ML20236N550
| ML20236N550 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 11/09/1987 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20236N440 | List: |
| References | |
| NUDOCS 8711160224 | |
| Download: ML20236N550 (15) | |
Text
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ATTACHMENT 1 .
I Consumers Power Company Big Rock Point Plant Docket 50-155 PROPOSED TECHNICAL SPECIFICATION PAGE CHAGES November 9, 1987 l
9711160224 871109 ADOCK 05000155 PDR P PDR i
7 Pages TSB0887-0118-NLO4 C____-._ '
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28 CORE CONFIGURATION l
-SECTION THROUGH FUEL '
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,uEL ou~0LE ANO C AN~EL FOS,1,0N COORD, NATES l OUT-OF-CORE INSTRUMENTATION J
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54 6.1~.2.1.' Source Range Monitor' Channel - Channels 6 and 7 sha11' provide logarithmic neutron flux level and period information from' source.
level:to'seven' decades above: source'1evel,.without moving detectors
'(approximately 10~1(to10~3%;of rated-power). 'The principal-
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components:in each channel.shall be a neutron detector, current. pulse-
>- . amplifier , source ~ range monitor instrument,' log count rate meter, log'
..' count-rate recorder and~ period meter._. Gas-filled Boron-10 lined Y -
40 4 proportional counters with a sensitivity of approximately, j
L12s counts /nvishall be used.as' detectors. SProvisions shall'be made for. remotely positioning lthe detectors. JBy movingLthe detectorsfaway
.from the midplane of the core, their effective. range may be~ extended.
1( short period on.either channel:shall'be annunciated in the control _!
-room..
6.1.2.IIDeleted ']
. a v.11 provide 6r1.2-3. Power-Range Monitor Channel -_ Channels 1. 2 and_3 logarithmic neutron. flux level.information'and per od scram protection'from approximately71 x 10~7 %'to 1%: rated power and linear ]
= neutron flux level-information from approximately 1% to 150%.ratedf ,
' power for the 84 fuel' bundle (core._ The principal components in each_ 1 channel shall- be: a neutron' detector,1 DC-wide range monitor, power level and period recorders and operatorfdisplay. assembly which jl indicates-powerflevel_and' period...The detectors'shall;be-gamma .l compensated ion chamb'rs e with a design sensitivity.of at least 1 2.2 x 10~l4 amperes /nv.. The channel-output shall be connected to.the:
reactor safety system-to provide high neutron-flux and short period scram. protection.-
6.1.2.4 In-Core Flux Monitors'- In-core' flux monitors shall be used to evaluate predicted power distributions and detect power oscillations or deviations from expected power distributions in time 3 for the t-operator to take corrective action to-avoid, exceeding local heat flux
. limits.
6.1.2.5- Deleted I
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57 6.1.5 Operating Requirements i
(a) Except as otherwise provided in these Technical Specifications, )
the reactor safety system shall be OPERABLE during POWER OPERATION as indicated in Section 6.1.2. This system shall be functionally tested during each MAJOR REFUELING shutdown, but not less frequently than once every 18 months and in addition shall be tested not less frequently than once a month using the switches provided to simulate sensor trips. ,
(b) The emergency condenser system control initiation sensors shall be functionally tested at each MAJOR REFUELING shutdown but not l 1ess frequently than once every 18 months.
(c) Both source range monitor channels shall be CPERABLE and measuring flux from the core during reactor start-ups, prior to the power level at which the power range monitor channels become l operative. -However, if one of the two source range monitor channels become inoperative during the course of start-up and prior to the power level at which the power range monitor channels become operative, then it will be permissible to hold
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the control rod pattern and power level attained until both !
channels are again OPERABLE.
(d) Deleted.
(e) All power range monitor channels shall be OPERABLE and able to provide:
(1) Logarithmic neutron flux level information and period scram protection during reactor start-up from approximately j 1 x 10 7% to approximately 1% of rated power. For reactor operation above approximately 1% of rated power, logarithmic neutron flux level information and period scram l protection are not required.
