ML20112F110
| ML20112F110 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 03/21/1985 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20112F106 | List: |
| References | |
| NUDOCS 8503270397 | |
| Download: ML20112F110 (17) | |
Text
.. _ _.
s 4
ATTACHMENT I to JPN-85-22 PROPOSED TECHNICAL SPECIFICATION CHANGES I
RELATED TO ANALOG TRANSMITTER TRIP SYSTEM (ATTS)
T l
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 DPR-59 B503270397 850321 PDR ADOCK 05000333 p
PDR 4
i
,-n.,-
~, '*~ ~~:
JAFNPP i.
3.1. BASES (cont'd) i cubchannel.- APRM's B. D and F are radioactivity are an indication of arranged similarly in the other leaking fuel.
A scram is initiated protection trip system.
Each protection whenever such radiation level exceeds trip system has one more APRM than is three times normal background.
The nocessary to meet the minimum number purpose of this scram is to reduce the Esquired per channel.
This allows the source of such radiation to the extent i
bypassing of one APRM per protection necessary to prevent excessive turbine trip system for maintenance, testing or contamination.
Discharge of excessive calibration.
Additional IRM channels amounts of radioactivity to the site j
hava also been provided to allow for environs is prevented by the air ejector i
bypnosing of one such channel.
The offgas monitors which cause'an isolation bases for the scram setting for the IRM, of the main condenser offgas line.
l APRM, high reactor pressure, reactor low water level, main steam isolation valve A Reactor Mode Switch is provided which (MSIV) closure, generator load rejection actuates or bypasses the various scram and turbine stop valve closure are functions appropriate to the particular discussed in Sections 2.1 and 2.2.
plant operating status.
Reference paragraph 7.2.3.7 FSAR.
Il Instrumentation for the drywell is l
The manual scram function is active in i
provided to detect a loss of coolant all modes, thus providing for a manual accident and initiate the core standby means of rapidly inserting control rods cooling equipment.
A high drywell during all modes of reactor operation.
pressure scram is provided at the saco setting as the Core and con-tainrent Cooling Systems (ECCS)
The APRM (high flux in startup or refuel) System provides protection initiation to minimize the energy which against excessive power levels and short-l.
i tust be accommodated during a loss-of-
)
coolant accident and to prevent return reactor periods in the startup and
!6 intermediate power ranges.
j to criticality.
This instrumentation is j
j a backup to the reactor vessel water The IRM System provides protection j
leval instrumentation.
against short reactor periods in these i
ranges.
High radiation levels in the main steam i
lino tunnel above normal levels that due The Control Rod Drive Scram System in j
to the nitrogen and oxygen designed so that all of the water which I
j Ausndment No. pd 1
l 33 l
O
-=
JAFNPP 4.1 BASES (cont'd)
The bi-stable trip circuit which is a part of The frequency of calibration of the APRM 1
the Group (B) devices can sustain unsafe failures flow biasing network has been established which are revealed only on test. Therefore, it is as.each refueling outage. The flow biasing necessary to test them periodically.
network is functionally tested at least once/
l,'
month and, in addition, cross calibration A study was conducted of the instrumentation checks of the flow input to the flow biasing 4
channels included in the Group (B) devices to network can be made during the functional calculate their unsafe failure rates. The non-test by direct meter reading. There are ATTS (Analog Transmitter Trip System) analog devices several instruments which must be calibrated i-(sensors and amplifiers) are predicted j
unsafefailurerateoflessthan20x10-gohavean and will take several days to perform the cali-failurea/
bration of the entire network. While the cali-l l
hr.
