ML20212M527
| ML20212M527 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 03/03/1987 |
| From: | Rajender Auluck Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20212M530 | List: |
| References | |
| TAC-60936, NUDOCS 8703120059 | |
| Download: ML20212M527 (10) | |
Text
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'o UNITED STATES Ig NUCLEAR REG'ULATORY COMMISSION o
WASHINGTON. D. C. 20555
\\...../
BOSTON EDISON CnMPANY DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
License No. DPR-35 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Boston Edison Company (the licensee) dated February 27, 1986, as corrected October 20, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Acti and the Commission's rules and reoulations 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 Commission; C.
There is reasonable 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 Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the nealth and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission'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 3.B of Facility Operating License No. DPR-35 is hereby amended to read as follows:
8703120059 870303 PDR ADOCK 05000293 P
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B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 99, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical _ Specifications.
3.
This license amendment id effective 30 days after the date of issuance.
i FOR THE NUCLEAR REGULATORY COMMISSION t
@f P.ajender Auluck, Project Manager BWR Project Directorate #1 Division of BVR Licensing
Attachment:
Changes'to the Technical Specifications Date of Issuance: March 3, 1987 J
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ATTACHMENT TO LICENSE AMENDMENT NO. 99 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 Revise the Appendix A Technical ~ Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the-captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 30 30 32
.32 33 33 3
38 38 60 60
)
61 61 67 67 l
7 g
,e 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 Refueling 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 Week During Refueling
.and Before Each Startup Inoperative
,C Trip Channel and Alarm Once Per Week During Refueling 4
and Before Each Startup-APRM High Flux B
Trip Output Relays (4)
Once/Heek (7)-
J Inoperative B
Trip Output Relays (4)
Once/Heek Downscale B
Trip Output Relays (4)
Once/Heek i
Flow Blas B
Calibrate Flow Blas Signal
.Once/ Month (1)
High Flux (157.)
B Trip Output' Relays (4)
Once Per Week 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) t High Hater Level in Scram Discharge Tanks D
Trip Channel and Alarm (4)
Every 3 Months i
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).
Turbine Control Valve Fast Closure A
Trip Channel'and Alarm (1)
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)
Reactor Pressure Permissive D
Trip Channel and Alarm (4)
Every 3 Months l
Amendment No. 7), 99 30 i
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TABLE 4 f.2
. REACTOR-PROTECTION 5 STEM-(SCRAM) INSTRUMENT. CALIBRATION-MINIMUM CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT CHANNELS
~
Instrument Channel Group (1)
Calibration Test (S)
MinimumFrequency(2)l IRM High Flux C-
. Comparison to APRM on Controlled Note (4)
Shutdowns Ful1 Calibration Once/ operating' cycle APRM High Flux Output Signal B
Heat Balance Once every 3 Days Flow Blas Signal B
Internal Power and Flow Test Each Refueling Outage LPRM Signal 6
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 Hater Level D
Note (7)
Note (7) i i
High Water Level in Scram Discharge Tanks D
Note (7)
Note (7) 5-l Turbine Condenser low Vacuum D
Note (7)
Note (7) l
' f-e Main Steam Line Isolation Valve Closure A
Note (6)
Note (6)
I, 1.
Main Steam Line High Radiation 8
Standard Current Source (3)
Every 3 Months Turbine First Stage Pressure Permissive D
Note (7)
Note (7) l-Turbine Control Valve Fast Closuie A
Standard. Pressure Source Every 3 Months
[
i Turbine Stop Valve Closure A
Note (6)
Note (6)
Reactor Pressure Permissive D
Note (7)
Note (7) l.
I.p A
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Amendment No. /B, 99 32
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NOTES FOR TABLE a.1.2 l '.
A description of four groucs 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'orovides an instrument channel ~ alignment. Calibration
~
using a radiation source shall be made each refueling outage.
~
4.
Haximum 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.
ETo verify transmitter outpuf, a daily instrument check will be
-performed. Calibration of the associated analog trip units will be l-performed concurrent with functional testing as specified in Table 4.1.1.
