 3 3E" 987 uct I 825-95 2. 3 3E-887 uC1/cc 925-97 2. 3 3E-987 u C1/cc td20 -td'8 C. 'd 3t. ldld/ u C1/cc h~C Qr 8
~ h eIr ~we 4 ~ lJe re hh r Irwin IWv e evr rr A?R -A1 0 AAF-AQR>>t 1/r r 926 -82 3. QQE" QQB u C 1/cc 827-QI 3.99E+999 uCt/cc 927-92 3.99E-996 uC1/cc OCb %J I e' C, QI 1/ cc hh re Lle IJ Stl' hv ~ ~
hh ee MJ 4 uC e/cc neo na nor nn3 ee I I e'CC 82B -I 9 I . 82E+88 I CFM 929 "95 6.63E-983 uCt/cc td'CJ-tdl I. Chh.-tdtdd ut't/cc 929-iH 7.BiE-993 uitxcc Qvv rn nbb ~ vs ~ ~ bc c.~nnn re ex<
~ ~~
Pat cent uf htlth alarm ) 8 I!Iti t APE-W'tyt>>w.'nrmp) I r.r.atinn: Pl. I my 4 PARV r y ~ era.v ~
~ .vvaaZ 4aaeeeeeaa Vvr pt..i Pe(Me e otrile e ~ eee .~ evr recqnnt vv4 v0l U; t. at reeve r1/Ql eee .~ l r r.r.f..reh 1
vVC~ vve'
0145 iTATI.lc' APR-IM PMP 298] Unit 2 Eff Iuentx rwnv nRTR P?i-rit e P tr-ri. ill l 825-93 2.33E-BQ7 UCI 825-85 NOT RVRILRBLE 925 "97 2.33E-887 uCl/cc QC5 k8 2. 3 ZC,-MRV Ul 't /CC Vt l4 tV tin tl vtl <<At 4JI Qvt hh t h<<I It I
~ ~ ~ ~ ~ II A?R P1 0 PK PAR )rl/,.
82BW2 3.98E-QQB u Cs/cc l. 927-91 3. QQE+898 UC)/CC 827-82 3.8QE-QQB uCt/CC OC 4 tCJ Lll 'I /'IX htI tl hv Vt 4. 09 QQl lt I<< I P I 4 92R <<QR o 33E mal> rgl l tcc I I 82S-IQ j.92E+88J CFH i l l 821-95 5.38E-QQt UC>/CC ldll'5 6/ 5.8uh.-Wd] UL:l/CC WC5 C5 3 4 5C. OQZj UCl/CC nag 4A <n T oar p& ~ v <<weJnnn vWvt Parcent nf hl h alarm ) 9 Ilni t APR-AP St~tuet hbr eel I rtra t i nn: $ l I ann 4 PORV TI' <<<< ~ .vv<<<<<< .vv<< 0'l<<<<0 Ol v<<<<t 0 MCgmml I tl VI I t tt'Vt ftl ~ Vt VV'to 'W'I U t 0I ltlat v <<<<
'III~I l NICItVII<<4 mls welt 'I le I ~IIVAJ I I't Pf I ~ ~
0 RT8TIE : O'A-A7 PAP 298$ Unit 2 Dfluantx 0146 r~u qnvq
'>1.-81 R A1F-AQP )il 1 925-93 2.33E-997 uC1 92S~ NOT RVRILRBLE ~~ "Z."SEC.~
925~ 2.33E-997 uC1 ul;1/cc jcc 9"~~ iQ 4..33C'994 Wt
%+1 tltI imari $ PR-91 0 AAF'. AQA iaaf 1 r'r r 926&2 3.99E-QQB 927-Qi 3.9QEt 999 uC1 / cc u C1/cc 927~ 3.99E-QQB u Ci/cc 'QcB~ i.23K+QQQ trC;i~'ww A 8P ~Ah QP ~ e QhQ 23~~ ccc I
928-19 I.92E+991 CFH I 929~ B.BBE-QQI uC1/cc
&W~ '5;SbL-bled] uL:1/cc I
le&-QB b. 57K-9&1 LICl / cc I 3 f9 t ov oK+QQQ 'Canto Par@ant of h1 h alara ) 9 I%i t $ %-FP Ststii+'orse], I or.s t i on. Sfi I oon 4 Pl'iRV Tr ae a. ~we 01.+a 4 Q1 esge g 00$ )001 ge gL ol came i Aocg hl I<
0 sTATIIQ . I')P9-A7 2QB] Un 1 t 2 Eff luente 0150 rLIAQ rIATA A?5-A1 R R 1 F-'PQ? nl 1 925 "93 2.33E-Q97 uC1 925-95 2.33E-Q97 u CI/CC 925 "Qi~ 2.33E-Q97 3h-1W'i'AP u Ct icc 1d'lh -M 2.'i ul;1rcc hht
~ IC J oh I4 4 hJ Jl CO ~
OO ~ ~ I hh 44t ~ ool IO i II A?II-AI 0 AAF-AAR iil ~r r 1 928-92 3.99E-QQB uCI/cc 927-91 3.QQE+QQQ uC1/CC 927-92 3.9QE-QQB uC1r'CC QC 4 ltd 41 4 T'%Std Ul I olol Il h't hhh 8'ul'I 44 V 4C ~ O 4Il too C le 4%I 4
~ ~ I I lol BOO 04 1 4; O'J M~I ~ ICi I'Lc 92B-IQ I.92E+QQj CFN 929-95 1.94E+QQQ uC1rcc ldCV-vt 1 ~ Idea.++did ul'1rcc Id 'B-Q'0 1. ld+E'tldld9 ul 1J cc I
noo In ~ ooe Jnnn r [le 1 i Percent of h1 h alarm ) 9 IInl t AiA-A7 Status. 'Hinh A)arm If.rgt1nn: I'RI 0 V~nt ltnrk I T>> I a g yV ~
