ML20127P728
| ML20127P728 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 05/07/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Power Authority of the State of New York |
| Shared Package | |
| ML20127P734 | List: |
| References | |
| DPR-59-A-089 NUDOCS 8505240062 | |
| Download: ML20127P728 (19) | |
Text
%,
UNITED STATES
[
g NUCLEAR REGULATORY COMMISSION g
j WASHINGTON, D. C. 20$55 s...../
POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 89 C
License No. DPR-59 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Power Authority of the State of New York (the licensee) dated March 21, 1985, as supplemented March 28, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission;
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C.
There is reason'able assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C(2) of Facility Operating License No.
DPR-59 is hereby amended to read as follows:
8505240062 850507 PDR ADOCK 05000333 P
.. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 89, are hereby incorporated in the license. The licensee shall operate,the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: May 7,1985 O
e
ATTACHMENT TO LICENSE AMENDMENT NO. 89 i
FACILITY OPERATING LICENSE N0. DPR-59 DOCKET NO. 50-333 Revise the Appendix "A" Technical Specifications as follows:
l Remove Insert 33 33 38 38 44 44 45 45 45a 45a 46 46 47 47 61 61 76 78 79 79 80 80 81 81 82 82 83 83 84 84 85 85 m
4 JAFNPP l
9, t
3.1. BASES (esst'd) cubchannel.
APRN's B. D and F are radioactivity are an indication of l
crranged similarly in the other leaking fuel.
A scram is initiated i
protection trip system.
Each protection whenever such radiation level exceeds
(
i trip system has one more APRM than is three times normal background.
The i
cecessary to meet the minimum number purpose of this scram is to reduce the l
required per channel.
This allows the source of such radiation to the extent I
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1 bypassing of one APRM per protectica necessary to prevent excessive turbine l
l trip system for maintenance, testing or contamination.
Discharge of excessive
}
calibration.
Additional IRN channels amounts of radioactivity to the site have also been provided to allow for environs is prevented by the air ejector I
1 bypassing of one such channel.
The offgas monitors which cause'an isolation
}
bases for the scram setting for the IRN.
of the main condenser offgas line.
I 1
APRN. high reactor pressure, reactor low i
water level, main steam isolation valve A Reactor Mode Switch is provided which (MSIV) closure, generator load rejection actuates or bypasses the various scram cad 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.
l l Instrumentation for the drywell is The manual scram function is active in provided to detect a loss of coolant all modes, thus providing for a manual l
l cecident and initiate the core standby means of rapidly inserting control rods cooling equipment.
A high drywell during all modes of reactor operation.
L pressure scram is provided at the came setting as the Core and con-
/
The APRN (high flux in startup or tainment cooling Systems (ECCS) refuel) System provides protection initiation to minimize the energy which against excessive power levels and short must be accommodated during a loss-of-reactor periods in the startup and coolant accident and to prevent return intermediate power ranges.
to criticality.
This instrumentation is l
a backup to the reactor vessel water The IRN System provides protection level instrumentation.
against short reactor periods in these ranges.
High radiation levels in the main steam line tunnel above normal levels that due The Control Rod Drive Scram System in
(
to the nitrogen and oxygen designed so that all of the water which Amendment No. pg 89 33 I
l h
I l
4 I.
r
-. ~ -
f.
JAFNPP 4.1 BASES (cont'd) k The bi-stable trip circuit which is a part of The frequency of calibration of the APRM i
-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/
month and, in addition, cross calibration i
A study was conducted of the instrumentation checks of the flow input to the flow biasing 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-T 1
failures /
bration of the entire network. While the cali-i l
hr..The non-ATTS bi-stable trip circuits are bration is being performed, a aero flow signal j
predgtedtohaveunsafefailurerateoflessthan will be sent to half of the APRM's resulting j
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 i
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 l
monitoring interval for analog devices as assumed significant and therefore, to avoid i
above, the instrument checks and functional tests spurious scrams, a calibration frequency I
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.
For example, the IRM is active during startup The bi-stable devices are monitored during plant and inactive during full-power operation.
j operation to record their failure history and es-Thus, the only test that tablish a test interval using the curve of Figure 4.1-1.
There are numerous identical bi-stable de-
{
vices used throughout the Plant's instrumentation system. Therefore, significant data on the
}
failure rates for the bi-stable devices should j
be accumulated rapidly.
l Amendment No. 89 38
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l
f.
t JAFNFP l
Table 4.1-1 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT FUNCTIONAL TEST MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRUMENT AND CONTROL CIRCUITS-Instrument Channel Group Functional Test Minimum Frequency (3)
Mode Switch in Shutdown A
Place Mode Switch in Sh'utdown Each refueling outage.
Trip Channel and Alarm Every 3 months.
