ML19224B288
| ML19224B288 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/31/1977 |
| From: | Metropolitan Edison Co |
| To: | Mullinix W NRC/IE |
| References | |
| TM-0301, TM-301, ZAR-771031, NUDOCS 7906140392 | |
| Download: ML19224B288 (30) | |
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DOCUMENI NO: 77T1' C S ( /
COPY MADE ON
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OF DOCUMENT PROVIDED BY v i fr METROPOLITAN EDISCN COMPANY.
Wilda R. Mullinix, NRC a
e 7906140331 mm o
e 197 043
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s FINAL SYSTEM DESCRIPTION (INDEX NO. 50)
SAFETY FEATURES ACTUATION SYSTEM (B&R Dwg. No. 3 011, Rev. 7, Sheets 1 and 2)
JERSEY C ENTRAL POWER & LIGHT COMPANY THREE MILE ISLAND NUCLEAR STATION UNIT NO. 2 Issue Date October, 1977
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Prepared by:
A.
D.
Pullin Burns and Roe, Inc.
700 Kinderkamack Road Oradell, N.J.
07649 I97 049
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APPENDIX
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TITLE
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TABLE NO.
Reactor Coolant Safety Injection 1
(:HP and LP Inject'on) Actuated A and 3 Equipment Reactor Building Cooling and Isolation 2
Actuated A and B Equipment Instrumentation and Controls 3
s Panel Mounted Annunciators and Computer 4
Input Listing
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i 197 050
-1 TABLE GF CONTENTS FOR SAFETY FEATURES ACTUATION SYSTEM Section Page
1.0 INTRODUCTION
1 1.1 System Functions 1
1.2 Summary Description of the System 2
1.3 System Design Requirements 8
2.0 DETAILED DESCRIPTION OF SYSTEM 10 2.1 Components 10 2.2 Instruments, Controls, Alarms and Protective Devices 11 3.0 PRINCIPAL MODES OF OPERATION 12 3.1 Startup 12 3.2 Normal Operation 12 3.3 Shutdown 13
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3.4 Special or Infrequent Operation 14 3.5 Emergency 14 4.0 HAZARDS AND PRECAUTIONS 14 i
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SAFETY FEATURES ACTUATION SYSTEM
1.0 INTRODUCTION
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1.1 System Functions The function of the Safety Features Actuation System (SFAS) is to, detect a loss-of-coolant accident (LOCA) and automa-tically actuate Engineered Safety Feature System and cer-tain other supporting plant components te control the effects of a LOCA.
The SFAS system interfaces with the following systems (Drawing Numbers refer to B&R Flow Diagrams) :
a.
Reactor Coolant, Make-up and Purification System (Dwg. No. 2024) b.
Chemical Addition System (Dwg. No. 2025) c.
Decay Heat Removal, System (Dwg. No. 2026) d.
Radwaste Disposal, Reactor Coolant -
Liquid System (Dwg. No. 2027) e.
Radwaste Disposal - Gas System (Dwg. No. 2028) ate Closed Cooling Wa'ter f.
Inter =eu i
System (Dwg. No. 2029) g.
Nuclear Services Closed Cooling Water System (Dwg. No. 2030) h.
Reactor Building Penetrations - Air and Nitrogen Pressure System (Dwg. No. 2032) i.
Nuclear Services River Water System (Dwg. No. 2033) j.
Reactor Building Emergency Cooling System (Dwg. No. 2033)
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k.
Reactor Building Emergency Spray System (Dwg. No. 2034).
J i97 052 ~
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1.
Core Flooding System (Dwg. No. 2034) m.
Decay Heat Closed Cooling Water System (Dwg. No. 2035) n.
Nitrogen for Nuclear and Radwaste (Dwg. No. 2036) o.
Heating and Ventilation, Turbine and Control Bldg. Area (Dwg. No. 2040) p.
, Reactor Bldg. Vent and Purge
. wg. No. 2041) q.
Heating and Ventilation, Auxiliary Bldg.
(Dwg. No. 2044) r.
Heating, Ventilation and Air Condi-tioning Control Bldg., Cable, Battery and Switchgear Rooms (Dwg. No. 2044) s.
Reactor Building Normal Cooling (Dwg. No. 2046) t.
Heating and Ventilation, Fuel Handling Bldg.
