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| | number = ML20011F104 | | | number = ML20011F104 |
| | issue date = 09/27/1986 | | | issue date = 09/27/1986 |
| | title = Radiological Emergency Preparedness Exercise 860927. | | | title = Radiological Emergency Preparedness Exercise 860927 |
| | author name = | | | author name = |
| | author affiliation = TENNESSEE VALLEY AUTHORITY | | | author affiliation = TENNESSEE VALLEY AUTHORITY |
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| =Text= | | =Text= |
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| '"3, BROWNS FERRY NUCLEAR PLANT-RADIOLOGICAL EMERGENCY PREPAREDNESS EXERCISE SEPTEMBER 27, 1986
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| :i--
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| 1 f.
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| l h ?[gdI -
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| oy 9003010101 860927 $1
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| . DR ADOCK0500g"g9 }p-; W M
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| -6 !
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| INTRODUCTION j
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| Annual exercises'are required by regulation.for each licensed commercial
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| ' C. e'~'-() . nuclear power plant in the United States. . The purpose of these exercises j i
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| a are to, test Radiological Emergency Plans (REPS)'to ensure'that the health J and safety of TVA employees and the general public is protected in the event'of a radiological accident. These exercises also serve to train emergency response personnel for the duties under REP and to observe the REP in action'so that areas in need of improvement can be identified, l
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| 1
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| 'The TVA actions during the exercise will be evaluated by NRC and the j State and local actions will be self evaluated. NRC will issue a formal -l inspection report concerning the exercise. I This exercise will be initiated from the BFN control room on September 27, 1986, at approximately 0800-CDT. The exercise will have a j duration of eight to nine hours.- The exercise will initially involve the l Onsite und offsite TVA emergency organizations. This will'be a limited 1
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| . participation exercise so the State of Alabama and the risk counties will participate but will not be evaluated by the Federal Emergency Management j Agency. '
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| Those participating in the exercise may include, but are not limited to, the following. '
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| A. -Browns Ferry Nuclear Plant B. Tennessee Valley Authority Central Emergency Control Center (CECC),
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| i gf } : Chattanooga. Tennessee v.
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| C. Alabama Emergency Management Agency (AEMA), Montgomery, Alabama D. Alabama Department of public Health, Montgomery, Alabama
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| .E. Lawrence County Government, Moulton, Alabama F. Limestone County Government, Athens, Alabama G. Morgan County Government, Athens, Alabama H. Lauderdale County Government, Florence, Alabama
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| /I . Tri-County District Health Services J. National Weather Services K. Nuclear Regulatory Commission (NRC) , ,
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| v 4
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| [1 __.___Q
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| } i )'.
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| 4
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| #, -Narrative Summ ry
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| 'With the resetor. increasing in power after a short maintenance outage, a rod drop accident 10 postulated causing the reactor to scram on main stream line high radiation. The "A" inboard and outboard main steam
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| ;p valves fail-to close permitting a brief release-of radioactive steam to
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| 'L tho'concensers before the~ operators can manually close the "A" valves.
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| This results in a-release of radioactive cteam through the utsek-to the environs via-the mechanical vacuum pumps. Unknown to the operators valve 85-286 off the scram discharge volume tank leaks releaning radioactive water and steam into,the reactor building. This Isak is stopped when the
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| ~
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| operator resets the scram. The reactor building ventilation system isolates and SBGTS starts. However, one of the two isolation dampers on the reactor building air intake falls to close.
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| An assistant unit operator in the vicinity of the CRD modules on the east sipe of the unit 3 reactor hears an air leak, locates the leak and notifies the unit operator. Maintenance is notified to repair the leak.
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| In=the process of repairing the air leak a union on the control air supply line which supplies air to the CRD scram inlet and outlet valves and to the drain vslve at the bottom of the CRD scram discharge volume tank completely separates. "Ihis break causes the.CRD scram inlet and outlet valves to fail in tho open position, a valve off the CRD scram dischargo volume tank fails to close. The scram air header depressurizes and all scram valvos open. Because of the low control air pressure the scram valves cannot be reset.
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| The valve leak off the scram dischargo volume restarts causing radioactive water and steam to be released into the reactor building. As time progresses, this leak is postulated to increase. This results in 9.. airborne contamination in the reactor building and in the operator starting to depreusurize the reactor using RCIC and the ADS valves.
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| A trip of- the RCIC and CED pumps with the reactor vessel pressuro greater than 450 psi is pnstulated. This prevents.the RHR and CS systems from adding makeup water to the vessel. It is further postulated that the air pressure in the accumulators for the ADS valves is so low that further depressurization of the reactor vessel with the ADS valves in impossible. The loss of makeup water capability to the reactor and the less of the relief valves for depressurization result in repressurization of the reactor, a continuous loss of water from the vessel through the leaking relief valve flange and uncovering of the core. Additionally, it is postulated that a maintenance team working the failed air intake isolation damper-inadvertently opened the second damper. This causes a unfiltered releaso from the unit 3 reactor building to the environment.
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| This release continues for approximately 1-1/2 hours until the damper can be reclosed.
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| S 1016E .
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| -1
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| A BROWS FERRY NUCLEAR PLANT RADIOLOGICAL EMER0ENCY PLAN (rep) EXERCISE The 1986 BFN rep exercise will be a small-scale exercico requiring partial participation by State, and local emergency response agencies.
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| , Exercise Goals The TVA' goals.for the 1986.BFN exercise are as follows:
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| : 1. To allow plant and offsite personnel to test and practice their response capability in accordance with the BFN REP and rep
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| - implementing procedures to protect plant personnel and the general l
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| public as .nppropriate.
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| : 2. To ensure that deficiencies observed in previous exercises have been
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| < corrected.-
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| : 3. 'lo identify emergency response capabilities that are in need of improvement or revision.
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| Exercise Objectivec Ceneral-Objectives l'- Demonstrate-the ability to alert and mobilize TVA emergency response personnel in a timely manner.
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| : 2. Demonstrate the ability to activate TVA emergency centers in a timely manner.
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| : 3. Demonstrate the adequacy, operability, and offective use of emergency communications equipment and the adequacy of the communications
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| - systems.
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| : 4. . Demonstrate _the ability of each emergency response facility manager C
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| to maintain command and-control over all emergency response "'
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| activities conducted from his facility throughout-the exercise.
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| : 5. Demonstrate the primary functional responsibilities and/or problem solving capabilities of emergency response personnel.
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| =
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| : 6. Demonstrate that timely and accurate information can be supplied to the State on a frequent basis.
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| _ 7. Demonstrate the ability to effectively generate protective action recommendations.
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| Specific Objectives A. Control Room Objectives
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| : 1. Demonstrate the ability of the Site Emergency Director (Shift Engineer) to classify an emergency condition in a timely manner.
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| 2 '. Dewonstrate the ability to formulate and implement protective action measures in a timely manner.
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| i hN&n '
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| 2-'
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| O 3., Demonstrate the precise and clear transfer of responsibilities from the Control Room staff to the TSC staff.
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| : 4. Demonstrate the ability of the Shift Engineer to periodically-inform Control Room personnel of the status of the emergency situation and the plant conditions.
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| : 5. Demonstrate.the primary functional responsibilities and problem solving capabilities of the control Room staff.
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| B. Technical Support Center (TSC) Objectives
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| : 1. Demonstrate the ability to alert and mobilize the TSC emergency response personnal in a timely manner.
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| : 2. Demonstrate the ability to activate the TSC in a timely manner.
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| : 3. Demonstrate that effective command and control occurs in the TSC. *
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| : 4. Demonstrate the precise and clear transfer of responsibilities from the Control Room staff to the TSC staff.
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| .5.
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| ~
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| Demonstrate the primary functional responsibilities and problem solving capabilities of the TSC staff.
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| : 6. Demonstrate the ability of the TSC staff to support the Control Room staff's effort to identify the cause of the incident, mitigate the consequences of the incident and place the unit in a safe, stable condition.
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| : 7. Demonstrate the proficiency of the Site Emergency Director in the TSC.to classify an emergency condition. " '
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| 8.. Demonstrate the ability to account for site personnel in a timely manner.
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| 9 ~. Demonstrate the ability to formulate and implement onsito protective actions in a timely manner.
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| : 10. Demonstrate the ability to perform timely assessments of onsite radiological conditions to support the formulation of protective action recommendations.
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| till .
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| ~t Q3_ h @c
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| v-a -
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| .a L.
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| b
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| : 11. Demonstrate the timely updating of TSC status boards.
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| C. Operations Support Centers (OSC) Objectives
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| : 1. Demonstrate the-ability to alert and mobilize the OSC emergency response personnel'in a timely manner.
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| : 2. Demonstrate the-ability to activato the OSC in a timely manner.
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| : 3. Demonstrate the ability of the OSC staff to initiate and coordinate activities in an efficient and timely manner.
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| : 4. Demonstrate that OSC teams are thoroughly. briefed on plant conditions before being dispatched.
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| .c 5. Demonstrate that adequate health physics support is provided to OSC teams.
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| .6. Demonstrate that.0SC team leaders provide effective command and control.
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| 7.. Demonstrate that adequate communications are maintained between OSC teams and the OSC.
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| : 8. Demonstrate that there is a timely and efficient transfer of information between the OSC and the TSC.
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| : 9. Demonstrate the ability to obtain and to analyze samples drawn from the.inplant normal or post-accident sampling systems.
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| 10.- Demonstrate the ability to direct and coordinate inplant health physics surveys in a timely manner. " '
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| lLI . . Demonstrate the ability to control the exposure of onsite emergency workers.
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| : 12. Demonstrate that a plant environmental monitoring team can be dispatched in a timely and efficient manner.
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| : 13. Demonstrate the timely updating of OSC status boards.
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| -D. . Central Emergency Control Center (CECC) ' Objectives
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| : 1. Demonstrate that the Operations Duty Specialist makes the initial notificatioa to the State in a timely manner.
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| : 2. Demonstrate the ability to alert and mobilize the CECC emergency response personnel in a timely manner.
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| *i'' ' A'
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| x .
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| 3 O 3.,
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| ~
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| Demonstrate the ability to act'ivate the CECC in a timely manner.
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| 4
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| " Demonstrate that the CECC Director makes a clear announcement-when he' determines the CECC operational.
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| '5.'
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| Demonstrate that effective command and control occurs in the
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| .CECC.'
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| i
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| : 6. Demonstrate the ability to effectively call upon and utilize TVA
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| : corporate or outside support organizations when required.
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| : 7. Demonstrate the ability to obtain vendor and other outsido resources as required.
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| : 8. Demonstrate the ability of the CECC staff to direct.and coordinate the deployment of Radiological Monitoring Teams in a timely manner.
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| f- -
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| : 9. Demonstrate the ability to perform dose assessment activities in a timely manner.
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| '10. Demonstrato the ability-to coordinate TVA dose assessment activities with those conducted by the State.
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| : 11. Demonstrate the ability of the dose assessment team to obtain, i
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| analyze, and use plant radiological condition information to produce dose assessments and to formulate timely protective action recommendations.
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| : 12. Demonstrate the ability to inform, update, and coordinate with State Radiological Health personnel regarding meteorological and-
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| . dose assessment information in a timely manner.
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| - 13. ~ Demonstrate the ability to inform and update FCC emergency response personnel regarding the status of an emergency condition in a timely manner.
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| : 14. Demonstrate the ability of the CECC plant assessment team to j analyze current plant conditions, identify projected trends and
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| (
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| potential consequences.
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| : 15. Demonstrate a timely and accurate flow of information from the TSC staff to the CECC assessment teams.
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| I .
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| 41 - 4
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| : 16. Demonstrate the ability of the Core Damage Assessment Team to generate source term information in a timely manner.
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| : 17. Demonstrate a timely and effective flow of information between
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| 'CECC radiological and. plant assessment teams.
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| : 18. Demonstrate that protective action recommendations are made by use of the Protective Action Guide (PAG) logic diagram.
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| : 19. Demonstrate the timely updating of CECC status boards.
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| : 20. Demonstrate-that protective action recommendations are provided to the State in a timely and clear manner.
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| : 21. Demonstrate that proper security is established for the CECC.
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| t
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| : 22. Demonstrate the ability to perform timely assessments of offsite and/or onsite conditions to support the formulation of protective action recommendations.
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| : 23. Demonstrate the ability to alert Federal and industrial emergency contacts in a timely manner.
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| E. Environs Assessment' Activities
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| : 1. Demonstrate the ability to coordinate Radiological Monitoring Teams in conjunction with the State.
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| : 2. Demonstrate the ability-of the Radiological Monitoring Teams to efficiently and effectively utilize their procedures to perform dose rate surveys, collection and analysisoof radiological samples, and other prescribed-radiological monitoring activities. -
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| : 3. Demonstrate the ability of the monitoring teams to follow contamination control procedures.
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| : 4. Demonstrate the ability to control the exposure of offsite emergency. workers. -
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| : 5. Demonstrate effective command and control of radiological
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| , monitoring activities from the plant, FCC, and/or CECC as
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| ,sppropriate.
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| : 6. ' Demonstrate the ability of Field Team members to use effective dress-out techniques using C-zone clothing under field conditions.
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| 1 l
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| wAt;*nN
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| ?
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| ;n- &
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| a f , s.
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| Q Q)n; ;
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| , F. Public Information Objectives ,
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| ,. 1 ~.
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| Demonstrate the ability to effectively function in the Joint Information Center (JIC) facility.
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| : 2. .f L t-Demonstrate the ability to establish'and. operate a rumor control i center with the Citizen's Action Line.
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| s
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| ^
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| : 3. Demonstrate the' ability to produce a news release from the CECC every two hours.
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| : 4. Demonstrate the ability to functionally staff the'Public Information component of the CECC.
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| 5.4 Demonstrate the ability of the TVA chief spokesperson to brief the media in clear, understandable terms.
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| L! G. Communications Objectives
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| -1. Demonstrate the REP notification procedure throughout the l notification chain, beginning at the.BFN Control Room and 1 ,
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| extending to State and local authorities. j 2.
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| ~
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| ( g) Demonstrate the adequacy of communications links between the-plant and the CECC.
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| ;: u 4 3. Demonstrate the adequacy of communications links between the L 4 CECC and the State EOC.
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| l l
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| '4. Demonstrate the-adequacy of communications links between tho-CECC and the JIC.
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| : 5. Demonstrate the adequacy of communication links between the CECC
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| -and the FCC.
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| 'P
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| : 6. Demonstrate the adequacy of radion in tho monitoring vans, at 1
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| Decatur, Alabama, at the CECC, and at the BFN TSC.
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| ' H. Exercise Operation Objectives
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| : 1. Provide specific and measurable objectives for'the exercise.
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| 2.- Improve controller and evaluator performance through an increased level of training. i r
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| : 3. Provide additional information in the scenario package, i.e.,
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| Public Information messages, meteorological data, and evaluation forms.
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| L L O- 4. Demonstrate the ability to adequately perform post-exercise V. critiques to determine any areas requiring additional capability L
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| improvement. i l
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| T-- -15 min Initial conditions-0745
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| .. Unit 1~_ operating at:1050 MW
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| . Unit 2 in a refueling outage
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| ! ., Unit 3
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| ~
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| - Operating at 10% power-- returning to power af ter --
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| a short maintenance outage.
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| - Has.been operating for app'roximately,one year.-
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| , -.Drywell control air compressor 3A tagged out for-maintenance.
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| , - CRD pump 3A tagged out for maintenance.
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| - Increasing power after a short maintenance outage.
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| L h
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| l 1016E v
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| w v
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| :T = 0- .
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| Rod decp tecid2nt occurs end racetor certas on main 0800 Hrs. (CST) line steam high radiation annunciators alarm in the control room. All' main steam isolation valves'close' except'for "A". inboard and outtoard valves Which the.
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| operator _noted failed to close'and promptly_ closed.
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| Operator aware of rod drop accident but not aware that
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| ! valve 85-286 off the scram discharge volume is leaking. Operator gets post treatment offgas-radiation high' alarm (RA-90-2654, XS-55-46, window 33) and reactor building radiation alarms RA 90-ID on annunciator XS-55-3A window 22 and RI-90-21 on panels 9-11.
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| T =.1 min. Operator resents scram Which stops leak. Reactor 0801 Hrs.- building ventilation system isolates and standby gas treatment (SBGT) system starts. However, one of the two isolation dampers (FC0 64-14) on the reactor building air intake fails to close. Using the RCIC system the operator maintains reactor water level.
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| T = 5 min. The shift engineer declares an ALERT based on main 0805 Hrs. (CST) steam line high radiation.
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| T = 15 min. Stack release radiation monitors 90-147 and 90-148 0815 Hrs.-(CST) indicate 1.9 x 104 cps and 1.7 x 104 cps respectively and are slowly increasing.
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| , T = 25 min. An assistant unit operator (AUO) in vicinity of CRD 0825' Hrs. (CST) modules on elevation 565 on west side of unit 3 reactor hears air leak, locates leak in union in CRD
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| . - control air supply line and notifies unit operator (UO). Maintenance will be dispatched to repair leak.
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| T = 50 min. Maintenance isolates and depressurizes air lines and 0850 Hrs. (CST). and starts repair of leaking union.
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| T = 1 hr. Fitter repressurizes the air line to determine if 0900. Hrs. (CST) the air leak is repaired. At this time the union completely separates. The scram air header depressurizes and all scram valves open.
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| T = 1 hr./ RA-90-ID on annunciator SX-55-3A window 22 and 10 min. RI-90-21A on panel 9-11 alarm. RR-90-1 on panel 9-2 0910 Hrs. (CST) and RI-90-21A reading 150 mc/hr.
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| T = 1 he/ The dose rato in the reactor building is continuing to 15' min. increase and is_up to 500 mr/hr. Operator notifies HP 0915 Hrs. (CST) to verify the reading. CAM 3RM90-57 located behind unit 2 elevator starts to alarm 3-RM-90-58 and craftsmen evacuate the reactor building.
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| 'T = 1 hr./ Hp verifles the reading and notifies the operator that 30 min. the activity is increasing.
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| 0930 Hrs. (CST) e 1016E
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| b T =-1 hr./ Th3 rcdiation 1sv31"in rs:ctoe building is up to-750
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| [ 35 min._
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| 0935 Hrs.E(CST) mc/hr and'in continuing to increase.
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| -T = 1 he./. ARM R1-90-21 goes offscale at 1000 mr/hr.
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| . 45' min.
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| 0945 Hrs. (CST)
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| T = 1:hr./. 'A maintenance team is sent to reactor building to
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| '50 min. locate radiation leak.
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| 0950 Hrs. (CST)
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| T = 2 he. . Drywell control air compressor 3B trips and will not
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| :1000 Hrs. (CST) restart. pA 32-70 (drywell control air pressure low)'
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| alarms.
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| T = 2 hr. Leak found on valve 85-286. Operator notified.
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| 30 min.
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| 1030 Hrs. (CST)
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| T = 2 hr./ Operator begins to depressurize at normal cooldown 35 min, rate using RCIC and by manually actuating the ADS 1035 Hrs. (CST) relief valves.
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| T = 2 hr./ pA 32-31 (main steam relief valve air accumulator 45 min. pressure low) alarms.
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| 1045 Hrs. (CST)
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| .- T =.3 hr. All' control room annunciator panels fail due to a 1100 Hrs. (CST) loss of 48V power. Loss of power results from overheating and shorting to ground of loose connection between the supply cable from the auto. transfer switch and the bus in panel circuit breaker board 9-9, cabinet 1.
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| T = 3 hr./ The site emergency director declares SITE AREA 15 min. EMERGENCY on loss of all annunciator panels for over
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| , 1115 Hrs. (CST) 15 minutes. plant evacuation will be initiated.
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| T = 4 hr. CRD pump 3D trips and will not restart. CRD pressure /
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| 1200 Hrs. (CST) flow goes to zero.
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| T = 4 hr./ Failed bus bar in panel 9-9 replaced and annunciator 10 min. panels returned to service.
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| 1210 Hrs. (CST)
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| T = 4 hr./ Maintenance team working on the failed air intake 1230 Hrs. (CST) damper inadvertently opens the second damper (FC0 64-13) creating a direct radiation leak to the environment. Site Emergency Director declares CENERAL-EMERGENCY based on loss of three fission product barriers.
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| T = 5 hr. RCIC turbine trips with reactor pressure at.500 psi.
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| 1300 Hrs. (CST) Insufficient air in accumulators to complete O- depressurization. Reactor begins to repressurize with MSRVs lifting on high pressure. Reactor water level decreasing- .
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| . 1016E
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| M s
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| i.T =I6'hr.- Tap of th3'fus1-uncoversd.-
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| ,$ - 1400. _ Hrs . - (CST) -
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| u.
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| Control air'. reestablished and scram inlet outlet valves-
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| -T =S7 hr./=
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| -30 min. 4 closed.; Leak secured.
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| 1530 Hrs. (CST)
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| ; t-T'= 7 hr./. Maintenance crew managers to close one air Intake
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| .l 40 niin. isolation damper thus terminating the radiation--
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| 1540 Hrs.J(CST)- release.
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| T..= 7 hr./ - Water level in vessel increasing.~
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| .45' min.-
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| 1545 Hrs.-(CST)'
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| n'.
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| gj 'T = 8,hr. Delli ends. -Plant stable.
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| 1600' Hrs. .(CST) i
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| \
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| -1016E 2' sh
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| - .. . e i
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| -7 =
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| f ~m d ).
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| y 5.. All. participating personnel will know the date of:the exercise but not its starting time or duration.
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| i T ,
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| : 6. Participating personnel and radiological monitoring vans from '
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| 4 . Chattanooga will be prestaged.
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| : 7. Participating personnel from Knoxville and equipment will be prestaged for the JIC.
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| 1
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| .8. Provide training for new CECC personnel I. Drills That Will Be Conducted ,
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| '1. One annual plant radiological monitoring drill,
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| : 2. -One semiannual plant health physics drill.
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| : 3. .One annual radiochemistry drill.
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| r
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| : 4. One quarterly communications drill.
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| : 5. .One annual plant communications drill, f-w ; 6. one annual offsite environs monitoring drill.--
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| ' ''M
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| : 7. One semiannual CECC dose assessment drill.
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| 'l J. Areas-Not to be Demonstrated I
| |
| : 1. Ingestion pathway activities. '
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| 2.- Onsite.and offsite recovery and reentry. "
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| f
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| .1
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| : 3. Fire drill activities. l 0792E'
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| ; > -c ,
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| L-t l, yl-l ': s , -
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| [:
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| b' R nc- <
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| I L J. A '
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| -BROWNS FERRY NUCLEAR PLANT l x 1 1986 REP EXERCISE.
| |
| ?o t:/ ,
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| b;- a
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| ~ ..J '
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| Message for: . Shift Eng1'neer Date:- 9/27/86 :
| |
| ~
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| Time: -15 min I
| |
| ;. -Message: THiS IS A DRILL
| |
| .i The 1985 BFN Rt> EXERCISE-sequence of everits will start shortly.
| |
| Please prefix all' initial, messages and notifications which you make or 1
| |
| * -are responsible for making with the words "THIS IS A DRILL, NO REAL EMERGENCY EXISTS." If any time during this exercise a real emergency
| |
| . occurs,..the site emergency director may terminate the exercise if he '
| |
| ' feels continuation of the exercise may adversely affect the plant response to the real emergency.
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| INITIAL CONDITIONS l
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| !
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| * Unit 1 operating at 1050 MWe. ,
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| a
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| ; -m-
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| . . .-- Unit 2 in a refueling outage.
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| D }]-
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| Initirl Conditions for BFH Unit 3
| |
| * Unit 3 operating'at 10% power - Returning to power af ter a short maintenance outage.
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| '
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| * Unit 3 has been operating for approximately 1 year.
| |
| * Drywell control air compressor 3A' tagged out for maintenance.
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| *: CR0 pump:3A-tagged out for maintenance, s e. . Increasing power after short maintenance outage.
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| l l
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| l Wi \
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| :C/
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| 3 g 1014E u.