I RFS Channel Test Switch A
Trip Channel and Alarm Every refueling outage or after 1
channel maintenance.
j IRM High Flux C
Trip Channel and Alarm (4)
Once per week during refueling or i
startup and before each startup.
J IRM Inoperative C
Trip Channel and Alarm (4)
Once per week during refueling or startup and before each startup.
i i
APRM j
High Flux B
Trip Output Relays (4)
Once/ week.
]
' Inoperative B
Trip Output Relays (4)
Once/ week.
j Downscale B
Trip Output Relays (4)
Once/ week.
l Flow Bias B
Calibrate Flow Bias Signal (4)
Once/ month (1).
I High Flux in Startup or Refuel C
Trip Output Relays (4)
Once per week during refueltag or startup and before each startup.
1 l
High Reactor Pressure 3
Trip Channel and Alarm (4)
Once/ month. (1)(8)
High Drywell Pressure B
Trip Channel and Alarm (4)
Once/ month. (1)(8) i Reactor low Level (5) _
B Trip channel and Alarm (4)
Once/ month.(1)(8) l High Water Level in Scram A
Trip Channel Once/ month.(7)
]
Discharge Instrument Volume i
I 1
High Water Level in Scram B
Trip Channel and Alarm (4)
Once/ month. (1)(8) l I
Discharge Instrument Volume i
Amendment No. y[, 94, 7)I 89 44 l
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o t
JAFNPP Table 4.1-1 (Cont'd)
REACTUR PROTECTION SYSTEM (SCRAM) INSTRUMENT FUNCTIONAL TEST MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRUMENT AND CONTROL CIRCUITS i
Instrument Channel Group (2) Functional Test Minimum Frequency (3)
Main Steam Line High Radiation B
Trip Channel and Alar $i(4)
Once/ week.
Main Steam Line Isolation Valve A
Trip Channel and Alarm Once/ month. (1) j Closure j
Turbine Control Valve EHC 011 A
Trip Channel and Alarm Onc6/ month.
Pressure i
{
Turbine First Stage Pressure B
Trip Channel and Alam(4)
Once/ month. (1)(8)
Permissive i
Turbine Stop Valve Closure A
Trip Channel and Alarm Once/ month. (1)
Reactor Pressure Permissive A
Trip Channel and Alarm Every 3 months.
I j
NOTES FOR TABLE 4.1-1 1.
Initially once every month until acceptable failure rate data are available; thereafter, a request may be 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 same design instrument operates in an j
environment similar to that of JAFNPP.
i
]
2.
A description of the three groups is' included in the Bases of this Specification.
3.
Functional tests are not required on the part of the system that is not required to be operable or are tripped.
If tests are missed on parts not required to be operable or are tripped, then they shall be performed prior 1
l to returning the system to an operable status.
I 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.
j Amendment No. )(, pf 89 45 l
i i
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I 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.
j 1
I 1
9 1
Intendent No. M M g, 89 45a
f.
I JAFNFP Table 4.1-2 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT CALIBRATION MINIMUM CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT 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 i
High Reactor Pressure 3
Standard Pressure Source Note (7)
High Dryvell 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 High Water Level in Scram B
Standard Pressure Source Every 3 months Discharge Instrument Volume 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) l Permissive Amendment No.
g, Af, g, g, 89 46
o f.
1 JAFNPP Table 4.1-2 (cont'd)
REACTOR PROTECTION STSTEN (SCRAN) INSTRUMENT CALIBRATION.
MINIMIBt CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRIRIENT CEANNELS Instrument Channel Group (1)
Calibration (4)
Minimus Frequency (2)
Turbine Control Valve Fast A
Standard Pressure Source Once/ operating cycle Closure Oil Pressure Trip Turbine Stop Valve Closure A
-Note (5)
Note (5)
Reactor Pressure Permissive A.
Standard Pressure Source Every 6 months NOTES FOR TABLE 4.1-2
- 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 tripped, but is required prior to return to service.
3.
The current source provides sa instrument channel alignment. Calibration using a radiation source shall be made each refueling outage.
4.
Response time is not a part of the routine instrument channel test but will be checked once per operating cycle.
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.
j Amendment No. 36. [ 89 47
9, t
JAFIIPP 4.2 BASg5 h 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 mode, and the' and calibrated at regularly scheduled in-system returned to its initial state. It tervals. h same design reliability is==r===d this task requires an estimated goal as the Reactor Protection System is 30 min. to complete in a thorough and work-generally applied. Censors, trip devices menlikemammerandjhattherelayshavea 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.
iy2(0.5) = 1 x 10 hr.
h ee instruments which, when tripped, result 10 *
= 40 days la a rod block have their contacts arranged in a 1 out of a logic, and all are capable For additional margia 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 optiman test interval that abould h sensors and electronic apparatus be maintained in order to maximize the re-have not been facluded here as these are liability of a given eh====1 (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 tests is approximately given by:
instruments. h checks which are made on a daily basis are adequate to assure operability of the sensors and electronic apparatus, 2_
and the test interval given above provides for i
=
r optimum testing of the relay circuits.