(Dwg. No. 2343) u.
Reactor Building Penetrations Isola-tion Valva Seal Water System (Dwg. No. 2397) v.
Reactor Building P3netrations Forced Air Cooling System (Dwg. No. 2497) w.
Diesel Generators (Refer to B&R Electrical Elementary Dwg. 3073 Sheets 57, 59 and 60) 1.2 Summary Description of the System (Refer to B&R,_Dwg._No_., _
3011, Rev. 7, Sheets 1 and 2 and Dwg. 3091, Sheets 1 to 199)
The SFAS consists of three sections, which are reactor building spray actuation, reactor coolant safety injection (high and-low pressure injection) actuation, and reactor building cooling and isolation actuation.
Each section itself has two redundant actuations called Actuation A and Actuation B.
The signal ultimately actuating each group of equipment in each section is called an ES Actuation j
I97 053 j
. 1 A
Signal and appears at each actuated piece of equipment on its respective B&R system flow diagrams.
The reactor building spray actuation section has six pressure switches that measure reactor building pressure.
The pt'ssure switches are located in the Fuel Handling and J.axiliary Buildings and are protected frcm internal missiles.
The three sensing lines for the pressure switches pass through penetrations in the reactor building.
Each sensing line has a manually operated isolation valve with indicating lights on Containment Isolation Panel 15.
Each isolation valve has an alarm on Engineered Safety Features Panel 13 which annunciates when its respective valve is closed.
Ali six pressure switches are set to actuate when the reactor building pressure rises to 30 psig.
Three of the pressure switches are grouped for Actuation A and three are grouped for Actuation B.
Each group has its three pressure switches electrically connected in a 2/3 logic matrix to the respective spray pump motor starting circuit.
When 2 out of 3 pressure switches for Actuation A or B have actuated, the re-spective reactor building spray pump PS-P-1A or 13 is automatically started.
The discharge valves for the reactor building spray pumps are actuated by the reactor building cooling and isolation actuation when the reactor building pressure reaches 4 psig.
Refer to the Reactor Building Emergency Spray System Description Index No. 28A.
Power for Reactor Building pray Actuation and test is provided by the 12SV DC Distribution Panels (Actuation A from DCC-LA & Actuation B from DCC-2A).
A manual block valve to isolate the line from the Reactor Building, a test switch, solenoid valve and a temporary j
" Test Air" connection are provided for each of the six pressure switches to test and calibrate each switch.
The manual block valves are located inside locked cabinets (Racks 472,455 & 467) and are not instrumented to indicate 197 054
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vblveposition.
Administrative control will assure that the valves are in the OPEN position except when their respective pressure switches are being tested or calibrated.
The Reactor Coolant Safety Injection Actuation section has three pressure transmitters that measure reactor coolant pressure and.are arranged in three channels.
The output signal of each pressure transmitter is sent to.a baffer amplifier.
Each amplified signal is sent to two bistables, a trip bistable and a bypass bistable.
Each bistable has two output signals.
One output signal is for Actuation A and one for Actuation B.
Power for safety injection channels 1, 2,
& 3 is provided by the 120V vital BUSSES 2-lV, 2-2V, and 2-3V respectively for Actuation A and B.
The reactor coolant trip bistables are arranged to change state and de-energize the A and 3 channel output relays when t'he reactor coolant pressure is at or below 1600 psig.
Each channel has the same number of output relays, and each relay has multiple sets of contacts.
The channel output relays are' located in the respective channel com-partment of the A and B Actuation relay cabinets.
Two sets of contacts of one output relay in each channel are w;. red to form a 2-out-of-3 matrix and are connected to the starting or energizing circuit of an individual pince of equipment to be actuated by an ES signal.
When 2 of the 3 channels are tripped, the 2/3 logic is com-pleted through the connected arrangement of channel out-put relay contacts and each group of equipment listed in Table 1 is automatically actuated.
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The reactor coolant bypass bistables are set to change state at a reactor coolant pressure of 1820 psig.
The 197 055 g
logic of the trip and bypass bistables allows the reactor coolant safety injection actuation to be bypassed during normal plant shutdown.
This is accomplished by depressing the reactor coolant bypass push button switch in each Actuation channel when the reactor coolant pressure is between 1820 and 1600 psig.