The non-ATTS bi-stable trip circuits are bration is being performed, a zero flow signal l
predigted to have unsafe failure rate of less than will be sent to half of the APRM's resulting l
2x10- failures /hr. The ATTS analog devices (sensors),
in a half scram and rod block condition. Thus, bi-stable devices (master and slave trip units) and if the calibration were performed during power supplies have been. evaluated for reliability operation, flux shaping would not be possible, j
by Mean Time Between Failure analysis or state-of-Based on experience at other generating the art qualification type testing meeting the re-stations, drift of instruments, such as quirements of IEEE 323-1974. Considering the 2-hour those in the flow biasing network, is not j
monitoring interval for analog devices as assumed significant and therefore, to avoid i
above, the instrument checks and function ~al tests spurious scrams, a calibration frequency l
as well as the analyses and/or qualification type of each refueling outage is established.
testing of the devices, the design reliability goal for system reliability of 0.9999 will be attained Group (C) devices are active only during
]
with ample margin.
a given portion of the operational cycle.
i For example, the IRM is active during startup j
The bi-stable devices are monitored during plant and inactive during full-power operation.
operation to record their failure history and es-Thus, the only test that j
tablish a test interval using the curve of Figure f'
i 4.1-1.
There are numerous identical bi-stable de-i i
vices used throughout the Plant's instrumentation system. Therefore, significant data on the failure rates for the bi-stable devices should be accumulated rapidly.
i l
Amendment No.
38
i JAFNPP Table 4.1-1 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT FUNCTIONAL TEST i
MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRUMENT AND CONTROL CIRCUITS i
1 Instrument Channel Group Functional Test Minimum Frequency (3) l Mode Switch in Shutdown A
Place Mode Switch in Shutdown Each refueling outage.
J Manual Scram A
Trip Channel and Alarm Every 3 months.
l i
RPS Channel Test Switch.
A Trip Channel and Alarm Every refueling outage or after i ;
channel maintenance.
IRM High Flux C
Trip Channel and Alarm (4)
Once per week during refueling or I
startup and before each startup.
1 IRM Inoperative C
Trip Channel and Alarm (4)
Once per week during refueling or j
startup and before each startup.
l l
APRM i
High Flux B
Trip Output Relays (4)
Once/ week.
Inoperative B
Trip Output Relays (4)
Once/ week.
l Downscale B
Trip Output Relays (4)
Once/ week.
I i
Flow Bias B
Calibrate Flow Bias Signal (4)
Once/ month (1).
l High Flux in Startup or Refuel C
Trip Output Relays (4)
Once per week during refueling or s
startup and before each startup.
High Reactor Pressure B
Trip Channel and Alarm (4)
Once/ month. (1)(8)
High Drywell Pressure B
Trip Channel and Alarm (4)
Once/ month. (1)(8) j i
j Reactor Low Level (5)
B Trip Channel and Alarm (4)
Once/ month. (1)(8) l 1
High Water Level in Scram A
Trip Channel Once/ month.(7).
i i
Discharge Instrument Volume i
High Water Level in Scram B
Trip Channel and Alarm (4)
Once/ month. (1)(8) j Discharge Instrument Volume AmendmentNo.k,%,7/
44 1.
4 I
JAFNFP
~
Table 4.1-1.(Cont'd) i j
REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT FUNCTIONAL TEST MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRUMENT AND CONTROL CIRCUITS Instrument Channel Group (2) Functional Test Minimum Frequency (3)
Main Steam Line High Radiation B
Trip Channel and Alarm (4)
Once/ week.
{-
Main Steam Line Isolation Valve A
Trip Channel and Alarm Once/ month.(1)
Closure Turbine Control Valve EHC Oil A
Trip Channel and Alarm Once/ month.
Pressure Turbine First Stage Pressure B
Trip Channel and Alarm (4)
Once/ month. (1)(8) j Permissive l
Turbine Stop Valve Closure A
Trip Channel and Alarm Once/ month. (1)
Reactor Pressure Permissive A
Trip Channel and Alarm Every 3 months.
i l
NOTES FCR TABLE 4.1-1 i
1.
Initially once every month until acceptable failure rate data are available; thereafter, a request may be t
)
made to the NRC to change the test frequency. The compilation of instrument failure rate data may include data obtained from other boiling water reactors for which the some design instrument operates in an environment similar to that of JAFNPP.
l l
l 2.
A description of the three groups is included in the Bases of this Specification, i
3.