(2) Linear neutron flux level information and high neutron flux !
scram protection from approximately 1% of rated power to ]'
rated power.
Any one of the three power range monitor channels may be taken out of service for surveillance testing or maintenance during reactor operation. If one channel is out of service, a trip on l either of the two remaining channels shall scram the reactor.
When maintenance is necessary, no major changes in power level, flux distribution or control rod pattern shall be made.
(f) During POWER OPERATION in-core flux monitors shall be operating to insure that local heat flux limits specified in Section 5.2.1 are not exceeded.
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i I Proposed TSB0887-0118-NLO4 u_
, . c 58 6.1.5 (Continued)
-(g) Protection against a " cold-water accident" is provided by recirculation pumps and valve interlocking. The valves on either side of the recirculating pumps are interlocked with' pump
. power such that each valve must be in its proper position before the pump motor can be starsed. If the suction valve-to the pump L is closed, the motor will be tripped. If the discharge valve and bypass valve are closed, the motor will be tripped.
(h) Minimum nuclear instrumentation in operation during SHUTDOWN operacion shall be the same as that required for REFUELING OPERATION, except that only one source range monitor channel shall be required.
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' CONTROL ~ ROD WITHDRAWAL PERMISSIVE SYSTEM g
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' ' " . 6.2'.1- -' Interlocks' l- ' Int'erlocks"shall prevent. control rod withdrawal when any of the ifo11owing conditiona exist:
e (a)(Whenanytwoofthethirty-two'scramaccumulatorsareat'-
t pressure below 700 psia.
1 (b) Rhen any?one of the'three power range l monitor channels reads: : 1
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'(1) .Less than 1 x 103 power, when reactsr power is above.t he N operating range of,thefsource range monitoring channels,
-(2) Greater than 105% power,'or
< (3) LA reactor period less than 15. seconds.
(c) .Vnen'the scram dump tank is bypasse'd. .,
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(d) When'the. mode selector switch is in the shutdown' position.
6;2.2 Opbrating Requirements-
'The control rod' withdrawal permissive interlocks shall always_ ben N .0PERABLE. 'No further withdrawal of control rods will'be-permitted-
.if'one of.these circuits.is found to-be inoperable.
' Permissive circuits 'shall be furictiodally tested prior to .each MAJOR- h 5
< REFUELING but no-less frequently than every 18 months. However, the' <
refueling interlocks will be- functionally ' tested prior to each MAJOR' .)
REFUELING. !
y 6.3- ' REFUELING OPERATION INTERLOCK SYSTEM 6.3.1
- Reactor' Refueling System. i
'n All of the ' erip devices not bypassed by the mode selector switch in' ,
.the refuel position shall be OPERABLE during all-REFUELING OPERATIONS. This shall include the sensors and trip devices of the..
reactor' safety. system as specified-for POWER OPERATION as follows:
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- High Reactor Pressure Low Reactor Water Level High Containment Sphere Pressure .]
High Scram-Dump Tank Level ,
Loss of Auxiliary Power Supply f
High' Neutron Flux l
'Short Period i Manual Scram l
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' :/ 7 3. 4 NORMAL P0llER OPERATION- i
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[. 'During normal POWER; OPERATION, the initial pressure regulator shall
. maintain-the reactor pressure at ite rated value by operating the turbine admission' valves. The turbine-generator load shall be
- established by the' control rod positions. The principal function of
. the operating personnel during this period s' hall be as follows: ,
[(a)' The maintenance'of a continuous watch in the control room for
. prompt attention to any annunciated alarms.
'(b)- The adjustment of the control rod. pattern to accommodate changes
'in reactivity and to mainta1n the desired power distribution.
l(c) The' evaluation of abnormal conditions and the initiation of
. corrective action as required. <
7.3.5 EXTENDED SHUTDOWN An extended SHUTDOWN shall be accomplished as follows:
'(a) Reactor power shall be reduced by manipulation of the control rods, and the main generator. load shall be decreased simultaneously. The turbine-generator shall be separated from the system.
(b) 'All centrol rods shall be inserted.