During plant start-up, when the reactor coolant pressure is between 1600 and 1820 psig, bypass reset push buttons are used to reset each Actuaticn channel.
The trip bistable must have changed state at 1600 psig prior to manual or automatic bypass reset, otherwise trip actuation will occur.
Automatic trip protection will occur at 1820 psig when the bypass bistable changes state.
The trip bistables and bypass bistables are located in three bistable cabinets in the cable room of the control building.
Pressure test modules are provided to test the function of the analog trip logic circuitry of each channel se-parately.
The reactor coolant pressure test modules are used to simulate a reactor coolant pressure transmitter signal to the buffer amplifiers in order 'to test the buffer amplifiers and bistables.
A bistable trip test device is used to test the reactor coolant trip bistable trip contacts and the logic circuitry up to and including the channel output relays "
Actuation A and B.
The reactor coolant safety injection auto actuation 2/3 matrix group test devices, used in conjunction with the TS4 channel selector switch, are used to test the a tomatic actuation of each equipment group separately in Actuation A or B by 5
simulating a tripped condition to the channel output relays for all three possible 2-out-of-3 channel combinations. 197 056
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The reactor coolant safety injection manual actuation and test devices are used to test the manual trip actua-
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tion of each group of equipment individually in Actuation A or a by bypassing the logic circuitry including the channel ou*put relays.
Power for the safety injection test and manual actuation circuits is provided by 125V DC Distribution Panel DCC-lA and DCC-2A for Actuation A and B respectively.
Manual actuation actuates all three groups of equipment simultaneously in Actuation A or B.
The reactor building cooling and isolation actuation section has six pressure switches that measure the reactor building pressure.
These are arranged in two groups of three channels for both Actuation A and B.
These pressure switches are connected to the same sensing lines as the pressure switches for the reactor building spray actuation section and are located with these pressure switches also.
All six pressure switches are set to actuate when the reactor building pressure rises to 4 psig.
The output signal for each pressure switch causes its respective channel output relays to be de-energized to actuate the reactor building cooling and isolation Actuation A and B equipment listed in Table 2, as well as reactor coolant safety injection equipment listed in Table 1.
Power for reactor building isolation and cooling channels 1, 2,
& 3 is provided by the 120V vital BCSSES 2-1V, 2-2V, & 2-3V respectively for Actuation A & B.
A manual block valve to isolate the line frcm the Reactor Building, a test switch, a solenoid valve and a tea.
ary " Test Air" connections are 3
provided for each of the six R.B.
Pressure Switches J
(BS-PS-3 25 9,6 0,61,BS-PS-3 9 8 7,8 8 & 89) to test and calibrate each switch.
The manual block valve 1 are located inside locked cabinets (Racks 472,455 & 4 and are not instru-197 057
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mented to indicate valve position.
Administrative control will assure that the valves are in the OPEN position excep t when their respective pressure switches are being tested or calibrated.
A defeat pushbutton in each channel of reacter building cooling and isolation Actuation A or B is provided to defeat a channel only after actuation has occurred.
This will allow the actuated equipment to be returned to the condition they.were in prior to being actuated.
A defeat reset pushbutton is provided to manually reset a defeat signal in order to restore trip activiation if building pressure is still 14 psig.
When building pressure drops below 4 psig, the pressure switch and logic circuit reset automatically.
The output relays must be reset manually, using the Channel Reset push button.
Reactor building cooling and isolation test devices are provided to test the function of the trip logic circuitry of each channel.
The auto actuation 2/3 matrix group test devices function in the reactor building cooling and iso-lation section the same way as in the reactor coolant safety injection section.
The manual actuation and test devices also function the same and are powered from the same 125V DC Distribution Panel as in the reactor coolant safety injection section, but cause actuation of reactor building cooling and isolation equipment as well as reactor coolant safety injection equipment.
All manual actuation devices are located in the control room on Auxiliary Systems Control Panel 3.
Test devices are located on Auxiliary Systems Control Panel 3 and Engi-neered Safety Features Panel 13.
Status lights for each r
piece of equipment actuated by the SFAS are on Engineered -
Safety Features Panel 13.
Lights, alarms and computer
- inputs are provided in each channel of all three actuation sections of the SFAS to provide indication of the status of each channel.
I97 058
There are two 2/3 logic actuation relay cabinets which are located in the cable room of the control building.