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| 1
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| [- ;i-D ,
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| '. - ~
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| k-BROWNS' FERRY NUCLEAR PLANT
| |
| . 1986 REP, EXERCISE
| |
| ! Message.for: Control Room Controller Date: 9/27/86 Time:. 0800 Message:- .THIS IS A DRILL
| |
| . Rod Drop accident has occurred and the reactor has scrammed on main steam high radiation.
| |
| '"A" inboard and outboard main steam isolation valves have failed to fully
| |
| ;N ' L Close.
| |
| : Post treatment offgas radiation high radiation alarm and reactor building high radiation alarms actuate (RA-90-10 and RI-90-21).
| |
| w Verbally supply this information to the operator by indicating.which
| |
| , annunciators are. sounding and by what control room instruments are
| |
| -indicating.
| |
| , 0 -
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| h Sn ; BROWNS FERRY = NUCLEAR PLANT
| |
| ? 1986: REP; EXERCISE i h s-J; u #
| |
| Message'for: Shift Engineer / Unit 3 Operator '' +
| |
| ~
| |
| -Date: 9/27/86 Time: -0801 '
| |
| Message::- THIS IS A DRILL '
| |
| .)
| |
| Scram has been reset,
| |
| '"A" inboard and outboard MSIV's have closed.
| |
| g; - Reactor Building ventalation system isolates and SBGT system starts.
| |
| HPCI fails''on auto start. '
| |
| Maintaining' reactor water level using RCIC. -
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| . , . t BROWNS FERRY NUCLEAR PLANT
| |
| ' f~q 1986-REP EXERCISE- t A[
| |
| -Message for - Control Room. I
| |
| -? .
| |
| Dates: 9/27/86 I
| |
| Time:. 0801 lt
| |
| ~ Message THIS IS A DRILL 1
| |
| Reactor building' isolates but one of the two dampers (FC0 64-14) at the- h s
| |
| air intake fails to close,
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| BROWNS FERRY NUCLEAR PLANT-o, 1986 REP EXERCISE
| |
| *n V 4 -- M/ . Message-for: 'Centrol Room Date: 9/27/86-LTime: 0803 Message:' THIS IS A DRILL An alert should be' declared based on main steamline high radiation. If f this has not occurred or is not in process prompt the Shift Engineer to
| |
| : 4. N'<;- 'make the declaration.-
| |
| * Contingency Message l .
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| 11
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| 4 1 BROWNS FERRY-NUCLEAR PLANT-
| |
| : s. 1 1986-REP EXERCISE
| |
| ;;.' ';7 ~3
| |
| , Q)j i
| |
| * Message.for: Control Room Controller Date: 9/27/86 Time: 0815 Message: THIS IS A DRILL s
| |
| l:
| |
| +.. -
| |
| Be aware that' the stack radiationLmonitors are slowly increasing. The
| |
| . Shift Engineer should notice this trend on the data sheets. -
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| . BROWNS FERRY NUCLEAR PLANT 1986 REP EXERCISE O Message.for:- Shift' Engineer Date: 9/27/86-
| |
| -Time: 0825 Message:- THIS IS A-DRILL-AVO la vicinity of CRD_ modules on elev. 565 on west side of Unit 3 reactor has reported an' air leak. He has-identified the leak to be in a union in the CRD control air supply line, i-O .
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| . i BROWNS FERRY- NUCLEAR PLANT 1986 REP EXERCISE ks [! '
| |
| l Hessage for:- Control Room Controller Date: 9/27/86 I u- ,
| |
| Time: 0830 Message: THIS IS A DRILL
| |
| .s ' ,
| |
| A= maintenance team should have be dispatched to repair air leak on' El'. 565.. If this has not been done or in process, instruct the Shift Engineer to iha so.
| |
| Contingency Message l
| |
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| " BROWNS FERRY NUCLEAR PLANT-1986 REP EXERCISE -I f5'p i;
| |
| 1 Q" - ~ / - ~
| |
| , f -M'essage for:. Maintenance Team on El. 525 s .,.
| |
| - Date: 9/27/86 l q
| |
| Time: 0900. j a
| |
| Message: THIS IS A DRILL
| |
| _ ~ l u
| |
| l d
| |
| ;1 During' repair efforts a union on the. control air supply line completely l
| |
| separates causing.a complete severing of the line, lL h
| |
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| ,, BROWNS FERRY-NUCLEAR PLANT
| |
| . Y5 ; 1986.~ REP EXERCISE
| |
| ; y
| |
| ,xf Message.for:: Shift _ Engineer.
| |
| 'Date: 9/27/86
| |
| > Time:. 0900
| |
| . Message: '-THIS'IS A DRILL i
| |
| -i lThe scram air header depressurtzes and all_ scram valves open.
| |
| i.
| |
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| | |
| 1 I
| |
| BROWS FERRY NUCLEAR PLANT
| |
| .,r 's 1985 REP EXEPCISE
| |
| . ('%J)
| |
| Message fort' 10C Controller l 1
| |
| Date: 9r27/86 Time: 0900 Messass: THIS IS A DRILL l
| |
| l If the control room has not sent a maintenance team to repair the failed damper (FC0 64-14) at the reactor building intake, have the TSC dispatch a team. l Contintency Messaae 1
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| u w- BROWNS FERRY NUCLEAR PLANT l 1986. REP EXERCISE
| |
| -Message for: Control Room Controller
| |
| . ~
| |
| 3 a".. Datei 9/27/86:
| |
| ~ Time: 0910 Message: THIS IS A DRILL 4
| |
| ]
| |
| 1
| |
| ,RA-90-10'and.RI-90-21A' alarm RR-90-1 and RI-90-21A indicating 150 mr/hr.
| |
| +
| |
| -.You should' indicate whicn instruments are alarming and verbally provide the data ~. l lc i-
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| ' BROWNS FERRY NUCLEAR PLANT s
| |
| 1986 REP EXERCISE-
| |
| _.4 s\ '
| |
| o
| |
| ' Message' for:: ' HP Controller r;g. . .
| |
| gi c . g. !Date: ~ 9/27/86-cm '
| |
| : Time :, - 091b l 1,
| |
| l
| |
| }u -Message:. THIS'.IS'A DRILL. i e
| |
| .l 3 ., , ,.
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| Dose' rate Insthe Rx. Bldg.'is indicating 500 mr/hr and increasing.. j l
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| ' CAM 3-RM-90-58 starts to alarm. .!
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| '...- _ _ . _ . . _ _ _ _ 4-...L.____-..._-_.---__.E..--.-------------------
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| ~--------+--J- - - - - I
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| BROWNS FERRY NUCLEAR PLANT !
| |
| es 1986 REP EXERCISE !
| |
| ' t>1 .
| |
| t l(, r i
| |
| Message fort Maintenance Team at Intake Date: 9/27/86 Times. 0930 l t
| |
| i Message THIS IS A DRILL !
| |
| I A damper has failed to isolate (FC0 64-14). I 1
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| ; ,.s 1986 REP EXERCISE !
| |
| t- ;
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| j 3 Et
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| )3. . )
| |
| Message for: HP Controller !
| |
| Date: 9/27/86 .
| |
| l Time: 0945 Message: THIS IS A DRILL ;
| |
| I h N
| |
| ! +
| |
| ARM RI-90-21 goes offscale high at 1000 mr/hr.
| |
| s 4
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| ..-t BROWNS FERRY NUCLEAR PLANT !
| |
| p- 1986 REP EXERCISE '
| |
| i
| |
| .- ( .)
| |
| '# l l Message for: Control Room Controller /TSC Controller l l
| |
| f -
| |
| Date: 9/27/86 i Time: 0950 Message: ,THIS IS A DRILL s
| |
| %- . 4 I k 's
| |
| / An OSC team should have been dispatched to the reactor bldg to locate the r source of the radiation leakage. If this has not been done or in - !
| |
| progress instruct the Site Emergency Director to do so.
| |
| 1 Contince_ncy Message i
| |
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| 1014E l
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| +
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| BROWNS FERRY NUCLEAR PLANT 1986 REP LXERCISE Message for: Shift Engineer Date: 9/27/86 Time: 1000 Message:
| |
| THIS IS A DRILL Drywell control air compressor 3B trips:and will not restart.
| |
| PA-32-70 alarm is actuated. .
| |
| 4 0
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| 5 O .
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| 1014E F
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| BROWNS FERRY NUCLEAR PLANT!
| |
| 7
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| * 1, .
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| ," 1946 REP. EXERCISE -
| |
| u , ,
| |
| LMessage for:l OSC Team '
| |
| y 1 4
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| l 9- .
| |
| 1,; Date:- 9/27/86
| |
| .r p s .4 7 + .
| |
| Time: 1030 >
| |
| d, M LMessage: .THIS IS A DRILL' L
| |
| ..t 1
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| +
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| F A leak is found on valve 85-286.-- j.
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| I BROWNS FERRY NUCLEAR PLANT 1986 REP EXERCISE
| |
| .O Message for: Control Room Controller Date: 9/27/86 Time: 1035 Message: THIS IS A DRILL Instruct the operator to begin to depressurize at normal cooldown rate using RCIC and by manually actuating the ADS relief valves, .
| |
| O .
| |
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| |
| 1014E
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| 2 i
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| BROWNS FERRY NUCLEAR PLANT 1986 REP EXERCISE !
| |
| f ;
| |
| Message for: Shift Engineer i
| |
| .Date: 9/27/86 ,
| |
| )
| |
| Time: 1045 i Message: ,THIS IS A DRILL s
| |
| . Main steem relief valve air accumulator pressure alarms-low - PA-32-31 ,
| |
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| S 1 I
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| 1 BROWNS FERRY NUCLEAR PLANT I 1986 REP EXERCISE !
| |
| l Message for: Shift Engineer Date: 9/27/86 Time: 1100 i i
| |
| Message: ,
| |
| THIS IS A DRILL ;
| |
| 1 l
| |
| ' Power has been lost to all annunciator panels. I o ,
| |
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| |
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| | |
| _g BROWNS FERRY NUCLEAR PLANT )
| |
| .dA 1986 REP EXERCISE If'') '~'
| |
| l Message fori Control Room Controller /TSC Controller A2 Date: 9/27/86 e
| |
| i Time: 1105 :
| |
| Message: THIS IS A ORILL w ..
| |
| As OSC team should be dispatched to determine the reason for.the !
| |
| annunciator failure.
| |
| l Contingency Message E
| |
| .f#
| |
| l
| |
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| |
| 1014E a
| |
| * 1 I[ . _ . . __
| |
| | |
| t 4
| |
| BROWNS FERRY NUCLEAR PLANT 1986 REP EXERCISE i A
| |
| ') Hessage for: Control Room Controller /TSC Controller l i
| |
| Date: 9/27/86 j Time: 1120 I Message: THIS IS A DRILL
| |
| .l 1
| |
| A Site Area Emeroency should*have been declared based on loss of all annunciator. panels for over 15 minutes. If this has not occurred or is '
| |
| y not inprogress instruct the Site Emergency Director to do so. 1 Contingency Message '
| |
| I
| |
| }
| |
| p.
| |
| 1014E
| |
| < + - - y +
| |
| | |
| i-BROWNS FERRY NUCLEAR PLANT l
| |
| , 1986 REP EXERCISE l
| |
| ( !
| |
| Message for: OSC Team Controller Date:- 9/27/86 !
| |
| Time: 1130 i i
| |
| Message: ,THIS IS A DRILL ;
| |
| ,. . \
| |
| Annunciator power loss'is due overheating and shorting to ground of loose l connection between the supply cable from the auto, transfer switch and I the bus in panel circuit breaker board 9-9, cabinet 1.
| |
| l i
| |
| i 6
| |
| 1 1014E 4
| |
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| _ _ _ _ _ _ - - - _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - " - ' - - - ^ ' - - ' - ~ ^ ^ - - - ^ '
| |
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| o-s.t . . . !
| |
| M; * * ~ BROWNS FERRY NUCLEAR PLANT S 4 u, 1986 REP EXERCISE fW ' Message. hor [
| |
| Shift Engineer i
| |
| Q:i
| |
| ..Date: 9/27/A6 l
| |
| .m . , - i
| |
| .;W :-Time: ; 1200:
| |
| L
| |
| ' Message:
| |
| THIS IS A DRILL !
| |
| ,. w ., .
| |
| l CR0 Pump 38'has tripped and will not restart. . -!
| |
| 6 q' . ;
| |
| CRD pressure / flow has.gone to 0.
| |
| * l
| |
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| |
| . BROWNS FERRY NUCLEAR PLANT
| |
| ,. .,c 1986 REP EXERCISE a s
| |
| . Q,) '
| |
| L Message for: OSC Team Date: 9/27/86 Time: 1210 Message: ,THIS IS A ORILL r,
| |
| ~ -
| |
| Failed bus.bar in panel 9-9 has been replaced and power has been restored
| |
| ! to the annunciator panels. .
| |
| a 1
| |
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| |
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| |
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| |
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| |
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| |
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| .c ' BROWNS FERRY NUCLEAR PLANT j
| |
| # ' ., 1986 REP EXERCISE ;
| |
| _s- .
| |
| a- .
| |
| 'j ii(
| |
| . Message for:- OSC-Team ~at Air Intake
| |
| /, 1
| |
| - Date: - 9/27/86 '>
| |
| J
| |
| , Time: 1230~ s 1
| |
| 4
| |
| *-l' ' c :i_
| |
| Messarje: THIS IS A DRILL .
| |
| w.
| |
| 1.-
| |
| 5
| |
| ,L,= . The'second' damper has'been inadvertently opened and cannot be closed. ;
| |
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| * BROWNS FERRV NUCLEAR PLANT c=.- s 1986 REP EXERCISE FU g
| |
| , Message for:' Controller at'Atr. Intake I Date: . 9/27/86
| |
| + Time: 1230
| |
| .)
| |
| . Message: THIS IS A DRILL
| |
| , .c ;
| |
| 4 < ?
| |
| , 4 The maintenance team has inadvertently opened the second damper and it ;
| |
| :cannot be reclosed.- The team should evacuate the area because of'the- j
| |
| %. radiation release. 1 i
| |
| .]
| |
| I
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| :n BROWNS FERRY WUCLEAR PLANT ,
| |
| 'g
| |
| ~~
| |
| f 1986 REP EXERCISE
| |
| 't )
| |
| x._. '
| |
| I Message for: Control Room Controller /TSC Controller j Date: 9/27/86 Times 1235 l
| |
| Message- THIS IS A DRILL
| |
| 'A General Emergency should be declared based on loss of three fission i product barriers. If this has not happened or in process instruct the l Site Emergency Director to do so. 4 l
| |
| 4 I
| |
| Contingency Message i
| |
| [ h i_/
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| BROWNS FERRY NUCLEAR PLANT ;
| |
| 1 1986 REP EXERCISE.
| |
| '/ s) l
| |
| ! \m,/
| |
| Message for: Control Room Controller )
| |
| Date: 9/27/86 i i
| |
| Time: 1300 j 1
| |
| Message: ,THIS IS A DRILL )
| |
| % . j 1
| |
| RCIC turbine trips with Rx pressure at 500 psi. l There is insufficient air in the accumulator to complete i depressurization. Reactor is beginning to repressurize with the MSRVs l lifting on high pressure. );
| |
| i
| |
| ; Reactor water level is decreasing. ;
| |
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| | |
| 6 'y BROWNS FERRY NUCLEAR PLANT 1986 REP EXERCISE Message for: Control Room Controller Date: 9/27/86 Time: 1400 Message:
| |
| THIS IS A DRILL s .
| |
| Indications that the top of the fuel is. uncovered.
| |
| O i
| |
| e O .
| |
| 1014E 4
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| 4
| |
| _6. g h--2,
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| y - .. -. .- -
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| I 4 .1 ;
| |
| i BROWNS FERRY NUCLEAR PLANT 1986 REP EXERCISE t, /,
| |
| Message for: Shift Engineer ;
| |
| i Date: 9/27/86
| |
| ]
| |
| Time: 1500 Message:- THIS IS A DRILL w .
| |
| HPCI has been returned to service and is operating. CRD pump 3B has been reestablished.
| |
| ]
| |
| I i
| |
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| neo
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| h j
| |
| i BROWNS FERRY NUCLEAR PLANT i 1986 REP EXERCISE !
| |
| i
| |
| / -
| |
| (j Message for:. Shift Engineer ;
| |
| l Date: 9/27/86 I i
| |
| Time: 1530 i Message: THIS IS A DRILL :
| |
| i Control air has been reestablished, scram inlet and outlet valves ore ;
| |
| 1 closed. Leak is secured. .
| |
| i 1
| |
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| .- . . . mn s . u . .. . . . TM%. .-;r.: 2 .
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| cm~* n w: g'','a _ ,, , . ,. .
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| :3.4, , c,.Y ', q. .o! ;
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| i - . ' ' . $ ,, Ch !. #p. .,.
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| |
| 2 : p sc .
| |
| :- E M,A
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| : m. ifM
| |
| , m BROWNSFER$0NUCLEARPLANT -
| |
| 49 1986 AEP EXERCISE m
| |
| s--
| |
| 61
| |
| --e ' w . 7, f"w' p, "
| |
| L ,
| |
| w - i)
| |
| 'h i.). .
| |
| -y q *y .=., ,[,Massage'.for:.
| |
| .. 'OSC Team Controller
| |
| : g. o. 2, #
| |
| i ..
| |
| ' Date: '9/27/86
| |
| ; y L)+. '%
| |
| :$[' ., .g Time 1540'
| |
| ;. 4 ;
| |
| + ,.
| |
| 4G' . Nessage: THIS IS A DRILL uy2.m, -
| |
| g.-
| |
| ,e ,
| |
| q ?ft ; iq. 2 A ';', /
| |
| 3..
| |
| 7
| |
| -: The' maintenance crew manages to close one of the air intake dampers'thus 1,l V .
| |
| > terminating.the radiation release.
| |
| i
| |
| ! J I v g
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| ( ,_ < a 1 - jff, a 1
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| - i $ '?. 1
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| $ 4
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| - . '.Liu.,+.=.....-.-.,--.....-....... ' '
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| | |
| i r
| |
| BROWN 5 FERRY NUCLEAR PLANT 1986 REP EXERCISE i
| |
| /s-s-i i
| |
| ~
| |
| l'\
| |
| Message-for:- Control Room Controller !
| |
| L- .Date: 9/27/86 l
| |
| Time: 1545 :
| |
| Mossage: ,THIS IS A DRILL l c.
| |
| Parameters indicate that the' water level in the vessel ts increasing. !
| |
| t p
| |
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| |
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| y.
| |
| BROWNS ~ FERRY NUCLEAR. PLANT d 1986 REP EXERCISE. I
| |
| ;f9
| |
| ''-]P 7g- Message for: Shift Engineer 4 I
| |
| ;7 . - - o' ate: 9/27/86~
| |
| u' -l 1
| |
| -e Time:
| |
| 1 1600 '!
| |
| :4 LMessage: THIS IS A DRILL I A <
| |
| y av c
| |
| :r ,
| |
| p Vessel level is restored. Plant is stable. .
| |
| . 1 i 1 1 :.. 1
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| |
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| 7- 1
| |
| : 4. -
| |
| p;; <
| |
| BROWNS 1 FERRY NUCLEAR PLANT
| |
| -1986 REP; EXERCISE 4
| |
| ' Message:for: , Site. Emergency Director.
| |
| 0 , . Date: 9/27/86
| |
| , -Time: 1605 4-1 Message:' THIS IS'A DRILL
| |
| [ '.
| |
| T
| |
| * Terminate
| |
| * exercise.
| |
| x . .
| |
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| |
| '}.'
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| |
| | |
| . .) .c; , h 7 Wh W [#"lT $'N
| |
| * N f on N b"*r!*"* , .
| |
| Page 1 of 3
| |
| ~~~'
| |
| BFN - IPD o '
| |
| BFN, IP-20 -
| |
| [NRC/C)
| |
| Attachment A
| |
| , , ~R E V ;0 0"0 0 ~l .' .
| |
| Unit No. - 3 '
| |
| Time
| |
| * E Ae < # [O W Parameter Instrument E,a_n eJ. Readint
| |
| { Reactor Level'(Accident) LI 3-62 (inches)
| |
| '(2ero at top of fuel) 9-3 _ /80 LI 3-52 /FO f -
| |
| Drywell Low Pressure (Low range)
| |
| PI 64-39A (Unit 1 only)
| |
| IR-64-159 (blue pen #2) 9-3
| |
| /. 5
| |
| .(-5 to +5 psis) /, /
| |
| E~
| |
| .Drywell Wide Range PI-64-160A 9
| |
| Pressure 9-3 /
| |
| ' IR-64-159 (red pen, #1)
| |
| (0 to 300 psig) /
| |
| Drywell Air Temperature TR 64-52A (OF) (black pen) l- ,
| |
| - 9-3 /.3 O ,
| |
| , Torus Water Temperature TI 64-55A (DF) (Unit 2 only) '~~
| |
| 9-3
| |
| * TR 64-161/162 (blue pen) (OF) 9-3 - /30 1
| |
| 1 %:
| |
| Torus Water Level LI-64-159A (0-20')* 9-3 ~2 IR-64-159 (green pen //3) (0-20')
| |
| g HPCI Flow FIC 73-33 (spm)
| |
| RCIC F, low 9-3 O FIC 71-36A (spm) 9-3 O RHR Loop I Pressure PI 74-51 (psig) 9-3 80 lq RHR Loop I Flow FI 74-50 (spm) 9-3 O RHR Loop II Pressure PI 74-65 (psig) 9-3 86~
| |
| RHR Loop-II Flow FI 74-64 (spm) 9-3 O Core Spray Loop I Press PI 75-20 (psis) 9-3 70 Core Spray Loop I Flow FI 75-21 (spm) ~-
| |
| 9-3 O Core Spray Loop II Press PI 75-48 (psig) 9-3 77 l- r. Core Spray Ldop II Flow FI 75-49 (spm) '
| |
| L,
| |
| . 9-3 O _
| |
| .After completion, hand carry to secretary in hallway outside TSC for distribution. (NRC/C Rpt 81-19]
| |
| L if
| |
| ( Distribution
| |
| * Technical Assessment Manager NRC. Coordinator i Maintenance Manager i . Operations Manager Radiochemical Engineer Health Physics CECC Communicator -
| |
| CECC (Telecopy)
| |
| ,me l _
| |
| 0175p I
| |
| L, aw.ud8' kaEsuw.-
| |
| p
| |
| | |
| \
| |
| 9 .
| |
| r h-REV 0000 ;
| |
| * Pago.2 of 3 ,
| |
| BFN - IP-(NRC/C1 d
| |
| ~ ' '
| |
| Unit No. '
| |
| " BFN, IP-20 : -
| |
| /G AttacpentA.
| |
| ', V Reactor ~Recire Pumps- ~
| |
| ^~
| |
| Time
| |
| * 15 MIM FO W,EN In-service (Y/N) '
| |
| ~
| |
| It yes, Loop flow FI-68-46 9-4 A1 8,g_
| |
| lbs/hr I 106 94 3y FI-68-48 lbs/hr I 106
| |
| < ' 94 gy .
| |
| Reactor Coolant Temp.- TR 68-2 Loop A (DF) red (Valid only if recire. 9-4 6b i' pumps running) Loop B (OF) black 9-4 524 Reactor-Level-(Accident)
| |
| (Zero at inst. zero) LI 3-46A (. inches) 9-5 2T p LI 3-46B (inches). 2. S
| |
| [ Reactor Pressure PI 3-54 (psig)
| |
| L 9-5 90 0
| |
| - PI 3-61 (psis) C PI 3-207 (psis) irn p Wo Reactor Level (Normal) LI 3-53 (inches)
| |
| (Zero at inst. zero) 9-5 II LI 3-60 (inches) 34 LI 3-206 (' inches) T4 i
| |
| Condenser vacuum P/TR 2-2 (in Hg) black
| |
| * 9-6 (1) Torus H2 cone.
| |
| (1) Torus 0 2 cone. H2 R 76-39 or 37(%)(blue pen) 9-54, 55 O 02 R 76-43 or 41(%)(blue pen)
| |
| (1) Drywell H 2 cone. 9-54, 55 - C, 3 %
| |
| (1) Drywell 0 2 cone. H2 R 76-39 or 37(%)(red pen) 9-54, 55 O 02 R 76-43 or 41(%)(red pen) 9-54, 55 i O. 5 % i ;
| |
| (1) are-active.
| |
| HS 76-49 and HS 76-59 must, be checked to determine what rec order pens Other-(specify)
| |
| * 't l
| |
| Eautoment operability - Check the listed equipment-for operability. If less
| |
| ~
| |
| .Boulement than fully operable, explain in REMARKS.