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(c) The. removal _-of reactor decay heat and the reduction of reactor pressure shall be accomplished by controlling reactor steam i flow. The rate of cooling of the reactor vessel shall not be allowed to exceed 100'F per hour.
R' (d) The' reactor shutdown cooling system shall be placed in operation whenever reactor pressure drops below a pressure sufficient to' :l maintain turbine seals. This system will complete the cool 1ng 1 of the reactor water'to 125'F.
(e) A minimum of one source range tionitor channel and one power range monitor channel shall be left in operation. All l instrumentation pertaining to control of activity release shall O be lefe in operation. {
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i' 7 . 3. 6 -- SHORT DURATION SHUTDOWN A SHUTDOWN of short duration may be accomplished while maintaining i system pressure. The turbine-generator shall be unloaded and l l ..
separated from the system. Reactor heat shall be accommodated by, l l
l system losses or bypassing steam to the main condenser.
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.I ATTACIDIENT 2:
Consumers Power Company l Big Rock Point Plant
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Docket 50-155
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4 POWER RANGE MONITOR SYSTEM DESCRIPTION November 9, 1987 4
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POWER RANGE MONITOR SYSTEM DESC'RIPTION i
Power Range Monitor Channels 1, 2 and 3 provide indication of neutron flux over the range of'1 x 10 % ~7 to'150% power. They are designed to measure intermediate and power range neutron fluxes when used with a compensated ion
.chambet., From the lower end of the measuremcat range to 1% power, a logarithmic j output is produced which automatically switches'to a 11 rear output between i 1% power and 150% power. The Power Range Monitor also overlaps the range ,
covered by;the Source Range Monitor by approximatley four decades, q Compensated ion chambers, RE-RIO2C, RE-RIO2B and RE-RIO2A, provide a-continuous de current' output in direct proportion to neutron flux level in the core. The ion chambers are located in vertical guide tubes at 120' positions around the core. They can be manually positioned by a winch located at the top of the-guide tubes. ,
The Power Range-Monitors are constructed of standard plug-in modules in a .
I chassis designed for instrument. rack mounting. Maintenance is accomplished by ,
]
module replacement. Chassis slides provide access to the top loaded modules ,
when the instrument is in its extended position. Instrument interfacing cables are connected on the' top rear section of the chassis deck. !
Compensated ion chamber outputs are directly connected to DC-wide range i monitors, RT-RIO9C, RT-RIO9B and RT-RIO9A located in the control room. A dual I
.high voltage power supply module, contained within the DC-wide range monitor, provides positive and negative de polarizing voltages for the compensated ion
-1 chamber. The input signal from the compensated ion chamber is conditioned and j amplified by the DC-wide range monitor femtoammeter module which is tied to an !
internal computer bus. The linear and logarithmic flux measurement functions, i the high flux /short period / rate of change trips and alarm functions, internal j compensations and-instrument calibration are performed by a micro-computer.
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l An operator interface is provided which includes a multi-functional " pixel"
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' display having digital and graphical presentations of output readings, trip settings and status, self-test and calibration data. A remote read-only j 1
operator display assembly. RM-RIO3C, RM-RIO3B and RM-RIO3A, is available for operators on the C01-C benchboard. This remote display consists of an electro-luminescent. display and display control logic module with function keys only.
l Two analog outputs, logarithmic power and linear power, are used. The output !
voltage signals drive two-pen continuous recording flux level recorders RR-RIO5C, RR-RIO5B and RR-RIO5A.
Alarm / trip set points are stored digitally in non-volatile memory. An internal calibration check facility, automatic on-line calibration, instrument self-test and operator / user prompting via the front panel display are provided.
Power Range Monitor trip contacts are connected to Reactor Protection System Channel.1 and Channel 2. Through Reactor Protection System logic, if two of three Power Range Monitors are tripped, a control rod scram is initiated.
Power Range Monitor trip contacts are actuated by: Hir. neutron flux at 120% power; short reactor period of 10 seconds when c,; rating between 1 x 10~7% power and 1% power; exceeding the MWt/ min rate of change of 50 MWt/ min between 1% power and 50% power or 20 MWt/ min between 50% power and 83.3% power; and loss of either (or both) high voltage power supply.
