ML20010B996
| ML20010B996 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 08/05/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20010B994 | List: |
| References | |
| TASK-2.E.4.2, TASK-TM NUDOCS 8108180615 | |
| Download: ML20010B996 (4) | |
Text
i 1
ATTACHMENT TO LICENSE AMENDMENT NO. 45 FACILITY OPERATING LICENSE NO. DPR DOCKET NO. 50-155 Revise Appendix A Technical Specifications by removing the page identified below and inserting the enclosed pages. The revised page contains the captioned amendment number and a' vertical line indicating the area of change.
Pg*
6-3
- The following pages are-included for format purposes only: 6-4 and 6-5.
-on
6.1.2-(Contd)
Trip Scram Contacts Coincidence Settir.g Warning Sensor and in Each in Each and Instrument Annunciation Trip Device Channel Channel Tolerance Special Features Ranges Trip Set Point High enclosure 2
1 out of 2 1 1.0 psi Closes containment 0 - 20 psig pressure (4 pres-above sphere isolation sure switches) atmospheric
- valves High scram dump 2
1 out of 2 5/1611/2 inch Alarms at level of Fixed level at -10"il /2" : bel ow.
tank level (4 below tank 10 inches below tank trip point tank center level switches) center line center line.
(no. range).
line.
T w
Recirculation 12 1 set out Approximately Position switch line va~ives of 2 10 percent of adjustable for closed (two cets full simulta-full valve of 6 position neous closure travel switches in each of both dis-of 2 channels) charge or both suction valves
,, n gg or any combina-y tion of both of ga these valves, gg one in each loop.
2
.N
- 5
- To be implemented at a convenient outage but not later than the refueling outage scheduled for the.first quarter.1982.
6.1.2 (Contd)'
Trip Scram Contacts Coincidence Setting karning Sensor and in Each in Each and Instrument Annunciation Trip Device Channel
- Channel, Tolerance Special Features Ranges Trip Set Point I
52 20 volts.
Closes all automat-
. Loss of auxiliary 1
1 out of 1 ically actuated con-power supply (voltage relay) tainment sphere isolation valves.
I 120 5 percent Interlocks prevent 0 to 125%
High neutron flux 3
2 out of 3 (each of 3 power of the 0 to 125 control red with-range flux monitors percent scale, drawal as described
? has a trip contact or 3812 per-in Section 6.2.1
- in each channel) cent of the 0 to 40 percent scale (any range) i Protectic.'.; gainst 3
1 downscale 5 percent low Except that the three picoammeter cir-1 upscale trip and 1 ad-downscale trips may be cuit failure ditional in-simultaneously bypassed strument at when the picoammeter 120% high trip range switches are pg simultaneously set to onerate below 40 x 10~5%
gg g-g pwer.
The bypass becomes g_
ineffective when the rance
$,o for any of the detectors y
is set above the 40 x 10-5g N
power.
10I second Placement of any 2 out
-100 see to 15 sec inter-Short period 2
1 out of 2 2
a (each of inter-of 3 range switches of infinity to mediate range mediate range the high level neutron
+10 sec (There is also Log-N period flux channels in the an annunciator monitors' has a power range position operated by trip contact in will bypass this period the start-up each channel)
. trip feature, channel period contacts.)
Manual. scram 1
1 out of-l (1 switch)
A 6.1. 2.1 Start-Up Channels - Channels 6'and 7 shall provide logarith-mic neutron flux level and period information from _ source level to five decades above source level, without moving detectors (approximately 10-9 to 10-% of rated power).
The principal components in each channel shall be a neutron detector, high-voltage power su, ply, current pulse amplifier, a five decade log count rate meter with low level period amplifier, log count rate indicator, and log count rate recorder. Gas-filled Baron-10 lined proportional counters with a sensitivity of approvimately 12 counts /nv shall be used as detectors.
Provisions shall be made for remotely positioning the c'etectors.
By moving the detectors away from the midplane of the core, their effective range may be extended several decadec. A short period on either channel shall be annunciated in the control room.
6.1.2.2 Intermediate Range Channels - Channels 4 and 5 provide logarithmic neutron flux level and period information from approximately 10-5% to rated power for the 84 bundle core.
The principal components in each channel shall be a neutron detector, dual high-voltage power supply, Log-N and period amplifier, Log-N indicator, period indicator, and Log-N i
recorder. The detectors shall be gamma compensated ion chambers with a design sensitivity of at least 2.2 x 10-14 amperes /nv.
6.1 3 Power Range Channels - Channels 1, 2 and 3 shall provide linear neutron flux level information from approximately 10-7% to 125%
rated power for the 84 fuel bundla core. The principal components in each channel shall be a neutron detector, dual power supply, picoammeter with console range switch and power level indicator, and power level recorder. The detectort shall be gamma compensated inn chambers with a design *asitivity of at least 2.2 x 10-4 amperes /
nv. The amplifier output shall be connected to the reactor safety system.
6.1.2 4 In Core Flux Monitors - In-core flux monitors shall be used to ovaluate predicted power distributions and detect power oscil-lations or deviations from expected power dis ~tributions in time for the operator to take corrective action to avoid e>ceeding local heat flux limits, i
6-6 ChangaNo.4,7, AmerJment No. 45
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