| |
| Operable (Init) Eculement Standby Liquid Control / Operable (Init)
| |
| CRD Pumps. ADS / Relief Vlvs V g Core Spray / 3A ed SBGT u /
| |
| Recire System _ v Control Room
| |
| / /
| |
| RHR (LPCI)- Emer, Press. _
| |
| / CAD-RHR.(CTNT Cooling) /
| |
| /-
| |
| HPCI v
| |
| ~
| |
| Diesels'-(U1 U2) _ /
| |
| RCIC
| |
| /
| |
| Diesels (U3) /
| |
| .EECW-i RHRSW / 500 KV Power
| |
| ' /
| |
| ~
| |
| / i
| |
| ~Feedwater System 161 KV Power /
| |
| s'
| |
| .Condent, ate System 4 KV System / )
| |
| / 480 V System Primary Containment ~
| |
| /
| |
| /
| |
| DC Power /
| |
| After completion, hand carry to secretary in hallway outside TSC forondistributi LDistribution *l
| |
| /
| |
| l Technical Assessment Hanager Maintenance Manager CECC Communicator Health Physics .
| |
| Operations Manager NRC Coordinator Radiochemical Engineer CECC (NRC/C(Telecopy)9)
| |
| Rpt.81-1 0175p m . . <,v,.m:e+4 ". I" botesivs 3
| |
| | |
| ~ .. . - - . . . .. . -
| |
| O f ' .c t o . .
| |
| 8
| |
| ; L
| |
| / '
| |
| .. Paso 3 of 3 BFN - IPD '
| |
| BFN, IP-20 Attachment A REV D 0,0 0
| |
| ^
| |
| (NRC/C)
| |
| ~ . '... ..
| |
| N ' Unit No.
| |
| 3 Time: "/Idiv [OW5]
| |
| SBGTS Total Flow =,(FI-65-50) + (FI-65-71) (SCFM) 9-25 O l .
| |
| 5-
| |
| * Unit 3 has indicators FI-65-50A. FI-65-71A
| |
| ! Drywell Radiation Unit 1 RM-90-272A'(R/hr) 9-54 O
| |
| , Unit 1 RM-90 273A (R/hr) 9-55
| |
| ~
| |
| O Unit 2 .
| |
| RM-90-272A (R/hr) 9-54 O Unit 2 RM-90-273A (R/hr) 9-55 O Unit 3 IW-90-272A (R/hr) 9-54 /. O '
| |
| t Unit 3 RM-90-273A (R/hr). 9-55 /. 4 i Torus Radiation
| |
| , Unit 1 RM-90-272B (R/hr) 9-54 0 -
| |
| 7-~
| |
| Unit 1 RM-90-273B (R/hr) 9-55 u -
| |
| i Unit 2 RM-90-2728 (R/hr) 9-54 o ,
| |
| L: Unit 2 RM-90-273B (R/hr) 9-55 O l- Unit.3 RM-90-272B (R/hr) 9-54 O L
| |
| Unit 3 RM-90-273B (R/hr) 9-55 O
| |
| . . . . Stack Radiation RR-90-147 red pen (Cps)(Unit 1 only) 9-2 / -
| |
| '. RR-90-1478 black pen (Cps)(Unit 1 only) 9-2 5
| |
| \~- - Stack Flow FI-1-90-271 (cfm)(Unit 1 only) 9-53 29 dad
| |
| ! Remarks:
| |
| .] After completion,-hand carry to secretary in hallway outside TSC for 8, : distribution.
| |
| Distribution .
| |
| l~
| |
| ! Technical Assessment Manager '
| |
| E Maintenance Manager Operations Manager .
| |
| - CECC Communicator I .
| |
| NRC Coordinator
| |
| (- Radiochemical Engineer
| |
| / *; 1 Health Physics l ,
| |
| CECC (Telecopy) (NRC/C Rpt.81-191 l
| |
| L ,
| |
| 'b p -
| |
| 0175p Page 8 ^
| |
| . -.ms w.. . . . .g ,
| |
| | |
| l' i' gg g $,51~ O R- T = l M I !d '
| |
| ~
| |
| Page 1 of 3 .
| |
| ~~~'
| |
| BFN - IPD '
| |
| ' " BFN. IP-20 -
| |
| L 't. (NRC/Cl Attachment A
| |
| , '[ -
| |
| "R E V .0 0'0 0 '.''.
| |
| Unit No. 3 Y /M4#.
| |
| Time [Old2/) .
| |
| . ,Paramet eg. Instrument r P a..n e,1,. Reading Reactor
| |
| '(Zero at Level'(Accident) top of fuel) LI 3-62 (inches) 9-3 _/d LI 3-52 /45' c .Drywell Low Pressure PI 64-39A (Unit 1 only) / . '5 (Low range) IR-64-159 (blue pen. #2) 9-3
| |
| (-5 to +5 psis) /, /
| |
| .Drywell Wide Range PI-64-160A
| |
| ~
| |
| Pressure 9 .'
| |
| IR-64-159 (red pen. #1) i .
| |
| Ia (0 to 300 psig) /
| |
| Drywell Air Temperature TR 64-52A (OF) (black pen) 9-3 /30
| |
| . Torus Water Temperature TI 64.-5 5 A ( DF) (Unit 2 only) ~~
| |
| 9-3 <
| |
| l-TR 64-161/162 (blue pen) (OF) 9-3 /30
| |
| .l t
| |
| Torus Water Level LI-64-159A (0-20 ' )- 9-3 '' 2 IR-64-159 (green pen. #3) (0-20')
| |
| ~2 1 u
| |
| HPCI Flow FIC 73-33 (spm) t 9-3 O RCIC Flow FIC 71-36A (spm) 9-3 0 RHR Loop I Pressure PI 74-51 (psig) 9-3 80 RHR Loop I Flow . FI 74-50 (spm) 9-3 O RHR Loop II Pressure PI 74-65 (psig).
| |
| 9-3 P S'~
| |
| 'RHR Loop II Flow FI 74-64.(gpm) ,
| |
| 9-3 O
| |
| . Core Spray Loop I Press PI 75-20 (psig) 9-3 FC _
| |
| .[' Core Spray Loop I Flow FI 75-21 (gpm) _,, O 9-3 i .L Core Spray Loop II Press PI 75-48 (psig) 9-3 '78
| |
| : Core Spray Loop II Flow FI 75-49 (spm) O
| |
| . 9-3 _
| |
| 1_
| |
| .After completion, hand carry to secretary in hallway outside TSC for distribution. (NRC/C Rpt 81-19]
| |
| j ;,
| |
| . Distribution
| |
| * i Technical Assessment Manager
| |
| . Maintenance Manager NRC Coordinator Operatior.s Manager Radiochemical Engineer r] Health Physics CECC Communicator CECC (Telecopy)
| |
| I J 0175p
| |
| - il, ?
| |
| l Page 6 l
| |
| . ., ~.- 4 m ,+ w.. a u- s sew '
| |
| | |
| i . 0.
| |
| 1
| |
| , , q R E V. 0 0 0 0' i Page 2 of 3 j! ' , ,
| |
| ~y .-f ' [NRC/C)
| |
| Unit No. 3 '~'' BFN - IP BFN, IP-20 l
| |
| .l
| |
| .f(_-}
| |
| ', Reactor Recire Pumps In-service (Y/N)
| |
| Time +" lAO WAttachmentA) /090) -
| |
| If yes, Loop flow FI-68-46 9-4 A& - 3 ao lbs/hr I 106 94 1 FI-68-48 lbs/hr I 106 3 . ,, ,
| |
| 1 94 g go )
| |
| Reactor Coolant Temp.- TR 68-2 Loop A (OF) red (Valid only if recire. 9-4 6.5 T pumps' running) Loop B (CF) black i 9-4 5 3 5~ ;
| |
| Reactor (Zero at Level (Accident) LI 3-46A (inches) inst. zero) 9-5 =~9 LI 3-468 (inches) u
| |
| -9 '
| |
| Reactor Pressure .PI 3-54 (psis) 9-5 92o PI 3-61 (psis) 4 PI 3-207 (psig) yzo l
| |
| fro '
| |
| Reactor Level (Normal)< LI 3-53 (inches) i (Zero at inst. zero) LI 3-60 (inches) 9-5 _
| |
| O LI 3-206 (' inches) o o
| |
| a.
| |
| Condenser vacuum P/TR 2-2 (in Hg) black i
| |
| "- 9-6 (1) Torus H 2 cone. _
| |
| : (1) Torus 0 2 conc. H2 R 76-39 or 37(%)(blue pen) 9-54, 55 O i
| |
| (1) Drywell.H 2 conc. 02 R 76-43 or 41(%)(blue pen) 9-54, 55 H2 R 76-39 or 37(%)(red pen) 0 3 fo (l) Drywell 02cone.
| |
| 9-54, 55 O 02 R 76-43 or 41(%)(red pen) l 9-54, 55 _C.3'h (1)are HSactive. 76-49 and HS 76-59 must be checked recorcerto determine pens wha Other (specify).
| |
| s
| |
| , Equipment Operability - Check the listed equipment for. operability. If less Equipment than fully operable, explain in REMARKS.
| |
| Opera,ble (Init) Equipment Standby Liquid Control / Operable (Ini_t1 CRD Pumps 3 4 mi ADS / Relief Vlvs _ /
| |
| Core Spray /
| |
| SBGT .__ /
| |
| Recire System Control Room <
| |
| /- Emer. Press.
| |
| RHR (LFCI)- .
| |
| /
| |
| RHR.(CTNT Cooling) CAD
| |
| / /
| |
| w HPCI Diesels''(U1 U2) _ ,
| |
| N eo
| |
| __ / p
| |
| 'RCIC. Diesels (U3) V EECW v __
| |
| f.* :
| |
| RHRSW /
| |
| v 500 KV Power __ /
| |
| Feedwater System 161 KV Power /
| |
| /
| |
| '. Condensate System 4 KV System /
| |
| / 480 V System Primary Containment 7
| |
| __ / DC Power
| |
| /
| |
| O After completion, hand carry to secretary in hallway outside TSC Distribution ufor on.distrib ti
| |
| [h- Technical Assessment Manager i
| |
| -Maintenance Manager CECC Communicator Health Physics .
| |
| Operations Manager NRC Coordinator Radiochemical Engineer CECC(Teleco$y)9)
| |
| (NRC/C Rpt.8 -1
| |
| .0175p w
| |
| , , s; & . *
| |
| * de d*- #
| |
| Y i e , ____--a. .
| |
| | |
| .a . . . . .
| |
| P.
| |
| f [I C
| |
| * Pago 3'of 3 1 BFN - IPD BFN, IP-20
| |
| ' ' ' Atitachment A 0 0,0 0
| |
| [NRC/C) '.-
| |
| ' R E .V .
| |
| g '
| |
| 3- Y/ enIAv.
| |
| * Unit No. . Time:
| |
| (0f0/)
| |
| SBGTS Total Flow = (FI-65-50) + (FI-65-71) (SCFM) 9-25 20 Unit 3 has indicators FI-65-50A, FI-65-71A
| |
| ~ p '- Drywell Radiation '
| |
| l Unit 1 RM-90-272A (R/hr) 9-54 o Unit 1 RM-90-273A (R/hr) 9-55 o Unit 2 , RM-90-272A (R/hr) 9-54 o
| |
| , Unit 2 RM-90-273A (R/hr) 9-55 o Unit 3 RM-90-272A (R/hr) 9-54 /, o Unit 3 RM-90-273A (R/hr) 9-55 /. 'I Torus Radiation-
| |
| , Unit 1 RM-90-272B (R/hr) 9-54 o r
| |
| Unit 1 RM-90-273B (R/hr) 9-55 c/
| |
| l ' Unit 2 RM-90-272B (R/hr) 9-54 o Unit 2 RM-90-273B (R/hr) 9-55 O Unit 3 RM-90-272B (R/hr) 9-54 O Unit 3 RM-90-273B (R/hr) 9-55 O ,
| |
| Y Stack Radiation RR-90-147 red pen (Cps)(Unit 1 only) 9-2 4-RR-90-1478 black pen (Cps)(Unit 1 only) 9-2 C Stack Flow FI-1-90-271 (cfm)(Unit 1 only) 9-53 20 eo Remarks:
| |
| _g After completion, hand carry to secretary in hallway outside TSC for
| |
| ,. distribution.
| |
| , Di s tributi on . .
| |
| Technical Assessment Manager f Maintenance Manager Operations-Manager .
| |
| - CECC Communicator i C NRC Coordinator Radiochemical Engineer 1 Health Physics .
| |
| 1, -CECC'(Telecopy) (NRC/C Rpt.81-19]
| |
| "( .
| |
| 0175p l
| |
| .. J.
| |
| 2,.,g ;.M,. - . .
| |
| _g''T%
| |
| | |
| g j S- f $ $.y - O R. '7~= / [ rwie) .p
| |
| ~~~'
| |
| BFN - IPD b '
| |
| BFN, IP-20 -
| |
| Yt-Attachment A-
| |
| -[NRC/C) .
| |
| '[ .
| |
| "R E V .0 0'0 0 Unit No. A ,
| |
| Time' l N '*s *'d (Clf/5 Paramotor Instrument Panel Reading Reactor Level (Accident) LI 3-62 (inches) 9-3 / 8 5~
| |
| '(Zero at top of fuel). LI 3-52 / F ar f -
| |
| Drywell Low Pressure (Low range)
| |
| FI 64-39A (Unit 1 only)
| |
| IR-64-159 (blue pen. #2) 9-3
| |
| /.5
| |
| (-5 to +5 psig) . I,f-E. .Drywell Wide Range PI-64-160A 9-3 i Pressure' IR-64-159 (red pen, #1)
| |
| (0 to 300 psig) i Drywell Air Temperature TR.64-52A (OF) (black, pen) 9-3 /30
| |
| . Torus Water Temperature TI 64-55A (DF) (Unit 2 cely) 9-3 -
| |
| TR 64-161/162 (blue pen) (OF) 9-3 /30 Torus Water Level LI-64-15 9A (0-20 ' )- 9-3 *E
| |
| ~A IR-64-159 (green pen #3) (0-20')
| |
| _g HPCI Flow FIC 73-33 (spm) 9-3 O ECIC F. low . FIC 71-36A (spm) 9-3 IZO RHR Loop I Pressure PI 74-51 (psig) 9-3 80' RHR' Loop I Flow FI 74-50 (spm) 9-3 O-RHR Loop II Pressure PI 74-65 (psis) 9-3 7 5'"
| |
| RHR Loop II Flow FI 74-64 (spm) 9-3 6 Core. Spray Loop I Press PI 75-20 (psig) 9-3 _ 70 Core Spray Loop I Flow FI 75-21 (gpm) --
| |
| 9-3 6 Core Spray Loop II Press PI 75-48 (psis) 9-3 77 Core Spray Ldop II Flow FI 75-49 (spm) '
| |
| 9-3
| |
| . _ d2 L,
| |
| After completion, hand carry to secretary in hallway outside TSC for distribution. INRC/C Rpt 81-19]
| |
| 1 g Distribution
| |
| * Technical Assessment Manager NRC Coordinator Maintenance Manager Radiochemical Engineer Operations Manager Health Physics -
| |
| CECC Communicator CECC (Telecopy) 0175p Page 6 '
| |
| 'w
| |
| - - .-aw.< v :,. .a . .. A
| |
| | |
| ^
| |
| ,2 . .. c .
| |
| ~ REV 0000
| |
| . Page 2 of 3 (NRC/C)- "' BFN - IP-D~
| |
| Unit No. d .
| |
| BFN, IP -
| |
| Attachment A-L- Time LV Reactor Rectre Pumps -
| |
| " l5 'deiu (CR ).TE '
| |
| In-service (Y/N)
| |
| If yes, Loop flow FI-68-46 9-4 A,__p_,B o lbs/hr I 106 94 g o FI-68 lbs/hr I 106 94 g. o s Reactor Coolant Temp.- TR 68-2 Loop A (OF) red (7alid only if recire. 9-4 _ 53r
| |
| :pamps running) Loop B (OF) black 1
| |
| - 9-4 _ 537 i
| |
| ; Reactor Level (Accident) LI 3-46A (. inches) \
| |
| (Zero at inst. zero) 9-5 30 LI 3-468 (inches) _
| |
| 3o
| |
| -l Reactor Pressure PI 3-54 (psis) 9-5 990 PI 3-61 (psis) 1 PI 3-207 (psis) 390 i L
| |
| 3 '1o Reactor Level (Normal)- LI 3-53 (inches)
| |
| (Toro at inst. zero) 9-5 /Z l
| |
| LI 3-60 (inches) 4E LI 3-206 (' inches) _
| |
| 4E Condenser vacuum P/TR 2-2 (in Hg) black
| |
| * 9-6 (1) Torus H 2 cone.
| |
| i
| |
| =(1) Torus 0 2 cone. H2 R 76-39 or 37(%)(blue pen) 9-54, 55 _ C L
| |
| (1) Drywell H cone. 02 R 76-43 or 41(%)(blue pen) 9-54, 55 03'7o i
| |
| (1) Drywell 0 22 cone.
| |
| H2 R 76-39 or 37(%)(red pen) 9-54, 55- o 02 R 76-43 or'41(%)(red pen) 9-54, 55 _ O. s '70 i
| |
| [
| |
| (1).are HSactive, 76-49 and HS 76-59 must be checked toerdetermine wha L. .,- pens f Other (specify)
| |
| I
| |
| .Eautement operability - Check the listed equipment for operability.If -
| |
| less J_guipment ~ than fully operable, explain in REMARKS.
| |
| Operable (Init) Eaulement Standby Liquid Control Operable (Init)
| |
| .CRD Pumps ADS / Relief Vivs _
| |
| , . Core Spray tA awt SBGT L Recire System Control Room L
| |
| RiiR (LPCI)~ .
| |
| Emer. Press.
| |
| RHR.(CTMT Cooling) CAD-HPCI' Diesels'-(U1 U2) _.
| |
| RCIC our Diesels (U3) hJL EECW l
| |
| RHRSW 500 KV Power
| |
| ;Feedwater System 161 XV Power l
| |
| . Condensate System 4 KV System
| |
| ' Primary Containment
| |
| _ 480 V System
| |
| ~
| |
| DC Power After Distribution completion,
| |
| _- hand carry to secretary in hallway outside TSC for distribution .
| |
| !' N . Technical Assessment Manager = (
| |
| Maintenance Manager CECC Communicator Health Physics
| |
| = Operations Manager NRC Coordinator. ECC /Teleco
| |
| . . Radiochemical Engineer fNRC/dRpt.8fy 91
| |
| : 0175p u
| |
| ,,%.#y.wA][E" w A
| |
| | |
| ?6s.41- ,
| |
| i 5
| |
| Pago 3 et 3
| |
| ~~~''
| |
| BFN - IPD' BFN. IP-20 -
| |
| Attachment A. !
| |
| ~(NRC/C) R E .V 0 0,0 0,
| |
| , . '.. ' . ', , 1 Unit No. d Time:
| |
| / 5 4 /4/ [d{/5 SBGTS Total F. low =, (FI-65-50) + (FI-65-71) (SCFM) 9-25 20 Unit 3 has indicators FI-65-50A, FI-65-71A y Drywell Radiation *
| |
| : 'o' Unit 1 RM-90-272A (R/hr) 9-54 0
| |
| ., Unit 1 RM-90-273A (R/hr) 9-55 O Unit 2: .
| |
| RM-90-272A (R/hr) 9-54 o Unit 2 RM-90-273A (R/hr) 9-55 C' Unit 3 RM-90-272A (R/hr) 9-54 /. o Unit 3 RM-90-273A (R/hr) 9-55 /. 9 J Torus Radiation
| |
| . Unit 1 RM-90-272B (R/hr) 9-54 0 r
| |
| * Unit-1 Unit 2 RM-90-273B (R/hr) 9-55 0 *
| |
| [ Unit 2 RM-90-272B (R/hr) 9-54 o -
| |
| RM-90-273B (R/hr) 9-55 o Unit 3 RM-90-272B-(R/hr) 9-54 o Unit 3 RM-90-273B (R/hr) 9-55 o
| |
| Stack Radiation RR-90-147 red pen (Cps)(Unit 1 only) 9-2 /. U/O RR-90-147B black pen (Cps)(Unit 1 only) 9-2 /. '7x /o #
| |
| Stack Flow- FI-1-90-271 (cfm)(Unit 1 only) 9-53 l
| |
| - Remarks: '
| |
| 1 i i I
| |
| :1 After completion, hand carry to secretary in hallway outside TSC.for
| |
| .(. distribution.
| |
| Distribution .
| |
| f- Technical Assessment Manager
| |
| 'i Maintenance Manager p Operations Mana$er
| |
| '1 - 'CECC Communicator
| |
| - NRC Coordinator
| |
| ('
| |
| Radiochemical Engineer
| |
| /'"
| |
| Mealth Physics .
| |
| (. CECC (Telecopy) (NRC/C Rpt.81-19]
| |
| 0175p Page 8 -
| |
| 3.. ..
| |
| .:.w u w A L.~ 9.,7 M, i
| |
| | |
| l ie . _
| |
| Ni
| |
| . d.f vo ' Sb 6# - b '
| |
| - - P'8' 1 Of ~ 3 BFN- .IPD
| |
| .BFN,'IP-20 ,
| |
| N
| |
| [NRC/C)-. -
| |
| Attachment A- '~ '
| |
| _, ,, , , "R E V ;0 0"0 0 -
| |
| y Unit No.- ) Time / dr" [d 9Dd. .r)
| |
| PJeameter Instrument ganel, Reading l Reactor Level'(Accident) LI 3-62 (inches) 9-3 /90
| |
| '(Zero at top of fuel) LI 3-52 / 'r o f ~
| |
| Drywell Low Pressure (Low range)
| |
| PI 64-39A (Unit 1 only)
| |
| IR-64-159 (blue pen, #2) 9-3
| |
| /. 3
| |
| {
| |
| (-5 to +5 psig) 1. /
| |
| -I- .Drywell Wide Range PI-64-160A 9-3 l Pressure IR-64-159 (red pen, #1) .
| |
| (0 to 300 psig) i 1
| |
| Drywell Air Temperature TR 64-52A (OF) (black pen) 9-3 /30 ,
| |
| Torus Water Temperature TI 64-55A (OF) (Unit 2 only) 9-3 -
| |
| TR 64-161/162 (blue. pen) (OF) 9-3 73 1
| |
| Torus Water Level LI-64-159A -(0-20' )' 9-3 ~E IR-64-159 (green pen, #3) (0-20')
| |
| J HPCI Flow FIC 73-33 (spm) 9-3 0~
| |
| RCIC F. low FIC 71-36A (spm) 9-3 550 RHR Loop I Pressure PI 74-51 (psis) 9-3 80 RHR Loop I Flow FI 74-50 (spm) 9-3 O RHR Loop II Pressure PI 74-65 (psig) 9-3 8T RHR Loop II Flow . FI 74-64 (spm) 9-3 O 'I Core Spray Loop I Press
| |
| ~
| |
| PI 75-20'(psis) 9-3 70 Core Spray Loop I Flow FI 75-21 (spm) '--
| |
| O 9-3 i Core Spray Loop II Press PI 75-48 (psis) 9-3 7f
| |
| :. C, ore Spray Loop II Flow FI 75-49 (spm) '
| |
| . 9-3 O
| |
| .L After completion,-hand carry to secretary in hallway outside TSC for distribution. (NRC/C Rpt 81-191 1
| |
| -[-
| |
| . ,. . Distribution. '
| |
| Technical Assessment Manager NRC Coordinator Maintenance Manager Operations Manager Radiochemical Engineer Health Physics -
| |
| CECC Communicator CECC (Telecopy) s
| |
| ~ a 0175p e
| |
| g
| |
| ..ss v: 'M -
| |
| | |
| v.w. -
| |
| ' _ g y p _0 0 0' O
| |
| * , , Page 2 of 3 ,
| |
| (WRC/C) .
| |
| BFN - IP' e l Unit'No. -3 .
| |
| BFN,' IP-20 -
| |
| ttachment A
| |
| /$5'
| |
| -Reactor _Recire Pumps- "'
| |
| Time 09dd)- -'
| |
| In-service (Y/N) d If yes. Loop flow. FI-68-46 9-4-A__Q__,B.'o' lbs/hr I 106 9-4 A C FI-68-48 lbs/hr I 106 9-4 B -A Reactor Coolant Temp.-
| |
| TR 68-2 Loop A (OF) red (Valid only if recire. 9-4 53T pumps running) Loop B (OF) black 9-4 _ 535 Reactor-Level (Accident) LI 3-46A (inches)'
| |
| (Tero at inst. zero) 9-5 .35 --
| |
| ~
| |
| LI 3-46B (inches) _ 3 s- ~
| |
| Reactor Pressure PI 3-54 (psis)
| |
| PI 3-61 (psig) 9-5 770 PI 3-207 (psig) 7 90 s t es Reactor Level (Normal) LI 3-53-(inches)
| |
| (Zero at inst, zero) LI-3-60 (inches) 9-5 45 4t f LI 3-206 (~ inches) 45 -
| |
| Condenser vacuum P/TR 2-2 (in Hg) black
| |
| " 9-6 (1). Torus H 2 conc.