Where:
i = the optimum faterval between tests, t = the time the trip con-tacts are dioebled from performing their fume-ties while the test is la progress.
r - the espected failure rate of the relays.
Amendment No.
89 61
f.
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s JAPWFP
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TABLE 4.2-1 MINDERE TEST AIS CALIRRATION FREQUENCY FOR FCIS Instrument Ch====1 (S)
Instrument Fumetionsi Test
- Calibration Fr:;-_: :V Instrument Check (4) l I) Reactor High Pressure (1)
Once/3 months Nome (Shutdown Cooling Permissive)
- 2) Reactor Imw-low Mater Level (1)(5)
.(15)
Once/ day
- 3) Malm Steam High Temp.
(1)(5)
(15)
Once/ day
- 4) Main Steam Nigh Flow
, (1)(5)
(15)
Once/ day
- 5) Main Steam Low Pressure (1)(5)
(15)
Once/ day l
- 6) Beactor unter Cleammy (1)
Once/3 months.
Nome Eigh Temp.
- 7) Condenser Low vacuum (1)(5)
(15)
Once/ day g
Lonic System Functional Test (7) (9)
Fr;; ny j
1.
Main Steam Line Isolation valves Once/6 monthe Malm Steam Line Drain Valves Reactor Meter Sample Valves 2.
But - Isolation Yalve Control once/6 months Shutdeum Cooling Valves Read Spray 3.
Reactor Meter Clesemy Isolation once/6 asethe 4.
Dryuell Isolation Valves Once/6 months Tip Withdrauel Atmospheric Control Valves 5.
Standby Ces Treatment System once/6 anoths Reactor Building Isolation NOTE: See listing of notes following Table 4.2-6 for the notes referred to herein.
Amendment No. g 89 73
t JAFWP Table 4.2-2 MINDERE TEST AIS CALIERATION FREQUENCY FOR CORE M CONTAIIWWff COOLING SYSTBES Instrument Calibration Instemment Imotrusset Cheesel Panctional Test Pr:-.
._y Check (4)
~
- 1) Beactor Mater Iowel (1)(5)
(15)
Once/ day 2a) Drysell Pressere (non-ATTS)
(1)
Once/3 monthe Neon 2b) Drysell Pressere (ATTS)
(1)(5)
(15)
Dece/ day 3a) Beector Pressure (non-ATTS)
(1)
Once/3 monthe Nome 3b) Reactor Pressure (ATTS)
(t)(5)
(15)
Dece/ day
- 4) Auto Segoemeing Timero Nome Once/eperating cycle None l
(1)
Dece/3 esethe None
- 6) Trip System Bee Power IIseiters (1)
Nees Nome l
l l
- 8) Core Spray Sparger d/p (1)
Once/3 months Dece/ day
- 9) -Steam Line Nigh Flow (NFCI & 3CIC)
(1)(5)
.(15)
Dece/ day i
- 10) Steen Line/ Area Nigh Tony.(W CI & BCIC)
(t)(5)
(15)
Dece/ day.
- 12) EPCI & BCIC Steen Line Imu Pressere (1)(5)
(15)
Dece/ day
- 13) WCI Secties Source Levels (1)
Omee/3 monthe None
- 14) 4KT hergency Pouer Under-Voltage Gace/ operating Once/ operating cycle None
[
Eelays and Timere cycle e
- 15) WCI & BCIC Exheest Diaphrase (1)
Once/3 monthe None Pressere Nigh l
- 17) LPCI/ Cross Comoect Talve Position Dece/ operating Wome None cycle Note: See listing of notes following Table 4.2-6 for the notes referred to herein.
Amend.entNo.p.y. gas n
f.
8 JAFWFP TABLE 4.2-2 (CONT'D) l MINDEM TEST AIR CALIBRATION FREqtfENCY POR CORE AIS CONTADRIElfr COOLING SYSTEMS Logic System Functional Test Frequency I
I)
Core Spray Subsystem (7) (9) Once/6 months 2)
Low Pressure Coolant Injection Subsystem (7) (9) Once/6 months 3)
Containment Cooling Subsystem (9) Once/6 months 4)
RPCI Subsystem (7) (9) Once/6 months 5)
EPCI Subsystem Auto Isolation (7) (9) Once/6 months I
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. / 89 80 l
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o f.