Functional tests are not required on the part of the system that is not required to be operable or are l
tripped.
i i
l Iftestsaremissedonpartsnotrequiredtobeoperableoraretripped,thentheyshallbeperf$rmedprior j
to returning the system to an operable status.
l 4.
This instrumentation is exempted from the instrument channel test definition. This instrument channel functional test will consist of injecting a simulated electrical signal into the instrument channels.
I i
i l
Amendment No. )4P,JHf 45 I
v
--n-e JAFNPP Table 4.1-1 (Cont'd)
REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT FUNCTIONAL TEST MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRUMENT AND CONTROL CIRCUITS NOTES FOR TABLE 4.1-1 (cont'd) 5.
The water level in the reactor vessel will be perturbed and the corresponding level indicator changes will be monitored. This perturbation test will be performed every month after completion of the functional test program.
6.
Deleted.
7.
The functional test shall be performed utilizing a water column or similar device to provide assurance that damage to a float or other portions of the float assembly will be detected.
8.
Instrument check once per day.
!i I
Inuralient No.
45a
JAFNPP Table 4.1-2 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT CALIBRATION l
MINIMUM CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUME.NT CHANNELS Instrument Channel Group (1)
Calibration (4)
Minimum Frequency (2)
IRM High Flux C
Comparison to APRM on Maximum frequency once/ week Controlled Shutdowns APRM High Flux Output Signal B
Heat Balance Daily Flow Bias Signal B
Internal Power and Flow Every refueling outage Test with Standard Pressure Source LPRM Signal B
Trip System Traverse Every 1000 effective full power hours High Reactor Pressure B
Standard Pressure Source Note (7)
High Drywell Pressure B
Standard Pressure Source Note (7)
Reactor Low Water Level B
Standard Pressure Source Note (7)
High Water Level in Scram A
Water Column, Note (6)
Once/ operating cycle. Note (6)
Discharge Instrument Volume i
l High Water Level in Scram B
Standard Pressure Source Every 3 months Discharge Instrument Volume
.t Main Steam Line Isolation A
Note (5)
Note (5)
Valve Closure Main Steam Line High Radiation B
Standard Current Source (3)
Every 3 months Turbine First Stage Pressure B
Standard Pressure Source Note (7)
Permissive l
l Amendment No.
46 t
l
O.
JAFNPP Table 4.1-2 (cont'd) i REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT CALIBRATION MINIMUM CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT CHANNELS i
Instrument Channel Group (1)
Calibration (4)
Minimum Frequency (2)-
j Turbine Control Valve Fast A
Standard Pressure Source Once/ operating cycle Closure Oil Pressure Trip Turbine Stop Valve Closure A
Note (5)
Note (5)
S Reactor Pressure Permissive A
Standard Pressure Source Every 6 months i
1 i
NOTES FOR TABLE 4.1-2 I
1.
A description of three groups is included in the Bases of this Specification.
2.
Calibration test is not required on the part of the system that is not required to be operable, or is i
tripped, but is required prior to return to service.
I 3.
The current source provides an instrument channel alignment. Calibration using a radiation source shall be made each refueling outage.
l 4.
Response time is not a part of the routine instrument channel test but will be checked once per operating cycle.
l 5.
Actuation of these switches by normal means will be performed during the refueling outages.
6.
Calibration shall be performed utilizing a water column or similar device to provide assurance that damage to a float or other portions of the float assembly will be detected.
7.
Sensor calibration once per operating cycle. Master / slave trip unit calibration once per 6 months.
l AmendmentNo.ps,JHI 47
JAFNPP 4.2 BASES The instrumentation listed in Table 4.2-1 To test the trip relays requires that the through 4.2-6 will be functionally tested channel be bypassed, the ' test made, and the i
and calibrated at regularly scheduled in-system returned to its initial state.
It I
tervals. The same design reliability is assumed this task requires an estimated goal as the Reactor Protection System is 30 min. to complete in a thorough and work-generally applied. Sensors, trip devices manlikemannerand,ghattherelayshavea and power supplies are tested, calibrated failure rate of 10 failures per hour.
and checked at the same frequency as Using this data and the above operation, comparable devices in the Reactor Protec-the optimum test interval is:
tion System.