| |
| (1) Torus 0 2 cone. H2 R 76-39 or 37(%)(blue pen) 9-54, 55 O (1) Drywell H 2 cone. 02 R 76-43 or 41(%)(blue pen) 9-54, 55 C,3 90 (1) Drywell 0 2 cone. H2 R 76-39 or 37(%)(red pen) 9-54, 55 4 02 R 76-43 or 41(%)(red pen) 9-54, 55 0
| |
| : d. 3 70 (1)are HSactive.76-49 and HS 76-59 must be checked to r erdetermine pens what rec Other (seecifv)
| |
| Eculement Operability - Check the listed-equipment for operability. .If less '
| |
| Eculement than fully operable, explain in REMARKS.
| |
| Operable (Init) Equipment .
| |
| . Standby Liquid Control Operable (Initi_
| |
| CRD Pumps ADS / Relief Vlvs _
| |
| ,, 1 Core Spray 34out SBGT Recire System- Control Room _
| |
| 1RHR-(LPCI) .
| |
| Emer. Press.
| |
| RHR,(CTMT Cooling) CAD HPCI' Diesels *-(U1 U2)
| |
| M LRCIC Diesels (U3) _
| |
| i
| |
| 'RECW-RHRSW 500 KV power Feedwater System. 161 KV Power
| |
| ; Condensate System 4 KV System
| |
| . Primary Containment 480 V System DC Power After Distribution completion,
| |
| _ hand ccery to secretary in hallway outside TSC for distributi ._
| |
| on '
| |
| 9 Technical Assessment Manager
| |
| -Maintenance Manager Operations Manager CECC Communicator NRC Coordinator Health Physics .
| |
| * Radiochemical Engineer CECC (NRC/C(Telecopy)91 Rpt.81-1
| |
| ~0175p
| |
| - :,u n . - 4 w 'O
| |
| | |
| ^
| |
| 4.: 4 o
| |
| f,
| |
| ., PGge 3 of 3-BFN - IPD
| |
| ~~~' '
| |
| EFN, IP-20 - -
| |
| . Attachment A
| |
| [NRC/c)
| |
| RE7 00.00 . .'. ,
| |
| Unit No. 3 Time: / bf". D 90@
| |
| SBGTS Total Flow =,.(FI-65-50) + (FI-65-71) (SCFM) 9-25 20 Unit 3 has indicators FI-65-50A, FI-65-71A g Drywell Radiation *
| |
| :l. Unit 1 RM-90-272A (R/hr) 9-54 0 Unit 1
| |
| . RM-90-273A (R/hr) 9-55 O Unit 2 . RM-90-272A (R/hr) 9-54 O Unit 2 RM-90-273A (R/hr) 9-55 0 Unit 3 RM-90-272A (R/hr) 9-54 /, o Unit 3 RM-90-273A (R/hr) 9-55 /, '/
| |
| Torus Radiation
| |
| . Unit 1- RM-90-272B (R/hr) 9-54 C _
| |
| y
| |
| * Unit 1 RM-90-273B (R/hr) 9-55 O
| |
| * Unit 2.
| |
| [ RM-90-272B (R/hr) 9-54 7_ o .-
| |
| Unit 2 RM-90-273B (R/hr) 9-55 _ _ . _
| |
| (2 Unit 3 RM-90-272B (R/hr) 9-54 '~
| |
| a Unit 3 RM-90-273B (R/hr) 9-55 d Stack Radiation RR-90-147 red pen (Cps)(Unit 1 only) 9-2 2.J X /o #
| |
| RR-90-147B black pen (Cps)(Unit 1 only) 9-2 2. / X /0, #
| |
| Stack Flow FI-1-90-271 (cfm)(Unit 1 only) 9-53 20.oab Remarks:
| |
| ( -
| |
| 'g; After completion, hand carry to secretary in hallway outside TSC for distribution.
| |
| .m .
| |
| e Distribution .
| |
| L -Technical Assessment Manager '
| |
| l' Maintenance Manager Operations Manager f - CECC Communicat.or i L. - , NRC Coordinator Radiochemical Engineer Health Physics ,
| |
| y CECC (Telecopy)- (NRC/C Rpt.81-19]
| |
| L. '
| |
| 0175p Page 8, ,
| |
| ~ *
| |
| .: w w.ta: irs * * '
| |
| | |
| [ [y g f-- / f og pgg, 7 ,g 3
| |
| "*'' BFN - IPD
| |
| '' ' BFN IP-20 -
| |
| 'y.
| |
| INRC/C) Attachment A
| |
| [- -
| |
| "R E V .- 0 0"0 0
| |
| ~" ~
| |
| Unit No. 3 ,,
| |
| Time /
| |
| __ , ke" [@93d) ./
| |
| Paremeter. Instrument flatl Reading Reactor
| |
| '(Zero at Level top of'(Accident) fuel) LI 3-62 (inches) 9-3 /90 LI 3-52 2
| |
| ffo Drywell Low Pressure (Low range) PI 64-39A (Unit 1 only) *
| |
| /. 3
| |
| - XR-64-159 (blue pen #2) 9-3 '
| |
| (-5 to +5 psis) 1. l
| |
| . u. Drywell Wide Range PI-64-160A 9-3
| |
| ~
| |
| * Pressure IR-64-159 (red pen, #1) l .
| |
| (0 to 300 psig) t Drywell' Air Temperature
| |
| . TR 64-52A (OF) (black pen) 9-3 /30
| |
| . Torus Water Temperature ,
| |
| TI 64-55A (DF) (Unit 2 only) 9-3 ~~
| |
| TR 64-161/162 (blue pen) (OF) 9-3 /30
| |
| )
| |
| Torus Water Level 1
| |
| - LI-64-159A-(0-20')' 9-3 ~ I- '
| |
| I2-64-159 (green pen #3) (0-20')
| |
| HPCI Flow FIC 73-33 (spm) 9-3 O RCIC F. low FIC 71-36A (gpm)
| |
| RHR Loop I Pressure
| |
| '9-3 NO PI 74-51 (psig)
| |
| RHR Loop I Flow 9-3 80 FI 74-50 (spr.) 9-3 O RNR Loop II Pressure '
| |
| PI 74-65 (psig)
| |
| RHR Loop II Flow 9-3 8f FI 74-64 (spm) 9-3 #
| |
| Core Spray Loop I Press PI 75-20 (psig)
| |
| Core Spray Loop I Flow 9-3 80 _ }
| |
| FI 75-21 (spm) -
| |
| : 9-3 O !
| |
| Core Spray Loop II Press PI 75-48 (psis) 9-3 78
| |
| ' Core Spray Ldop II Flow FI 75-49 (spm)
| |
| L- . 9-3 O After completion, distribution. hand carry to secretary in hallway outside TSC for (NRC/C Rpt 81-19]
| |
| Distribution _ -
| |
| Technical Assessthent Manager Maintenance Manager NRC Coordinator Operations Manager Radiochemical Engineer CECC Communicator Health Physics -
| |
| CECC (Telecopy)
| |
| ~
| |
| 0175p ,
| |
| .. .. Page 6 1
| |
| ,, J h vt.d...L 'e -
| |
| ' iMb-
| |
| | |
| .wm . ' . ;
| |
| R E V -0 0 0 0 -
| |
| ,, Page 2 of 3 ,
| |
| i
| |
| '(WRC/C) 'y "' BFN - IP-Unit No..
| |
| ~
| |
| J' " BFN, IP-20 -
| |
| /.db foetai Attachment A .
| |
| Reactor'Recirc Pumps ~
| |
| Time
| |
| ; " ~
| |
| In-service (Y/N) d - /
| |
| If yes.. Loop flow 'FI-68-4 94 A o 3 o lbs/hr I 106 94 3.o --
| |
| FI-68-48 lbc/hr I 106 y 94 g ,
| |
| i Reactor Coolant Temp. TR 68-2 Loop A (CF) red v
| |
| i: (Valid only it recire. 9-4 _ 53T pumps running) . Loop B (OF) black 9 _ 53 T ' '
| |
| Reactor (Zero at Level (Accident) LI 3-46A (-inches) inst. zero) 9-5 3f LI 3-468 (inches) 3 s- ;
| |
| Reactor Pressure PI 3-54 (psig)
| |
| PI 3-61 (psig) 9-5 UO l PI 3-207 (psis) Ffo ,
| |
| 2 't o '
| |
| : j. Reactor Level (Normal) LI 3-53.(inches)
| |
| (Zero at inst zero) 9-5 MS '
| |
| J LI 3-60 (inches) 45-LI 3-206 (' inches) 45 !
| |
| Condenser vacuum P/IR 2-2 (in Hg) black
| |
| '* - 9-6 (1) Torus H 2 cone.
| |
| (1) Torus 0 2 cone. H2 R 76-39 or 37(%)(blue pen) 9-54, 55 O (1) Drywell H cone. 02 R 76-43 or 41 N (blue pen) 9-54, 55 C. 3 *7o l
| |
| f (1) Drywell 0 22 cone.
| |
| H2 R~76-39 or 37(%)(red pen) 9-54, 55 O 02 R 76-43 or 41(%)(red pen) 9-54, 55 C. 3 '/o '
| |
| (1);HS 76-49:and HS 76-59 must be checked to determine are 6.ctive.- what recorder pens Other (specify) l s. _.
| |
| Eautoment Operability - Check the listed equipment for operability. If less Eaulement' than fully operable explain . in REMARKS.
| |
| Operable (Init) Equipment
| |
| , Standby Liguld Control Operable (Init)
| |
| CRD Pumps- ADS / Relief Vlvs Core Spray. 3A SBGT
| |
| 'Recire System Control Room _
| |
| RHR (LPCI) .
| |
| , 'Emer. Prese.
| |
| o RdR.(CTMT Cooling) CAD-h' HPCI Diesels'-(U1 U2)
| |
| RCIC our Diesels (U3)
| |
| -EECW RHRSW 500 KV Power p Feedwater System 161 XV Power g~
| |
| Condensate System 4 XV System Primary Containment 480 V System DC Power After completion, hand carry to secretary in hallway outside ISC for Distribution u distrib on.
| |
| ti L ,
| |
| Technical-Assessment Manager
| |
| 'A Maintenance Manager CECC Communicator Health Physics .
| |
| Oprations Manater NRC Coordinator Radiochemical Engineer CECChTeleco$y (NRC/ Rpt.8 - 91 h 0175p r__.
| |
| _....,....d***7 c.. =*
| |
| | |
| Pago 3 of 3
| |
| ~~~'
| |
| BFN - IPD
| |
| ~
| |
| BFN, IP-20 -
| |
| Attachment A .
| |
| (NRC/C) ' R E .V 0 0.0 0 -
| |
| ~''...
| |
| * Unit No. J Time: AP {O 930 . .nf SBGTS Total Flow =, (FI-65-50) + (FI-65-71) (SCFM) 9-25 20 Unit 3 has indicators FI-65-50A, FI-65-71A i Drywell Radiation -
| |
| . Unit 1. RM-9C-272A (R/hr) 9-54 O i-Unit 1 RM-90-273A (R/hr) 9-55 0 Unit 2 .
| |
| RM-90-272A (R/hr) 9-54 . O f Unit 2 Unit 3 RM-90-273A (R/hr)
| |
| RM-90-272A (R/hr) 9-55 9-54 O
| |
| /, o Unit 3 RM-90-273A (R/hr) 9-55 /, 9
| |
| ~f .
| |
| l- L Torus Radiation l: ,
| |
| Unit 1 RM-90-272B (R/hr) 9-54 O
| |
| : l. 7 '
| |
| Unit 1 RM-90-273B (R/hr) 9-55 O '
| |
| ' Unit 2 RM-90-272B (R/hr) 9-54 0 -
| |
| Unit 2 RM-90-273B (R/hr) 9-55 0 Unit 3 RM-90-2728.(R/hr) 9-54 2 / /o Unit 3 RM-90-2738 '(R/hr) 9-55 / v/o !. Stack Radiation RR-90-147 red pen (Cps)(Unit 1 only) 9-2 2. / X /O RR-90-1478 black pen (Cps)(Unit 1 only) 9-2 2.o Y /o #
| |
| Stack Flow FI-1-90-271 (cfm)(Unit 1 only) 9-53 20dod s .
| |
| ' Remarks:
| |
| l l l .
| |
| -1 After completion, hand carry to secretary in hallway outside TSC for
| |
| .(. distribution. ,
| |
| o Distribution- .
| |
| , Technical. Assessment Manager F Y Maintenance Manager Operations Manager i - CECC Communicator i L: NRC Coordinator Radiochemical Engineer Health Physics .
| |
| CECC (Telecopy) (NRC/C Rpt.81-19]
| |
| i l(Q l u 0175p e
| |
| l, Page 8 , ,.
| |
| :.M.xxars:iteh-.. n --:.- 'A
| |
| | |
| m.
| |
| 4
| |
| [ .00' L'/
| |
| jooo /1 [5f of b O/~5 ' .
| |
| Page 1 et 3
| |
| "~~' BFN - IPD BFN, IP-20 -
| |
| A INRC/C) Attachment A-
| |
| '[
| |
| R E V .0 0"0 0 3
| |
| Unit No._ _ Time d P.
| |
| NOOC)
| |
| ' Parameter, Instrument Panel Reading Reactor
| |
| '(Zero at Level'(Accident) top of-fuel) LI 3-62 (inches) 9-3 /90 LI 3-52 /90
| |
| ~Drywell Low Pressure f (Low range)
| |
| PI 64-39A (Unit 1 only)
| |
| IR-64-159 (blue pen, #2)
| |
| /. 5 9-3
| |
| +-
| |
| (-5 to +5 psig) . I, I
| |
| , _ u. ,Drywell Vide Range ' PI-64-160A
| |
| : f. -
| |
| Pressure 9-3 i YR-64-159 (red pen, #1) .
| |
| (O to 300 psig) I Drywell Air Temperature TR 64-52A (OF) (black pen)
| |
| ,. 9-3 /3o
| |
| . Torus Water Temperature TI 64-55A (DF) (Unit 2 only) -
| |
| 9-3 -
| |
| TR 64-161/162 (blue pen) (OF) 9-3 /3 O Torus Vater Level LI-64-159A (0-20')- 9-3 ~d IR-64-159 (green pen #3) (0-20') ,,
| |
| HPCI Flow FIC 73-33 (gpm) 9-3' O RCIC F. low FIC 71-36A (spm) 9-3 TW RHR Loop I Pressure PI 74-51 (psis)
| |
| RHR Loop I Flow 9-3 70 FI 74-50 (gpm) 9-3 O RHR Loop II Pressure PI 74-65 (psis) 9-3 75-RHR Loop II Flow FI 74-64 (spm) ,
| |
| 9-3 O Core. Spray Loop I Press PI 75-20 (psig) 9-3 _ 7/ O '
| |
| ' Core Spray Loop I Flow FI 75-21 (spm) '--
| |
| 9-3 O Core Spray Loop II Press PI 75-48 (psig) 9-3 78 i C, ore Spray Loop II Flow FI 75-49 (spm) '
| |
| . 9-3 6-L. After completion, hand carry to secretary in hallway outside TSC for distribution.- (NRC/C'Rpt 81-19)
| |
| .1
| |
| ( Distribution -
| |
| Technical Assessment Manager Maintenance Manager NRC Coordinator Operations Manager Radiochemical Engineer Health Physics CECC Communicator -
| |
| CECC (Telecopy) 0175p I
| |
| :. ~. ..
| |
| Page 6, ' " _,,i
| |
| .. .-4ihi * *. /. .. 4 - --
| |
| | |
| F '. . .
| |
| nEV 0000-
| |
| - , , Page 2 of 3 ,
| |
| (NRC/C) BFN - IP-
| |
| ~
| |
| ~~~'*' 1
| |
| -Unit No. . BFN IP-20' - I
| |
| [N.
| |
| , , \.);- Reactor Recirc Pumps g Time ok $6.
| |
| Attachment A
| |
| //dar$ i' In-service (Y/N) # }
| |
| ' If.yes,' Loop flow FI-68-46 9-4 A,, g., B_ c3 lbs/hr I 10 6- 94 g.o
| |
| , FI-68-48 lbs/hr I 106 __
| |
| 94- g 4 j Reactor Coolant Temp. TR 68-2 Loop A (OF) red
| |
| -(Valid only if recire. 9-4 _ 53 5~
| |
| , pumps running) Loop B (0F) black 9-4 634 x 3_. -
| |
| Reactor (Zero at Level (Accident) LI 3-46A'(inches)-
| |
| inst. zero) 9-5 3 5" LI 3-46B (inches) 3r Reactre Pressure PI 3-54 (psig) 9-5 7'70 PI 3-61 (psis)
| |
| PI 3-207 (psis) 8 t r>
| |
| x '/ o Reactor Level (Normal) LI 3-53 (inches)
| |
| (2ero at inst. zero) LI 3-60 (inches) 9-5 N
| |
| _ 4 sr LI 3-206 (' inches) 45 Condenser vacuum P/TR 2-2 (in Hg) black
| |
| * 9-6 '
| |
| -(1)' Torus H 2 cone.
| |
| (1) Torus 0 2 conc. H2 R-76-39 or 37(%)(blue pen) 9-54, 55- O (1) Drywell H -conc. 02 R 76-43-or 41(%)(blue pen) 9-54,'55
| |
| _ o,3 %
| |
| 1
| |
| ., '(1) Drywell 0 22 cone. .
| |
| H2 R 76-39 or 37(%)(red pen) 9-54, 55 O I
| |
| 02 R 76-43 or 41(%)(red pen) 9-54, 55
| |
| [ a. 3 'fs -
| |
| e (ll'HS 76-49 are active. and HS'76-59 must be checkedr to determine wh er pens
| |
| 'Other (specify) t l.
| |
| J Eautement Operability - Check the listed equipment for operebility. It less Roulement than fully operable, explain-in REMARKS.
| |
| Operable (Init) Eauipment i
| |
| Standby Liquid Control Operable (Init_},
| |
| 4 l.
| |
| CRD Pumps ADS / Relief Vivs E Core Spray 2 A m/ SBGT _
| |
| Recire System. Control Room ,
| |
| .RHR (LPCI) .
| |
| Emer. Press.
| |
| RHR;(CTMT Cooling) CAD HPCI.
| |
| nur Diesels'-(U1 U2) _
| |
| RCIC Diesels (U3)
| |
| EECW-
| |
| )L RHRSW 500 KV Power a 'Feedwater System 161 KV Power p ,
| |
| Condensate System 4 KV System g Primary containment _
| |
| 480 V System DC Power After completion, hand carry to secretary in hallway outside TSC uforondistrib ti Distribution
| |
| :(,
| |
| c
| |
| ' Technical Assessment Manager Maintenance Manager CECC Communicator Health Physics
| |
| < Operations Manager NRC Coordinator Radiochemical Engineer CECC (NRC/C(Telecopy)9]
| |
| Rpt.81-1 0175p- .
| |
| x .
| |
| ....s,....
| |
| - ,A..r, . I '
| |
| | |
| ^
| |
| ., Page 3 of 3 4
| |
| ~~~'
| |
| BFN - IPD-
| |
| * BFN..IP-20 -
| |
| ,'' Attachment A
| |
| [MRC/C)
| |
| ' . R E .V 0 0,0 ~. ',-.;
| |
| 4 Unit'No. 3 Time: 4 b. [/00d)
| |
| .f SBGTS Total Flow = (FI-65-50).6 (FI-65-71)-(SCFM)' 9-25 20-
| |
| ~
| |
| Unit 3 has indicators FI-65-50A. FI-65-71A I
| |
| Drywell Radiation '
| |
| Unit 1 Unit 1 RM-90-272A (R/hr) 9-54 d RM-90-273A (R/hr) 9-55 o [,,
| |
| Unit 2 ,
| |
| RM-90-272A (R/hr) 9-54 O Unit 2 RM-90-273A (R/hr) 9-55 O Unit 3 RM-90-272A (R/hr) 9-54 /, o l
| |
| Unit 3 RM-90-273A (R/hr) 9-55 /, V l Torus Radiation
| |
| . Unit 1 RM-90-272B (R/hr) 9-54 6- l Unit 1 RM-90-273B (R/hr) 9-55 0
| |
| * 1 Unit 2 RM-90-272B (R/hr) 9-54 o '
| |
| Unit 2 RM-90-273B (R/hr) 9-55 o z Unit 3 RM-90-272B (R/hr) 9-54 s.o K /0 -L l Unit 3 RM-90-273B (R/hr) 9-55 v. o x /o l Stack Radiation RR-90-147 red pen (Cps)(Unit 1 only) 9-2 /. o r /0 4g j RR-90-147B black pen (Cps)(Unit 1 only) 9-2 0,9 y /o l
| |
| Stack Flow FI-1-90-271 (cfm)(Unit 1 only) 9-53 2 0 # 00 Remarks:
| |
| After completion, hand carry to secretary in hallway outside-TSC for
| |
| '.%1 distribution.
| |
| q Distribution .
| |
| Technical Assessment Manager T Maintenance Manager
| |
| , Operations Manager l
| |
| -i - CECC Communicator * '
| |
| .- NRC Coordinator Radiochemical Engineer h1. Health Physics .
| |
| ( CECC (Telecopy) (NRC/C Rpt.81-19]
| |
| L-0175p
| |
| .. Page 8
| |
| .r . .
| |
| .1,h;W4&uMo b., A us -
| |
| | |
| hh $T $t D b bdk Pyr) .
| |
| Page 1 ot 3 t
| |
| ~~~'
| |
| BFN - IPD-L BFN, IP-20 - -
| |
| L f (NRC/Cl '
| |
| Attachment A ,,' ,
| |
| ,,R E V .0 0'0'0- -
| |
| Unit No. ,
| |
| , l'imed e- 6030) :
| |
| Parameter Instrument i ag g_ane}, Reading Reactor
| |
| '(2ero at Level top of(Accident) fuel) LI 3-62 (inches) 9 /89 LI 3-52 /79 4 IDrywell Low Pressure
| |
| - f- (Low range)
| |
| PI 64-39A (Unit 1 only) '
| |
| /.3
| |
| - IR-64-159 (blue pen. #2) 9-3
| |
| (-5 to +5 psig) .
| |
| I, f
| |
| . . .Drywell Wide-Range
| |
| * PI-64-160A Pressure- 9-3 i
| |
| - XR-64-159 (red pen. #1)
| |
| (0 to 300 psig) i Drywell Air Temperature TR 64-52A (0F) (black pen)
| |
| ,,, 9-3 /M -
| |
| . Torus Water Temperature TI 64-55A (DF)-(Unit 2 only) 9-3 ~
| |
| TR 64-161/162 (blue pen) (OF) !
| |
| 9-3 /28 l h l.,
| |
| 4.- Torus Water Level o LI-64-159A (0-20')* 9-3 "' d p XR-64-159 (green pen. #3) (0-20')
| |
| HPChFlow FIC 73-33 (spm)
| |
| I' 9-3 O RCIC F. low FIC 71-36A (spm). 9-3 STO RHR Loop I Pressure PI 74-51 (psis)
| |
| RHR Loop I. Flow 9-3 80 FI 74-50-(spm) 9-3 O RNR Loop II Pressure PI 74-65 (psig)
| |
| RHR Loop'II Flow 9-3 8f I FI 74-64 (spm) 9-3 O-
| |
| [ Core Spray Loop I Press PI 75-20 (psig) 9-3 i' 70 Core Spray Loop I Flow FI 75-21 (spm) '--
| |
| 2 '
| |
| 9-3 0 Core Spray. Loop II Press PI 75-48 (psig) 9-3 72l
| |
| : t. C, ore Spray Loop II Flow.- FI 75-49 (gpm) '
| |
| . 9-3 O L L After completion, hand carry to secrotary in hallway outside ISC for distribution.
| |
| (NRC/C Rpt 81-19]
| |
| . j '..
| |
| 1 p, .
| |
| Distribution
| |
| * lj -Technical Assessment Manager Maintenance Manager NRC Coordinator Operations Manager Radiochemical Sngineer
| |
| .- CT;CC Communicator Health Physics >
| |
| CECC (Telecopy)
| |
| ,M -
| |
| O 0*75p l4. .
| |
| L .
| |
| Page 6, ,,,. &
| |
| ~2 A n:..n -e- '
| |
| ~.