One cabinet is for Actuation A and one is for Actuation B.
Each cabinet is separated into four compartments for channels 1, 2,
3 and manual actuation, with fire barriers.
Wiring between compartments is accomplished through metal clad vire ways.
When groups of equipment containing valves designated as critical service are test actuated, the critical ser.vice test reset switch ES, on Engineers Safety Features Panel 13, are used to return the valves to their normal operating positions as indicated by action of their limit switches.
This provides verificat.'on, by light indication, that these valves operate and re-turn to their normal co.nditons after clearing the Engineered Safety (ES) signal.
This minimizes the ab-normal condition of these valves during the test period.
1.3 System Design Requirements Channels 1, 2 and 3 for Actuation A and B in each actua-tion section are powered separately from the red, green and yellow vital power supplies respectively (2-1V, 2-2V, and 2-3V).
In the reactor coolant safety injection actuation and reactor building cooling and isolation actuation sections, loss of power to any channel results in a channel trip which is its fail safe position.
Since each of the channels is powered from a separate supply, loss of power to one channel will not result in equipment actuation.
Tripping of another channel while one channel is without power will cause equipment actuation because the 2-out-of-3 logic is satisfied.
Loss of power -to a reactor building spray actuation pressure switch does not result in a channel trip.
Since channels 1, 2, and.3 for each actuation section are powered from the same source,-
loss of power disables the actuation section.
197 059
1 Lights and alarms are DC powered or alternatively have vital AC power supply so that each channel status is indicated for all conditions.
Two different power sources from two DC buses (DCC-1A and DCC-2A) provide power for manual and test circuits.
Means are provided for automatic actuation of the reactor coolant safety injection, reactor building cooling and isolation, and reactor building spray sections of the SFAS.
Means of manual actuation are also provided for the reactor coolant emergency injection and reactor building cooling and isolation sections from the control.
room.
Manual actuation through the SFAS is not provided for the reactor building spray section because there are only two pumps requiring actuation.
Therefore, manual starting of the reactor building spray pumps is ac-complished by using their respective control switches in the control room.
Actuation A or B in each of the three actuation sections of the SFAS requires 2-out-of-3 pressure sensing devices to be actuated in order to cause equipment actuation.
This is to prevent equipment actu-ation from a power loss to only one channel.
The failure of a single component or a faulty actuation signal in one channel will not prevent the system from fulfilling its actuation functions nor 'will it initiate unnecessary action of the system.
The SFAS seismic design classification is Class I.
The seismic Class I equipment is designed for Zone.I loads.
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The 2/3 logic actuation relays are separated-in Actuation j
A and Actuation B cabinets.
Lights are provided on both cabinets to indicate the status of each channel.
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"o The SFAS is designed to allow testing of each component of a channel by testing the component individually, by testing sections of a channel, or by testing the entire channel.
Testing devices are also designed to allow auto actuation of each group of equipment individually in the reactor coolant safety injection and reactor building cooling and isolation actuation sections.
Auto actuation can be tested by all three combinations of 2-out-of-3 channels.
Other testing devices are also designed to test manual actuation of each group of equipment individually.
There are three groups of equipment in each actuation section for Actuation A and three groups for Actuation B.
This arrangment is made so that testing of the equipment actuation will not interfere with the normal operation of the plant.
The SFAS is a redundant system in that it has Actuation A and Actuation E.
Each channel is inde-pendent and is electrically and physically separated from the other channels.
2.0 DETAILED DESCRIPTION OF THE SYSTEM 2.1 Components
-2.1.1
- Reactor Coolant Pressure Transmitters RC-3A-PT3, RC-3B-PT3 and RC-3A-PT4 The three reactor coolant pressure transmitters are located inside the reactor building.
They are Foxboro type E-ll GH force balance pressure transmitters with a range from 0 to 1
2500 psig and an electrical output of 10 to 50 ma DC.
The transmitters are designed to withstand the reactor building atmosphere conditions following a LOCA.
197 061.
2.1.2 Reactor Building Pressure Switches for Reactor Building Cooling and Isolation Actuation; BS-PS-3259, 3260, 3261, 3987, 3988 and 3989 For a description of these pressure switches, refer to Table 3 (Instrumentation and Controls) in the Reactor Building Emergency Spray System Description, Index No. 28A.