~ ooeeae yWllmaa vms uoO 01.ss ~
4 01 +oooo I Iol l I C ~C A VVI 001 Ikl Iti ~ VO 00C VV I Uo. IIC'IIII I I'II clo 01+oswo
~
ll ~ 00CJ000 VVI>>'VV
c:TATS lc' 979-I'.17 PHP 29Bj UnSt 2 EFF)uentx 0200 i WAN hDTA A? 'S -A1 R R AF PA? nl 1 925 "93 2.33E-997 uCS 925-95 2.33E-897 uCS/cc 925-97 C. $ Ãh-SdSd/ u1'1/cc I Pl II hP) ~ MJ I%I 1I el el I J Jl
~ ~ QV'1 I 1 II I~
A?R-AS R Pnr-agy Sil 1/ir 92B -92 3. QQE-QQB u CS/cc 927 "9$ 3.99E+GQQ uC1/cc 927-82 3.99E-QQB u CS/cc SIC 4 J OC'%OVAL ul 'if \'le hei Pl W4 V SIP C'P hh h J ~ J We'I Q4Q
~
ii C I /cf OhR Oa 5orJ.Qo9 r II i (lele 82B-}8 S.82E+QQS CFH 929-95 J.93E+QQQ u CS/cc Sd'M -Sd/ S . 5 HL+SdSdSd u1'1/cc k)2 5 95 ) 5 3EtVWld UL) J CC h~o in
~ ee v a~hrznnn ~ e ee ~ eeee ee re Irii ~ ~
Percent aF hSyh alarm > 9 l,lns t I',P9-lA cits tun.'hrmnl nrntsnn: ci.(RF Vmt cltRrk I Te sn.a
~
f 1/V ~
~
C 1
~ ~
a vO ~ (r.v'1 I Vg/ L..eVWr I le leaei IIII l ~ h
~
Ve VVI Vvv I hhc'Jhhh U . l
~ ~ P'+PI 1
Ie 1 'iI PIP ~ ~
'?
Ie ~ VVI 'VI nhCJhh?
'ATllq .'P9-A7 PIIP 298$ Unit 2 Eff luents 0215 gLlg Q h CITQ A7l A1 R ?7F AA? nl t 925-93 2.32E-997 uCI 925-95 2.32E-Q97 uCIrcc 925-97 2.32E-Q97 uCtrcc Id85-tN C. ZCL-IdIfl ul'I r cc hhC WC 4
~ ~ %I ll J~ ~
h II Sar I %W ~ hhlI ht \ II
~
I ~ APR-AI 0 AAF-PAR ssC s rr 3.9QE-QQS uCIrcc, i'28-92 Q27-9$ 3. QQE+QQQ uCIrcr. 927-92 3.QQE-QQB uCIrcc IbC 0 Stg 4~2 $ C,YROI $ MI hh h h'1 I II ~ I hh ~ I)LL'll I l Isle
~ ~
WC V NC L ~ C Jla I WCI J n~o no 0 1C'af~lm $ II I i I'Sr 92B-$ 9 $ .92E+89$ CFH 929-95 $ .3QEtQ9$ uCIrcc Id'Z5-Idà $ .8Idh.+Idtdl uI'Ircc Rich RID j 3 LIE'tQQI j UL1/ CC hhO aoa o in ar was h hr e aa ~nhn
~ eraoao I C, li Per cent nf high alarm > 9 itn tuw.
l.lnI t Tt ~e.s I fP%r ~
~
F09-)0 d Is I l VWo ~ Hw tw1 I i), ICtlltl loVW
~ ee 4l ~ ~
m V<VVI I rlrlfirlrlrl VVV U'.;4 I ll Pll I: 4I r.rP t I nn. S,lRF Vent Ntgrk III ~ l ~ h COC'imh< 4e VVl 'VI
0 '~TATll< . (PAL-Afl PHP 29BS Un 1 t 2 EFF lucent s 0230 I 4lohl nPTo Pr~S Qt g 7 QP QQQ ill 1 925-83 2.39E-Q97 uC1 925-95 2.3GE-997 u C1/cr. 825 "87 2.38E-QQ7 uC1/CC UZ5 -LH 2. S ldh-ldfdf ul.'1/cc hhc' UC N Ih li hht hhh I t I U U 'UUI UUU
~ ~ I A>R -P1 9 PPF-PPR ill I /r r 92S-92 3.99E-MB uC1/cc I 827-9t 3.88E+QQQ uCl/cc 827-92 3.98E-QQB u Cl /cc A&
OCD RfJ W DC tee l
~
MC I /1 'Lo riIll hh II hv NJ4 U Ul 'f hl
~
J lv I hh
~
UU l ..VI
~ Iv ~
l Boo 04 g 3Etre t ~ (NA 92B-t9 Q.QQEt999 CFtt Ilail 829-85 2. QGEtBQ u Cl /cc ldÃ9 ~/ 1 ldldLtldld 1 uL'1/CC 025 C ~ QGEtQQ k u C. l cc / noo aOD v lnw
~ ~ ~
cc nnt i %a I C'lt Percent aF hl b alarm > 8 l.lni t WS-A1 %tlat tnr. Norma.) l hrntihn'. I!ni t Vi.nt t .~.v k.v 4 v 01+a al 01 vaaI 1I ~ 'ZCC hhf Ue,v4 bl vaaI '9 MC l VI hh I Te f l/U ~o IJ%t Ltk fJ%JI ~ ~ ~ I lIUI IN ~ I VI VVk I l INII
~ I I I'UI NI ~ I ~ VV I
CTQTI!9 . A,"6-AA PHP 29Bj Unit 2 Eff luetlts 0245
> 'UtOM h ATA A? 1 <<A1 R 7 AF-AA? Ut t 925 "93 2.3QE" 997 uC1 925-95 2. 3 QE-997 u C1/cc 925-97 2.39E"997 u C1/cc.