| |
| | |
| ~
| |
| c ; , ,
| |
| U , ,,
| |
| nyy.o000 Page 2 of 3-j r .(NRC/C)
| |
| ~
| |
| ~~''' BFN - IP-Unit No. '
| |
| BFN,.IP '.. '
| |
| i
| |
| [~l
| |
| , L/ -
| |
| -Reactor Recite Pumps -
| |
| g ''Time NA 1.kr"AttachmentA(/0 In-service (Y/N) '
| |
| .i
| |
| " s If yes, Loop flow FI-68-46 9-4 AB lbs/hr I 106 94 3 FI-68-48 lbs/hr I 106 9-4 B _. !
| |
| Reactor Coolant Temp.: TR 68-2 Loop A (OF) red (Valid only if recire. 9-4 _ 5.3 I pumps running) Loop B (OF) black 9-4 _ 5 3 2.
| |
| , Reactor
| |
| .(Zero at Level (Accident) LI 3-46A (inches) in.st. zero) 9-5 35 LI 3-46B (inches) 3r Reactor Pressure PI 3-54 (psis) 9-5 <TD PI 3-61 (psig)_ _
| |
| 1 PI 3-207 (psig) Sto-790 Reactor Level (Normal) LI 3-53-(inches)
| |
| (Zero at inst. zero) LI 3-60 (inches) 9-5 _ W .,
| |
| LI 3-206 (' inches) W Condenser vacuum-
| |
| //% )
| |
| P/TR 2-2 (in Hg) black 9-6 (1) Torus H 2 cone.
| |
| (1) Torus 0 2 cone. H2 R 76-39 or 37(%)(blue pen) 9-54. 55 (1) Drywell H2 cone. 02 R 76-43-or 41(%)(blue pen) 9-54, _55 8 1 H2 R 76-39 or 37(%)(red pen) 0..$ #/g 1 (1) Drywe11~02 cone. 9-54, 55 d 02 R 76-43 or 41(%)(red pen) 9-54, 55 V 0. 3 -fo (1):HS are active. 76-49 and HS 76-59 must be checked recorder to pens determine wh
| |
| ;0ther (specifv) 4 Eautement Operability - Check the listed equipment for operability. If less
| |
| -Eauipment- than' fully operable, explain in REMARKS. i
| |
| ' Standby Liquid Control-Operable (Init) Equipment Operable (Init)
| |
| CRD Pumps ADS / Relief V1vs _
| |
| Core. Spray _
| |
| 3 A m c/ _ SBGT -
| |
| 'Recire System Control Room RHR (LPCI) ,
| |
| Emer. Press.
| |
| RHR,(CTMT Cooling) CAD
| |
| -HPCI Diesels'-(U1 U2) __
| |
| RCIC o d- Diesels (U3) ,
| |
| 'EECW _
| |
| RHRSW- 500 KV Power .
| |
| Feedwater System 161 KV Power
| |
| ., Condensate System 4 KV System Primary Containment 480 V System DC Power O After-completion, hand carry to seccetary in hallway outsidesrTSC
| |
| -Distribution ution for di t ib d Technical. Assessment Manager -
| |
| Maintenance Manarer CECC Communicator Health Physics Operations Manage,r- NRC Coordinator Radiochemical Engineer CECC Teleco (NRC/ Rpt.8 91 0175p
| |
| ., w ,....,- . .d."I*I . ' SN )
| |
| | |
| -w .4 $
| |
| l Page 3 of 3
| |
| -BFN --IPD-
| |
| ^
| |
| BFN, IP-20 '. -
| |
| Attachment A
| |
| ^'
| |
| *REV *
| |
| [NRC/C] -
| |
| 0 0,0 0 .
| |
| * U'n i t No . Time: O30 -
| |
| SBGTS Total Flow m, (FI-65-50) + (FI-65-71) (SCFM) 9-25 20 t Unit 3 has indicators FI-65-50A, FI-65-71A i Drywell Radiation '
| |
| t
| |
| [ Unit 1 RM-90-272A (R/hr) 9-54 O Unit 1 , RM-90-273A (R/hr) 9-55 f> ,
| |
| Unic 2 .
| |
| RM-90-272A (R/hr) 9-54 O Uni: 2 RM-90-273A (R/hr) 9-55 O Unit 3 RM-90-272A (R/hr) 9-54 /. O +
| |
| Unit 3 RM-90-273A (R/hr) 9-55 /,'r
| |
| .l'' .
| |
| O Torus Radiation
| |
| . Unit l' RM-90-272B (R/hr) 9-54 O '
| |
| Unit 1 r RM-90-273B (R/hr) 9-55 O '
| |
| [ Unit 2 RM-90-272B (R/hr) 9-54 0 -
| |
| Unit 2 RM-90-27.3B (R/hr) 9-55 O Unit 3 RM-90-272B (R/hr) 9-54 O
| |
| : 1. Unit 3 RM-90-273B (R/hr) 9-55 0
| |
| t.
| |
| -Stack Radiation RR-90-147 red pen (Cps)(Unit 1 only) 9-2 RR-90-147B black pen (Cps)(Unit 1 only) 9-2 IX/df CY/O
| |
| * f Stack Flow- FI-1-90-271 (cfm)(Unit 1 only) 9-53 1h /26 Remarks:
| |
| 1- ^ ' .
| |
| o
| |
| .j ,
| |
| =
| |
| L{ After. completion, hsnd carry to secretary in hallway outside TSC for distribution.
| |
| .'s .
| |
| , y Distribution .
| |
| l' : Technical Ass 6ssment Manager f Maintenance Manager Operations Manager ..
| |
| '1 - CECC Communicator I i .
| |
| NRC Coordinator
| |
| ' Radiochemical Engineer Health Physics .
| |
| . -CECC (Telecopy) (NRC/C Rpc.81-19]
| |
| f 1-
| |
| ! L -
| |
| l 0175p
| |
| =n .
| |
| Page 8 -
| |
| a; h.., ,
| |
| , A , Ma a." t' .+ 4-W -
| |
| .____.___1_.
| |
| | |
| I gg 7,.- d Mrs ., Page 1 of 3-BFN - IPD
| |
| 'k '
| |
| 'BFN, IP-20 -
| |
| * f.
| |
| l
| |
| .$ ' Attachment A INRC/Cl -
| |
| . 1t E V . 0 0'0 0 ~~'d Unit No.
| |
| , Time 3P h/dD) e Parameter Instrument P.aD,el Reading 1 Reactor
| |
| '(Zero at Level'(Accident) top of fuel) LI 3-62 (inches) 9-3 /92 LI 3-52
| |
| / 't E i
| |
| 'Drywell Low Pressure f- (Low range)
| |
| PI 64-39A (Unit 1 only) '
| |
| _%3 '
| |
| - IR-64-159 (blue pen, #2) 9-3
| |
| (-5 to +5 psig) -
| |
| /. /
| |
| i .Drywell Wide Range PI-64-160A -
| |
| Pressure 9-3 I IR-64-159-(red pen. #1)
| |
| (0 to 300 psig)
| |
| I
| |
| ^
| |
| Drywell Air Temperature TR 64-52A (OF) (black. pen) 9-3 /30 ,
| |
| . f. . Torus Water Temperature TI 64-55A (OF) (Unit 2 only) 9-3 -
| |
| TR 64-161/162 (blue pen) (OF) 9-3 /30 l~
| |
| Torus Vater Level LI-64-159A.(0-20')- 9-3 --3 IR-64 159 (green pen, #3) (0-20')
| |
| 1 '
| |
| l HPCI Flow FIC 73-33 (spm) 9-3 O l ,
| |
| RCIC F. low FIC 71-36A (spm)
| |
| RHR Loop I Pressure 9-3 f50 PI 74-51 (psig) 9-3 80 RHR Loop I Flow FI 74-50 (spm) 9-3 O RHR Loop II Pressure- PI 74-65 (psig) 9-3 _ 8f RHR Loop II-Flow FI 74-64-(spm)
| |
| ,, 9-3 O Core Spray Loop I Press PI 75-20 (psig)
| |
| Core Spray Loop I Flow 9-3 80 FI 75-21 (spm) '--
| |
| 9-3 8 Core Spray Loop II Press PI 75-48 (psig) 9-3 77 t
| |
| C, ore Spray Ldop II Flow. FI 75-49 (spm) '
| |
| . 9-3 &
| |
| L After completion. hand carry to secretary in hallway outside TSC for distribution. (NRC/C Rpt 81-19)
| |
| Distribution '
| |
| Technical Assessment Manager Maintenance. Manager NRC Coordinator Operations Manager Radiochemical Engineer Health Physics '-
| |
| CECC Communicator CECC (Telecopy) 0175p
| |
| 'p -
| |
| nL '
| |
| .m-s?A** ' ' -~ aA
| |
| | |
| .e 7 lu s .
| |
| t L ,
| |
| ggV 000.0
| |
| . \
| |
| ' , ., Paso 2 ef>3 o (NRC/C) BFN - IPA Unit'No. 3 .
| |
| ~~''
| |
| . BFN, IP
| |
| * i 75 -
| |
| 3 ttachment A ~
| |
| Reactor Rocire Pumps Time f".' //GO' l L d, , .
| |
| In-service (Y/N) .d' 4"
| |
| : 1. .If yes. Loop flow' 9-4
| |
| * . FI-68-46 lbs/hr I 106 A.
| |
| 8__ i FI-68-48 94 A.
| |
| lbs/hr I 106 94 g
| |
| -~
| |
| Reactor Coolant Temp.-
| |
| [ (Yalid only if recire. TR 68-2' Loop A (0F) red 9-4 _SM pumps- running) - Loop B (0F) black' 9-4 _ $~/d i ReactorLevelkAccident)LI3-46A(inches).
| |
| (Zero at inst. zero) 9-5 37 LI 3-46B (inches) -
| |
| 57 Reactor Pressure PI 3-54 (psis) 9-5. '7 PI 3-61 (psis) _ 790 '
| |
| PI 3-207-(psig) 79 0
| |
| !- 79 0 L Reactor Level (Normal) LI 3-53 (inches)
| |
| L (Zero at inst. zero) LI 3-60 (inches) 9-5 47 LI 3-206 (' inches) 47 I
| |
| Condenser vacuum
| |
| #{
| |
| P/TR 2-2 (in Hg) black 6
| |
| ' (1) Torus H 2 cone.
| |
| (1) Torus 0 2 cone. H2 R 76-39 or 37(%)(blue pen) 9-54, 55 O (1) Drywell H cone. 02 R 76-43 or 41(%)(blue pen) 54, 55 O. 3 70 (1) Drywell 0 22 cone. H2 R 76-39 or 37(%)(red pen) 9-54, 55 O 02 R 76-43 or 41(%)(red pen) 9-54, 55 A 3 '7o
| |
| '(1)are HS
| |
| .Other (specify)-
| |
| active.76-49 and HS 76-59 must be chacked rto pensdetermine w
| |
| '+
| |
| - r i
| |
| Eautement Ooerability - Check the listed equipment for operability. If less
| |
| : j. Eaulement than fully. operable, explain in REMARKS.
| |
| I' Operable (Init) Equiement Standby Liquid Control Operable (Init)
| |
| CRD' Pumps' ADS / Relief V1vs p Core Spray xA o.A SBGT .
| |
| K Recire System _ , , , Control Room L .RHR (LPCI) ,
| |
| Emer. Press.
| |
| L RHR.(CTMT Cooling) CAD
| |
| ~ HPCI -
| |
| e,uf Diesels'-(U1 U2) 7 LRCIC Diesels (U3)
| |
| EECW _
| |
| RHRSW [ 500 KV Power 161 KV Power a Feedwater System
| |
| . Condensate System.
| |
| 4 KV System Primary Containment 480 V System DC Power After.
| |
| D_istribution completion, hand carry to secretary in hallway outside TSC for distributi n '
| |
| d-., Technical Assessment Manager L
| |
| Maintenance Manager CECC Communicator Health Physics Operations Manager NRC Coord nator
| |
| . Radiochema} cal Engineer CECC (NRC/C(Telecopy)9)
| |
| Rpt.81-1 0175p. .
| |
| M.
| |
| ,,_..,t. <a[*8* . - - MM R
| |
| | |
| Ay, . , .
| |
| Pago 3 of 3 .;
| |
| BFN - IPD BFN. IP-20 -
| |
| Attachment A. 1 (NRC/C)
| |
| *RE7 00,00 ~~.'.
| |
| 4 Unit No. Time: 3 kf" [//dd)/
| |
| : l. SBGTS Total Flow =,(FI-65-50) + (FI-65-71) (SCFM) 9-25 80
| |
| . Unit 3 has indicators FI-65-50A FI-65-71A Drywell Radiation -
| |
| Unit 1 RM-90-272A (R/hr) 9-54 O I Unit 1 RM-90-273A (R/hr) 9-55 0 - I Unit 2 ,
| |
| 'RM-90-272A (R/hr) 9-54 o Unit 2 RM-90-273A (R/hr) 9-55 O l Unit 3
| |
| ~
| |
| : D RM-90-272A (R/hr) 9-54 /, o 1 Unit 3 RM-90-273A (R/hr) 9-55 1, 9 1 .
| |
| L Torus Radiation
| |
| . Unit 1 RM-90-2728 (R/.hr) 9-54 O
| |
| : i. (
| |
| Unit 1 RM-90-273B (R/hr) 9-55 O
| |
| * I
| |
| [ Unit 2' RM-90-272B (R/hr) 9-54 0 '
| |
| Unit 2 RM-90-273B (R/hr) 9-55 O Unit 3 .RM-90-272B (R/hr) 9-54 0 l Unit 3 RM-90-273B (R/hr) 9-55
| |
| ~
| |
| O l
| |
| , Stack Radiation RR-90-147 red pen (Cps)(Unit 1 only) 9-2 df/o f #/03 RR-90-147B black pen (Cps)(Unit 1 only) 9-2 .l Stack Flow- FI-1-90-271 (cfm)(Unit 1 only)' 9-53 oc bob .
| |
| Remarks: l
| |
| ,l After completion, hand _ carry to secretary in hallway outside TSC for
| |
| ' distribution.
| |
| l r Distribution ,
| |
| Technical Assessment-Manager T Maintenance' Manager
| |
| ,. , Operations Manager
| |
| ' -1 - CECC Communicator I
| |
| -NRC Coordinator Radiochemical Engineer b [] . Health Physics l
| |
| !, CECC (Telecopy) (NRC/C Rpt.81-19] '
| |
| l l
| |
| l 219
| |
| 'f-0175p.
| |
| Page 8 .
| |
| .t .. . >
| |
| ~
| |
| *. ,;, M ; M :::.He*$ts k ,s., _ g,,
| |
| | |
| lO ' 7 C p]g gg" ~
| |
| g-0 BFN - IPD
| |
| ' ~~''
| |
| i ,
| |
| 5 '' BFN, IP-20 -
| |
| .h
| |
| : f. '[NRC/C) '
| |
| * Attachment A ,
| |
| ~R E V . 00"o o -
| |
| { -Unit No.
| |
| , ime h/.30) -
| |
| -Parameter Instrument
| |
| ~
| |
| g_antti Eeading Reactor Level (Accident) LI 3-62 (inches) 9-3
| |
| '(Zero at top of fuel) LI 3-52 _ /f2
| |
| /Pa f- Drywell Low Pressure (Low range)
| |
| PI 64-39A (Unit 1 only) '
| |
| /, 3
| |
| - IR-64-159 (blue pen #2) 9-3
| |
| (-5 to +5 psig)
| |
| L.i
| |
| ,Drywell Wide Range PI-64-160A Pressure 9-3 !
| |
| IR-64-159 (red pen. #1)
| |
| (0 to 300 psig) l '
| |
| Drywell Air Temperature TR 64-52A (OF) (black. pen)
| |
| .e 9-3 __ / 5 0 :
| |
| . Torus Water Temperature ,
| |
| TI 64-55A (DF) (Unit 2 only)- 9-3 -
| |
| i TR 64-161/162 (blue pen) (OF) 9-3 /3 d
| |
| -\.. {
| |
| Torus Water Level LI-64-159A (0-20')- 9-3 -2 IR-64-159 (green pen, #3) (0-20') :
| |
| ,, - 7_. :
| |
| HPCI Flow FIC 73-33 (spm) 9-3 O ]
| |
| pi RCIC F. low FIC 71-36A (spm)
| |
| RHR Loop I Pressure 9-3 SST ;
| |
| PI 74-51 (psis) 9-3 80 RHR Loop I Flow FI 74-50 (spm) 9-3 ~O
| |
| 'RHR Loop II Pressure PI 74-65'(psig) 9-3 TT' -
| |
| L RHR Loop II Flow ,
| |
| FI 74-64 (spm) 9-3 O j
| |
| Core Spray Loop I Press PI 75-20 (psis) 9-3 _ 80
| |
| . Core Spray Loop I Flow FI 75-21 (spm) ~~
| |
| 9--3 O Core Spray Loop II Press PI 75-48 (psig) .
| |
| .; Core Spray Loop II Flow 9-3 78 l FI 75-49 (spm) '
| |
| . 9-3 O i t e After completion hand carry to secretary in hallway outside TSC for-distrioution. [NRC/C Rpt 81-19]
| |
| y- (
| |
| Q Distribution ' i Technical ~ Assessment Manager Maintenance Manager MRC Coordinator r Operations Manager Radiochemical Engineer CECC Communicator Health Physics -
| |
| CECC (Telecopy)
| |
| M
| |
| 'I -
| |
| , 0175p e 4h.c es h WWA*-
| |
| | |
| c6 -
| |
| __vyy .: <
| |
| W E *
| |
| .n E Y 0000-Page 2 of-3 4 (NRC/CU
| |
| ']-' BFN - IP-s
| |
| '~''
| |
| ' Unit *Noi:
| |
| BFN .IP-20 Li 7l
| |
| ." 1 ,Att hment A-LU Reactor Recirc Pumps -
| |
| Time ~ bL f' - // < W
| |
| !!''~
| |
| In-service (Y/N) 4- 4, 3
| |
| ?
| |
| If yes, Loop flow FI-68-46 9-4 'A_ s lbs/hr I 106 94 g FI-68-48 lbs/hr I 106 94- g 9 . Reactor Coolant Temp.
| |
| (Yalid only it recire. TR 68-2 Loop A (OF) red 9-4 507 pumps running)- Loop B (OF) black
| |
| ~
| |
| 9-4 __ S O S~
| |
| Reactor
| |
| .(Zero at Level (Accident) LI 3-46A (inchea) inst. zero) 9-5 37 LI 3-46B (inchos)
| |
| E 37 Reactor Pressure PI 3-54 (psig) 9-5 79 PI 3-61 (psig)
| |
| PI 3-207 (psis) -73 o
| |
| - 736 7 L ' Reactor Level (Normal). 'LI 3-53 (inches) 9-5 (Zero at inst zero) LI 3-60 (inches) M7 LI 3-206 (' inches) _
| |
| +7
| |
| _ 4T .
| |
| 1 Condenser vacuum P/TR 2-2 (in Hg) black t 9-6 L' (1) Torus H2 cone.
| |
| l (1) Torus 0 2 cone. H2 R 76-39 or 37(%)(blue pen) 9-54, 55 O
| |
| , (1) Drywell H 02 R 76-43 or 41(%)(blue pen) 9-54, 55 y (1) Drywell 0 2 cone.2 cone.
| |
| H2 R 76-39 or 37(%)(red pen) 9-54, 55
| |
| __ C . W o .
| |
| o v
| |
| 02 R 76-43 or 41(%)(red pen) 9-54, 55 0.3 %
| |
| (1)are HSactive.
| |
| 76-49 and HS 76-59 must be checkedrecorder to determinepens what Other (speelfy) 1, =
| |
| Equipment Operability - Check the listed equipment for operability. If less-Joulement' than fully operable, explain in REMARKS.
| |
| o Operable (Init); Eaulement Standby Liquid Control Operable (Init)
| |
| CRD Pumps ADS / Relief Vivs Core Spray A Aet SBGT L Racire System __,
| |
| Control Room .
| |
| p
| |
| -RHR (LPCI) .
| |
| ,_, Emer. Press, c RHR.(CTMT Cooling)
| |
| _ , _ CAD HPCI Diesels'-(U1 U2) _
| |
| Ls .RCIC rwd Diesels (U3)
| |
| J EECW- .
| |
| ' 1
| |
| - RilRSV - 500 KV Power
| |
| ~
| |
| Feedwater System 161 KV Power
| |
| .: . Condensate System 4 K7 System _
| |
| Primary Containment 480 V System L. DC Power
| |
| " ~
| |
| After completion, hand carry to secretary in hallway outside TSC uforondistrib ti:
| |
| Distribution ~
| |
| i
| |
| .[N Technical Assessment Manager o Maintenance Manarer CECC Communicator Health Physics .
| |
| Operations Manage,r. NRC Coordinator g
| |
| Radiochemical Engineer CECC (NRC/C(Telocopy)91 Rpt.81-1 0175p_ ,
| |
| , , t;
| |
| ;, ,,,. . ..c - .A ..
| |
| | |
| - . - _ _ . . .. - ~ _ - . -
| |
| r ~ * . ,
| |
| s
| |
| , Paso 3 of 3 BFN - IPD
| |
| * BFN IP-20 -
| |
| ."' Attachment A
| |
| ' R E .V ''. '. .
| |
| (NRC/C1 -
| |
| 0 0.0 0
| |
| * Unit No. Time 3 kP hMO ,
| |
| SBGTS Total Flow =, (FI-65-50) + (FI-65-71) (SCFM) 9-25 EO Unit 3 has indicators FI-65-501. FI-65-71A Drywell Radiation -
| |
| Unit 1 R3-90-272A (R/hr) 9-54 (?
| |
| , Unit 1 RM-90-273A (R/hr) 9-55 o Unit 2 ,
| |
| FN-90-272A (R/hr) 9-54 ,
| |
| 6>
| |
| Unit 2 RM-90-273A (R/hr) 9-55 O ;
| |
| Unit 3 RM-90-272A (R/hr) 9-54 1. o Unit 3 RM-90-273A (R/hr) 9-55 t . 't focus Radiation
| |
| , Unit 1 RM-90-2723 (R/hr) 9-Sa O i
| |
| [
| |
| Unit 1 RM-90-273B (R/hr) 9-55 O
| |
| * I Unit 2 RM-90-2728 (R/hr) 9-54 C ,-
| |
| Unit 2 l RM-90-2738 (R/hr) 9-55 O '
| |
| Unit 3 RM-90-272B (R/hr) 9-54 o i Unit 3 Im-90-273B (R/hr) 9-55 0 m
| |
| . Stack Radiation RR-90-147 red pen (Cps)(Unit 1 only) 9-2 3 t /d 3 RR-90-1478 black pen (Cps)(Unit 1 only) 9-2 4 r/d 3 Stack Flow FI-1-90-271 (cfm)(Unit 1 only) 9-53 2 caco l
| |
| { Remarks:
| |
| 4 M ter completion, hand carry to secretary in hallway outside TSC for
| |
| , distribution.
| |
| Distribution .
| |
| ' f' Technical Assessment Manager Maintenance Manager Operations Manager .
| |
| . CECC Communicator
| |
| , 'NRC Coordinator Radiochemical Engineer Mealth Physics .
| |
| y CECC (Telecopy) (NRC/C Rpt.81-19]
| |
| l l ..
| |
| y -
| |
| 0175p Page 8 x a .; , s '.
| |
| | |
| ^
| |
| .l.... tioob Cst et T= 4 fA r .+ / mud . P m 1 .f 3
| |
| ~
| |
| '~~' BFN - IPD bin, IP-20 ..
| |
| ( '
| |
| L P. [4dC/C1 Attachment A Unit No.
| |
| l ~R E V .0 0'0 0 7I.
