ML20100Q959
| ML20100Q959 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/14/1984 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML20100Q926 | List: |
| References | |
| NUDOCS 8412170270 | |
| Download: ML20100Q959 (5) | |
Text
-
y.
TABLE 4.3-2 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEMS INSTRUMENTATION SURVEILLANCE REOUIREMENTSL CHANNEL' MODES IN WHICH CHANNEL
. CHANNEL-FUNCTIONAL SURVEILLANCE Q.
- FUNCTIONAL UNIT CHECK CALIBRATION TEST REOUIRED c
-I>
3.
REACTOR BUILDING SPRAY r
(
a.
Reactor Building Pressure rn High-High coincident with 7
HPI Signal S
R M(4) 1,' 2, 3 '
E b.
Automatic Actuation Logic N/A N/A M(IX3X5).
1, 2, 3 4
w 4.
OTHER SAFETY SYSTEMS
~
a.
Reactor Building Purge Exhaust Duct Isolation on High Radioactivity 1.
Gaseous S
Q M
All Modes.
h I
b.
Steam Line Rupture Matrix 1.
Low SG Pressure N/A R#
N/A 1, 2, 3 l
4 i
2.
Automatic Actuation Logic N/A N/A-M(3) 1, 2, 3 c.
Emergency Feedwater 1.
MFW Pump Turbine A and B Control Oil Low S
R N/A 1, 2, 3 i
i 2.
OTSG A and B Level Low-Low S
R N/A 1,2,3,4.
- The specified 18 month calibration frequency may be waived for Cycle V provided the surveillance is performed during Refuel V.
t i
I 8412170270 841214 l
PDR ADOCK 05000302 I
P
- PDR, 1
=
g
- TABLE 4.3-6 O
REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS 3
H>r-CHANNEL.
CHANNEL-p Q
INSTRUMENT CHECK CALIBRATION -
rn N
c 1.
Reactor Trip Breaker Indication M
N.A.
3 H
2.
Reactor Coolant Temperature-Th M
R w
3.
Reactor Coolant Pressure M
R l
4.
Pressurizer Level M
R#
5.
Steam Generator Level M
R w
'E l
y 6.
Steam Generator Pressure M
R#
M 7.
R' Temperature 8.
Motor Driven Emergency M
R Feedwater Pressure 9.
Nuclear Services Closed M
R.
Cycle Cooling Pumps Discharge Pressure 10.
Nuclear Services Closed M
R Cycle Cooling Cooler Outlet Temperature
- The specified 15 month calibration frequency may be waived for Cycle V provided the surveillance is performed during Refuel V.
e y --'
y 1;.
y.
TABLE 4.3-7 POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.
G o
CHANNEL CHANNEL.
-Q INSTRUMENT CHECK
. CALIBRATION si ra 1.
. Power Range Nuclear Flux M
.Q*
lcq 2.
Reactor Building Pressure M
-R 3.
Source Range Nuclear Flux
,M R*
b 4.
Reactor Coolant Outlet Temperature M
R h
5.
Reactor Coolant Total Flow Rate M
R 6.
RC Loop Pressure M
R 7.
Pressurizer Level M
R#
8.
Steam Generator Outlet Pressure M
R#'
9.
Steam Generator Level M
R.
(Primary EFW Flow Detector) 4
{
10.
Borated Water Storage Tank Level M
R 11.
Startup Feedwater Flow Rate M
R#
l 12.
Reactor Coolant System Subcooling Margin Monitor M
R 13.
PORY Position Indicator (Primary Detector)
M R:
14.
PORY Position Indicator (Backup Detector)
M R
13.
PORY Block Valve Position Indicator M
R 16.
Safety Valve Position Indicator (Primary Detector)
M R
17.
Safety Valve Position Indicator (Backup Detector)
M R
18.
timergency Feedwater Ultrasonic Flow Indicator M
-R (Backup EFW Flow Detector)
- Neutron detectors may be excluded from CHANNEL CALIBRATION
- The specified 18 month calibration frequency may be waived for Cycle V provided the surveillance is performed during Refuel V.
- POWER OPERATED RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.3.2-The power operated relief valve (PORV) and its associated block valve shall be OPERABLE.
. APPLICABILITY:
MODES 1,2, and 3.
ACTION: -
a.
With the PORV inoperable, within I hour either restore the PORY to
- OPERABLE status or close the associated block valve and remove power from the block valve; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
.With the block valve inoperable, within I hour either restore the block valve to
- OPERAdLE status or close the block valve and remove power from the block valve or close the PORV and remove power from the associated solenoid valve; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
The provisions of Specification 3.0.4 are not applicable.
c.
SURVEILLANCE REOUIREMENTS 4.4.3.2.1 In addition to the requirements of Specifications 4.0.5, the PORY shall be demonstrated OPERABLE at least once per 18 months by performance of a CHANNEL CALIBRATION.#
r 4.4.3.2.2 The block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel.
- The specified 18 month calibration frequency may be waived for Cycle V provided the surveillance is performed during Refuel V.
CRYSTAL RIVER - UNIT 3 3/4 4-4a
5 PLORIDA POWER CORPORATION -
CRYSTAL RIVER UNIT 3 DOCKET NO. 50-306/ LICENSE NO. DPR-72 REQUEST NO. 82, SUPPLEMENT 4 -
' SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION E
DESCRIPTION OF REOUEST:
This' submittal requests ' that the 18 month calibration frequency for the following specifications be waived for Cycle V until Refuel V.
-4.3.2.1.1.(4.b.1)
Steam Line Rupture Matrix, Low Steam Generator Pressure
- 4.3.3.5(4).
Remote Shutdown Instrume nt, Pressurizer Level 4.3.3.5(6).
Remote Shutdown Instrument, Steam Generator Pressure
' 4.3.3.6(7)
Pressurizer Level
- 4.3.3.6(8)
. Steam Generator Outlet Pressure 4.3.3.6(11)
Startup Feedwater Flow 4.4.3.2.1.
Power Operated Relief Val e The current surveillance interval, including the allowed 25% extension, will end in Mid-February of 1985.
It is necessary to shot down in order to perform the referenced calibra.ons. FPC currently plans to begin shutdown on March 9,1985 for Refuel V.
SGNIFICANT HAZARDS CONSIDERATION DETERMINATION:
(x)
Amendment is not likely to involve a significant hazards consideration.
- (
.)
Amendment is likely to involve a significant hazards consideration.
BASS FOR DETERMINATION:
This amendment is considered not likely to involve a significant hazards consideration, because the actual time extension is small. The extension beyond the allowed interval (22.5 months) will be less than one month.
REOUEST IMPLEMENTATION DATE:
Florida Power Corporation requests that this amendment request be handled expeditiously.
It is critical that this request be resolved by February 14,1985, as a plant shutdown will be necessary to perform the referenced calibrations. -
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