PRO -ldll 2. 3 ML-ldld7 ul'1/cc Ah c n 4 nnw I nnn wr IV V W4 %IV W 4 H
~
e 1 ~ I S A? R -Al R AAF-AAR 1tl tetr ~ 92B "92 3. 9QE-QQB UC1/cc 927 -91 3. QQE+GQQ u C1/cc 927-92 5.!ATE-993 u C1/cc QCO QA 4 ~ 4 JC,'Ptl&'J MC I J'C nh h W ss ~ nn
%LV" '0 s ~ ~%
s C'I ~ aveI V le I /r I lo neo no > zrinn t ur't (cc 928>>19 Q.GQE+QQQ CFtt 929-95 J.BQEtGQI uC1/cc Mcb-N/ 1. SML+tdld) Ut'1/CC to25 93 t .'oQK1'QUt t U t 1/ cc
'V nneinnn noo %44 t0 ~
n n QQh OWQ ~ r crt
% ~
Percent of htgh alarm > 9 I!ni t APS-A) Stptttw: Mnrmtt.l nratinn:,I!ni t Vr.tl t I T,. s jyv m ns
~ ~
t . S oui S a ~ Ol. tlat S 1 0)J\ll
~ ~ ~
IN ~ l t
~ '7OC I Vl I
hht VV I U'. II ~ t Qll Ot,
~ tl'4l Ne n~
lg OCC hht l V4 VV 4
iTRTlg . nag-nA PHP ZQB1 Un >t 2 EFF luants 0252 CllAH ~ na~ AP'l-Af R ? QF'-ÃL" <<1 1 825 "83 2.39E-Q97 uC1 925-95 2. 3 QE" 987 uCt/CC 925 &7 2. 3 QE-997 vent/CC WW kP! 2:3 idt,-M'/ u1'1 /CC Ilh C4 SICa
~ ~
6Nl ~ r rl hnh
~
I I f I 1%CIA
~
lr nI
~ ~ ~
Pyt:-P1 ~ anr-mP <<I 1/rr 928-92 7.17&981 uCs/cc 927-91 3.98E+QQQ u C1/CC 927-92 3.99E-QQB u'C /cc 1 OC O O'J 1IC %MOD 4 4'I l,'% nhh NIL4 NII nr 4 ~ ~ rl tw
~ nn I I I llNI I 41 ~
D II Vlo nba no 1 7C'ann 1 QZB-18 Q.QQE~QQQ CFtt 929-85 1.B4E+QQ1 uC1/cc lfz5 Id/ 1.'u 4hPwd1 u1'1/cc R72J-QB ! .BALT'801 vt 1/cc nho cn% &0
~
nnr innn n 4tNII ~ %AH r&Ine ~ ~ I Percent oF btgh alarm 1 8 I!ni t AP5-91 Sty t11w: Mhrmall l Oratibn: I!ni t Vmt r r L.r kr era 4 '? OC'C'hl I f~e ~Ilk
~ ~ ~ ~
b1.rr 4 I 'I VI \
~
b1 rhea ~ I I ~ ill NI ~ ~
?OC'hf l I VI< VV@ U' bl I I'tgll IIIIll IN ~ ~ I ~ I VI VVJ
STATIS . ÃS-AA PHP 298 I Un I t 2 Eff )uantx 0253 Cwgl IJ Q RTR A?5-At R 7AF-.AA? III I 825-83 2.39E-987 uC1 925-85 NOT RVRILRSLE 925~ 2.39E-887 uCt/CC tdZ5-M '2.3tda.-tdld/ ut't /CC hh C' h J Sl I I l NI SWIB UI I I
~
r rII A?R&1 0 AAF AAR I>l I I'r r 92B-Q2 j.4BE+982 uCt r'CC 827-81 3. QQEIQQQ u C1F cc 827-92 3.88E-QQB uCticc CIC 4 'ClJ I JRTOSJ III I P loL' hhh h I f Cr' hh I Ua S eaa I/ 44 02 R 124 2 l 5E+1291 >>I
~
tI'II 928-]8 8.89E+899 CFH 829-85 1.83EtQQt uCtxcc ldll -M/ l.ttdt,t'tdtd] ut'I/cc IR29 RJ L . 4 3KM'I uCI u c'c rgo I9 n nn~iann Parcant af ht h alarm > 9 Igni t Ãc-At Stat>>c1 Hhrea 1 I hI .~ t i r,n.t I ln i t Vw t I
~ f~
Te er.no
~
k.s IP% hl
~ ~
ba mere l~ ~ OI rl Qtmra I I I VI l I I I@I III ~
~ ~
l I?Oe'ht I
~ Vl VVl U:."I ~ ~ I 4II 0 I
I I I 41 III ~
< OC'C mh!