2.1.~
Reactor Building Pressure Switches for Reactor Building Spray Actuation; BS-PS-3253, 3254, 3255, 3256, 3257, 3258 For a description of these pressure switches, refer to Table 3 (Instrumentation and Controls) in the Reactor Building Emergency Spray System Description, Index No. 28A.
2.1.4 Reactor Coclant Trip Bistables BTl, BT2, BT3 and Reactor Coolant Bypass Bistables BT4, BTS, BT6 The reactor coolant trip and bypass bistables have two outputs each.
One output is for Actuation A and one for Actuation B.
These bistables are set at the minimum dead-band.
The bistables receive an electrical signal proportional to the reactor coolant pressure and are set to change state at a selected pressure.
The bypass bistables are set to change state when the reactor coolant has decreased to 1820 psig.
The trip bistables are set for 1600 psig.
The bistables reset automatically.
2.2 Instruments, Controls, Alarms and Protective Devices
~5 2.2.1 Instrumentation and Controls Major system instrumentation and controls are listed in Table 3.
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2.2.2 Alarms and Computer Inputs Panel mounted annunciators and computer inputs are listed in Table 4.
2.2.3 Protective Devices There are no devices in the SFAS that are provided for the specific purpose of protecting the system itself.
3.0 PRINCIPAL MODES OF OPERATION 3.1 Startup Before normal plant startup commences, the three manually operated isolation valves, in each of the three pressure sensing lines for the reactor building spray actuation pressure switches and the reactor building cooling and isolation actuation pressure switches, must be open.
As the plant is started up and the reactor coolant pressure reaches 1600 psig, the reactor coolant trip bistables reset.
The bypass. bistable manual reset pushbuttons PB2/RCIA, RC2A, RC3A, and PB2/RClB, RC2B, RC3B on the Auxiliaries Systems Control Panel 3 should be actuated to obtain reactor coolant safety injection protection.
If these pushbuttons are not utilized, the bistables BT4, BTS and BT6 will automatically reset when the reactor coolant pressure rises above 1820 psig.
3.2 Normal Operation
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During normal plant operation, the SFAS is in a passive mode.
It detects a LOCA by sensing a decrease in reactor coolant --
pressure and/or increase in reactor building pressure which result when a LOCA occurs.
The reactor coolant -emergency ---
.. injection actuated equipment Iisted in Table -1 is automati- -
cally actuated by the reactor coolant emergency injection actuation section when the reactor coolant pressure is decreased to 1600 psig.
When the reactor building pressure increases to 4 psig, the reactor building cooling and isolation actuation section automatically actuates the reactor building cooling and isolation equipment listed in Table 2.
It also automatically actuates the reactor coolant emergency injection actuated equipment listed in Table 1 if it has not been actuated by a low reactor coolant pressure occurrence.
The reactor building spray pumps are automatically actuated by the reactor building spray actuation section when the reactor building pressure increases to 30 psig.
3.3 Shutdown During normal plant shutdown, the reactor coolant pressure decreases as it is cooled.
When the reactor coolant pressure decreases to 1820 psig, the reactor coolant low pressure trip bypass permit light and cirucit will be actuated in each channel for reactor coolant safety injection Actuation A and B.
The reactor coolant safety injection manual by-pass pushbuttons PB2/RClA, RC2A, RC3A, and PB2/RClB
- RC2B, RC3B must be actuated after the permit light and circuit are actuated, but before the reactor coolant pressure has decreased to 1600 psig.
This action is required to prevent unnecessary actuation of the reactor coolant safety in-jection equipment during shutdown.
An alarm on Control-Panel 13 set at 1650 psig annunciates if the bypass has not been actuated.
The reactor building spray actuation and reactor building
-[
cooling and isolation sections maintain their passive mode of operation and provide continuous protection during and after shutdown. 197 064 e,---
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3.4 Special or Infrequent Operation Manual testing as discussed in Section 1.2 is provided for on-line-testing to prove operability and to demonstrate reliability.
3.5 Emergency 3.5.1 pianual Actuation by the SFAS during a LOCA If a LOCA occurs and the SFAS has not automatically actuated the emergency equipment, manual actuation by the SFAS is available at all times and the manual actuation pushbuttons on the Auxiliaries Systems Control Panel 3 are utilized to actuate the emergency equipment.