3 id(2(0.5) = 1 x 10 hr.
i Those instruments which, when tripped, result 10 *
= 40 days in a rod block have their contacts arranged in a 1 out of n logic, and all are capable For additional margin a test interval of being bypassed. For such a tripping of once/ month will be used initially.
arrangement with bypass capability provided, there is an optimum test interval that should The sensors and electronic apparatus be maintained in order to maximize the re-have not been included here as these are liability of a given channel (7). This takes analog devices with readouts in the control account of the fact that testing degrades re-room and the sensors and electronic apparatus liability and the optimum interval between can be checked by comparison with other like j
tests is approximately given by:
instruments. The checks which are made on a daily basis are adequate to assure operability of the sensors and electronic apparatus,
=y 2_
and the test interval given above provides for i
j r
optimum testing of the relay circuits.
i j
Where:
i = the optimum interval 1.
_j l
between tests.
t = the time the trip con-l tacts are disabled fron performing their func-tion while the test is in progress.
r = the expected failure rate of the relays.
Amendment No.
61
JAFNPP TABLE 4.2-1 E
MINIMUM TEST AND CALIBRATION FREQUENCY FOR PCIS Instrument Channel (8)
Instrument Functional Test Calibration Frequency Instrument Check (4) l
- 1) Reactor High Pressure (i)
Once/3 months None (Shutdown Cooling Permissive)
- 2) Reactor Low-low Water Level (1)(5)
(15)
Once/ day
- 3) Main Steam High Temp.
(1)(5)
(15)
Once/ day
- 4) Main Steam High Flow (1)(5)
(15)
Once/ day
- 5) Main Steam Low Pressure (1)(5)
(15)
Once/ day
- 6) Reactor Water Cleanup (1)
Once/3 months None High Temp.
- 7) Condenser Low Vacuum (1)(5)
(15)
Once/ day g
Logic System Functional Test (7) (9)
Frequency l
1.
Main Steam Line Isolation valves Once/6 montha Main Steam Line Drain Valves Reactor Water Sample Valves 2.
RHR - Isolation Valve Control Once/6 months Shutdown Cooling Valves Head Spray 3.
Reactor Water Cleanup Isolation Once/6 months 4.
Drywell Isolation Valves once/6 months Tip Withdrawal Atmospheric Control Valves I'
5.
Standby Gas Treatment System once/6 months i
Reactor Building Isolation NOTE: See listing of notes following Table 4.2-6 for the notes referred to herein.
I AmendmentNo.JI 78
~
JAFNPP Table 4.2 MINIMUM TEST AND CALIBRATION FREQUENCY FOR CORE AND CONTAINMENT COOLING SYSTEMS Instrument Calibration Instrument 4
Instrument Channel Functional Test Frequency Check (4)
- 1) Reactor Water Level (1)(5)
(15)
Once/ day-2a) Drywell Pressure (non-ATTS)
(1)
Once/3 months None 2b) Drywell Pressure (ATTS)
(1)(5)
(15)
Once/ day 3a) Reactor Pressure (non-ATTS)
(1)
Once/3 months None 3b) Reactor Pressure (ATTS)
(1)(5)
(15)
Once/dr.y
- 4) Auto Sequencing Timers None Once/ operating cycle None l
(1)
Once/3 months None
- 6) Trip System Bus Power Monitors (1)
- 8) Core Spray Specger d/p (1)
Once/3 months Once/ day
(1)(5)
(15)
Once/ day
(1)(5)
(15)
Once/ day.
(15)
Once/ day
- 13) HPCI Suction Source Levels (1)
Once/3 months None
- 14) 4KV Emergency Power Under-Voltage Once/ operating Once/ operating cycle None Relays and Timers cycle
-l 1
Once/3 months None l
Pressure High i
l
- 17) LPCI/ Cross Connect Valve Position Once/ operating None None j
cycle l
Note: See listing of notes following Table 4.2-6 for the r.otes referred to herein.