I ~ I V4 VV l
<TAT)l< . ):g%-)')il- PMP 28B) Un) t 2 EFF)uantz 0300 l LjAN QATA n~i-i) )) ~aF'-iris'25 rrl 1 W3 2. 3 QE-987 uC) Q25 "95 2.3BE"997 u C1/cc 925-97 2.39E-997 u C1/cc, Lf20 -M 2. 3 Uh:-MLf/ uL'1/cc ass c' p) ~ a as sl pill sl Sa lair asked Ial I I
~ ~ I ~ II n"S-a1,~ Pnr-ning >>1 1/ot 928&2 2.55E+BQ) 927-91 3. QQD 989 uC1/cc 927-82 3.9QE" BBB u C) /cc J arC 4 tlat Ir 4C,C'OW J Mr I l L'4 nsl SI D ss ra ctrl asas ~ nn ~
V4lss i+4
~ ss ~ ~
M no o w'bR nbrinnr
'I ~ ~ I r r I's S%
82B -) 8 Q. GGE+898 CFH 923 "95 1 .7 BEt99) u C1/cc Lf~5 -hf/ ) ./h)'+)l))d) u)'1/cc 825 )./bC11Nr nbo
~ sa a rnas aIn e.nnr>nnn ~ as ass ~ asasas Par cant af h)ah alarm ) 8 I!ni t INC-A) Stratum.l Not mP ) I nrptinn. ),lni t Vent I T... I. s i Ol ~ I ~ VI s ~
61 Ill'QI III~ r I ~ ~OC nnr I Vle VV J V'4 I II I 01 I shall III ~
< CCC nnr I ~ I Vl VV l
lucent %TATI lg ~ APC,- fig 288i Un t t 2 Eff z 0315 Ctla N nnTn res-rii a res'-iris'25-93 ill 1
- 2. 3 QE" 897 uC1 925-95 2.3QE-Q97 925 "87 2.3QE-Q97 3'-IN'NP uC1/cr uCt/cc Lf/5 W5 2. v t.'1/cr hhC' Vle J ~
h al
~ ~ ~ 'e I < ~
4I ~
~ hhee Wrl IIQ J '4I I ~I P~P-Pt ~ Par-egg II l I /nn 928-92 4.27Et QQi uCS/cr 927 "Qi 3. QQEt888 uC1/cc 927-92 8.4BE-Q82 uCt/cc )
liltQ Std C 32ETRQi Vl 1/1 ~ hh Q6V II h'+ ak L ~ JaeVI II eII hh I ~ W4 ~ II I 4'VI 82a Qo 2 O 0C'<l1lh 1 g Cl I'cc 828-iQ Togae Q.QQEt998 CFH Q29-95 i . 7QEtQQ i u C1/cc lN d -Lfi')C
/idL+tAd i u 1;1/cc O 'IM l 7 ldET LN'l UC,)/cc neoe asee el n een ee nnrinnn ae aeee ~ aeae ae re'w Parc111t of h1gh alarm > 8 59 l)ni t OPS-f11 Rtg t>ls. glares) I nrll t i nn 1 l/n i t Vl.n t T....
I ~ W Hk I . S baal a I~ 01, I S
~ III'II 01 ~ ~ ~
a ~ i w AA1
~OC vva U;. 4 01 IIIyII IIIwl III~ ~
O I ~ OCC'AI evC vva
AW-AA luentz 0319 wTATI!9 . 2BBj Un 1t 2 EFF t LtAN AATA A?5 A1 A 7AF AR?. 925-93 2.39E-Q97 VC1 Q25-95 2. 3 QE" 987 Wdr'HP u C1icc 925-87 2.3QE-Q97 u C1/cc ldÃ5 -N 2. 3 ldL u\;1/cc n>> c' rl I os ~
~ ~ >> 's P I Iln os I I lel OSQJ n plrI ~ ~ ~
P? R -A1 '4 AAF-PAR t t f' .s' t 928 "Q2 1.53E+992 uC1/cc 927-81 3.QQE+QQQ uC1/cc 927-82 8.77E-QB2 u C1F cc SS4 LfJ $ 4 7 E'T CHS 1 Ml>>l Jl'4 pssl rl n>> rl >>p Pirl I .. s>> r WV Wf s 4r vs 00s 4 I>> ~I r'o
~
4 044 <<04 2 4 7E~AA 1 II I I Isn S 82B-JB B.BBEw898 CFH 929 -95 I.B7EtQQ) VC1/cc ltft!5 ltf/ ) .b.rh.t'ldld1 ul'1/CC Qi& 99 I . 4 7 E1"QB ) v C. 1 I c c n43 s
~
nnt."~nnn tl n~ o Oo>>o<< I I C'as Percent aF h1 h alarm > 8 Igni t l)P5"AI Stptpw. Nerve) I nrptinn: ljni t Vt.nt l Tee<<>> ~ L>>O>> <<>>>>O I g 1rlr ~ SrV rlk Plko I ~ 41ess4
~
4)>>>><<o 'TtlC 401 rr>>rs l tous ns ~ lo I vl vvo 1 Ueoslo
~
O'I>>>><<o~ '?I ~ XC sr'ys Psst sss >vs 441 vvo
<TATI I< ~ ~-AQ PMP 2QBI Un tt 2 EFF luents 0330 CLIAh) QATA A? < A1 R 7 PF'-AA? >tl 1 925 -83 2. QE-QQ7 uC1 3 825-95 2.38E-QQ7 u CI/cc 925-97 2. 3 QE-987 u C1/cc IdÃ'0 -W 2. SMk.-idid/ uL;I/cc 4C J t4n 4h rhr
~
4441 hhh
~
444 wt I C I
~ ~ ~
A?R-ll1 > ?! F-PLURI.I lti 1/r r 82B "92 3.9QE-QQB u C1/cc 927-9J 3.BGE>999 u CI/cc 927-82 4.BQE-982 u CI/Cc SC 0 ITJ 4 ~ 0Ll'WlJ / MCI/wk hA A V h'%C
~I ! I%r hP) ~
C ~ I lA \444
~
uh ~ t% I P leC AVO AO 7 RE+0+ 1 IIV t (AI% 928-IB Q.BBDBQB CFH 929 "95 I.B IKt QQI uC1/cc WZJ-If/ I II It,+1did] ut;1/cc 82i -99 i . a ETQQ I u C1/ cc nAo I~ n n nneannn OM
%% %% %% %%% ~
Per can t cF hi p h al arm ) 8 I!ni t AP"5-0 % to tus: Nr.rma 1 I nrem t i nn: I in i t Vm t I T. . ~ k. W sICI s b1. ) 61 I II'W t I II QI tll ~ I ~ 7nC 1 hh1 U'. k 01 I tt%III ttWI III