4.O HAZARDS AND PRECAUTION The primary safety precaution to be observed in the operation of the SFAS is to make certain that all manually operated isolation valves, in the sensing lines for the reactor building pressure switches in the reactor building spray section and the reactor building cooling and isolation section, are open during plant operation.
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197 065 M
TABLE I REACTOR COOLANT SAFETY INJECTION (HP AND LP INJECTION) ACTUATED EQUIPMEN7 ACTUATION A GROUP 1 Group 2 Group 3 DC-P-1A DH-V4A DH-P-LA DC-V96A DH-VSA MU-V16A DF-X-1A DH-V8A MU-V16B MU-P-1A DH-V102A MU-V36 (Critical Services Valve)
NR-P-1A MU-P-1B NR-P-1B NS-P-1A NR-V9A NR-V42A G2-12 NR-V40A NS-V84B T-lE-2E-2 NS-P-lC Bus 2-lE (Auto Loading)
T3E-4E-2 T12E-22E-2 T31E-41E-2 TllE-21E-2
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197 066
TABLE I (Cont.)
REACTOR COOLANT SAFETY INJECTION (HP AND LP INJECTION) ACTUATED EQUIPMENT ACTUATION B Group 1 Group Group 3 DC-P-1B DH-V4B DH-P-1B DC-V96B DH-V5B MU-V16C DF-X-1B DH-V8B MU-V16D MU-P-1B DH-V102B MU-V37- (Critical Services Valve)
NR-P-lD MU-P-lC NR-P-lC NS-P-1B NR-V9B NR-V42B Bus 2-2E (Auto loading)
NR-V40B NS-V32 k (Critical Services T2E-lE-2 NS-P-lC NS-V67 Valves)
T4E-3E-2 T22E-12E-2 NS-V83A T21E-llE-2 NS-V83B NS-V84A NS-V215 NS-V216 T41F-31E-2 p
=
e 4
197 067 b
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TABLE 2 REACTOR BUILDING COOLING AND ISOLATION ACTUATED EQUIPMENT Actuation A
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Group 1 Group 2 Group 3 AH-V81 AH-E-4A AH-C-8A AH-V101 AH-E-llA AH-E-llB AH-V102 AH-E-25 AH-E-llc AH-V105 AH-R-5244 AH-E-12A AH-V107 AH-V125A AH-E-12B CF-Vll6 BS-VlA AH-E-19A CF-V144 BS-V4A AH-E-19B DC-Vil4 CA-V2 AH-P-1A DH-V3 CA-V4A AH-VlA NM-V52 CA-V5B AH-VlB NR-V51A CA-V9 AH-V4A RB-Z-1A CA-V10 AH-V4B RR-V2A DH-V3 AH-V5 RR-V2B RB-Z-1B AH-V60 RR-VSA RR-P-1B AH-V62 RR-V5B RR-V25C AH-V72 RR-V5C WDG-V6 AH-V74 SV-V55 WD -Vl99 IC-P-1A WDL-V1095 WDG-Vll26 IC-V27 WDL-P-2A IC-V5 WDL-V22 MU-VA Critical WDL-V270 MU-V2B Service MU-V18 Valves MU-V372 NR-P-2A NS-V72 Critical NS-V81 Serv. Vivs RR-P-1A RR-V25A RR-V25B RR-V25C
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I97 068 -
TABLE 2 (Cont. )
REACTOR BUILDING COOLING AND ISOLATION ACTUATED EQUIPMENT Actuation B Group 1 Group 2 Group 3 AH-E-llD AH-D-4073 AH-C-8B AH-V80 AH-E-4B AH-E-llE AH-V103 AH-E-5 AH-E-12A AH-V104 AH-E-llc AH-E-12B AH-V106 AH-EP-5246B AH-E-19A AH-V108 AH-V125B AH-E-19B CF-Vil5 BS-VlB AH-P-1B DC-V103 BS-V4B AH-V2A DC-Vil5 CA-V1 AH-V2B DH-V2 CA-V3 AH-V3A NM-V104 CA-V4B AH-V3B NR-V51B CA-V6 AH-V6 RR-V2C CA -V8 AH-V61 RR-V2D RR-P-lD AH-V63 RR-V6C RR-V25C-S2 AH-V71 RR-V6D WDG-V.