Additional reactor protection from instrument circuit failure is achieved by scramming the reactor when one Power Range Monitor is indicating less than 1 x 107 % power (downscale), and a second Power Range Monitor is tripped due to high flux or short period or rate of change (upscale).
All trip contacts go to the tripped condition upon loss of power to the Power
-Range Monitor. Also, all Power Range Monitor trips are annunciated on the Nuclear Steam Supply System annunciator panel in the control room.
MIO787-1583A-BT01-NLO4
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[ The Power Range Monitor also provides input to'the Nuclear Steam Supply System l
annunciator panel to warn of approaching trip limits. Annunciation occurs at:
105% power;'15 second reacter period between 1 x 10 ~7 % power.and 1% power; 37.5 MWt/ min between 1%' power and 50% power; 15.0 MWt/ min between 50% power-and f
83.3 power; or 10.0 MWt/ min when above 83.3% power.
The above annunciation set points, that warn of approaching trip limits, also open contacts in the control rod drive withdrawal permissive circuity. Thus, if an alarm is actuated, the operator is prevented from withdrawing control rods another notch until the alarm has cleared. One contact from e'cha Power '
Range Monitor, wired in series, provides this function.
Three additional contacts, one from each Power Range Monitor, are wired in j
' series with the above permissive circulty. These contacts open on power failure, close at greater than 1 x 10 7% power, and open at less than i
-1 x 107 % power. In parallel with these'three contacts are two contact's in i
series, one from each Source Range Monitor. The Source Range Monitor contacts a
open on power failure, open at less than 1 cps, close from 1 cps and to j 4000 cps, and open at greater than 4000 cps. This arrangement permits Control rod drive withdrawal, provided both' Source Range Monitors are operating, up to 4000 cps (4'x 106 % power). At 4 x 106 % power, the Source Range Monitor l contact. ither' contact) open and withdrawal permissive must now come through the Power Range Monitor contacts. The control rod drive withdrawal permissive ,
circuitry then requires all three Power Ranger Monitors indicating greater than 1 x'10~7 % power.
Three contacts, one from each Power Range Monitor, are wired in series with the refuel setback relay (4K40) . These contacts open on power failure, close from 0% power to 0.4% power, and open at greater than 0.4% power. These contacts prevent control rod withdrawal when any Power Range Monitor is greater than 0.4% power and the reactor mode switch is in the refuel position.
MIO787-1583A-BT01-NLO4 A =___ _-
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1 IJ ATTACHMENT.3 j j
Consumers Power Company -J l Big' Rock Point Plant l Docket 50-155 'i
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POWER RANGE MONITOR BLOCK DIAGRAM i (CHANNELS-1, 2 and 3)
November 9, 1987 l
l 1 Page MIO787-1583A-BT01-NLO4
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POWER RANGE MONITOR BLOCK DIAGRAM ;
E (CHANNEL 1, 2 AND 3) i i
COMPENSATED' ION CHAMBER i
, > > RE-RIO 2 C/B/ A
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LJLJLJ i j ENCLOSURE 120 i
"/ PENETRATION VAC
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RPS SIG J5 CHANNEL 1' ]
I J4 2 RPS !
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+HV - DC-WIDE RANGE MONITOR CHANNEL 2 A1J3 .
REFUEL J9 =
RT-RIO9C/B/A _ - SETBACK
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A1J4 ANNUN.
J6 = CRDI . .
PERMISSIVE J7 J3 J2 FLUX 120 x REMOTE RECORDER VAC / J3 DISPLAY gg. RR-RIO5C/ B/ A R103C/B/A l:
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ATTACHMENT 4 .
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Consumers Power Company 1 Big Rock Point Plant Docket 50-155 NED0-30883-A GE LICENSING TOPICAL REPORT (NUMAC-LRM)
November 9, 1987 i
(
l 60 Pages MIO787-1583A-BT01-NLO4
)
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