~ < hC'C't'.t(
I VI VV I gyes ~ yW I ~ I Vl VVC ~ C~ ~
%TATI Ig . fig%,-IW PIP 298) Un1t 2 EFF )vent t: 0345 IvLIAQ n ATA A? kt -9 1 R 7 QF- PA? >>1 t 925 "93 2.39E-Q97 uCt 925-95 2.3QE-997 uCt/CC 925-97 2.3QE-997 uCticc N 4. 3 IdL-tdlf/ ut t/cc htt C' le h rth St hhP ~ hhh rvr tl IMka atM Vt I
~ ~
I ~ p" p -At 1 7 4F-AA >> f'1 err 1 928-92 3.QQE"QQB uCt/cc 927-9$ 3.9QE+999 uCt jcc 927-92 3.37E-992 uCt/CC RC 0 hrI tt hv LfJ C ~ 4 RCTRO tr hP hh 1 Qt le& meal
~e ~ M Wla ~ ~ MJ l~ Ml Irr I ls No no CAr~net ul 1 PCC 92B-JQ Q.QQE+999 CFOG>
929 -95 1. 52Et991 u Ct /CC hf4d 1.'0'4t.+tdtd 1 ut;1 Icc tdt'29 99 1. 5 2LTOQ71 u C 1 cc / neov vrrv 1
~
nvr n nnr>nnn vt vrtv vrvr R r\
~
re
~ ~ ~
Pttr cant ttF htyh a1arm > 9 I,Ini t A)8-pip'tp ttte: Nnt I nrem tinn.t Sft I non 4 PORV Tr re v ~
~
f p%t ~
.vvarvv .vva vtlklllrlIlk Irkktr 01 ~
vrv k ttvtt k 0'1 vier rv ~
~ ~ ~ kkl Mt C'0Cghhf Vr VVI VV'k UI I .vtt ~ ~
1 ra ~ 1 rI AC'k 00>
'gl 0tltw rrrIve k rvva vVI
%TATI g l flPR- fll:.l PHP ZQBI Un tt 2 EFF)uents 0400 t VAN Q AT% 9?C ltll R 7PF-QA? ttl 1 925-93 2.3QE-987 uCt Q25-95 2.39E-Q87 uCl/cc 825-97 2.3QE-897 uCs/cc IdZ5-tN 2.3ldL hfdf/ uL'1/cc tttIC Ntt J I6 I NI V
~I 4'I tie ~ tt CINI J It 4I ilI ~
n". R -P l ~ n VF-any 1 I'rr 828-82 3.9QE-QQB uCl/cc 927-QI 3. QQEt 898 uCl/cc 927 -92 3. 2 3E-Q92 uCl/cc NJC D ClJ c ~ T'Dc,>itcl I tt '4 l /u1 ' PItt tl CNeU 92a pa
'lt NIT tl I+ Atl 4 ~ T~ 41 ~ NINt ~l 4tall ~
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'~'M4 ~ ~ PI ~ r 44 o2n no R t Of'Qc II r1 r'hh t'2B-IB -3. 5E-917 CFH 929-95 C.32E-QB6 uC1/cc r Ucl-MC O.SZt.-edb uL:1/cc I los& 95 0. 3 2f 'lAQlb u C11 cc nhO fn ~ IO o nnf innn Cf <>rt 825~ 2.3QE-QQ7 uCt 925W5 NOT RYRILRBLE 925~ 2.3QE-887 uCtrcc vt;t/cc f WM JCIx n F4 ~ 4V%sf" 8AI I QQ I'll% J AN At 4 QRF QQQ ill <it r 928 "82 l.53E-984 uCtrcc I 127 Wf 3.QQE+QQQ uCtrcc 927 W2 4.3BE-983 uCt/cc +co~ t%hh o z ac aeo 4lglP LM n% II ~ 'tP W%h SI4V-'~ 4~ I+ %a@ WWll IJ let I lsl>> B~oo B t 7E~Mc grt rcc 82B-lQ -3. 5E-Qf7 CFH QCB~ ~ 923-95 3.23E-QQS uCtrcc PRE 5 2bE SQb uC1 jcc goo in~ V nVo nnrinnn SQrt SO C e'xt Parcant nF htyh alarm t 9 I/nit K5-A7 Stttt>>a: Nw eel I nrptihn. I.lni t Vmt TI mme i'Y I t.aa, l'v~ 4 x dltt\ll'Nr ~ erase ~ O'hC OOI vevvle vv'x U; .,l, I Px 'ppl d ~ ~ ~ 'W t t 4I Ill~ tx ( VVI hhh hhC'J DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE VIII. F. PLUME EXPOSURE DATA Table provides data for the Offsite Radiation Monitoring Teams. The data set presents data for the ~ time between 0430 to 0901. A given data set is applicable for the fifteen minutes following the time listed. A listing and explanation of less than obvious terms used in the table are as follows: ROUTE; refers to the predesignated, color coded, survey routes.
- 2. Rl, Bl, Yl, R2, B2, Y2; refers to the specific color coded survey route where:
Rl=Red, closest to plant Bi=Blue, closest to plant Yl=Yellow, closest to plant R2=Red, farthest from plant B2=Blud, farthest from plant Y2=Yellow, Farthest from plant
- 3. Sample Point refers to the predesignated lettered points. Readings which follow indicate the distance traveled from the lettered point of origination, at which the listed dose rate was encountered.
4 ~ AIR SAMPIE, IOD; the iodine activity results of are in units of pCi/cc and were developed based on scenario postulated thyroid dose projections.
- 5. NET CPM; the iodine activity in counts per minute.