. Amendment No. 77, 99 33
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3.1 BASES (Cont'd) i4.1 SASES (Ccnt'd) to-perform its function adequately.
refueling outage.
The f. low biasing networt is functionally A source range monitor (SRM) testec at least once per montn system is also provided to supply anc, in addition. cross additional neutron level calibration checks of the flow information during start-up but has input.to the flow biasing. 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.
" Refuel" and "Startup/ Hot Standby" There are several instruments modes with tne APRM 15% scram, and which must be calibrated and it L
the power range eith the flow will take several days to perfccm
-biased rod block and scram.
The the calibration of.the entire IRM's provide aaditional protection network.
While the calibration in the " Refuel" and "Startup/ Hot is being performed, a zero ficw Standby" modes.
Thus, the IRM and signal will be sent to nalf 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 i
required in the "Run" mode.
generating stations, drift of instruments, sucn as those in the 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 levet scrams are required for calibration frequency of each Startup/ 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, the IRM is active during startup The requirement to have the scram and inactive during full-power functions, as indicated to Table operation.
Thus, the only test 3.1.1, operable in the Refuel mode that is meaningful is the one is 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 not diminish the are performed just prior to use need for the reactor protection of the instrument.
system.
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 cevices) provide alarms,
' turbine first stage pressure trips or scram functions.
An (45% of rated), tile scram availability analysis is detailed in NED0-21617A (12/78).
I Surveillance frequencies for the SDV system instrumentation is detailed in Amendment Number 65.
NRC concurrence with this surveillance pro-Amendment No. #, 99 38
m
.,t PNPS TABLE 4.2.A MINIMUM TEST AND CALIBRATION FREQUENCY FOR PCIS Instrument Channel (5)
Instrument Functional Test Galibration Frequengy Instrume'nt Check 1)
Reactor High Pressure (1) (7)
(7)
Once/ day 2)
Reactor Low-Low Hater 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)
Fg gy_ency e
1)
Main Steam Line Isolation Vvs.
Once/6 months Main Steam Line Drain Vvs.
~
Reactor Water Sample Vvs.
, p-2)
RHR - Isolation Vv. Control Once/6 months-I Shutdown Cooling Vvs.
~
Head Spray Discharge to Radwaste p
3)
Reactor Water Cleanup Isolation Once/6 months 5,.
4)
Drywell Isolation Vvs.
Once/6 months TIP Hithdrawal Atmospheric Control Vvs.
Sump Drain Valves P
5)
Standby Gas Treatment System Once/6 months Reactor Building Isolation i
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Amendment No. 99 60
3
~q; PNPS-TABLE 4.2.B MINIMUM TEST AND CALIBRATION FREQUENCY FO.R.QSQS Instrument Channel Instrument Functional Test Calibration Frequency Instrument Check 1)
Reactor Water Level
.(1)-(7)
-(7)
Once/ day 2)
Drywel1 Pressure
-(1).(7)
(7)
Once/ day 3)
Reactor Pressure (1) (7)
(7)
Once/ day-4)
Auto Sequencing Timers NA Once/ Operating cycle
'None 5)
Pressure Interlock (1)
Once/3 months None i]
6)
Start-up Transf. (4160V)
None a.
Loss of Voltage Relays Monthly Once/ Operating cycle 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.;
e 9)
Core Spray Sparger d/p NA Once/ Operating cycle.
Once/ day i)
(1)
Once/3 months None p
(1)
Once/3 months None il[
- 12) Safeguards Area High Temp.
(1)
Once/3 months None
-}
Once/3. months None-j i
- 14) HPCI Suction Tank Levels (1)
Once/3 months None
- 15) Emergency 4160V Buses A5 & A6 Monthly Once/Oper.iting Cyc h Non'e Loss of Voltage Relays
.l, 1
'61 Amendment No. 61 99 l
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';CTES FOR TABLES 4.2.A THROUGH 4.2.G 1
Initially once par month until exposure hours (M as defined on Figure 5
4.1.1) is 2.0 x 10 ; 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 oerformed during each startup or during controlled shutdowns with a required frequency not to exceed once per week.
Instrument-checks shall be cerformed 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 simulated 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-systems.
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.42, 99 67