| |
| Time h /m le
| |
| . @40/)
| |
| Parameter Instrument ganti a Reedine Reactor Levez (Accident) LI 3-62 (inches) 9-3 /92
| |
| '(Zero at top of fuel) LI 3-52 /9 L f -
| |
| Drywell Low Pressure (Low range)
| |
| PI 64-39A (Unit 1 only)
| |
| IR-64-159 (blue pen. #2) 9-3
| |
| /, 3
| |
| (-5 to +5 psis) / ,1
| |
| : 1. .Prywell Wide Range PI-64-160A 9-3 1
| |
| Pressure IR-64-159 (red pen. #1)
| |
| (0 to 300 psig) I Drywell Air Temperature TR 64-52A (OF) (black pen) 9-3 /3C f
| |
| . Torus Vater Temperature TI 64-55A (DF) (Unit 2 only) '
| |
| 9-3 -
| |
| TR 64-161/16: (blue pen) (OF) 9-3 /30 Torus Water Level LI-64-159A (0-20' )- 9-3 ~2 IR-64-159 (green pen, #3) (0-20')
| |
| HPCIFlow FIC 73-33 (gpm) O 9-3 RCIC F. low
| |
| , FIC 71-36A (spm) 9-3 SEO RHR Loop I Pressure PI 74-51 (psis) 9-3 80 RHR Loop I Flow FI 74-50 (gpm) 9-3 0 RHR Loop II Pressure PI 74-65 (psig)
| |
| RHR Loop II Flow 9-3 _8T FI 74-64 (spm) ,,
| |
| 9-3 O_
| |
| Core Spray Loop I Press PI 75-20 (psis)
| |
| ~
| |
| 9-3 8 0 __
| |
| Core Spray Loop I Flow FI 75-21 (spm) --
| |
| 9-3 0 Core Spray Loop II Press PI 75-48 (psig) .
| |
| 9-3 77 Core Spray Ldop II Flow FI 75-49 (spm) '
| |
| . 9-3 O L After completion, hand carry to secretary in hallway outside TSC for distribution. INRC/C Rpt 81-19)
| |
| )f
| |
| ( Distribution
| |
| * Technical Assessment Manager NRC Coordinator Maintenance Manager Operations Manager Radiochemical Engineer Health physics '*
| |
| CECC Communicator CECC (Telecopy) 0175p
| |
| - Page 6.'
| |
| ' ~- -
| |
| ..- a A n.-., . me..u
| |
| | |
| yt y y 0000 '
| |
| Pcte 2 of 3 :
| |
| (NRC/C) "*** BFN - IP-Unit No. '
| |
| * 8FN. IP-20 *
| |
| ~ '
| |
| / Time __44/*.~/,=ete .
| |
| ( Reactor Rectre Pumps g
| |
| -'' AttachmentA)I DJc/ ;
| |
| In-service (Y/N) 7 ;
| |
| If yes. Loop flow FI-68-46 9-4 A 8 lbs/br I 106 94 3 FI-68-48 lbs/hr I 106 g 94 3
| |
| Reactor Coolant Temp. TR 68-2 Loop A (OF) red (Yalid only if recire.
| |
| pumps running) 9-4 4#
| |
| Loop B (OF) black ,
| |
| 9-4 _ I9la [.
| |
| Reactor (Tero at Level (Accident) LI 3-46A (inches) inst. sero) 9-5 37 LI 3-46B (inches) ,
| |
| t7 Reactor Pressure PI 3-54 (psis) 9-5 _ 4 70 PI 3-61 (psis)
| |
| PI 3-207 (psis) __ G 7 o
| |
| _ 97o~~ ,
| |
| Reactor Level (Normal) LI 3-53 (inches)
| |
| (Zero at inst zero) 9-5 /7 !
| |
| LI 3-60 (inches) +7 LI 3-206 (' inches) 47
| |
| * Condenser vacuum P/TR 2-2 (in Hg) black
| |
| * 9-6 i
| |
| (1) Torus H 2 conc. ,
| |
| ! (1) Torus 0 2 conc. H2 R 76-39 or 37(%)(blue pen) 9-54, 55 O l (1) Drywell H conc. 02 R 76-43 or 41(%)(blue pen) 9-54 55 Cr3 ''/o t
| |
| (1) Drywell 0 22 cone. H2 R 76-39 or 37(%)(red pen) 9-54. 55 o 02 R 76-43 or 41(%)(red pen) 9-54 55 _ o. A 7o _
| |
| (1)areHSactive.
| |
| 76-49 and HS 76-59 must be checked order to determine pens what Other (speelfy)
| |
| * l -
| |
| Eculement Operability - Check the listed equipment for operability. If less Roulemen_t_
| |
| than fully operable. explain in REMARKS.
| |
| Operable (Init) Eculement Standby Liquid Control Operable (Init)''
| |
| l CRD Pumps MBout ADS / Relief V1vs _
| |
| ~ Core Spray SBGT -
| |
| Recire System Control Room __
| |
| l RHR (LPCI) .
| |
| Emer. Press. .
| |
| I. RHR.(CTMT Cooling) CAD NPCI e o A-Diesels'-(U1 U2) _
| |
| RCIC Diesels (U3) _
| |
| RECW RHRSW 500 KV Power Feedwater System 161 KV Power Condensate System 4 KV System Primary Containment 480 V System DC Power
| |
| -After completion, hand carry to secretary in hallway outside TSC for distribution Distribution
| |
| * O, Technical. Assessment Hanager CECC Communicator Health Physics ,
| |
| Maintenance Manarer Operations Manage,r NRC Coordinator
| |
| ' Radiochemical Engineer CECC (NRC/C(Telecopy)91 Rpt.81-1 0175p .
| |
| .....,.f. <Ad*I" 5ib
| |
| | |
| ~~-
| |
| f, ,
| |
| Page 3 of 3 SFN - IPD BFN. IP-20 -
| |
| ~ * '
| |
| ., Attachment A (NaC/C)
| |
| REY 00.'00 .
| |
| ' Unit No. 3 Time: N bt*, ) mew. (/fC};
| |
| SBGTS Total Flow =,(FI-65-50) + (FI-65-71) (SCFM) 9-25 20 Unit 3 has indits. tors FI-65-50A FI-65-71A
| |
| * Drywell Radiation
| |
| * Unit 1 RM-90-272A (R/he) 9-54 O
| |
| _ Unit 1 RM-90-273A (R/ht) 9-55 o Unit 2 , RM-90-272A (R/hrt 9-54 e Unit 2 RM-90-273A (It/hr) 9-55 0 Unit 3 RM-90 212A (R/hr) 9-54 Ao Unit 3 RM-90-273A (R/ht-) 9-55 /, 4 Torus Radiation
| |
| , Unit 1 RM-90-2726 (R/ht) 9-54 O r
| |
| Unit 1 RM-90-273D (R/hr) 9-55 O '
| |
| [ Unit 2 RM-90-2723 (R/hr) 9-54 0 ,-
| |
| Unit 2 RM-90-2738 (R/h.r; 9-55 O Unit 3 RM-90-272B (R/he) 9-54 o Unit 3 RM-90-273B (R/hr) 9-55 O Stack Radiation RR-90-147 toc pen (Cps)(Unit 1 only) 9-2 .5 #/8 RR-90-14?B blu.h pen (Cps)(Unit 1 only) 9-2 4Y/O' Stack Flow FI-1-90-271 (cfra)(Unit 1 only) 9-53 Ecpeo Remarks: ,
| |
| After completion, hand carry to secretary in hallway outside TSC for
| |
| , distribution.
| |
| Distribution .
| |
| fJ Technical A:;sessment Manager '
| |
| Maintenance Manager Operations Manager ,,
| |
| f . CECC Communicator L NRC Coordinator Radiochemical Engineer
| |
| .] Health Physics ,
| |
| ly CECC (Telecopy) [NRC/C Rpt.81-19)
| |
| L 0175p Page 8 , ,,.,
| |
| . A.ut.r,ucA. *.: .. a.w., 2msiis
| |
| | |
| g h [S[ CE b MN Page 1 et 3
| |
| "' SFN - IPD -
| |
| j ,
| |
| N ' BFN IP-20 -
| |
| I t. Attachment A
| |
| ~
| |
| INRC/C1
| |
| , '[ ,
| |
| . ~R E V c0 0'0 0 ~.-' ' .
| |
| Unit No.
| |
| ; - Time h dP" hd,hlp )
| |
| t Parameter Instrument i e Z a.g.e.l. Readint i
| |
| Reactor
| |
| '(Zero at Level top of(Accident) fuel) LI 3-62 (inches) 9-3 _ /90
| |
| [ LI 3-52
| |
| /90 Drywell Low pressure P1 64-39A (Unit 1 only)
| |
| (Low range)
| |
| /, 3 IR-64-159 (blue pen, #2)- 9-3
| |
| (-5 to +5 psig) II
| |
| : l. I.. Drywell Wide Range PI-64-1601 Pressure 9-3 1 IR-64-159 (red pen. #1)
| |
| (0 to 300 psig)
| |
| . l- I i Drywell Air Temperature TR 64-52A (OF) (black pen) m- 9-3 /30
| |
| . Torus Water Temperature TI 64-55A (OF) (Unit 2 only) 9-3 **
| |
| TR 64-161/162 (blue pen) (OF) 9-3 /3 o l k Torus Water Level LI-64-159A (0-20')'
| |
| % 9-3 -2 l IR-64-159 (green pen, #3) (0-20')
| |
| HPCkFlow FIC 73-33 (spm) 9-3 O RCIC F. low FIC 71-36A (spm) 9-3 f5'O RHR Loop I Pressure PI 74-51 (psis)
| |
| RHR Loop I Flow 9-3 /I, f FI 74-50 (spm) 9-3 20,000 RHR Loop II Pressure PI 74-65 (psis)
| |
| RHR Loop II Flow 9-3 75' FI 74-64 (spm) ,
| |
| 9-3 6 Core Spray' Loop I Press PI 75-20 (psig)
| |
| Core Spray Loop I Flow 9-3 80 FI 75-21 (spm) -'
| |
| 9-3 __
| |
| O Core Spray Loop II Press PI 75-48 (psig)
| |
| Core Spray Loop II Flow 9-3 _ 78 FI 75-49 (spm) '
| |
| . 9-3 0 L .,
| |
| After completion, hand carry to secretary in hallway outside TSC for distribution.
| |
| l' INRC/C Rpt 81-19) y.
| |
| \
| |
| [, Distribution
| |
| * Technical Assessr:mnt Manager
| |
| { Maintenance Manager NRC Coordinator i
| |
| Operations Manager Radiochemical Engineer CECC Communicator Health Physics '-
| |
| CECC (Telecopy) 0175p
| |
| .L *
| |
| ..- Page 6
| |
| ._ ..c A<.< s . 4
| |
| ____----__--__-_-______--_______.________--_________--___~-___-__-
| |
| ~ . M ._ _ _ _
| |
| | |
| ,-? ' . '
| |
| REV 0000
| |
| * , , Page 2 of 3 .
| |
| (WRC/C)- 3 ~' 8FN - IP-Unit No. J BFN, IP-20
| |
| (^' Reactor Recire Pumps Time M I M Attachment A
| |
| /A& 3 td
| |
| * V) In-service (Y/N)
| |
| ~
| |
| {
| |
| If yes, Loop flow FI-68-46 9-4 A__ B lbs/hr I 106 94 t_
| |
| FI-68-48 lbs/hr I 106 i 94 g-Reactor Coolant Temp. TR 68-2 Loop A (OF) red (Valid only it recire.
| |
| pumps running) 9-4 /82 I Loop 8 (0F1 blacr.
| |
| 9-4 _ /F O teactor (2ero atLevel inst. (Accident) zero) LI 3-46A (inches) 7-5 JT t
| |
| LI 3-46B (inches) 3 ?F L
| |
| t Reactor Pressure PI 3-54 (psis) i 9-5 __ 570 PI 3-61 (psis) i PI 3-207 (psis) S30_ >
| |
| 5 '/ O_ ;
| |
| ' Reactor Level (Normal) LI 3-53 (inches)
| |
| (Zero at inst. zero) 95 45" l
| |
| LI 3 60 (inches) M
| |
| ! LI 3-206 (' inches) __
| |
| #r i
| |
| Condenter vacuum P/TR 2-2 (in Hg) black
| |
| * 9-6 i (1) Torus H 2 conc. i (1) Torus 0 2 cone. H2 R 76-39 or 37(%)(blue pen) 9-54, 55 C (1) Drywell H cone. 02 R 76-43 or 41(%)(blue pen) 9-54, 55 - o,3 Fu (1) Drywell 0 22 conc. H2 R 76-39 or 37(%)(red pen) 9-54, 55 !
| |
| i i
| |
| O (3)are HSactive.
| |
| 02 R 76-43 or 41(%)(red pen) 76-49 and HS 76-59 must be checkedr to 9-54, 55 determine wha er pens O
| |
| 0, f %
| |
| j Other (speelfy) !
| |
| i l
| |
| ~
| |
| Equipment Operability - Check the listed equipment for operability.If less Eaulement_ than fully operable, explain in REMARKS. 1 Operable (Init) Eaulement Standby Liquid Control Operable (Init) ;
| |
| CRD Pumps ADS / Relief Vivs Core Spray o.uk SBGT !
| |
| i Recire System Control Room l
| |
| t RHR (LPCI) .
| |
| Emer. Press. ;
| |
| RHR.(CTMT Cooling)
| |
| CAD
| |
| !. HPCI. Diesels'-(U1 U2) l RCIC M Diesels (U3) _
| |
| i EECW RHRSW 500 KV Power feedwater System 161 KV Power Condensate System 4 KV System Primary containment i 480 V System l
| |
| DC Power After completion, hand carry to secretary in hallway outside TSC for distributio Distribution CN n
| |
| * V Technical Assessment Hanager Maintenance Manar,er CECC Communicator Health Physics .
| |
| Operations Manater NRC Coordinator ECC
| |
| - Radiochemical Engineer NRC/hTeleco$y)9)
| |
| Rpt.8 1 0175p .
| |
| ._...,..-,L*s''L m>M -
| |
| | |
| . . - o
| |
| )
| |
| ., Page 3 of 3 i
| |
| ~~~' '
| |
| BFN - IPD l BFN, IP-20 *-
| |
| Attac!'.mont A i
| |
| [WRC/C)
| |
| ' REY 0 0,0 0 -')
| |
| .1 3 W/r Unit No. Time: CAae) l SBGIS Total Flow =,(FI-65-50) + (FI-65-71) (SCFM) 9-25 20 {
| |
| Unit 3 has indicators FI-65-50A, FI-65-71A !
| |
| Drywell Radiation
| |
| * Unit 1 RN-90-272A (R/hr) 9-54 C
| |
| _ Unit 1 RM-90-273A (R/hr) 9-55 O Unit 2 .
| |
| RN-90-272A (R/hr) 9-54 o Unit 2 RM-90-273A (R/hr) 9-55 (>
| |
| Unit 3 RN-90-272A (R/hr) 9-54 /, D J
| |
| 1 l Unit 3 RM-90-273A (R/hr) 9-55 L9 J
| |
| \
| |
| -Torus Radiation !
| |
| , Unit 1 RM-90-2728 (P/hr) 9-54 O I
| |
| [
| |
| Unit 1 RM-90-2738 (R/hr) 9-55 O
| |
| * 1 Unit 2 RM-90-272B (R/hr) 9-54 r> -
| |
| Unit 2 RM-90-273B (R/hr) 9-55 ,,_ O ;
| |
| > Unit 3 RM-90-272B (R/hr) 9-54 0 l Unit 3 RM-90-273B (R/hr) 9-55 O
| |
| : s. Stack Radiation RR-90-147 red pen (Cps)(Unit 1 only) 9-2 Zl/d RR-90-147B black pen (Cps)(Unit 1 only) 9-2 ,,, 3 )(/() .3 Stack Flow FI-1-90-271 (cfa)(Unit 1 only) 9-53 pg,06d Remarks:
| |
| ] After completion, hand carry to secretary in hallway outside TSC for
| |
| ' v,
| |
| , distribution.
| |
| Distribution .
| |
| l Technical Assessment Manager
| |
| * I f Maintenance Manager
| |
| , Operations Manager .
| |
| l 1 - CECC Communicator ?
| |
| , NRC Coordinator Radiochemical Engineer l
| |
| Health Physics l
| |
| y CECC (Telecopy) (NRC/C Rpt.81-19) 1 L YE M
| |
| ~~'
| |
| Paga 8
| |
| ',ik.
| |
| l
| |
| : 2. a . w e d d:-.. _' -
| |
| | |
| 73ook f s.r og D Shr + Imm
| |
| }''' , Page 1 of 3 ,
| |
| ~~'' BFN - IPD BFN, IP-20 -
| |
| '3 (NRC/C1 '
| |
| Attachment A
| |
| , [ "R E V .0 0'O O ~,-' ' .. ,
| |
| Unit No. 3 Time b . M ,b h3C/) r h,tameter Ins trumertt. M P.ending f.eactor
| |
| '(Zero at Level top of(Accident) fuel) LI 3-62 (inches) 9-3 __/IT LI 3-52
| |
| ,,,43 5 Drywell Low Pressure PI 64-39A (Unit 1 only) '
| |
| (Low range) IR-64-159 (blue pen, #2) /-3 9-3
| |
| (-5 to +5 psig) til
| |
| .Drywell Wide Range PI-64-160A Pressure 9-3 l
| |
| ~ TR-64-159 (red pen, #1)
| |
| (0 to 300 psig) l Drywell Air Temperature TR 64-52A (OF) (black pen) 9-3 /30 f . Torus Vater Temperature TI 64-55A (DF) (Unit 2 only) 9-3 ~
| |
| TR 64-161/162 (blue pen) (OF) 9-3 /3 0 l Torus Water Level 'LI-64-159A (0-20')- 9-3 ~2 IR-64-159 (green pen, #3) (0-20')
| |
| HPCI Flow FIC 73-33 (gpm) 9-3 O RCIC Flow FIC 71-36A (spm) 9-3 RHR Loop I Preesure PI 74-51 (psig)
| |
| RHR Loop I Flow 9-3 /40 FI 74-50 (spm) 9-3 2A##O-RHR Loop II Pressure PI 74-65 (psig)
| |
| RHR Loop II Flow FI 74-64 (spm) 9-3 8(
| |
| 9-3 O Core Spray Loop I Press PI 75-20 (psig) 9-3 %D Core Spray Loop I Flow FI 75-21 (gpm) ~--
| |
| 9-3 __ O Core Spray Loop II Press PI 75-48 (psig) 93 s Core Spray Loop II Flow 78 FI 75-49 (spm) '
| |
| . 9-3 O L.
| |
| After distribution. completion, hand carry to secretary in hallway outside TSC for (NRC/C Rpt 81-191 I
| |
| f Distribution '
| |
| Technical Assessment Manager Maintenance Manager NRC Coordinator Operations Manager Radiochemical Engineer CECC Communicator Health Physics '*
| |
| CECC (Telecopy)
| |
| , I_
| |
| 017;p .
| |
| - l,, . ..
| |
| ...~ ..
| |
| Page 6
| |
| -a u.a ... .., ,,, g ,
| |
| | |
| *o,- . ,- - .
| |
| REV .0 0 0 0 i
| |
| , , Page 2 of 3 '
| |
| (NRC/Cl 3 "' BFN - IP- l Unit So+ _ J
| |
| " BFN IP-20 -
| |
| . (m Reactor Recire Pumps Time Skr*%.'v Attachment f /l cl/ A V )- In-service (Y/N) t) ~ ''
| |
| i If yes, Loop flow FI-68-46 9-4 A. 8 lbs/hr I 106 94 3 FI-68-48 lbs/hr I 106 9-4 5..
| |
| Reactor Coolant Temp. TR 68-2 Loop A (OF) red E (Valid only if recire. 9-4 [67 j pumps running) Loop 3 (0F) black 9-4 _ d, F !
| |
| Reactor (Zero at Level (Accident) LI 3-461 (inches) inst. zero) 9-5 Jo 4
| |
| LI 3-46B (inches) -
| |
| Io Reactor Pressure PI 3-54 (psis) 9-5 $#D PI 3-61 (psig) l PI 3-207 (psig) Cao 4 Sao
| |
| )
| |
| Reactor Level (Normal) LI 3-53 (inches)
| |
| (Zero at inst. zc o) LI 3-60 (inchest 9-5 40 LI 3-206 (' inches) &
| |
| +O -
| |
| 3 Condenser vacuum- P/TR 2-2 (in Hg) black
| |
| * 9-6 I l
| |
| (1) Torus H 2 cone.
| |
| (1) Torus 0 2 conc. H2 R 76-39 or 37(%)(blue pen) 9-54, 55 8 (1) Drywell H cone. 02 R 76-43 or 41(%)(blue pen) 9-54, 55 O. 3 '7o )
| |
| (1) Drywell 0 22 cone. H2 R 76-39 or 37(%)(red pen) 9-54, SL o 1 02 R 76-43 or 41(%)(red pen) 9-54, 55 _ O< 3 '70 (1) are HSactive.76-49 and HS 76-59 must be checkedrecorder to determine pens that Other (speelfy)
| |
| Eautement operability - Check the listed equipment for operability. If less
| |
| ~
| |
| Eculement than fully operable, explain in REMARKS.
| |
| operable (Init) Eaulement Standby Liquid Control Operable (Init_)
| |
| CRD Pumps ADS / Relief Vivs Core Spray %), ~
| |
| SBGT Recire System _
| |
| ~
| |
| Control Room RHR (LPCI) .
| |
| Emer. Press.
| |
| RHR,(CTNT Cooling) CAD HPCI Diesels'-(U1 U2)
| |
| RCIC ml Diesels (U3)
| |
| \ EECW exdr ; _i
| |
| ) RHRSW 500 KV Power Feedwater System 161 KV Power
| |
| . Condensate System 4 KV System Primtry Containment 480 V System DC Power s After completion, hand carry to secretary in hallway outside TSC for distributi Distribution. on.
| |
| Technical Assessment Manager Maintenance Manager CECC Communicator Health Physics .
| |
| Operations Manager NRC Coordinator
| |
| . Raolochemical Engineer CECC (NRC/C(Telecopy)9]
| |
| Rpt.81-1 0175p
| |
| ~~
| |
| ,( .s... .
| |
| : i. ANI" . .~drM
| |
| | |
| ~
| |
| i 4
| |
| 4 * ',
| |
| Page 3 of 3 I BFN - IFD J BFN. IP-20 -
| |
| ' Attachment A !
| |
| R E .V 0 0,0 0 (NRC/C) .-
| |
| . )
| |
| .i
| |
| * Unit No. Time: be Adv h30/) .e
| |
| )
| |
| )
| |
| SBGTS Total Flow = (FI-65-50) + (FI-65-71) (SCFM) 9-25 80 Unit 3 has indicators FI-65-50A, FI-65-71A -)
| |
| Drywell Radiation -
| |
| Unit 1 RM-90-272A (R/hr) 9-54 0
| |
| _ Unit 1 RM-90-273A (R/hr) 9-55 Cd Unit 2 .
| |
| RM-90-272A (R/hr) 9-54 o I f Unit 2 Unit 3 RM-90-273A (R/hr)
| |
| IW-90-272A (R/hr) 9-55 9-54 /o O l J
| |
| Unit 3 RM-90-273A (R/hr) 9-55 _ /. ? I Torus Radiation
| |
| . Unit 1 RM-90-272B (R/hr) 9-54 O l r
| |
| * Unit 1 RM-90-2738 (R/hr) 9-55 0
| |
| * i
| |
| [ Unit 2 RM-90-272B (R/hr) 9-54 o .-
| |
| Unit 2 RM-90-273B (R/hr) 9-55 0 Unit 3 RM-90-272B (R/hr) 9-54 4, oho - E 1 Unit 3 RM-90-273B (R/hr) 9-59 c,o co 3-1 3
| |
| Stack Radiation RR-90-147 red pen (Cps)(Unit 1 only) 9-2 21/6 I RR-90-147B black pen (Cps)(Unit 1 only) 9-2 3 Y/d 3 l Stack Flow FI-1-90-271 (cfm)(Unit 1 only) 9-53 2 0 /x D l Remarks:
| |
| l After completion, hand carry to secretary in hallway outside TSC for
| |
| { distribution.
| |
| o Distribution .
| |
| Technical Assessment Manager ll' Maintenance Manager Operations Manager 1 . CECC Communicator NRC Coordinator Radiochemical Engineer
| |
| {
| |
| ] Mealth Physics .
| |
| . l 8., CECC (Telecopy) (NRC/C Rpt.81-19]
| |
| (
| |
| ===
| |
| 0175p Page 8
| |
| ,a w m .:.te:bwk..r. ---a.
| |
| | |
| ~''
| |
| i T* g3o h ds r a 7 '= 5 A r f 3 ,
| |
| ,,,e 1 of ,
| |
| ~
| |
| ~~'' SFN - IPD f '
| |
| * BFN, IP-20 -
| |
| : t. twic/C1 '
| |
| Attachment A "R E V .0 0'0 0 . i Unit No.