ERE-90 SF-1 DONALD C. COOK NUCLEAR PLANT EMERGENCY RESPONSE EXERCISE VIII. F. PIUME EXPOSURE DATA, cont. Dose rate data for a given time period should be provided as appropriate for the route, both color and traverse points, being taken and the time. Air sample data should be provided only if a centerline sample is obtained and following sample analysis at the counting vehicle. The player shall analyze the actual sample obtained and determine the activity of the actual sample. At that time the Controller shall interject and provide the concentration postulated by the scenario; The activities are based on a 10 cubic foot air sample and a 4% efficiency for the scintillation detector. An asterisk indicates the dose rates are less than 1 mR/hr. Because release rates were elevated to meet drill objectives, the resultant iodine sample count rates would have been beyond the capabilities of the counting equipment. Therefore, the iodine sample count rates have been reduced by a factor of 1000 to verify players capability of calculating sample activities. LEGEND * = (] mR/hr Particulate MDA = 2.50 -E-09 pCi/cc Iodine MDA = 2.86 E-10 pDi/cc Dose Rate = mR/hr .Ooen Window Readings = 1.5 x Dose Rate Distance = Miles ERE-90 SF-2 PLUME EXPOSURE DATA TIME: 0446 0500 Air Sam le Data From Sample Distance Dose Distance Dose Route Point From Rate From Rate Particulate Iodine Ci/cc c m ici/cc c m .1 4 Red 1 A .3 423 1.31E- 3.28E+5 East ~ 4 4 ~ 7 1.2 16 .8 16 1.3 2.51E-6 6.31E+4 Blue 1 A .9 83 East 1.0 144 1.1 83 Yellow 1 The plume has not arrvied Red 2 The plume has not arrived Blue 2 The plume has not arrived Yellow 2 The plume has not arrived ERE-DO PI.UHE EXPOSURE DATA TIHE: 0430- 0445 Air Sam le Data From Sample Distance Dose Distance Dose Route Point From Rate From Rate Particulate Iodine ICi/cc c m IjCi/cc c m .1 4 Red 1 A .3 423 1.31E-5 3.28E+5 East .4 4 Blue 1 The plume has not arrived Yellow 1 The plume has not arrived Red 2 The plume has not arrived Blue 2 The plume has not arrvied Yellow 2 The plume has not arrived PLUME EXPOSURE DATA TIME'501 0515 Air Sam le Data From Samp e Distance Dose Distance Dose toute Point From Rate From Rate Particulate Iodine iCi/cc c m Ci/cc c m .2 2 Red 1 .3 289 8.90E-6 2.24E+5 .4 2 East .1 0.7 l. 1.3 0.8 17 0.9 88 Blue 1 A 1.0 152 2.65E-6 6.67E+4 1.1 88 East 1.2 17 Yellow 1 The plume has not arrived Red 2 The plume has not arrived Blue 2 The plume has not arrived Yellow 2 The plume has not arrived i. PLUME EXPOSURE DATA TIME: 0516 0530 Ax r Sam 1 e Data From Sample Distance Dose Distance Dose toute Point From Rate From Rate Particulate Iodine iCi/cc c m jci/cc c m A .1 1 <ed 1 .2 174 5.39E-6 1.35E+5 East .3 1 0.7 1.3 0.8 ll 0.9 57 Blue 1 1.0 98 1.72E-6 4.31E+4 1.1 57 East 1.2 ll 1.0 2 1.5 58 C 1.1 2 1.6 55 1.2 4 1.7 5 9.99E-8 2.51E-3 ellow 1 1.3 5 1.8 4 West 1.4 55 2.0 2 1.1 4 1.7 51 1.2 ll 1.8 37 7.64E-7 ,1.92E-4 1.3 22 1.9 22 <ed 2 1.4 37 2.0 ll 1.5 51 2.1 4 East 1.6 57 Blue 2 The plume has not arrive Yellow 2 The plume has not arrived PLUHE EXPOSURE DATA TI HE: 0531 0545 Air Sam le Data From Sample Distance Dose Distance Dose Route Point From Rate From Rate Particulate Iodine Ci/cc c m Ci/cc c m .1 1 Red 1 ~ 2 109 3.37E-6 8.48E+5 East .3 1 0.7 0.8 7 1.2 0.9 35 1.3 Blue 1 A 1.0 61 1.06E-6 2.666E+ East 1.1 35 1.0 14 1.5 59 1.1 31 1.6 57 1.2 41 1.7 50 1.02E-7 2.57E+3 Yellow 1 C 1.3 50 1.8 41 West 1.4 57 1.9 31 2.0 14 1.1 4 1.7 53 1.2 ll 1.8 39 1.3 23 1.9 23 7.80E-7 1.96E+4 Red 2 1.4 39 2.0 11 B 1.5 53 2.1 .4 East 1.6 59 Blue 2 The plume ha s not arrive Yellow 2 The plume has not arrived PLUME EXPOSURE DATA TIME: 0546 0600 Air Sam le Data From Sample Distance Dose Distance Dose Route Point From Rate From Rate Particulate Iodine jCi/cc c m Ci/cc c m .1 Red 1 .2 60 7.00E-6 1.76E+5 East .3 0.7 1.2 0.8 4 1.3 0.9 19 Blue 1 A 1.0 33 2.65E-6 6.67E-4 East 1.1 19 1.0 1.6 29 1.1 3 1.7 18 1.2 8 1.8 8 1.3 18 1.9 3 4.77E-7 1.20E+4 Yellow 1 C 1.4 29 2.0 n 1.5 34 1.1 2 1.7 30 1.2 6 1.8 22 1.3 13 1.9 13 1.4 22 2.0 6 4.43E-7 1.11E+4 Red 2 B 1.5 30 2.1 2 East 1.6 33 0.2 6 1.0 25 0.4 15 1.2 15 3.88E-7 9. 