AmendmentNo.[,I/,[
I 79
a JAFNPP
=
TABLE 4.2-2 (CONT'D)
MINIMUM TEST AND CALIBRATION FREQUENCY POR CORE AND CONTAINMENT COOLING SYSTEMS Logic System Functional Test Frequency 1)
Core Spray Subsystem (7) (9) Once/6 months 2)
Low Pressure Coolant Injection Subsystem (7) (9) Once/6 months t
3)
Containment Cooling Subsystem (9) Once/6 months i
4)
HPCI Subsystem (7) (9) Once/6 months 5)
HPCI Subsystem Auto Isolation (7).(9) Once/6 months 6)
ADS Subsystem (7) (9) Once/6 months 7)
RCIC Subsystem Auto Isolation (7) (9) Once/6 months 8)
ADS Relief Valve Bellow Pressure Switch (7) (9) Once/ operating cycle NOTE: See listing of notes following Table 4.2-6 for the notes referred to herein.
i Amendment No. /
80
JAFNPP TABLE 4.2-3 l
MINIMUM TEST AND CALIBRATION FREQUENCY FOR CONTROL ROD BLOCKS ACTUATION 4
Instrument Functional Instrument Check.
Instrument Channel Test (5)
Calibration (12)(4) l I
1)
APRM - Downscale (1)
Once/3 months Once/ day 2)
APRM - Upscale (1)
Once/3 months Once/ day r
l 3)
IRM - Upscale (2)
(3)
(6)
Once/ day l
4)
IRM - Downscale (2)
(3)
(6)
Once/ day 4
l 5)
RBM - Upscale (1)
Once/3 months once/ day I
j 6)
RBM - Downscale (1)
Once/3 months Once/ day I
!~
7)
SRM - Upscale (2)
(3)
(6)
Once/ day 8)
SRM - Detector Not in Startup Position (2)
(3)
(6)
None
}
9)
IRM - Detector Not in Startup Position (2)
(3)
(6)
None l
i l
- 10) Scram Discharge Instrument Volume -
Once/ month Once/3 months -
Once/ day l[
{
High Water Level (Group B Instruments)
(1)
)
i Logic System Functional Test (7) (9)
Frequency l
1)
System Logic Check Once/6 months f
NOTE: See listing of notes following Table 4.2-6 for the notes referred to herein.
l 4
j Amendment No. /,f//
81 h
1
+
t 7
_ = ~.
i 4
JAFNPP TABLE 4.2-4 MINIMUM TEST AND CALIBRATION FREQUENCY FOR RADIATION MONITORING SYSTEMS Instrument Functional Instrument Check Instrument Channel Test Calibration-(12)(4) j i
j 1)
Refuel Area Exhaust Monitors (1)
Once/3 months Once/ day-1 2)
Reactor Building Area Exhaust Monitors (1)
Once/3 months once/ day Turbine Building Exhaust Monitors (1)
Once/6 months Once/ day l
Radwaste Building Exhaust Monitors (1)
Once/6 months Once/ day i
3)
Off-Gas Radiation Monitors (1)
Once/3 months Once/ day t
4)
Main Control Room Ventilation Monitor (1)
Once/3 months Once/ day 5)
Mechanical Vacuus Pump Isolation See Table 4.1-2 l
l t
6)
Liquid Radwaste Discharge Mcnitor (1)
Once'3 months once/ day when j
discharging l
Logic System Functional Test (7)(9)
Frequency l
1)
Reactor Building Isolation Once/6 months 2)
Standby Cas Treatment Sys. Actuation once/6 months d
3)
Steam Jet Air Ejector Off-Cas Line Once/6 months Isolation
- 'l 4)
Mechanical Vacuum Pump Isolation Once/ Operating Cycle i
5)
Liquid Radwaste Discharge Isolation Once/6 months NOTE: See listing of notes following Table 4.2-6 for the notes referred to herein.
l l
Amendment No. /
82
JAFNPP TABLE 4.2-5 MINIMUti TEST AND CALIBRATION FREQUENCY FOR DRYWELL LEAK DETECTION 4
Instrument Functional Calibration Instrument Check j
Instrument Channel Test Frequency (4)~
l 1)
Equipment Drain Susp Flow Integrator (1)
Once/3 months once/ day 2)
Floor Drain Sump Flow Integrator (1)
Once/3 months Once/ day a
NOTE:
See listing of notes following Table 4.2-6 for the notes referred to herein.