| |
| ime h3M ) "
| |
| Parameter Instrument :
| |
| E3.n.e}, Readine Reactor Level'(Accident) LI 3-62 (inches)
| |
| '(Zero at top of fuel) LI 3-52 9-3 U l 98 Drywell Low Pressure PI 64-39A (Unit 1 only) '
| |
| (Low range) /, I IR-64-159 (blue pen. #2) i 9-3
| |
| (-5 to +5 psis) . I ,1 i
| |
| E. .Drywell Wide Range PI-64-160A 9-3 Pressure IR-64-159 (red pen #1) 1 (0 to 300 psig) {
| |
| 1 Drywell Air Temperature TR 64-52A (OF) (black pen)
| |
| ' 9-3 /3f
| |
| : f. . Torus Vater Temperature TI 64-55A (OF) (Unit 2 only) i 9-3 - -
| |
| TR 64-161/162 (blue pen) (OF) 9-3 /Y O Torus Water Level LI-64-159A (0-20 ')- ~5 i
| |
| 9-3 IR-64-159 (green pen. #3) (0-20')
| |
| HPCI Flow FIC 73-33 (spm) 9-3 O RCIC Flow FIC 71-36A (spm) 9-3 O RHR Loop I Pressure PI 74-51 (psig)
| |
| RHR Loop I Flow 9-3 /40 FI 74-50 (spm) 9-3 20 0FD RHR Loop II Pressure '
| |
| '8f PI 74-65 (psis) 9-3 '
| |
| RHR Loop II Flow FI 74-64 (gpm) ,
| |
| 9-3 6 Core Spray Loop I Press PI 75-20 (psig)
| |
| Core Spray Loop I Flow 9-3 _fO FI 75-21 (spm)
| |
| O 9-3 -
| |
| Core Spray Loop II Press PI 75-48 (psig)
| |
| C, ore Spray Loop II Flow 9-3 _ 78 FI 75-49 (spm) '
| |
| . 9-3 6 L
| |
| After completion, hand carry to secretary in hallway outside TSC for _
| |
| distribution. (NRC/C Rpt 81-19]- I Distribution
| |
| * l Technical Assessment Manager Maintenance Manager NRC Coordinator Radiochemical Engineer 1- Operations Manager l Health Physics -
| |
| {- CECC Communicator CECC (Telecopy) 0175p
| |
| -I gt
| |
| ...~ Page 6.* 'a-
| |
| .. - a w n . a < ww -
| |
| | |
| q
| |
| .. o' 1 j, REV 0000 Pete 2 of 3 (NRC/C) "' BFN - IP- 1
| |
| } Unit No. BFN, IP-20
| |
| .' J Att3chment A i
| |
| ) Reactor Recire Pumps Time 8 4 r" C/MCPD o (V ' In-service (Y/N) e If yes, Loop flow FI-68-46 9-4 A_
| |
| lbs/hr I 106 94 R.
| |
| 3
| |
| , FI-68-48 lbs/hr I 106 a 94 g Reactor Coolant Temp. TR 68-2 Loop A (OF) red (Valid only if recire. 9-4 SSC pumps running) 1 Loop B (OF) black 9-4 554 Reactor Levelzero)
| |
| (Iero at inst. (Accident) LI 3-46A (inches) 9-5 '- N LI 3-46B (inches)
| |
| -M Reactor Pressure PI 3-54 (psis)
| |
| PI 3-61 (psis) 9-5 //0 T PI 3-207 (psis) // o r __
| |
| //v r Reactor Level (Normal) LI 3-53 (inches)
| |
| (Iero at inst. zero) 9-5 8 LI 3-60 (inches). 0 LI 3-206 (inches) ,
| |
| Condenser vacuum C_ !
| |
| P/TR 2-2 (in Hg) black 9-6 1 (1) Torus H 2 cone. j (1) Torus 0 2 cone. H2 R 76-39 or 37(%)(blue pen) 9-54, 55 O (1) Drywell H cone. 02 R 76-43 or 41(%)(blue pen) 9-54, 55 /5 3 "/a
| |
| : (1) Drywell 0 22 cone. H2 R 76-39 or 37(%)(red pen) 9-54, 55 C i 02 R 76-43 or 41(%)(red pen) 9-54, 55 0, 5 %
| |
| i (1)are HSactive.
| |
| 76-49 and HS 76-59 must be checked to determine recorder pens what Other (speelfy) :
| |
| Eaulement Operability - Check the listed equipment for operability. If less Eculoment than fully operable, explain in REMARKS. .
| |
| Standby Liquid Control Operable (Initt Eaulement Operable (Init)
| |
| CRD Pumps ADS / Relief V1vs .
| |
| Core Spray M SBGT .
| |
| Recire System Control Room RHR (LPCI) .
| |
| Emer. Press.
| |
| RHR (CTNT Cooling) CAD
| |
| +
| |
| HPCI m2_d Diesels'-(U1 U2) _
| |
| RCIC o.uf-Diesels (U3)
| |
| : g. EECW
| |
| )
| |
| RHRSW Feedwater System-500 KV Power 161 KV Power Condensato System 4 KV System Primary Containment 480 V System '
| |
| DC Power After completion, hand carry to secrotary in hallway outside TSC for Distribution u on distrib ti O, Technical Assessment Manager Maintenance Manager CECC Communicator Health Physics .
| |
| Operations Manager NRC Coordinator Radiochemical Engineve CECC (NRC/C(Telecopy)9)
| |
| Rpt.81-1 0175p.
| |
| L ,
| |
| a.. s.# . : . A,Page _7 , ,, ,wab
| |
| | |
| Page 3 cf 3 BFN - IPD '
| |
| * ' BFN. IP-20 -
| |
| ,'' Attachment A
| |
| [NRC/C)
| |
| *REV 0 0,U.0 '. . '. .;.l
| |
| * Unit No. 1 Time: __ dM /33d ,
| |
| SBGTS Total Flow = (FI-65-50) + (FI-65-71) (SCFM) 9-25 80
| |
| * Drywell Radiation
| |
| * Unit 3 has indicators FI-65-50A. FI-65-71A i Unit 1 RM-90-272A (R/hr) 9-54 C ,
| |
| Unit 1 RM-90-273A (R/hr) 9-55 O i Unit 2 .
| |
| RM-90-272A (R/hr) 9-54 o f Unit 2 Unit 3 RM-90-273A (R/hr)
| |
| RM-90-272A (R/hr) 9-55 9-54 O
| |
| /, o i Unit 3 RM-90-273A (R/hr) 9-55 A 't
| |
| { .
| |
| L Torus Radiation Unit 1 RM-90-272B (R/he) 9-54 6-f Unit 1 RM-90-273B (R/hr) 9-55 O
| |
| * l
| |
| [ Unit 2 RM-90-2728 (R/hr) 9-54 O ,-
| |
| Unit 2 I RM-90-273B (R/hr) 9-55 C j Unit 3 RM-90-272B (R/hr) 9-54 O '
| |
| l Unit 3 RM-90-2738 (R/hr) 9-55 O i 3
| |
| Stack Radiation RR-90-147 red pen (Cps)(Unit 1 only) 9-2 MD RR-90-1478 black pen (Cps)(Unit 1 only) 9-2 3 x/o#
| |
| Stack Flow FI-1-90-271 (cfm)(Unit 1 only) 9-53 2D, coe) '
| |
| Remarks: i t -
| |
| , j After completion, hand carry to secretary in hallway outside TSC for
| |
| .v, distribution. ,
| |
| Distribution . 7 Technical Assessment Manager '
| |
| T Maintenance Manager Operations Manager ..
| |
| 1 . CECC Communicator
| |
| , NRC Coordinator
| |
| ( Radiochemical Engineer Mealth Physics
| |
| / .1
| |
| ( CECC (Telecopy) (NRC/C Rpt.81-19]
| |
| L.
| |
| ,0175p
| |
| :.uxu. - .. .A
| |
| | |
| _ _ . - . . - . ~. . . . - - -_- - -- --- -- .
| |
| I
| |
| !ho /t d 5E CE N5 '#
| |
| . Pato 1 Gf 3 BFN - IPD BFN, IP-20 L (NRC/C1 Attachment A
| |
| ,' 7' , . ;
| |
| ~R E V .0 0'0 0 Unit No.
| |
| l ' Time $ kr: )m l o 044W) l Parameter .-
| |
| Instrument DJapel, Reading l
| |
| J Reactor Level (Accident) LI 3-62 (inches) 9-3 l
| |
| '(Zero at top of fuel) LI 3-52 ~/f
| |
| -/ F
| |
| ' f. Drywell Low Pressure PI 64-39A (Unit 1 only) '
| |
| (Low range) IR-64-159 (blue pen, #2) /. 9
| |
| - 9-3
| |
| (-5 to +5 psis) _ l . 't
| |
| .Drywell Vide Range PI-64-160A-Pressure 9-3 f IR-64-159 (red pen #1) i (0 to 300 psig) l Drywall Air Temperature TR 64-52A (0F) (black pen) 9-3 _/ .\
| |
| . Torus Water Temperature TI 64-55A (DF) (Unit 2 caly) 9-3 -
| |
| i TR 64-161/162 (blue pen) (DF) 9-3 N Torus Water Levs1 LI-64-159A (0-20')-
| |
| "t'A 9-3 ~2 i
| |
| IR-64-159 (green pen, #3) (0-20')
| |
| HPCI Flow FIC 73-33 (spm) 9-3 O RCIC F. low FIC 71-36A (spm) 9-3 O RHR Loop I Pressure PI 74-51 (psis) 9-3 //-O RHa Loop I Flow FI 74-50 (spm) 9-3 20, vard RHR Loop II Pressure PI 74-65 (psig) 9-3 N80 l RHR Loop II Flow FI 74-64 (gpm) ,
| |
| 9-3 6 Core Spray Loop I Press PI 75-20 (psig) 9-3 2 ?f /
| |
| Core Spray Loop I Flow FI 75-21 (spm) ~
| |
| 9-3 O I Core Spray Loop II Press PI 75-48 (psig) 9-3 28/
| |
| r Core Spray Loop II Flow FI 75-49 (spm) . 9-3 O L
| |
| After completion, hand carry to secretary in hallway outside TSC for distribution. (NRC/C Rpt 81-191 1 1 - l
| |
| [' Distribution - \
| |
| 1 Technical Assessment Manager Maintenance Manager NRC Coordinator Operations Manager Radiochemict.1 Engineer Health Physics ''
| |
| CECC Communicator CECC (Telecopy) 0175p
| |
| ,I.
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| 'L~ ,
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| ' " " " ' ~ ~
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| It E V 0000
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| ' , , Page 2 of 3 '
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| i htc/C) g "' 8FN - IP -
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| Unit No. ,
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| BFN. IP-20 '
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| Attachment A C/W
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| $kt. % ie Reactor Recite Pumps ~
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| Time
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| ^~ ~
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| In-service (Y/N)
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| If yes. Loop flow . FI-68-46 9-4 A B lbs/hr I 106 g.4 g FI-68-48 lbs/hr I 106 94 g Reactor Coolant Temp. TR 68-2 Loop A (SF) red (Valid only it recire, 9-4 _ SS~G pumps running) !.oop B (OF) black 9-4 554 Reactor (Zero atLevel inst. (Accident) tero) LI 3-46A (inches) 9-5 _ -/fS~
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| LI 3-468 (inches)
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| - M S-Reactor Pressure PI 3-54 (psis) 9-5 //0 0 PI 3-61 (psig)
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| PI 3-207 (psis) Noe wo Reactor Level (Normal) LI 3-53 (inches)
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| (Zero at inst. zero) 9-5 0 LI 3-60 (inches) o LI 3-206 (' inches) O Condenser vacuum P/TR 2-2 (in Hg) black
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| * 9-6 (1) Torus H 2 cone.
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| -(1) Torus 0 2 cone. H2 R 76-39 or 37(%)(blue pen) 9-54, $5 O (1) Drywell H 2 conc. 02 R 76-43 or 41(%)(blue pen) 9-54, SS H2 R 76-39 or 37(%)(red pen) O, yg (1) Drywell 0 2 conc. 9-54, 55 O 02 R 76-43 or 41(%)(red pen) 9-54, 55 At%
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| (1) are HSactive.76-49 and HS 76-59 must be checked to determineens what recorder p --
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| Other (speelfy)
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| Eautement Operability - Check the listed equipment for operability. If less Eculement than fully operable, explain in REMARKS.
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| Operable (Init) Equipment _
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| Standby Liquid Control Operable (Init)
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| CRD Pumps ADS / Relief V1vs -
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| Core Spray om.# SBGT .
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| Recire System Control Room _
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| RHR (LPCI) ,
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| Emer. Press.
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| RHR.(CTNT Cooling) CAD Diesels'-(U1 U2)
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| ~
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| HPCI RCIC c> w it Diesels (U3) ]
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| EECW ed ~~
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| RHRSW $00 KV Power Feedwater System 161 KV Power Condensate System ~ 4 KV System ~
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| Primary Containment 480 V System DC Power .
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| After completion, hand carry to secretary in hallway outside TSC for distribution Distribution .
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| O. Technical Assessment Manager Haintenance Manater CECC Communicator Health Physics .
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| vperations Manager NRC Coord}nator ECC
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| . Radiochemical Engineer NRC/bTeleco$y Rpt.8 9) 0175p .
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| . . ....a Ad"I" - - -. < M qal u. . . . . - -
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| ., Paso 3 of 3 8FN - IPD BFN. IP-20 -
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| Attachment A (WRC/C)
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| 'REV 0 0,0 0 -
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| Unit No. 3 Timet dd e. / M " [/Vo SBGTS Total Flow =,(FI-65-50) + (FI-65-71) (SCFM) 9-25 O Unit 3 has indicators FI-65-50A, FI-65-71A
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| - Drywell Radiation -
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| Unit 1 RM-90-272A (R/hr) 9-54 6
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| , Unit 1 RM-90-273A (R/hr) 9-55 0 Unit 2 . RM-90-272A (R/hr) 9-54 o Unit 2 RM-90-273A (R/hr) 9-55 O Unit 3 RM-90-272A (R/hr) 9-54 /. O Unit 3 RM-90-273A (R/hr) 9-55 / ,1 l' '
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| Torus Radiation
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| , Unit 1 RM-90-2728 (R/hr) 9-54 O e
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| * Unit 1 RM-90-273B (R/hr) 9-55 o
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| * Unit 2 RM-90-272B (R/hr) 9-54 O ,-
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| Unit 2 RM-90-273B (R/hr) 9-55 C Unit 3 RM-90-272B (R/hr) 9-54 O Unit 3 RM-90-273B (R/hr) 9-55 O 3 EX O Stack Radiation RR-90-147 red pen (Cps)(Unit 1 only) 9-2 RR-90-147B black pen (Cps)(Unit 1 only) 9-2 ,_ g gjp Stack Flow FI-1-90-271 (cfm)(Unit 1 only) 9-53 2C), e Remarks:
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| ( -
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| 1 After completion, hand carry to secretary in hallway outside TSC for 1, distribution.
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| Distribution .
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| Technical Assessment Manager
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| * P Maintenance Manager Operations Mana$er .
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| . CECC consnunicator T L. , NRC Coordinator Radiochemical En61neer Health Physics iy. CECC (Telecopy) (NRC/C Rpt.81-19)
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| ~
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| 0175,p I
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| '. Page 8 A,, ..
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| w ws. .
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| 1
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| '[ Csr en f= 6 A + h ~^
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| ~ !
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| jfjo A page 1 of 3 BFN - JPD i
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| [h- '
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| BFN, IP-20 Attachment A I
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| (NRC/C) *
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| ~" '
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| "R E V .0 0'0'0 .
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| Unit No.
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| Time b N8) "
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| Parameter Instrument \
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| Estel.
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| e Reading
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| [ l
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| {
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| 1 Reactor
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| '(Iero Level at top (Accident) LI 3 62 (laches) of fuel) 9-3 -/0 0 LI 3-52 -to o Drywell Low Pressure PI 64-39A (Unit 1 only) *
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| (Low range) E
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| ~
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| IR-64-159 (blue pen, #2) 9-3
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| (-5 to +5 psis) / , 2. !
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| I. .Drywell Wide Range PI-64-160A 9-3 Pressure IR-64-159 (red pen. #1) l .
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| f (0 to 300 psig) l l l Drywell Air Temperature TR 64-52A (OF) (black pen) 1 9-3 _ / (e O i f, . Torus Water Temperature TI 64-55A (OF) (Unit 2 only) 9-3 -
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| i TR 64-161/162 (blue pen) (OF) 9-3 /30 5
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| Torus Vater Level LI-64-159A (0-20')' 9-3 E IR-64-159 (green pen. #3) (0-20') !
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| HPCI Flow FIC 73-33 (spm) 9-3 O RCIC F. low FIC 71-36A (spm) 9-3 0 RHR Loop I Pressure PI 74-51 (psis) 9-3 /[O RHR Loop I Flow FI 74-50 (spm) 9-3 _ 20. Our>
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| RHR Loop II Pressure PI 74-65 (psig) 9-3 22fC RHR Loop II Flow FI 74-64 (spm) ,,
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| 9-3 _
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| O Core Spray Loop I Press PI 75-20 (psig) 9-3 _ 23 / {
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| Core Spray Loop I Flow FI 75-21 (spm) -'
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| 9-3 _
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| O Core Spray Loop II Press PI 75-48 (psig) 9-3 86/
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| Core Spray Ldop II Flow FI 75-49 (spm) '
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| . 9-3 O After completion, hand carry to secretary in hallway outside TSC for -
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| distribution. (NRC/C Rpt 81-19]
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| I' f Distribution
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| )
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| ( ' !
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| Technical Assessment Manager Maintenance Manager NRC Ciordinator Operations Manager Radiochemical Engineer l Health Physics -
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| CECC Communicator CECC (Telecopy)
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| ]
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| I 0175p I
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| L. *
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| ...- Page 6 '
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| . . ww + ..o -
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| 2- M
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| c . - '
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| e- a REV 0000 l * . , Page 2 of 3 ,
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| I (NRC/Cl "' BFN - IP-Unit No.
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| * BFN. IP-20 -
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| { .
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| g (4 h Time Attachment A Reactor Recire Pumps
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| * 4~ (MO&}
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| O- In-service (T/N)
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| If yes. Loop flow 9-4 A FI-68-46 lbs/hr I 106 g.4 -B FI-68-48 3 lbs/hr I 106 94 g Reactor Coolant Temp. TR 68-2 Loop A (SF) red (Valid only if recire. 9-4 _ 65 G pumps running) Loop B (OF) black 9-4 STM Reactor (Zero atLevel (Accident) LI 3-46A (inches) inst. sero) 9-5 LI 3-468 (inches) -/ F 5~
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| -e r s-Reactor Pressure PI 3-54 (psis) 9-5 //vo PI 3-61 (psig)
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| PI 3-207 (psig) //o o noo Reactor Level (Normal) LI 3-53 (inches)
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| (Zero at inst, zero) LI 3-60 (inches) 9-5 &
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| O LI 3-206 (' inches) &
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| Condenser vacuum P/TR 2-2 (in Hg) black
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| * 9-6 (1) Torus H 2 conc.
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| (1) forus 0 2 conc. H2 R 76-39 or 37(%)(blue pen) 9-54, SS O 02 R 76-43 or 41(%)(blue pen)
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| (1) Drywell H 2 cone. 9-54, 55 O.3"/o (1) Drywell 0 2 cone. H2 R 76-39 or 37(%)(red pen) 9-54, 55 o 02 R 76-43 or 41(%)(red pen) 9-54 55 C. 3 7o (1)areHSactive.
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| 76-49 and HS 76-59 must be checked toerdetermine pens what recor Other (speelfy)
| |
| Equipment operability - Check the listed equipment for operability.If less Eautement than fully operable, explain in REMARKS.
| |
| Operable (Init) Equipment Standby Liquid Control operable (Init)
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| CRD Pumps ouA ADS / Relief Vivs _
| |
| Core Spray SBGT -
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| Recire System Control Room RHR (LPCI) .
| |
| Emer. Press.
| |
| RHR.(CTNT Cooling) CAD HPCI Diesels'-(U1 U2)
| |
| RCIC M Diesels (U3) _
| |
| EECW mt RHRSW 500 KV Power Feedwater. System i 161 KV Power
| |
| .Condensato System 4 KV System Primary Containment _. 480 V System DC Power After completion, hand carry to secretary in hallway outside TSC for distributio Distribution n.
| |
| O Technical Assessment Manager Maintenance Operations Manater
| |
| . Manager CECC Communicator NRC Coordinator Radiochemical Engineer Health Physics .
| |
| CECC i
| |
| (NRC/C(Telecopy)9)
| |
| Rpt.81-1
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| {
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| 4 , (gg g8 "eg , >#
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| L
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| },. ,
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| . I t
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| U l~ '
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| ., Page 3 of 3
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| ~~'' '
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| BFN - IPD L BFN. IP-20 -
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| ,'" Attachment A
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| [NRC/C)
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| 'REV 0 0,0 0 -
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| * Unit No. 1 Time: .
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| OO StGTS Total Flow =, (FI-65-50) + (FI-65-71) (SCFM) 9-25 O s Drywell Radiation Unit 3 has indicators FI-65-50A. FI-65-71A Unit 1 RM-90-272A (R/hr) 9-54 6 '
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| L ,, Unit 1 RM-90-273A (R/hr) 9-55 D Unit 2 .
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| RM-90-272A (R/hr) 9-54 o f Unit 2 Unit 3 RM-90-273A (R/hr)
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| RM-90-272A (R/hr) 9-55 9-54 O
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| /, o Unit 3 RM-90-273A (R/hr)
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| (l Torus Radiation 9-55 /, 'T l .
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| Unit 1 RM-90-2728 (R/hr) 9-54 o i
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| ' f .
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| Unit 1 RM-90-273B (R/hr) 9-55 O *
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| [ Unit 2 RM-90-272B (R/hr) 9-54 0 Unit 2 RM-90-273B (R/hr) 9-55 O L Unit 3 RM-90-272B (R/hr) 9-54 /,, or/o 3
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| : Unit 3 RM-90-273B (R/hr) 9-55 c, vno 3
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| . Stack Radiation RR-90-147 red pen (Cps)(Unit 1 only) 9-2 / O t /O I RR-90-1478 black pen (Cps)(Unit 1 only) 9-2 2.o / /o r Stack Flow FI-1-90-271 (cfm)(Unit 1 only) 9-53 2 C MD Remarks: '
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| L .
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| l t After completion, hand carry to secretary in hallway outside TSC for 3, distribution.
| |
| ! 1
| |
| , . Distribution .
| |
| , Technical Assessment Manager T Maintenance Manager !
| |
| l i j i Operations Manager . l CECC Communicator l
| |
| ' NRC Coordinator Radiochemical Engineer l
| |
| Mealth Physics
| |
| {
| |
| p CECC (Telecopy) (NRC/C Rpt.81-19] '
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| i 0175p Page 8 .
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| . & ww 'a: Inh-- - s.
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| Y jfhO [ $S 7" 'G/L [# ?b f5 , page 1 ct 3
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| \
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| *"*' BFN - IPD BFN, IP-20
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| ,' ..-l A (NRC/Cl -
| |
| Attachment 4 I
| |
| . ..' "R E V . 0 0' 0 0 ~'
| |
| .- I., !
