ML20128B929
| ML20128B929 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 06/27/1985 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20128B916 | List: |
| References | |
| NUDOCS 8507030389 | |
| Download: ML20128B929 (5) | |
Text
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ATTACHMENT Consumers Power Company Big Rock Point Plant Docket 50-155 PROPOSED TECHNICAL SPECIFICATION PAGE CHANGES June 27, 1985 8507030389 850627
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PDR ADOCM 05000155 P
PM 4 pages IC0685-0233-NLO4
9 48 5.2.3 Liquid Poison System (Contd) concentration in the reactor water has been reduced to 100 ppm or less.
One squib primer and trigger assembly from the equalizing line shall be removed and test-fired at least every 18 months. These shall be tested on an alternate basis ensuring valve replacement every 36 months.
One squib primer and trigger assembly from the remaining five units shall be removed and test-fired at least every 18 months.
These shall be tested on an alternate basis.
In no case shall a squib primer and trigger assembly remain in service longer than five years. The tests shall consist of monitoring of the input firing current and shearing of the integral inlet cap.
5.2.4 Reactivity Coefficients During initial loading of a core, the moderator temperature and void coefficients shall be measured.
(a)
The power coefficient shall meet the following requirement at all times during the reactivity life of the core: The control rod movement required to produce a given power change with the reactor pressure constant and the reactor water at saturation temperature with this pressure shall always infer a negative power coefficient.
(b)
The moderator temperature coefficient, over the reactivity life of the core (inferred from critical control rod position),
during uniform heating of the core shall be limited such that the potential maximum ok k
added by heating the moderator isalwayslessthanoneIbkaIgg (c)
The overall effect of increasing reactor power at constant pressure shall be a loss of reactivity whenever the reactor is operating so as to produce a net steam flow. The only condition under which a positive effect could be produced would be low temperature, in which case no steam voids would be formed. The increase in moderator temperature could then produce a small positive effect.
Proposed TSB0585-0200A-NLO4 L.
57 6.1.4 (Contd)
(Deleted)
(d)
Emergency Condenser Control A pressure switch shall initiate automatic operation of the emergency condenser if the reactor pressure reaches 100 10 psi above the reactor operating pressure.
6.1.5 Operating Requirements (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 less frequently than once every 18 months.
Proposed TSB0585-0200A-NLO4
59 6.2 CONTROL ROD WITHDRAWAL PERMISSIVE SYSTEM 6.2.1 Interlocks Interlocks shall prevent control rod withdrawal when any of the following conditions exist:
(a)
When any 2 of the 32 scram accumulators are at pressure below 700 psia.
(b)
When 2 of the 3 power range channels read below 5 percent on their 0 to 125 percent scales (or below 2 percent on their 0 to 40 percent scales) when reactor power is above the minimum operating range of these channels. This interlock may be bypassed when all three of the power range channels are set on the minimum operable range.
(c)
When the scram dump tank is bypassed.
(d)
When the mode selector switch is in the shutdown position.
6.2.2 Operating Requirements The control rod withdrawal permissive interlocks shall always be operable.
No further withdrawal of control rods will be permitted if one of these circuits is found to be inoperable.
Permissive circuits shall be functionally tested prior to each major refueling but no less frequently than every 18 months. However, the refueling interlocks will be functionally tested prior to each major refueling.
6.3 REFUELING OPERATION INTERLOCK SYSTEM 6.3.1 Reactor Refueling System All of the trip devices not bypassed by the mode selector switch in the refuel position shall be operative during all refueling operations. This shall include the sensors and trip devices of the reactor safety system as specified for power operation as follows:
High Reactor Pressure Low Reactor Water Level High Containment Sphere Pressure High Scram Dump Tank Level Loss of Auxiliary Power Supply High Neutron Flux Short Period Manual Scram Proposed TSB0585-0200A-NLO4
7 76a 7.6 (Contd)
Reference Procedure System or Function Frequency of Within These Urdergoing Test Routine Tests Specifications Containment sphere access 6 months or less airlocks leakage rate Control rod performance At each major refueling Section 5.2.2 shutdown **
Liquid poison system Two months or less during Section 5.2.3 component operability power operation. One equalizing line squib and one remaining squib assembly test fired at least every 18 months.
Reactor safety system At each major refueling Section 6.1.5 scram circuits requiring shutdown
- plant shutdown to check Reactor safety system scram One month or less Section 6.1.5 circuits not requiring plant shutdown to check Containment sphere isola-At each major refueling Section 6.1.5 tion trip circuits shutdown
- Emergency Condenser At each major refueling Section 6.1.5 Trip Circuits shutdown
- Control rod withdrawal per-Prior to each major Section 6.2.2 missive interlocks function refueling shutdown
- Refueling operation At each major refueling Section 6.3.3 controls function shutdown Calibration and functional One month or less Section 6.4.3 test of air ejector off-gas and stack-gas monitors Calibration of emergency One month or less Section 6.4.3 condenser vent monitors Calibration of process one month or less - Ef-Section 6.4.3 liquid monitors fluent to Canal monitor Three months or less -
Section 6.4.3 Remaining monitors
- But no less than once every 18 months l
- But no less than once every 20 months Proposed TSB0585-0200A-NLO4 L