1 I
i 1
1.
i AmendmentNo.[
83
.=
1 JAFNPP TABLE 4.2-6 MINIMUM TEST AND CALIBRATION FREQUENCY FOR SURVEILLANCE INSTRUMENTATION i
j
.f INSTRUMENT CHANNEL CALIBRATION FREQUENCY INSTRUMENT CHECK (4) l 1)
Reactor Water Level Once/6 months Once Each Shift
'l i
2)
Reactor Pressure Once/6 months Once Each Shift i
1 3)
Drywell Pressure Once/6 months Once Each Shift 4)
Drywell Temperature Once/6 months Once Each Shift j
j 5)
Suppression Chamber Temperature Once/6 months Once Each Shift i
f 6)
Suppression Chamber Water Level Once/6 months Once Each Shift 7)
Control Rod Position Indication None Once Each Shift l
8)
Neutron Monitoring (APRM)
Five/ week Once Each Shift 9)
Neutron Monitoring (IRM and SRM)
Note 13 Note 13 l
- 10) Drywell-Suppression Chamber Differential Pressure Once/6 months Once Each Shift
- 11) Safety / Relief Valve Position Indicator (Primary)
Note 14
'Once/ Month
- 12) Safety / Relief Valve Position Indication'(Secondary)
Note 14 Once/ Month 3
Amendment No. g, g, g 84 i
i 1
i l
l NOTES FOR TABLES 4.2-1 THROUGH 4.2-6 1.
Initially once every month until acceptance failure 9.
The logic system functional tests shall l
l rate data are available; thereafter, a request may include a calibration of time delay j
be made to the NRC to change the test frequency.
relays and timers necessary for proper The compilation of instrument failure rate data may functioning of the trip systems.
include data obtained from other boiling water reactors i
for which the same design instruments operate in an 10.
At least one (1) Main Stack Dilution l
environment similar to that of JAFNPP.
Fan is required to be in operation in order to isokinetically sample the 2.
Functional tests are not required when these instru-Main Stack.
ments are not required to be operable or are tripped.
Functional tests shall be performed within seven (7) 11.
Uses same instrumentation as Main Steam l
days prior to each startup.
.Line High Radiation. See Table 4.1-2.
I 3.
Calibrations are not required when these instruments
- 12. See Technical Specification 1.0.F.4, I
i are not required to be operable or are tripped.
Definitions, for meaning.of term.
].
Calibration tests shall be performed within seven
" Instrument Check".
(7) days prior to each startup or prior to a pre-planned shutdown.
13.
Calibration and instrument check-l surveillance for SRM and IRM i
4.
Instrument checks are not required when these instru-Instruments are as specified in Tables ments are not required to be operable or are tripped.
4.1-1, 4.1-2, 4.2-3.
i 5.
This instrumentation is excepted from the functional 14.
Functional test is performed once each j
i test definition. The functional test will consist of operating cycle.
}
injecting a simulated electrical signal into the measurement channel.
15.
Sensor calibration once per operating cycle. Master / slave trip unit calibration l
6.
These instrument channels will be calibrated using once per 6 months.
j simulated electrical signals once every three months.
t l
7.
Simulated automatic actuation shall be performed once each operating cycle. Where possible, all logic system functional tests will be performed using the test jacks.
i l
8.
Reactor low water level, high drywell pressure and high
^
j radiation main steam line tunnel are not included on i
Table 4.2-1 since they are tested on Table 4.1-2.
l AmendmentNo.)(I,//,yf 85
.