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| Unit No. h /~
| |
| Time hMO)
| |
| Parameter Instrument
| |
| [ M Readint
| |
| [ Reactor
| |
| '(Zero at Level top of(Accident) fuel) LI 3 62 (inches) 9-3 _ -/0 0
| |
| ,1 LI 3-52 -/vo '
| |
| l f Drywell Low Pressure (Low range)
| |
| PI 64-39A (Unit 1 only)
| |
| IR-64-159 (blue pen. #2)
| |
| : 2. &
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| - 9-3
| |
| (-5 to +5 psig) /, 2
| |
| .Drywell Wide Range PI-64-160A Pressure 9-3 I IR-64-159 (red pen #1)
| |
| (0 to 300 psig) (
| |
| Drywell Air Temperature {
| |
| TR 64-52A (OF) (black pen) 9-3 _ /7f i
| |
| : f. . Torus Water Temperature TI 64-55A (OF) (Unit 2 only) i 9-3 -
| |
| TR 64-161/162 (blue pen) (OF) 9-3 90 I Torus Water Level LI-64-159A (0-20')' 9-3 "2 IR-64-159 (green pen, #3) (0-20')
| |
| HPCI Flow FIC 73-33 (spm) 9-3 6~ N RCIC F. low FIC 71-36A (gpm) 9-3 O 1
| |
| RHR Loop I Pressure PI 74-51 (psig)
| |
| RHR Loop I Flow 9-3 /b FI 74-50 (spm) 9-3 20,0*o RHR Loop II Pressure PI 74-65 (psig) 9-3 22fo j
| |
| ; RHR Loop II Flow FI 74-64 (spm) ,
| |
| 9-3 O l Core Spray Loop I Press PI 75-20 (psig) ^
| |
| 9-3 ,,__fc]!L
| |
| .i Core Spray Loop I Flow FI 75-21 (spm) ~-'
| |
| 9-3 0 Core Spray Loop II Press PI 75-48 (psis) .
| |
| 9-3 '
| |
| Core Spray Loop II Flow ZY/ __
| |
| FI 75-49 (spm) '
| |
| . 9-3 8 L
| |
| After completion, hand carry to secretary in hallway outside ISC for distribution.
| |
| (NRC/C Rpt 81-19)
| |
| N1 1
| |
| /- (' Distribution
| |
| * l i
| |
| Technical Assessment Manager L Maintenance Manager NRC Coordinator Operations Manager Radiochemical Engineer Health Physics *.
| |
| CECC Communicator CECC (Telecopy) 9 4
| |
| 0175p
| |
| -i
| |
| (- .
| |
| . ...- ... Fase 6. ' i ,c ,
| |
| E w s.. + .. . e >-
| |
| | |
| 7 4 {/ . .,- - .
| |
| }t E y 0000
| |
| ', il' . ' . .. Page 2 of 3
| |
| [NRC/C) ~~*' BFN - IP.-
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| S Unit No. '
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| " BFN. IP-20 '
| |
| Attachmeqt A
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| /" - Reactor Recire Pumps
| |
| * Time - 9 kf. (/SM)~
| |
| ('}/ In-service (Y/N)
| |
| If yes Loop flow FI-68-46 9-4 A lbs/hr I 106 94
| |
| -- R 3
| |
| FI-68-48 lbs/hr I 106 j 94 g Reactor Coolant Temp.- TR 68-2 Loop A (OF) red (Valid only if recire. 9-4 SSL pumps runnin6)
| |
| Lo0P 5 (OF ) black 9-4
| |
| $5(
| |
| Reactor (Zero at Level (Accident) LI 3-46A (inches) inst. sero) 9-5 "/Tf LI 3-46B (inches) !
| |
| -<5 r t Reactor Pressure PI 3-54 (psis) ;
| |
| PI 3-61 (psis) 9-5 //00 )
| |
| PI 3-207 (psig) / /o o l
| |
| //oo i Reactor Level (Normal) LI 3-53 (inches)
| |
| (Zero at inst. tero) 9-5 S LI 3-60 (inches) -
| |
| 0 LI 3-206 (' inches) -
| |
| Condenser vacuum C1 P/TR 2-2 (in Hg) black 9-6 s
| |
| - (1) Torus H 2 cone.
| |
| (1) Torus 0 2 cone. H2 R 76-39 or 37(%)(blue pen) 9-54, 55 C (1) Drywell H cone. 02 R 76-43 or 41(%)(blue pen) 9-54, SS (1) Drywell 0 22 conc.
| |
| O, 3 *To H2 R 76-39 or 37(%)(red pen) 9-54, 55 C O 02 R 76-43 or 41(%)(red pen) 9-54, 55 _ o. 3 Yo l- (1)are HS'76-49 active. and HS 76-59 must be checked corder topens determine wh
| |
| [ Other (specify)
| |
| Esutement Operability - Check the listed equipment for operability. If less
| |
| ~
| |
| Enuiement than fully operable, explain in REMARKS, Operable (Init) Ecutement E
| |
| ~ Standby Liquid Control Operable (Init}_
| |
| CRD Pumps ADS / Relief V1vs.
| |
| Core Spray ~4 SBGT .
| |
| Recire System Control Room Emer. Press.
| |
| RHR (LPCI) .
| |
| RHR.(CTNT Cooling) __
| |
| CAD HPCI Diesels'-(U1 U2)
| |
| 'RCIC rebuve_,1fgpwtg Diesels (U3)
| |
| RECW c>u r '
| |
| RHRSW. 500 KV Power Feedwater System 161 KV Power Condensate System 4 KV System _
| |
| e Primary containment _ 480 V System ,
| |
| l DC Power i-After completion, hand carry to secretary in hallway outside TSC Distribution u for distrib on, Technical Assessment Manager (O)-
| |
| CECC communicator {
| |
| Maintenance Manarer Operations Manage,r Health Physics NRC Coordinator ECC 1
| |
| Radiochemical Engineer NRC/bTeleco[y Rpt 8 91 0175p
| |
| ...e m.d'_I*_ _ . _JEM
| |
| +1
| |
| -s_ .- . _._.
| |
| | |
| 4 .a.
| |
| * Page 3 of 3 8FN - IPD
| |
| * '' BFN. IP-20 -
| |
| (NRC/C)
| |
| .'' Attachment A
| |
| ' REY 0 0,0 0 .
| |
| * Unit No. Time: 7 d /*. h N dn)
| |
| SBGTS Total Flow =,(FI-65-50) + (FI-65-71) (SCFM) 9-25 C Unit 3 has indicators FI-65-50A, FI-65-71A Drywell Radiation '
| |
| Unit 1 RM-90-272A (R/hr) 9-54 O
| |
| . Unit 1 RM-90-273A (R/hr) 9-55 o Unit 2 .
| |
| RM-90-272A (R/hr) 9-54 o Unit 2 RM-90-273A (R/hr) 9-55 O Unit 3 RM-90-272A (R/hr) 9-54 /, c7 Unit 3 RM-90-273A (R/hr) 9-55 /, V Torus Radiation
| |
| . Unit 1 RM-90-2728 (R/he) 9-54 0 r
| |
| * Unit 1 RM-90-273B (R/hr) 9-55 O *
| |
| [ Unit 2 RM-90-272B (R/hr) 9-54 0 Unit 2 RM-90-2738 (R/hr) 9-55 O Unit 3 RM-90-272B (R/hr) 9-54 3. o y to '
| |
| Unit 3 RM-90-273B (R/hr) 9-55 2.o no f :
| |
| ~ Stack Radiation RR-90-147 red pen (Cps)(Unit 1 only) 9-2 /,0 t /O f i RR-90-147B black pen (Cps)(Unit 1 only) 9-2
| |
| ! /.4 v/o T
| |
| ! Stack Flow FI-1-90-271 (cfm)(Unit 1 only)
| |
| \
| |
| 9-53 ao e ,
| |
| Remarks:
| |
| i l t After completion, hand carry to secretary in hallway outside TSC for
| |
| { distribution.
| |
| Distribution .
| |
| ,d '
| |
| Technical Assessment Manager Maintenance Manager Operations Manager ..
| |
| CECC Communicator T
| |
| , NRC Coordinator Radiochemical Engineer
| |
| )1 '
| |
| Health Physics CECC (Telecopy) (NRC/C Rpt.81-19]
| |
| L
| |
| .. ( ,
| |
| g-0175p
| |
| .- Page 8 . . .
| |
| ., Ye* r%
| |
| * i
| |
| | |
| ,i gn gy 7'= 7A< N30 mi
| |
| ~~~'
| |
| SFN - IPD
| |
| ( '
| |
| BFN, IP-20 - ',
| |
| ' y, !NRC/C1 -
| |
| Attachment A
| |
| ~R E V O 0"0 0 '.' "-
| |
| 3 Unit No.
| |
| , Time dC bD Parameter Instrument ganel Readine Reactor
| |
| '(Zero at Level top of(Accident) fuel) LI 3-62 (inches) 9-3 /80 LI 3-52 /ro Drywell Low Pressure f- (Low range)
| |
| PI 64-39A (Unit 1 only) *
| |
| : 7. E
| |
| - IR-64-159 (blue pen. #2) 9-3
| |
| (-5 to +5 psig) I . 2_
| |
| : s. .Drywell Wide Range PI-64-160A 9-3 l Pressure IR-64-159 (red pen. #1) _
| |
| (0 to 300 psig) I Drywell Air Temperature TR 64-52A (OF) (black pen) n- 9-3 /73~ *
| |
| . Torus Water Temperature TI 64-55A (DF) (Unit 2 only) 9-3 '
| |
| TR 64-161/162 (blue pen) (CF) 9-3 /M Torus Water Level LI-64-159A (0-20')- 9-3 -E
| |
| % IR-64-159 (green pen #3) (0-20')
| |
| HPCI Flow FIC 73-33 (spm) 9-3 /Cao RCIC F. low FIC 71-36A (gpm) 9-3 O RHR Loop I Pressure PI 74-51 (psig)
| |
| RHR Loop I Flow 9-3 //O FI 74-50 (spm) 9-3 20,OPO RHR Loop II Pressure PI 74-65 (psig)
| |
| RHR Loop II Flow 9-3 bM FI 74-64 (spm) ,,
| |
| 9-3 O Core Spray Loop I Press PI 75-20 (psig)
| |
| Core Spray Loop I Flow 9-3 27/
| |
| FI 75-21 (spm) -
| |
| 9-3 0 Core Spray Loop II Press PI 75-48 (psis) 9-3 23/
| |
| Cpre Spray Ldop II Flow FI 75-49 (spm)
| |
| . 9~3 6 L After completion, hand carry to secretary in hallway outside TSC for distribution. (NRC/C Rpt 81-19)
| |
| Distribution
| |
| * Technical Assessment Manager Maintenance Manager NRC Coordinator L Operations Manager Radiochemical Engineer Health Physics CECC Communicator -
| |
| CECC (Telecopy)
| |
| ~
| |
| . 0175p p '
| |
| . aw.- - ~.4 -4
| |
| | |
| #4
| |
| * REV 0000
| |
| * , , Page 2 of 3 ,
| |
| l
| |
| [NRC/C) g ~~'' '
| |
| BFN - IP-
| |
| ' Unit No. J *
| |
| * BFN. IP-20 -
| |
| Time % j k Attachment A Reactor Recite Pumps " '" f / r ass $ -
| |
| In-service (Y/N)
| |
| If yes, Loop flow 9-4 A. B FI-68-46 lbs/hr I 106 94 FI-68-48 3 lbs/hr I 106 94 g Reactor Coolant Temp. TR 68-2 Loop A (OF) red (Yalid only if recire. 9-4 _ 556 pumps running) Loop B (OF) black 9-4 SS(
| |
| 2eactor Level (Accident) LI 3-46A (inches) 9-5 25 (Zero at inst sero) LI 3-468 (inches) M Reactor Pressure PI 3-54 (psis) 9-5 //o o PI 3-61 (psis) //c o PI 3-207 (psis)
| |
| //oc>
| |
| Reactor Level (Normal) LI 3-53 (inches)
| |
| (Zero at inst. zero) LI 3-60 (inches) 9-5 3d
| |
| .34 LI 3-206 (~ inches)
| |
| ' ._ 3 4 Condenser vacuum P/TR 2-2 (in Ng) black
| |
| * 9-6 (1) Torus H 2 conc.
| |
| (1) Torus 0 2 COB 0* H2 R 76-39 or 37(%)(blue pen) 9-54, 55 O (1) Drywell H 2 cone. 02 R 76-43 or 41(%)(blue pen) 9-54 55 d. 3 '7o (1) Drywell 0 2 conc. H2 R 76-39 or 37(%)(red pen) 9-54, 55 o 02 R 76-43 or 41(%)(red pen) 9-54, 55 o, .e fa, (1) are HS active.
| |
| 76-49 and HS 76-59 must be checked to determine ens what recorder p Other (specify) _
| |
| Ecutement Operability - Check the listed equipment for operability. If less Boulement than fully operable, explain in REMARKS.
| |
| operable (Init) Ecutement Standby Liquid C%.crol CRD Pumps ADS / Relief V1vs k rable (Init) cru/ SBGT Core Spray Recire System Control Room RHR (LPCI) .
| |
| Emer. Press.
| |
| CAD RHR,(CTMT Cooling)
| |
| HPCI Diesels'-(U1 U2) _
| |
| }
| |
| RCIC Diesels (U3) o.u f EECW 500 KV Power RHRSW Feedwater System __.
| |
| 161 KV Power Condensate System 4 KV System ,
| |
| - Primary containment 480 V System DC Power
| |
| ~
| |
| -Distribution After completion, hand carry to secretary 1n hallway outside TSC for distribution Technical Assessment Manager gaintenanceManager CECC Communicator Health Physica perations Manager NRC Coord}nator
| |
| . . Radiochemical Engineer CECC{Telecogy{9)
| |
| (NRC/ Rpt.8 -
| |
| . 0175p )
| |
| I
| |
| +?***I
| |
| ~ '
| |
| .w...... - S.W
| |
| | |
| Page 3 of 3 8FN - IPD i BFN, IP-20 -
| |
| Attachment A (NRC/C) *REV 0 0,0 0
| |
| ',. . '., . j
| |
| , l ,
| |
| Unit No. 3 Time: M hf_dd SBGTS Total Flow = (FI-65-50) + (FI-65-71) (SCFM) 9-25 C Unit 3 has indicators FI-65-50A, FI-65-71A
| |
| - Drywell Radiation. - i j
| |
| Unit 1 RM-90-272A (R/hr) 9-54 O i
| |
| ,. Unit 1 RM-90-273A (R/hr) 9-55 U
| |
| Unit ? }
| |
| RM-90 272A (R/hr) 9-54 o f Unit 2 Unit 3 RM-90-273A (R/hr)
| |
| RM-90-272A (R/hr) 9-55 9-54 O
| |
| /. o l
| |
| Unit.3 RM-90-273A (R/hr) 9-55 /, 9
| |
| { ,
| |
| t forus Radiation l
| |
| . Unit 1 RM-90-2728 (R/hr) 9-54 8 r
| |
| * Unit 1 RM-90-273B (R/hr) 9-55 O *
| |
| [ Unit 2 RM-90-2728 (R/hr) 9-54 O Unit 2 RM-90-273B (R/hr) 9-55 .C Unit 3 RM-90-272B (R/hr) 9-54 _,,,4 0t/0 %
| |
| Unit 3 RM-90-273B (R/hr) 9-55 S.o t/0
| |
| * f
| |
| ., Stack Radiation RR-90-147 red pen (Cps)(Unit 1 only) 9-2 12//0 J RR-90-1478 black pen (Cps)(Unit 1 only) 9-2 /./ / /0 T I
| |
| Stack Flow FI-1-90-271 (cfm)(Unit 1 only)
| |
| ' 9-53 oge l Remarks:
| |
| i .-
| |
| 1, After completion, hand carry to secretary in hallway outside TSC for distribution.
| |
| Distrib"tton .
| |
| Technical Assessment Manager '
| |
| 4' Maintenance Manager Operations Manager CECC Communicator T
| |
| - NRC Coordinator
| |
| (- Radiochemical-Engineer Mealth Physics ,
| |
| /ly. CECC (Telecopy) (NRC/C Rpt.81-19]
| |
| L
| |
| *~
| |
| 0175p Page 8 .
| |
| , .t . .-
| |
| 2,;:.w e M A -.. ~ -. J M
| |
| | |
| $ fi60 h CSf' ok Y= V W * . tcs' 1 et 3 BFN - IPD (9. '
| |
| BFN. IP-20 Attachm6nt A (NRC/C)
| |
| "R E V .0 0'0 o '." '.
| |
| Unit No. Time [b hO)
| |
| Parameter Instrumers e f,1D.e),, Readint
| |
| ~
| |
| Reactor Leve1 (Accident) LI 3-62 (inches) 9-3 /f0
| |
| '(Zero at top of fuel) LI 3-52 dm Drywell Low Pressure PI 64-39A (Unit 1 only)
| |
| (Low range)
| |
| /,7 IR-64-159 (blue pen. #2) 9-3
| |
| (-5 to +5 psig)
| |
| { /, I E. .Drywell Wide Range PI-64-160A Pressure 9-3 i IR-64-159 (red pen #1)
| |
| (0 to 300 psig) I Drywell Air Temperature TR 64-52A (0F) (black pen) 9-3 /48 f .
| |
| . Torus Water Temperature TI 64-55A (DF) (Unit 2 only) 9-3 - ~
| |
| TR 64-161/162 (blue pen) (OF) 9-3 /30 l
| |
| Torus Water Level LI-64-159A (0-20')- 9-3 ~d XR-64-159 (green pen. #3) (0-20')
| |
| HPCI Flow FIC 73-33 (spm) 9-3 /0F0 RCIC F, low FIC 71-36A (spm) 9-3 O RHR Loop I Pressure PI 74-51 (psig)
| |
| RHR Loop I Flow 9-3 /N FI 74-50 (spm) 9-3 20,000 RHR Loop II Pressure PI 74-65 (psis) 9-3 ___ 260 RHR Loop II Flow FI 74-64 (spm) ,,
| |
| 9-3 -
| |
| O Core Sprisy Loop I Press PI 75-20 (psig) 9-3 _ Z%l Core Spray Loop I Flow FI 75-21 (spm)
| |
| * 9-3 O Core Spray Loop II Press PI 75-48 (psig) 9-3 C, ore Spray Loop II Flow 28 /_
| |
| FI 75-49 (spm) '
| |
| . 9-3 O L
| |
| After completion, hand carry to secretary in hallway cutside TSC for distribution. (NRC/C Rpt 81-19)
| |
| # ~
| |
| Distribution
| |
| * Technical Assessment Manager Maintenance Manager NRC Coordinator L Operations Manager Radiochemical Engineer CECC Comraunicator Health Physics '-
| |
| m'-
| |
| 0175p CECC (Telecopy) f o s .$*8* /. 4
| |
| | |
| p p
| |
| o R3y 0000
| |
| .. Page 2 of 3 ,
| |
| (NRC/C) j BFN - IP -
| |
| Unit No. '
| |
| BFN. IP-20 -
| |
| ttachment f'v Reactor Recire Pumps Time 8h /6003 A
| |
| In-service (T/N) --
| |
| If yes. Loop flow FI-68-4s 9-4 A_ . 3 1bs/hr I 106 g. ;,
| |
| F1-68-4t lbs/hr I 106 3 g.4 g Reactor Coolant Temp.-
| |
| (Valid only it recire. TR 68-2 Loop A (oF) red 9-4 5/D pumps running)
| |
| Loop B (OF) black 9-4 508
| |
| ,,, Reactor Level (Zero at inst. (Accident) LI 3-46A (inches) zero) 9-5 29 LI 3-46B (inches) 2r Reactor Pressure PI 3-54 (psis)
| |
| PI 3-61 (psis) 9-5 ~743 PI 3-207 (psit) _
| |
| 743 74 3 Reactor Level (Normal) LI 3-53 (inches)
| |
| (Zero at inst. zero) LI 3-60 (inches) 9-5 34 LI 3-206 ('laches) _
| |
| 34 3+
| |
| condenser vacuum P/TR 2-2 (in Hg) black
| |
| * 9-6 1
| |
| (1) Torus H 2 cone.
| |
| (1) Torus 0 2 cone. H2 R 76-39 or 37(%)(blue pen) 9-54. 55 (1) Drywell H conc. 02 R 76-43 or 41(%)(blue pen) - 6 9-54, 55 (1) Drywell 0 22 conc.
| |
| 0,3 "/o
| |
| [ H2 R 76-39 or 37(%)(red pen) 02 R 76-43 or 41(%)(red pen) 9-54, 55 0 e i 9-54, 55 _ O, 3 fo l
| |
| (1)are HS 76-49 active. and HS 76-59 must be checked a recorderto pensdeterm'ne wh Other (specify) i Eaulement Operability - Check the listed equipment for operability. If less ~
| |
| Roulement than fully operable, explain in REMARKS.
| |
| Standby Liquid Control Operable (Init) Eauipment
| |
| ' Operable (Init)
| |
| CRD Pumps ADS / Relief Vivs l
| |
| ' Core Spray c.o t SBGT Rectre System control Room _
| |
| RHR (LPCI) ,
| |
| Emer. Press.
| |
| RHR.(CTMT Cooling) CAD HPCI Diesels *-(U1 U2)
| |
| ~RCIC Diesels (U3) _
| |
| EECW _M RHRSV ~ 500 KV Power Feedwater System 161 KV Power
| |
| . Condensate System 4 K7 System Primary Containment 480 V System DC Power After completion, hand carry to secretary in hallway outside TSC for di Distribution (s,. ~
| |
| > stribution A Technical Assessment Manager Maintenance Manager CECC Communicator Health Physics .
| |
| Operations Manager NRC Coordinator ECC Radiochemical Engineer fNRC/hTelecoSy Rpt 8 9) 0175p
| |
| : m. . . . . . , , - Ad*8* a- i 4
| |
| | |
| 4 s
| |
| ., Pete 3 of 3
| |
| ''~~' '
| |
| BFN - IPD BFN, IP-20 -
| |
| . Attachment A R E .V 0 0,0 0 (NRC/C) ',. - -
| |
| ' Unit No. 8 4 e.
| |
| Time:
| |
| /40f)
| |
| SBGTS Total Flow =,(FI-65-50) + (FI-65-71) (SCFM) 9-25 O Unit 3 has indicators FI-65-50A, FI-65-71A l' Drywell Radiation
| |
| * l Unit 1 RM-90-272A (R/hr) 9-54 O Unit 1 RM-90-273A (R/hr) 9-55 o Unit 2 . RM-90-272A (R/hr) 9-54 . O f Unit 2 Unit 3 RM-90-273A (R/hr)
| |
| RM-90-272A (R/he) 9-55 9-54 _ /. O C _
| |
| Unit 3 RM-90-273A (R/hr) 9-55 /Y Torus Radiation
| |
| . Unit 1 RM-90-2728 (R/hr) 9-54 6 e
| |
| * Unit 1 RM-90-2738 (R/hr) 9-55 O *
| |
| ' Unit 2 RM-90-2728 (R/hr) 9-54 o Unit 2 RM-90-273B (R/hr) 9-55 C ~,..
| |
| Unit 3 RM-90-272B (R/hr) 9-54 /_, o t /0 7 Unit 3 RM-90-2738 (R/hr) 9-55 /, o r/o Y Stack Radiation RR-90-147 red pen (Cps)(Unit 1 only) 9-2 /. vt /# I RR-90-1478 black pen (Cps)(Unit 1 only) 9-2 5,o t /o 5-Stack Flow FI-1-90-271 (cfm)(Unit 1 only) 9-53 _26,Oon Remarkst j
| |
| After completion, hand carry to secretary in hallway outside TSC for distribution.
| |
| < Distribution .
| |
| Technical Assassment Manager
| |
| # Maintenance Manager Operations Manager .
| |
| CECC Communicator T L. NRC Coordinator Radiochemical Engineer 1 Health Physics 3
| |
| g CECC (Telecopy) (NRC/C Rpt.81-19)
| |
| M
| |
| ~
| |
| Page 8 x a u . s .'.
| |
| ~
| |
| 1
| |
| | |
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| i PLANT HP DATA t, -t I
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| -W i-'
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| > ,^ ; -DIRECT' RADIATION READINGS '
| |
| i :
| |
| N.- UNIT 3 REACTOR BUILDING EL 565 '
| |
| Direct Gamma Dose in MR/hr Above Background 0800- 0900 1000 1200 1300 1400 Area Description I Time 0859 0959 1159 1259 1359 ON j I 'Outside door to airlock 0 5 5 5 5 20 2 Inside airlock 0 30 30 28 26 200 1 3 Unit 3 side of airlock 5 230 200 180 170 2,000 4 Near CRD volume control tank 6 275 240 216 205 2,400 5 Near west' side CRD modules 7 320- 280 250 238 2,800 6 Near drywell access 8 370 320 290 270 3.200 7 Inside door from unit 2 8 370 320 290 270 3.200 8 Outside door from unit 2 4 185 160 145 135 1,600 i 9 Near south wall 10 450 400 360 340 4,000 10 Southeast corner _ 15 690- 600 540 510 6,000 11 Near east side CRD modules 20 920 800 720 680 8,000 ,
| |
| 12 Near northeast corner 25 1,150 1,000 900 850 10,000 Note: Beta dose = 2X Gamma dose 1041E
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| DIRECT EADIATION READINGS FROM UNIT 3 SBGTS DUCTWORK f
| |
| Direct Gamma Dose in MR/hr Above Background 0800 0900 1000 1200 1300 1400-Description !. Time: 0859 0959 1159 1259 '1359 ON
| |
| =s Contact 6 275 240 215 205 2,400 1 ft. 6 275- 240 215 204 2,400 2 ft. 5 240 210 190 178 2,100 5 ft. 4.5 207 180 162 153- 1,800 10 ft. 2.5 103 90 80 76 900 20 ft. 1 34 30 27 25 300 1041E C
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