74E+3 Blue 2 C 0.6 25 1.4 6 West 0.8 30 Yellow 2 The plume has not arrived VRF-90 PLUHE EXPOSURE DATA TIHE: 0601 0615 Air Sam le Data From Sample Distance Dose Distance Dose Route Point From Rate From Rate Particulate Iodine Ci/cc m Ci/cc c m .1 Red 1 A .2 38 1.18E-6 2.96E+4 East .3 0.7 1.2 0.8 2 1.3 0.9 13 Blue 1 A 1.0 21 3.79E-7 9.53E+3 East 1.1 13 1.0 3 1.6 12 1.1 5 1.7 11 1.2 7 1.8 7 2.28E-7 5.73E+3 1.3 ll 1.9 5 Yellow 1 C 1.4 12 2.0 3 West 1.5 13 1.3 1 1.9 19 1.4 4 2.0 14 1.5 8 2.1 8 2.81E-7 7.07E+3 1.6 14 2.2 4 Red 2 B 1.7 19 2.3 1 East 1.8 25 0.0 6 0.8 27 Blue 2 C 0 ' 27 1.0 15 3.88E- 9.74E+3 West 0.6 32 1.2 6 Yellow 2 The plume has not arrived. roF-nn PLUME EXPOSURE DATA TIME: 0616 0630 Air Sam le Data From Sample Distance Dose Distance Dose Route Point From Rate From Rate Pa>ticulate Iodine >Ci/cc c m Ci/cc .1 Red 1 .2 25 7.73E-7 1.94E+4 East ~ 3 0 1.1 7 Blue A 1.2 13 East 1.3 7 2.23E-7 5.63E+3 0.8 1.4 0.9 1.5 1.40E-7 3.52E+3 Yellow 1 1.0 1.6 C 1.1 1.7 Mest 1.2 0 1.8 2 2.4 8 Red 2 1.9 5 2. 5'.6 5 1.71E-7 4.30E+3 2.0 8 2 B 2.1 ll 2.7 East 2.2 13 ~C 2.3 3 3.4 Blue 2 2.6 9 3.7 2.47E-7 6.20+3 B 2.8 16 3.8 East 3.0 20 3.7 ll 4.7 19 Yellow 2 3.9 19 4.9 ll 2.84E-7 7. 14E+3 B 4.1 21 5.1 8 East 4.3 24 PLUHE EXPOSURE DATA TINE: 0631 0645 Air Sam le Data From Sample Distance Dose Distance Dose Route Point From Rate From Rate Particulate Iodine llCi/cc c m Ci/cc .1 Red 1 .2 14 4.36E-7 1.09E+4 East .3 1.0 1.3 4 Blue 1 A 1.1 1;4 1.34E-7 3.37E+4 East 1.2 0.7 1.2 0.8 1.3 0.9 1.4 7.59E-8 1.91E+3 Yellow 1 C 1.0 1.5 West 1.1 1.6 1.7 1.7 2.3 1.8 2.4 1.9 2.5 1.07E-7 2.69E+3 . 2.0 2.6 Red 2 B 2.1 2.7 East 2.2 2.3 1 3.5 2.4 2 3.6 1.33E-7 3.34E+3 Blue 2 B 2.5 4 3.7 East 3.0 ll 2 9 3.7 7 4.7 13 3.9 13 4.9 7 2.57E-7 6.46E+3 Yellow 2 B 4.1 19 5.1 2 East 4.3 22 PLUME EXPOSURE DATA TIME: 0646 0700 Air Sam le Data From Sample Distance Dose Distance Dose Route Point From Rate From Rate Particulate Iodine LCi/cc c m Ci/cc A .1 Red 1 ~ 2 2.62E-7 6.57E+ East .3 1.0 1.4 1.1 Blue 1 A 1.2 8.39E-8 2.11E-3 East 1.3 .7 1.2 1 1.8 1.3 2. 1.9 5.04E'-8 1.27E+3 Yellow 1 1.4 2 2.0 C 1.5 3 2.1 West 1.6 3 2 ~ 1.9 2.4 3 2.0 2.5 2 5.9E-8 1.45E+3 Red 2 B 2.1 2.6 East 2.2 2.3 3.2 6 2.4 1 3.4 3 2.6 3 3.6 1 8.28E-8 2.08E+3 Blue 2 B 2.8 6 3.7 East 3.0 7 3.5 4.5 3 ' 4.7 3.9 4.9 1.00E-7 2.52E+3 Yellow 2 B 4.1 5.1 East 4.3 O~ PLUME EXPOSURE DATA TIME: 0701 0715 Air Sam le Data From Sample Distance Dose Distance Dose Route Point From Rate From Rate Particulate Iodine ICi/cc c m Ci/cc c m .1 ted 1 A .2 1.80E-4 4.53E+3 East .3 1.0 1.3 Blue 1 A 1.1 1.4 East 1.2 5.18E-8 1.30E+3 1.1 1.6 1.2 1.7 J 1.3 1.8 3 '7E-8 8.23E+2 1.4 1.9 Yellow 1 C 1.5 2.0 West 2.1 1.8 2.3 1.9 2.4 2.0 2.5 3.98E-8 1.00E+3 Red 2 B 2.1 2.6 East 2.2 2.3 3.2 2.4 3,4 2.6 3.6 ~C 5.33E-8 1. 34E+3 Blue 2 B 2.8 3.7 East 3.0 3.7 2 4.7 3.9 3 4.9 6.37E-8 1,.60E+3 Yellow 2 B 4.1 5 5.1 East 4.3 5 ERF-nn 'Pf.UME EXPOSURE DATA TIME: 0716 0730 Air Sam le Data From Sample Distance Dose Distance Dose Route Point From Rate From Rate Particulate Iodine Ci/cc c m Ci/cc c m .1 Red 1 A ~ 2 9.00E-8 2.26E+3 East .3 ~ \ II Blue 1 A .9 1 1.2 3.45E-8 8.67E-2 East 1.0 2 1.6 2.2 1.7 2.3 ~ \ 1.8 2.4 1.96E-8 4.94E+2 Yellow 1 C 1.9 2.5 West 2.0 1.5 2.2 1.6 2.3 1.7 2.50E-8 6.28E+2 Red 2 B 1.9 East 2.0 1.7 2.7 1.9 1 2.9 3.21E-8 8.07E+2 Blue 2 B 2.1 1 3.1 East 2.3 3 2.5 3.5 2.7 1 3.7 2.9 2 3.9 3. 