ML20058B952
| ML20058B952 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/22/1993 |
| From: | NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20058B924 | List: |
| References | |
| NUDOCS 9312020295 | |
| Download: ML20058B952 (9) | |
Text
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Docket No. 50-245 B14673 I
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Millstone Nuclear Power Station, Unit No. I Proposed Revision to Technical Specifications I
Scram Discharge Volume - Control Rod Block Instrumentation Marked-Up Pages to Technical Specifications November 1993 9312O20295 931122 PDR ADOCK 05000245 p
OCT 311986 LIMITING CONDITION FOR OPERATION 3.2 PROTECTIVE INSTRUMENTATION Aoplicability:
Applies to the plant instrumentation which performs a protective function.
Objective:
To assure the operability of protective instrumentation.
Specification:
Primary Containment Isolation F' unctions A.
When primary containment integrity is required, the Ifmiting conditions of operation for the instrumentation that f aitiates primary containment isolation are given in Table 3.2.1.
Emeroency Core Coolina subsystems Actuation B.
The limiting conditions for operation for the instrumentation which initiates the emergency core cooling subsystems are given in Table 3.2.2 except as noted in Specification 3.5.F.6.
C.
Control Rod Block Actuation g
The limiting conditions of omeration for the instrumentation that 1.
initiates control rod block we given in Table 3.2.3.
SURVEILLANCE REQUIREMENT 4.2 PROTECTIVE INSTRUMENTATION Applicability:
Applies to the surveillance requirements of the instrumentation that performs a protective function.
Objective:
To specify the type and frequency of surveillance to be applied to protective instrumentation.
s Specification:
4 _
>The instrumentation to be functionally tested and calibrated as indicated in Table 4.2.1.
pnW So kW
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s Millstone Unit 1 3/4 2-1 otly a
OCT ;il 1986 TABLE 3.2.3 INSTRUMENTATION THAT INITIATES ROD BLOCK Minimum Number of Operable Instrument Channelspe[1)
Trip System Instrument Trip Level Setting _
1(7)
APRM Upscale (Flow Biased)
See Specification 2.1.28 II)
APRM Downscale 23/125 Full Scale I
Rod Block Monitor Upscale (Flow Biased) 5.65 W + 42 (2) 50) 1 1(6)
Rod Block Monitor Downscale 23/125 Full Scale 3
IRM Downscale(3) 23/125 Full Scale 3
IRM Upscale
$108/125 Full Scale (4) 2 SRM Detector not in Startup Position 2(5)
SRM Upscale
$10 counts /sec.
5 d'
Scram Discharge Volume - Water Level High
$14 inches above lower cap to
@\\
501V pipe weld 1\\
Scram Discharge Volume - Scram Trip Bypassed N/A
't
(*ep lA g e w>bb i
Millstone Unit 1 3/4 2-7
t OCT 311986 Table 3.2.3 Continued INSTRUMENTATION THAT INITIATES R00 BLOCK CRAMI Of3C/fM M Notes:
VV/J 764 f Gt/E L. ///6i/
AA!O 7"7fZ, (1) For the STARTUP/ HOT STANDBY and Run positions of the Reactor de Selector Switch, there shall be two operable or tripped trip systems for each function except the SRM rod blocks; IRM downscale are not operable in the RUN position and APRM downscale need not be operable in the STARTUP/ HOT STANDBY mode.
If the first column cannot be met for one of the two trip systems, this condition may. exist for up to seven days provided that during that time the operable system is functionally tested immediately and daily thereafter; if this condition lasts longer than'seven days, the system shall be tripped.
If the first column cannot be met for both trip systems, the systems shall be tripped.
(2) W is the recirculation flow required to achieve rated core flow expressed in percent.
(3) IRM downscale may be bypassed when it is on its lowest range.
(4) This function may be bypassed when the count rate is 2100 cps or when all IRM range switches are above Position 2.
(5) One of these trips may be bypassed. The SRM function may be bypassed, in the higher IRM ranges, when the IRM upscale rod block is operable.
(6) The trip may be bypassed when the reactor power is $30% of rated.
A RBM channel will be considered inoperable if there are less than half the total number of normal inputs from any LPRM level.
(7) There must be a total of at least four (4) operable or operating APRM channels.
(8) o/*thdad i
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Millstone Unit-1 3/4 2-8 p/.2.0
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Addition to 4.2 Surveillance Requirement Page 3/4 2-1 i
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When the reactor mode selector switch is in the REFUEL or SHUTDOWN position and fuel is in the reactor vessel, no control rod block functions are mquired to be operable l
provided that all control rods are fully inserted, and either electrically or hydntulically i
l disarmed. Thereafter, daily surveillance shall be performed to verify that all control rods l
rennin either electrically or hydraulically disarmed.
i Addition to Table 3.2.3, Page 3/4 2-8 i
I i
(8)
One (1) Scram Discharge Volume - Water level High mstrument per mstrument volume l
tank is required to be operable. If either of the instruments become inoperable, a rod block shall be initiated within one hour.