e e
JAFNPP TABLE 4.2-3 NINDEBE TEST AIR CALIBRATION FREQW!NCT FOR COIFFROL BOD annert ACTUATION Instrument Functional Instrument Check-Instrument Chamael Test (5)
Calibration (12)(4) l 1)
APRN - Doenscale (1)
Once/3 aceths Once/ day 2)
AFRN - Upscale (1)
Once/3 months Once/ day 3)
IEN - Upscale (2)
(3)
(6)
Once/ day 4)
IEN - Dounseale (2)
(3)
(6)
Once/ day 5)
REM - Upscale (1)
Once/3 months Once/ day 6)
RBI - Downscale (1)
Once/3 months Once/ day 7)
SRM - Upscale (2)
(3)
(6)
Once/ day 8)
SEN - Detector Not in Startup Position (2)
(3)
(6)
None 9)
IRN - Detector Not in Startup Position (2)
(3)
(6)
None
- 10) Scram Discharge Instrument Volume -
Once/ month once/3 months Once/ day High Water Level (Group B Instruments)
(1)
Logic System Functional Test (7) (9)
M :-- - V l
1)
System logic Check Once/6 months NOTE: See listing of notes following Table 4.2-6 for the notes referred to herein.
hwat No./ g 89 81
t,
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i JAFNPP
+
g s
TABLE 4.2-4 c'y c
MINIMA ( TEST Alm CALIBRATION PREQUENCY FOR RADIATION IMITORING SfSTEMS Instrument hectional Instrument Check Instrument th===1 Test Calibration' (12)(4) j-1)
Refuel Area Exhaust Monitors (1)
Once/3 months once/ day p
2)
Beactor Building Area Exhaust Monitors (1)
Once/3 months Once/ day Turbine Building Exhaust Monitors (1)
Once/6 months Once/ day 1
Radueste Building Fwhannat Nealtors.
(1)
Once/6 months once/ day i
3) off-Ces Radiation Monitors (1)
Once/3 months once/ day 1
~
- 4). Main Control Acom Ventilation Monitor (1)
Once/3 months once/ day 5)
Mechanical Vacuum Pump Isolation See Table 4.1-2 j
6)
Liquid Radusste Discharge Monitor (1)
Once/3 months Once/ day when discharging Imaic System Functional Test (7)(9)
Fregeancy l
l 1)
Reactor Building Isolation once/6 monthe 2)
Standby Cas Treatment Sys. Actuation Once/6 monthe 3)
Steen Jet Air Ejector off-Ces Line Once/6 months Isolation i
4)
Mechsmical Vacuum Pump Isolation once/ Operating Cycle 5)
Liquid Radunste Discharge Isolation Once/6 months K
NOTE: See listing of notes following Table 4.2-6 fo'r.the notes referred to herein.
Amendment No. / 89 82 s
f.
I JAFNPP TABLE 4.2-5 MINIMUM TEST AND CALIBRATION FREQUENCY FOR DRYWELL LEAK DETECTION Instrument Functional Calibration Instrument Check Instrument Channel Test Frequency (4) l 1)
Equipment Drain Sump Flow Integrator (1)
Once/3 months once/ day 2)
Floor Drain Sump Flow Integrator (1)
Once/3 months Once/ day NOTE: See listing of notes following Table 4.2-6 for the notes referred to herein.
Amendment No. )[ 89 83 I
l
'g, i
JAFNPP-TABLE 4.2-6 MINIMUM TEST AND CALIBRATION FREQUENCY FOR SURVEILLANCE INSTRUMENTATION INSTRUMENT CHANNEL CALIBRATION FREQUENCY INSTRUMENT CHECK (4) l 1)
Reactor Water Level Once/6 months Once Each Shift 2)
Reactor. Pressure Once/6 months Once Each Shift 3)
Drywell Pressure Once/6 months Once Each Shift 4)
Drywell Temperature Once/6 months Once Each Shift 5)
Suppression Chamber Temperature Once/6 months.
Once Each Shift 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 Amendment No. g, g, g 89 84
~
f.
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
rate data are available; thereafter, a request may include a calibration of time delay 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 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.
3.
Calibrations are not required when these instruments 12.
See Technical Specification 1.0.F.4, 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
l surveillance for SRM and IRM l
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.
5.
This instrumentation is excepted from the functional 14.
Functional test is performed once each j
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 6.
These instrument chan.,r.ls will be calibrated using once per 6 months.
simulated electrical signals once every three months.
l 7.
Simulated automatic actuation shall be performed once j
each operating cycle. Where possible, all logic system I
l functional tests will be performed using the test jacks.
l l
8.
Reactor low water level, high drywell pressure and high radiation main steam line tunnel are not included on Table 4.2-1 since they are tested on Table 4.1-2.
Amendment No. )(, yI, yf 89 85 I
_-