ML20154D494

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Proposed Tech Specs Reflecting New Min Calibr & Test Frequencies for Instrument Channels Being Upgraded by Installation of Analog Trip Sys
ML20154D494
Person / Time
Site: Pilgrim
Issue date: 02/27/1986
From:
BOSTON EDISON CO.
To:
Shared Package
ML20154D487 List:
References
NUDOCS 8603060114
Download: ML20154D494 (8)
v • d • e


Text

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Attachment B Proposed Technical Specification Change for Analog Trip System Pages affected:

30 l 32 33 38 60 61 1 8

67 '

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0603060114 060227 I DR ADOCK 050 g 3 l

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TABLE 4.1.1 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION FUNCTIONAL TESTS MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTR. AND CONTROL CIRCUITS -

Group (2) Functional Test Minimum frequency (3)

Mode Switch in Shutdown A Place Mode Switch in Shutdown Each Refueltag Outage Manual Scram A Trip Channel and Alarm Every 3 Months RPS Channel Test Switch (5) A Trip Channel and Alarm Each Refueling Outage IRM High Flux C Trip Channel and Alarm (4) Once Per Heek During Refueling and Before Each Startup Inoperative C Trip Channel and Alarm Once Per Week During Refueling and Before Each Startup APRM ~

High Flux B Trip Output Relays (4) Once/Heek (7)

Inoperative

~

B Trip Output Relays (4) Once/Heek Downscale - B Trip Output Relays (4) Once/Heek-Flow Blas Calibrate Flow Blas Signal B Once/ Month (1)

High Flux (15%) '

B Tr!p Output Relays (4) Once Per Heek During Refueling and Before Each Startup High Reactor Pressure D Trip Channel and Alarm (4) (1)

High Drywell Pressure ,

D Trip Channel and Alarm (4) (1)

Reactor Low Hater Level (6) D Trip Channel and Alarm (4) (1)

High Hater Level in Scram Discharge Tanks D Trip Channel and Alarm Every 3 Months Turbine Condenser Low Vacuum D Trip Channel and Alarm (4) (1) l Main Steam Line High Radiation B Trip Channel and Alarm (4) Once/Heek Main Steam Line Isolation Valve Closure A Trip Channel and Alarm (1) l Turbine Control Valve Fast Closure A Trip Channel and Alarm (1) -

l Turbine First Stage Pressure Permissive D Trip Channel and Alarm (4) Every 3 Months l Turbine Stop Valve Closure A Trip Channel and Alarm (1) l Reactor Pressure Permissive D Trip Channel and Alarm (4) Every 3 Months l Amendment No. 79 30

TABLE 4.1.2 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT CALIBRATION MINIMUM CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT CHANNELS Instrument Channel Group (1) Calibration Test (5) Minimum Frequency (2)

IRM High Flux C Comparison to APRM on Controlled Notel(4)

Shutdowns Full Calibration Once/ operating cycle APRM High Flux Output Signal B Heat Balance Once every 3 Days Flo" Blas Signal B Internal Power and Flow Test Each Refueling Outage LPRM Signal B TIP System Traverse Every 1000 Effective

_ Full Power Hours High Reactor Pressure D Note (7) Note (7)

High Drywell Pressure D Note (7) Note (7)

Reactor Low Water Level D Note (7) Note (7)

High Water Level in Scram Discharge Tanks D Note (7) Note (7)

Turbine Condenser Low Vacuum D Note (7) Note (7) l Main Steam Line Isolation Valve Closure A Note (6) Note (6)

Main Steam Line High Radiation B Standard Current Source (3) Every 3 Honths Turbine First Stage Pressure Permissive D Note (7) Note (7) l Turbine Control Valve fast Closure A Standard Pressure Source Every 3 Honths Turbine Stop Valve Closure A Note (6) Note (6)

Reactor Pressure Permissive D Note (7) Note (7) l Amendment No. 79 32

NOTES FOR TABLE 4.1.2

1. A description of four groups is included in the bases of this Specification.
2. Calibration tests are not required when the systems are not required to be operable or are tripped.
3. The current source provides an instrument channel alignment. Calibration using a radiation source shall be made each refueling outage.
4. Maximum frequency required is once per week.
5. Response time is not a part of the routine instrument channel test, but will be enecked once per operating cycle.
6. Physical inspection and actuation of these position switches will be performed during the refueling outages.
7. Calibration of these devices will be performed during refueling outages.

