ML20064H238
| ML20064H238 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 03/09/1994 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20064H244 | List: |
| References | |
| NUDOCS 9403170216 | |
| Download: ML20064H238 (17) | |
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UNITED STATES y,' s j
Ji NUCLEAR REGULATORY COMMISSION
$k WASHINGTON. D.C. 20556 0001
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a 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. 207 License No. DPR-59 l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Power Authority of the State of New York (the licensee) dated July 15, 1993, 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 Commission-1 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 health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part j
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 2.C.(2) of Facility Operating License No. OPR-59 is hereby amended to read as follows:
j 9403170216 940309 ADOCKOSOOOg88 DR
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i (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 207, are hereby. incorporated in the 1
license. The licensee shall operate the facility in accordance with i
the Technical Specifications.
I 3.
This license amendment is effective as of the date of its issuance to be implerented prior to startup following the next FitzPatrick refueling j
outage.
t FOR THE NUCLEAR REGULATORY COMMISSION 9 U 0. (W Robert A. Capra, Director Project Directorate I-l s
Division of Reactor Projects - I/II j
Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical Specifications i
Date of Issuance: March 9, 1994 i
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ATTACHMENT TO LICENSE AMENDMENT N0. 207 FACILITY OPERATING LICENSE N0. DPR-59 DOCKET NO. 50-333 Revise Appendix A as follows:
Remove Paaes Insert Paaes 33 33 34 34 41a 41a 43 43 45 45 46 46 47 47 57 57 64 64 65 65 78 78 84 84 Revise Appendix B as follows:
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JAFNPP f
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3.1 BASES (cont'd) subchannel. APRM's B, D and F are arranged similarly in A Reactor Mode Switch is provided which actuates or the other protection trip system. Each protection trip system bypasses the various scram functions appropriate to the has one more APRM than is necessary to meet the particular plant operating status. Reference paragraph minimum number required per channel. This allows the 7.2.3.7 FSAR.
bypassing of one APRM per protection trip system for maintenance, testing or calibration. Additional IRM channels The manual scram function is active in all modes, thus have also been provided to allow for bypassing of one such providing for a manual means of rapidly inserting control channel. The bases for the scram setting for the IRM, rods during all modes of reactor operation.
APRM, high reactor pressure, reactor low water level, main steam isolation valve (MSIV) closure, and generator load The APRM (high flux in startup or refuel) System provides rejection, turbine stop valve closure are discussed in protection against excessive power levels and short reactor Sections 2.1 and 2.2.
periods in the startup and intermediate power ranges.
instrumentation for the drywell is provided to detect a loss of The IRM System provides protection against short reactor i
coolant accident and initiate the core standby cooling periods in these ranges.
equipment. A high drywell pressure scram is provided at the same setting as the Core and Containment Cooling Systems 3
(ECCS) initiation to minimize the energy which must be accommodated during a loss-of-coolant accident and to prevent retum to criticality. This instrumentation is a backup to the reactor vessel water level instrumentation.
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Arnendment No. yI, gd, ggf 207 sa
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JAFNPP 3.1 BASES (cont'd)
The Control Rod Drive Scram System is designed so that The IRM high flux and APRM _< 15% power scrams all of the water which is discharged from the reactor by a provide adequate coverage in the startup and ir tramediate scram can be accommodated in the discharge piping.
range. Thus, the IRM and APRM systems are required to Each scram discharge instrument volume accommodates be operable in the refuel and startup/ hot standby modes.
in excess of 34 gallons of water and is the low point in The APRM :s120% power and flow referenced scrams the piping. No credit was taken for this volume in the provide sc@ed protection in the pcwer range (reference design of the discharge piping as concerns the amount of FSAR SeWa 7.5.7). The power range is covered only by water which must be accommodated during a scram.
the APRM3. Thus, the IRM system is not required in the run mode.
During normal operation the discharge volume is empty; however, should it fill with water, the water discharged to The high reactor pressure, high drywell pressure, reactor the piping from the reactor could not be accommodated, low water level and scram discharge volume high level which would result in slow scram times or partial control scrams are required for startup and run modes of plant rod insertion. To preclude this occurrence, level deteciion operation. They are, therefore, required to be operational instruments have been provided in each instrument volume for these modes of reactor operation.
which alarm and scram the reactor when the volume of water reaches 34.5 gallons. As indicated above, there is The requirement to have the scram functions indicated in sufficient volume in the piping to accommodate the scram Table 3.1-1 operable in the refuel mode assures that without impairment of the scram times or amount of shifting to the refuel mode during reactor power operation insertion of the control rods. This function shuts the does not diminish the protection provided by the Reactor reactor down while sufficient volume remains to Protection System.
accommodate the discharged water and precludes the situation in which a scram would be required but not be Turbine stop valve closure occurs at 10 percent of valve able to perform its function adequately.
closure. Below 217 psig turbine first stage pressure (30 percent of rated), the scram signal due to turbine stop A Source Range Monitor (SRM) System is also provided to valve closure is bypassed because the flux and pressure supply additional neutron level information during startup scrams are adequate to protect the reactor.
but has no scram functions (reference paragraph 7.5.4 FSAR).