98E-8 1.00E+3 ellow 2 B 3.1 3 4.1 0' East 3.3 3 PLUHE EXPOSURE DATA TIHE: 0731 0745 Air Sam le Data From Sample Distance Dose Distance Dose Route Point From Rate From Rate Particulate Iodine jCi/cc c m Ci/cc c m ted 1 The plume ha s ended 1.0 1.3 Blue 1 A 1.1 1.4 3.45E-8 8.67E+2 East 1.2 1.2 1.7 1.3 1.8 1.4 1.9 1.96E-B 4.94E-2 Yellow 1 C 1.5 2.0 West 1.6 2.1 1.9 2.3 2.0 2.4 Red 2 B 2.1 2.5 ~ r 2.50E-8 6.28E+2 East 2.2 2.4 I 3~2 2.6 Blue 2 B 2.8 3.6 3. 21E-8 8.07E+2 East 3.0 3.5 4 ~4 3 3.7 1 4.6 2 3.9 2 4.8 1 3.98E-8 1. OOE+3 Yellow 2 B 4.0 3 5.0 East 4.2 3 r:ul: nn PLUHE EXPOSURE DATA TIHE: 0746 0800 Air Sam le Data From Sample Distance Dose Distance Dose Route Point From Rate From Rate Particulate Iodine JCi/cc c m Ci/cc c m Red 1 The plume ha s ended 1.0 4 1.3 2.2 Blue 1 1.1 22 1.4 4 6.49E-7 1. 63E+4 1.2 36 1.3 1.7 1.4 1.8 Yellow 1 C 1.5 1.9 1.33E-8 3.34E+2 West 1.6 1.8 2.3 1.9 n 2.4 2.0 ~ I 4 2.5 n 1.52E-8 3.82E+2 Red 2 B 2.1 2.6 East 2.2 2.7 3.1 2.8 3.2 Blue 2 B 2.9 3.3 ~ I 2.17E-S 5.46E+2 East 3.0 3.4 4 ~4 3.6 4.6 3.8 4.8 2.43E-8 6.10E+2 Yellow 2 B 4.0 5.0 East 4.2 v>>r.. nn ID PLUME EXPOSURE DATA TIME: 0801 0815 Air Sam le Data From Sample Distance Dose Distance Dose Route Point From Rate From Rate Particulate Iodine l>Ci/cc c m Ci/cc Red 1 The plume has ended Blue 1 The plume has ended 0.8 ~ ' 1.3 0.9 1.4 1.0 1.5 (MDA Yellow 1 1.1 1.6 1.2 0.8 1.4 0.9 1.5 1.0 1.6 n 1.01E-8 2.55E+2 1.1 Red 2 C 1.2 East 1.3 1.0 1.3 C 1.1 1.4 Blue 2 East 1.2 1.36E-9 3.42E+2 2.2 2.7 2.3 2.8 2.4 2.9 1.62E-8 4.08E+2 Yellow 2 C 2.5 3.0 East 2.6 PLUHE EXPOSURE DATA TIHE: 0816 0830 Air Sam le Data From Sample Distance Dose Distance Dose toute Point From Rate From Rate Particulate Iodine VCi/cc c m pCi/cc c )m led 1 The plume ha s ended Blue 1 The plume has ended Yellow 1 The plume has ended Red 2 The plume has ended J\ d~ \ 0.2 ~ 1.0 0.4 1.2 Blue 2 C 0.6 1.4 8. 15E-9 2.05E+2 East 0.8 0.7 1.5 0.8 1.7 0.9 1.8 1.01E-8 2.54E+2 Yellow 2 C 1.1 1.9 East 1.3 PLUHE EXPOSURE DATA TIHE: 0831 0845 Air Sam le Data From Sample Distance Dose Distance Dose Route Point From Rate From Rate Particulate Iodine jCi/cc c m Ci/cc c m Red 1 A East The plume has ended Blue 1 B East The plume has ended Yellow 1 B The plume has ended East Red 2 C The plume has ended East 0.1 1.0 0.2 1.2 Blue 2 C 0.4 1.4 East 0.6 1.5 0.8 0.7 1.5 0.8 1.7 0.9 1.8 5.49E-9 1 . 38E+2 Yellow 2 C 1.1 1.9 East 1.3 PLUHE EXPOSURE DATA TIHE: 0846 0901 Air Sam le Data From Sample Distance Dose Distance Dose oute Point From Rate From Rate Particulate Iodine >Ci/cc c m VCi/cc c m (ed 1 The plume has ended Blue 1 The plume has ended Yellow 1 The plume has ended Red 2 The plume has ended Blue 2 The plume ha s ended Yellow 2 The plume has ended 0 DONALD C. COOK NUCLEAR POWER PLANT - 0431-0445 'sa Vs 10 MILE EPZ I BERRIEN COUNTY , ~ I COOK NUCLEAR PLANT (I I' ' ROUTES S SAMPLING POINTS ~ ~ I \ ~ ~ ~~ ~ ~ rarer ~ <<<<<<<< el ~ c ceca <<casse Cares C~ ~ ee sa<<<<<< ~ ac<<ces <<r II - ==. ':.--:::::-:ll-,:-gP <<ss cc II a<<cs C r ll 'all w t<<c ~ Is ecs ~ <<sc\ << ~ eecca e<<c I<<c e<<s l<S60 A rr ~ ~ 'IJrl( ~ R ~ ~ SENTtU] IIAIISN Pi I se CSU J ~ II ...'I'I an ci ! ~ / I 5( (t(((5 ~ j ~ ~ ~, I ss ~ I I')aw'l<< ~ =. c ~ ~ ~s Ia I ~ il I ~ e~ la, I" 5(. l sl ~l 5 >C(( I asla ~ ~ I ~ I~ I 5(s( t( I U I~ + j! ~ '<< c Jb r rS '8'L ~ ls s /.. 0 0 LC5 P ~ LI' I Cg0 aX 'Q((aa ssa<<r I I",fs( I( sll ~ ( ~ IC I a. '<< 1 l(S ~ 'I Cas<<( II ~ l~ 11 Is ~ S y ~ T AIL 'T~ (ac s I ,(I<<( ~, ,I (I r ls ~ l' I I l I,a ,~ @ I Is c 5 ~ I' 2ro N ~~ l a aa ~ ~; rrl I J
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