IC-P-1B RR-V6E WDL-P-2A IC-V3N SV-V54 WDL-P-2B IC-V4 WDL-V1092 WDL-V271 MU-V2B Critical WDL-Vll25 MU-V18 Service MU-V25 Valves MU-V376 NR-P-2B NS-V100[ Critical Service Valve RR-P-lC RR-V25D RR-V25E
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TABLE 3 INSTRUMEtJTATIOti At3D cot 4TROLS Input OutpuL Identification Description Function Location TyQe Hange Range Setpoint TPS-3253,3254, Test Energizes the solenoid valve Engineered Pushbutton H/A N/A N/A 3255,3256,3257 Switch in the pressure sensing line Safety Features
& 3258 to reactor building pressure Panel 13 switch BS-PS-3253, 3254, 3255,3256,3257, 3258 for building spray pump DS-P-1A/
ID in order to calibrate and test the pressure switch with a temporary air test connec-tion.
TPS-3259,3260 Test Energizes the solenoid valve Distable Cabinets Pushbutton N/A N/A.
N/A
& 3261 Switch in the pressure sensing line A/D to raactor building pressure switch DS-PS-3259, 3260, 3261 for building cooling and isolation actuation A,B for channels 1,2, and 3 in order to calibrate and test the pressure switch with a tem-porary air test connection.
PDl/RCA RCD Switch Provides manual actuation of Aux 111arles Pushbutton N/A N/A N/A all rear. tor coolant safety in-Systems Control jection actuated equipment for Panel 3 actuation A,D or test actuation of any group of equipment for actuation A,D.
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l TAllLE 3 (Continued)
INSTRUMENTATIOtt AND CONTROLS Input Output Identification Description Function Location Type Range Range Setpoint PBl/RDA/RBB Switch Provides manual actuation of Auxiliaries Pushbutton N/A N/A N/A all reactor building cooling Systems Control and isolation actuated equip-Panel 3 ment for actuation A,B or i
test actuation of any group of equipment for actuation A,B.
(Actuation of all re-actor building cooling and isolation actuated equipment includes reactor coolant safety injection equipment).
PB2,PB3,PB4/
Switch Provides a means of testing the Auxiliaries Pushbutton N/A N/A N/A manual actuation of a selected Systems Control l
RCA and PD2, P B 3, PB4/RCB group or groups during test of Panel 3 reactor coolant safety injection actuation A.D.
PB2,PB3,PD4/
Switch Provides a means of testing the Auxiliaries Pushbutton N/A 11/A N/A manual actuation of a selected Systems Control RDA and PD2, Panel 3 PB3, PD4/RDB group or groups during test of reactor building cooling and isolation actuation A and D.
PB8/RCA,RCB Switch Provides a means of energizing Auxiliaries Pushbutton N/A N/A N/A the holding coils of groups Systems Control 1,2,3 of the reactor coclant Panel 3 safety injection A,B equipment and the ree.ctor building cooling and isola.gon A,B actuated equip-ment during test for actuation A,B.
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's TABLE 3 (Continued)
INSTHUMENTATION AND CONTHOLS Input Output i
Identification Description Function Location Type Range Range Setpoint j
TS4/RCA,RCB Selector Provides a means of lining up Engineered Manual N/A N/A N/A Switch the auto actuation 2/3 matrix Safety Features Selector test to test the actuation Panel 13 of group 1,2,3 of the reactor coolant safety injection A.D equipment by causing actuation of each group with all three possible 2/3 matrices using test switches TS1, TS2, TS3/
RCA/ RCD.
TS1, TS2, TS3/
Switch Provides a means of testing the Engineered Pushbutton N/A N/A N/A RCA,RCB auto actuation of group 1,2,3 Safety Features of the reactor coolant safety Panel 13 injection A,D equipment by causing actuation of the group.
TS4/RDA,RDB Selector Provides a means of lining up Engineered Manual N/A N/A N/A Switch the auto actuation 2/3 matrix Safety Features Selector test to test the actuation Panel 13 of group 1,2,3 of the reactor building cooling and isolation A,8 equipment by causing actua-tion of each group with all three possible 2/3 matrices using test switches TS1, TS2, TS3/RBA,RBD.