Amendment No. }8,1/4 W 34
JAFNPP TABLE 3.1-1 (cont'd) i REACTOR PROTECTION SYSTEM (SCRAMI INSTRUMENTATION REQUIREMENT Minimum No.
Modes in Which Function of Operable Must be Operable Total Number of instrument instrument Channels Channels per Refuel Startup Run Provided by Design -
Action Trip System (1)
Trip Function Trip Level Setting' (6) for Both Trip Systems (1) 2 APRM Downscale 2: 2.5 indicated on X
6 Instrument Channels A or B
[
scale (9) 2 High Reactor Pressure s 1045 psig X(8)
X X
4 Instrument Channels A
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High Drywell Pressure s 2.7 psig X(7)
X(7)
X 4 Instrument Channels A
2 Reactor Low Water 2: 177 in. above TAF X X
X 4 Instrument Channels A
Level l
3 High Water Leve! in s 34.5 gallons per X(2)
X X
8 Instrument Channels A
Scram Discharge Volume Instrument Volume 4
Main Steam Line s 10% valve closure X(5) 8 Instrument Channels A
Isolation Valve Closure i
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l Amendment No.1)I, h, p,7/, p, gd,1/9,1p 207 41a 1
JAFNPP TABLE 3.1-1 (cont'd)
REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENT NOTES OF TABLE 3.1-1-(Cont'd)
C.
High Flux IRM.
D.
Scram Discharge Volume High Level when any control rod in a control cell containing fuel is not fully inserted.
E.
APRM 15% Power Trip.
7.
Not required to be operable when primary containment integrity is not required.
8.
Not required to be operable when the reactor pressure vessel head is not bolted to the vessel.
9.
The APRM downscale trip is automatically bypassed when the IRM Instrumentation is operable and not high.
- 10. An APRM will be considered operable if there are at least 2 LPRM inputs per levei and at least 11 LPRM inputs of the normal complement.
- 11. See Section 2.1.A.1.
- 12. The APRM Flow Referenced Neutron Flux Scram setting shall be less than or equal to the limit specified in the Core Operating Umits Report.
- 13. The Average Power Range Monitor scram function is varied as a function of recirculation flow (W). The trip setting of this function must be maintained as specified in the Core Operating Umits Report.
- 14. The APRM flow biased high neutron flux signal is fed through a time constant circuit of approximately 6 seconds. The APRM fixed high neutron flux signal does not incorporate the tir'e constant, but responds directly to instantaneous neutron flux.
- 15. This Average Power Range Monitor scram function is fixed point and is increased when the reactor mode switch is place in the Run position.
I 207 Amendment No. p, r%, gd, y//, gd,7/,7j(,19b, if, if9, if2 43
JAFNPP TABLE 4.1-1 (Cont'd)
REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT FUNCTIONAL TEST MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRUMENT AND CONTROL CIRCUITS Instrument Channel Groun (2)
Functional Test Minimum Freauency (3)
Main Steam Une Isolation Valve Closure A
Trip Channel and Alarm Once/ month.(1)
Turbine Control Valve EHC Oil Pressure A
Trip Channel and Alarm Once/ month.
Turbine First Stage Pressure Permissive B
Trip Channel and Alarm (4)
Once/ month.(1)(8)
Turbine Stop Valve Closure A
Trip Channel and Alarm Once/ month.(1)
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 environment similar to that of JAFNPP.
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 to retuming 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.