To verify transmitter output, a daily instrument check will be performed. Calibration of the associated analog trip units will be performed concurrent with functional testing as specified in Table 4.1.1.

i Amendment No. 79 33

3.1 BASES (Cont'd) 4.1 BASES (Cont'd) t to perform its function adequately. refueling outage. The flow blasing network is functionally  ;

A source range monitor (SRM) tested at least once per month e system is also provided to supply and, in addition, cross additional neutron level calibration checks of the flow information during start-up but has input to the flow blasing network no scram functions. Ref. Section can be made during.the functional 7.5.4 FSAR. The APRM's cover the test by direct meter reading.

j

" Refuel" and "Startup/ Hot Standby" There are several instruments -

modes with the APRM 15% scram, and which must be calibrated and it

< the power range with the flow will take several days to perform biased rod block and scram. The the calibration of the entire IRM's provide additional protection network. While the calibration in the " Refuel" and "Startup/ Hot is being performed, a zero flow Standby" modes. Thus, the IRM and signal will be sent to half of APRM 15% scram are required in the the APRM's resulting in a half

" Refuel" and "Startup/ Hot Standby" scram and rod block condition.

modes. In the power range the APRM Thus, if the calibration were system provides the required performed during operation, flux

, protection. Ref. Section 7.5.7 shaping would not be possible.

FSAR. Thus, the IRM system is not Based on experience at other  ;

required in the "Run" mode, generating stations, drift of f instruments, such as those in the i The high reactor pressure, high Flow Blasing Network, is not drywell pressure, reactor low water significant and therefore, to level and scram discharge volume avoid spurious scrams, a high level scrams are required for calibration frequency of each Startep/ Hot Standby and Run modes refueling outage is established.

of plant operation. They are, therefore, required to be Group (C) devices are active only ,

operational for these modes of during a given portion of the reactor operation. operational cycle. For example, i the IRM is active during startup The requirement to have the scram and inactive during full-power j functions, as indicated in Table operation. Thus, tne only test 3.1.1, operable in the Refuel mode that is meaningful is the one l 1s to assure that shifting to the performed just prior to shutdown  ;

Refuel mode during reactor power or startup; i .e., the tests that  ;

operation does nct diminish the are performed just prior to use I need for the reactor protection of the instrument.

system.  !

i Group (D) devices, while similar The turbine condenser low vacuum in description to those in Group scram is only required during power (B), are different in use because

operation and must be bypassed to they (the analog transmitter / trip start up the unit. Below 305 psig unit devices) provide alarms, turbine first stage pressure trips or scram functions. An j (45% of rated), the s; ram availability analysis is detailed j in NED0-21617A (12/78). l Surveillance frequencies for the SDV system instrumentation is detailed in Amendment Number 65.

NRC concurrence with this surveillance pro-t Amendment No. 79 38

PNPS TABLE 4.2.A MINIMUM TEST AND CALIBRATION FREQUENCY FOR PCIS Instrument Channel (5) Instrument functional Test Calibration Frequency Instrument Check ,

1) Reactor High Pressure (1) (7) (7) Once/ day
2) Reactor Low-Low Water Level (1) (7) (7) Once/ day
3) Reactor High Water Level (1) (7) (7) Once/ day
4) Main Steam High Temp. (1) Once/3 months None
5) Main Steam High Flow (1) (7) (7) Once/ day
6) . Main-Steam Low Pressure (1) (7) (7) Once/ day
7) Reactor Water Cleanup High Flow (1) Once/3 months Once/ day
8) Reactor Water Cleanup High Temp. (1) Once/3 months None Logic System Functional Test (4) (6) Fr,equency
1) Main Steam Line Isolation Vvs. Once/6 months Main Steam Line Drain Vvs.