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i TADLE 3 (Continued)
INSTRUMENTATION AND CONTROLS Input Output Identification Description Function Incation Type Range Rango Setpoint Pal /PDIA, RB2A Switch Provides a means of manually Auxillaries Pushbutton N/A N/A N/A RB3A and PB2/
defeating a reactor building Systems Control i
RBlB, RB2B, RB3B cooling and isolation actua-Panel 3 tion signal after actuation has occurred to allow the actuated equipment to be returned to their operating condition prior to being actuated.
PD2/RBIA, RD2A, Switch Provides a means of manually Auxillaries Pushbutton N/A N/A N/A RB3A and PB2/
resetting a defeat actuation Systems Control RBIB, RB2B, RB3B signal to all reactor building Panel 3 a
cooling and isolation actuated equipment in order to restore trip protection.
Reactor Coolant Pressure Provides a means of simulating Distable Manual Varied 0-+10VDC N/A Pressure Test Signal any reactor coolant pressure Cabinets Dial Manually I
Units (3 Units)
Simulator to test the output of the No. 124, 125, 126 C124, C125, buffer amplifier and bistablca C126,
in each channel Reactor Coolant Switch Provides a means of testing Distable Key N/A N/A N/A Distable Trip each of the trip bistables to Cabinets Switch Test Switch emit a trip actuation signal.
No. 124,125,126 (3 switches)
C124,C125, C126
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TABLE 3 (Continued)
INSTRUMENTATION AND CONTitOLS Input Output Identification Description Function Incation Type Range Range Setpoint critical service Switch Dy being held in the reset Engineered Safety Normal-Reset N/A N/A N/A j
valve switches position it allows critical Features Panel 13 with Spring i
service valves to automati-Return to
[
cally return to their nonnally Normal open position after being closed by teot actuation.
YM-FilS-4 3 3 0 Test Reset Test reset switch for Rn Switch Isol.
"A" Group 3 IC-V2, IC-VS, MU-V2A, MU-V2D, MU-V377, NS-V72 & NS-V81.
YM-FilS-4 3 H Test Reset Test reset switch for RB Switch Isol. "D" Group 3 IC-V3, IC-V4, MU-V376, MU-V18, MU-V25 & NS-V100.
YM-FilS-4 3 3 2 Test Reset Test reset switch for SI Switch Act.
"B" Group 3 MU-V37, NS-V32 & NS-V67.
YM-FliS-4 37 7 Test Reset Test reset switch for SI Switch Act. "A" Group 3 MU-V36.
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9 TABLE 4 (Continued)
PANEL MOUNTED ANNUNCIATORS AND COMPUTER INPUT LISTING COMPUTER INPUTS:
Alarm Setpoints Input Variable Identification Heasured Variable, units liigh
' Low Source Range "A"=2836,2837,2838 Reactor building spray pressure 30 peig N/A Pressure switches 0-100 psig "B"=3281,3264,3265 switches A/D actuated.
DS-PS-3253,3254,3255/
3256,3257,3258 2839,3050 Reactor building spray 2/3 logic N/A N/A 2 out of 3 channel energized /
con.plete actuation A/D.
output relays for deenergized actuation A/D.
"A"=2821,2822,2823 Reactor coolant emergency injection N/A 1820 Reactor coolant not triggered /
"D*=2846,2847,2848 actuation A/D bypass permitted in psig bypass bistable triggered channel 1,2,3.
DT4, DT5, DT3 "A"=3161,3162,3163 Reactor coolant pressure below 1600 N/A 1600 reactor coolant trip not triggered /
"B"=3164,3165,316E psig in channel 1,2,3 for actua-psig bistable DT1,DT2,DT3 triggered tion A/D.
"A*=2815,2816,2817 Reactor coolant emergency injectjon N/A N/A manual actuation and deenergized/
- B"=2840,2841,2842 manual actuation or test of equipment test logic relay energized group 1,2,3 for actuation A/D.
"A*=2818,2819,2820 Reactor coolant emergency injection N/A N/A 2 out of 3 channel energized /
- D"=2843,2844,2845 2/3 logic complete in equipment group output relays for deenergized 1,2,3 for actuation A/D.
actuaction A/D.
"A"=2833,2834,2835 Reactor building cooling and iso-4 psig N/A pressure EWitches unactuated /
"B"=3278,3279,3280 lation pressure switches A/B DS-PS-3259,3260,3261, actuated actuated.
DS-PS-3987,3988,3989
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