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Docket No. 50-245 B14673 t
Millstone Nuclear Power Station, Unit No.1 Proposed Revision to Technical Specifications Scram Discharge Volume - Control Rod Block Instrumentation Retyped Pages to Technical Specifications November 1993
4 LIMITING CONDITION FOR OPERATION
~
3.2 PROTECTIVE INSTRUMENTATION applicability:
Applies to the plant instrumentation which performs a protective function.
I Objective:
To assure the operability of protective instrumentation.
Specification:
A.
Prinry Cont ainment Isolation Functions When primary containment integrity is required, the limiting conaittom i
of operation for the instrumentation that initiates primary containment isolation are given in Table 3.2.1.
l B.
Emeraency Core Coolina Subsystems Actuation The limiting conditions for operation for the instrumentation which 4
initiates the emergency core cooling subsystems are given in Table 3.2.2 except as noted in Specification 3.5.F.6.
C.
Control Rod Block Actuation 3
I.
The limiting conditions of operation for the instrumentation that initiates control rod block are given in Table 3.2.3.
SURVEILLANCE REQUIREMENT 1
4.2 PROTECTIVE INSTRUMENTATION Aeolicability:
Applies to the surveillance requirements of the instrumentation that performs a protective function.
Objective:
To specify the type and frequency of surveillance to be applied to protective l
instrumentation.
Specification:
A.
The instrumentation to be functionally tested and calibrated as l
j indicated in Table 4.2.1.
B.
When the reactor mode selector switch is in the REFUEL or SHUTDOWN position and fuel is in the reactor vessel, no control rod block functions are required to be operable provided that all control rods are fully inserted, and either electrically or hydraulically disarmed.
Thereafter, daily surveillance shall be performed to verify that all controls rods remain either electrically or hydraulically disarmed.
4 Millstone Unit 1 3/4 2-1 Amendment No.
0119
.. - ~.
TABLE 3.2.3 INSTRUMENTATION THAT INITIATES ROD BLOCK Minimum *? umber of Operable instrument Channels per Trio System"'
Instrument Trio Level Settino l'"
APRM Upscale (Flow Biased)
See Specification 2.1.28 1"
APRM Downscale 2 3/125 Full Scale 8
l
Rod Block Monitor Upscale (Flow Biased)
$.65 W + 42:
23 l
Rod Block Monitor Downscale 2 3/125 Full Scale 3
IRM Downscale
13/125 Full Scale 3
IRM Upscale
$ 108/125 Full Scale 2
SRM Detector not in Startup Position 2
SRM Upscale
$10' counts /sec.
Scram Discharge Volume - Water level High
$ 14 inches above lower cap to SDIV pipe weld 1-Scram Discharge Volume - Scram Irip Bypassed N/A d
Millstone Unit 1 3/4 2-7 Amendment No.
0120 i
TABLE 3.2.3 (ccntinu d)
INSTRUMENTATION THAT INITIATES R0D BLOCK Notes:
(1)
For the STARTUP/ HOT STANDBY and Run positions of the Reactor Mode Selector Switch, there shall be two operable or tripped trip systems for each function except the scram discharge volume -- water level high and the SRM rod blocks; IRM downscale are not operable in the RUN position and APRM downscale need not be operable in the STARTUP/ HOT STANDBY mode. If the first column cannot be met for one of the two trip systems, this condition may exist for up to seven days provided that during that time the operable system is functionally tested immediately and daily thereafter; if this condition lasts longer than seven days, the system shall be tripped.
If the first column cannot be met for both trip systems, the systems shall be tripped.
(2)
W is tie recirculation flow required to achieve rated core flow expressed in percent.
(3)
IRM downr.cale may be bypassed when it is on its lowest range.
(4)
This function may be bypassed when the count rate is 2100 cps or when all IRM range switches are above Position 2.
(5)
One of these trips may be bypassed. The SRM function may be bypassed, in the higher IRM ranges, when the IRM upscale rod block is operable.
(6)
The trip may be bypassed when the reactor power is $30% of rated. A RBM channel will be considered inoperable if there are less than half the total number of normal inputs from any LPRM level.
(7)
There must be a total of at least four (4) operable or operating APRM channels.
(8)
One (ble.1) Scram Discharge Volume -- Water Level High instrument per instrument volume tank is required to be opera If either of the instruments become inoperable, a rod block shall be initiated within one hour.
Millstone Unit 1 3/4 2-8 Amendment No.
0120
,-