Reactor Water Sample Vvs.

2) RHR - Isolation Vv. Control Once/6 months Shutdown Cooling Vvs.

Head Spray Discharge to Radwaste

3) -Reactor Water Cleanup Isolation Once/6 months
4) Drywell Isolation Vvs. Once/6 months TIP Withdrawal l Atmospheric Control Vvs.

Sump Drain Valves l

5) Standby Gas Treatment-System Once/6 months L Reactor Building Isolation l

t i

Amendment No. 60 l

l r

PNPS TABLE 4.2.8 MINIMUM TEST AND CALIBRATION FREQUENCY FOR CSQ5 Instrument Channel Instrument Functional Test Calibration Freggency Instrument Check

1) Reactor Hater Level (1) (7) (7) Once/ day
2) Drywell Pressure (1) (7) (7) Once/ day
3) Reactor Pressure (1) (7) (7) Once/ day
4) Auto Sequencing Timers NA Once/ Operating cycle None
5) ADS - LPCI or CS Pump Disch.

Pressure Interlock (1) Once/3 months None

6) Start-up Transf. (4160V)
a. Loss of Voltage Relays Monthly Once/ Operating cycle None
b. Degraded Voltage Relays Monthly Once/ Operating cycle None
7) Trip System Bus Power Monitors Once/ operating cycle N/A Once/ day
8) Recirculation System d/p (1) Once/3 months Once/ day
9) Core Spary Sparger d/p NA Once/ Operating cycle Once/ day
10) Steam Line High Flow (HPCI & RCIC) (1) Once/3 months None.
11) Steam Line High Temp. (HPCI & RCIC) (1) Once/3 months None
12) Safeguards Area High Temp. (1) Once/3 months None
13) HPCI and RCIC Steam Line Low Pressure (1) Once/3 months None
14) HPCI Suction Tank Levels (1) Once/3 months None 15)- Emergency 4160V Buses A5 & A6 Monthly Once/ Operating Cycle. None j Loss of Voltage Relays

! Amendment No. 61 i

NOTES FOR TABLES 4.2.A THROUGH 4.2.G

1. Initiall'y once per month until exposure hours (M as defined on Figure 4.1.1) is 2.0 x 10 5 ;-thereafter, according to Figure 4.1.1 with an interval not less than one month nor more than three months.
2. Functional tests, calibrations and instrument' checks are not required when these instruments are not required to be operable or are tripped.

Functional tests shall be performed before each startup with a required frequency not to exceed once per week. Calibrations of IRMs and SRMs shall be performed during each startup or during controlled shutdowns with a required frequency.not to exceed once per week. Instrument checks shall be performed at least once per' day during those periods when the instruments are required to be operable.

3. This instrumentation is excepted from the functional test definition.

The functional test will consist of injecting a simulated electrical signal into the measurement channel.

These instrument channels will be calibrated using $1mulated electrical signals once every three months.

4. Simulated automatic actuation shall be performed once each operating cycle. Where possible, all logic system functional tests will be performed using the test jacks.
5. Reactor low water level, high drywell pressure and high radiation main steam line tunnel are not included on Table 4.2.A since they are tested on Table 4.1.2.
6. The logic system functional tests shall include a calibration of time delay relays and timers necessary for proper functioning of the trip system.
7. Calibration of analog trip units will be performed concurrent with functional testing. The functional test will consist of injecting a simulated electrical signal into the measurement channel. Calibration of associated analog transmitters will be performed each refueling outage.

Amendment No. 67

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