Amendment No. p. 6/, E)d,J2Er 207 45
JAFNPP TABLE 4.1-2 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT CALIBRATION MLNIMUM_CAllBBAI!ON FREQUENCLES FOR REACTOR PROTECTION INSTRUMENT C1LA_NNELS instrument Charinel Group (1)
Calibration Minimum Frequency (2)
IRM High Flux C
Comparison to APRM on Maximum frequency once/ week 1
Controlled Shutdowns APRM High Flux Output Signal B
Heat Balance Daily Flow Bias Signal B
Intemal Power and Flow Test Every refueling outage with Standard Pressure Source LPRM Signal B
TIP bystem Traverse Every 1000 effective full power hours High Reactor Pressure B
Standard Pressure Source Note (6)
.I High Drywell Pressure B
Standard Pressure Source Note (6) j Reactor Low Water Level B
Standard Pressure Source Note (6)
High Water Level in Scram A
Water Column, Note (5)
Once/ operating cycle, Note (5)
Discharge Instrument Volume High Water Level in Scram B
Standard Pressure Source Every 3 months Discharge Instrument Volume Main Steam Line Isolation A
Note (4)
Note (4)
Valve Closure Turbine First Stage Pressure B
Standard Pressure Source Note (6)
Permissive 4
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Amendment No. 4/,4[, @, p @,1f6, if3 207 i
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IABLE 4.1-2 (Cont'd)
REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT CALIBRATION MIN! MUM CALIBBAIl0N_EBEQUENCIES FOR REACTOR PROTECTION INSIBUMENT CHAN_NELS Instrument Channel Group (1)
Calibration 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 (4)
Note (4)
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 retum to service.
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Deleted 4.
Actuation of these switches by normal means will be performed during the refueling outages.
5.
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.
j G.
Sensor calibration once per operating cycle. Master / stave trip unit calibration once per 6 months.
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Amendment No. 4f, ff,8[, if6. If3 207 47 1
JAFNPP 3.2 BASES (cont'd)
High radiation monitors in the area of the main steam lines The trip settings of approximately 300 percent of desi n flow 0
have been provided to detect gross fuel failure as in the for this high flow or 40 F above maximum ambient for high control rod drop accident. A trip setting of 3 times normal temperature are such that uncovering the core is prevented and full-power background is established to close the main steam fission product release is within limits.
line drain valves, the recirculation loop sampio valves, the mechanical vacuum pump isolation valves, and trip the pumps, The RCIC high flow and temperature instrumentation are to limit fission product release. For changes in the Hydrogen arranged the same as that for the HPCI. The trip settings of Water Chemistry hydrogen injection rate, the trip setpoint may approximately 300 percent for high flow or 40 F above be adjusted based on a calculated value of the expected maximum ambient for temperature are based on the same radiation level. Hydrogen addition will result in an increase in criteria as the HPCI.
the N-16 carryover in the main steam.
The reactor water cleanup system high temperature Pressure instrumentation is provided to close the main steam instrumentation are arranged similar to that for the HPCI. The isolation valves in the run mode when the main steam line trip settings are such that uncover:ng the core is prevented and pressure drops below 825 psig. The reactor pressure vessel fission product release is within limits.
thermal transient due to an inadvertent opening of the turbine bypass valves when not in the run mode is less severe than The instrumentation which initiates ECCS action is arranged in a the loss of feedwater analyzed in Section 14.5 of the FSAR, dual bus system. As for other vitalinstrumentation arranged in therefore, closure of the main steam isolation valves for this fashion, the specification preserves the effectiveness of the thermal transient protection when not in the run mode is not system even during periods when maintenance or testing is required.
being performed. An exception to this is when logic functional testing is being performed.
The HPCI high flow and temperature instrumentation are provided to detect a break in the HPCI steam piping. Tripping The control rod block functions are provided to prevent of this instrumentation results in actuation of HPCI isolation excessive control rod withdrawal so that MCPR does not valves. Tripping logic for the high flow is a 1 out of 2 logic.
decrease to the Safety Limit. The trip 1/,3/,'}d,p,p.1/4,1[7 2N Amendment No.
57
JAFNPP TABLE 3.2-1 INSTRUMENTATION THAT INITIATES PRIMARY CONTAINMENT ISOLATION Minimum No.
of Operable Total Number of instrument Instrument Channels Channels Per Provided by Design Trip System (1)
Instrument Trip Level Setting for Both Trip Systems Action (2) 2 (6)
Reactor Low Water Level 2177 in. above TAF.
4 A
1 Reactor High Pressure s 75 psig 2
O (Shutdown Cooling isolation) 2 Reactor Low-Low-Low Water Level a 18 in. above the TAF 4
A 2 (6)
High Drywell Pressure s 2.7 psig 4
A 2
High Radiation Main s 3 x Normal Rated 4
E Steam Line Tunnel Full Power Background r
2 Low Pressure Main Steam Line z 825 psig (7).
4 B
2 High Flow Main Steam Line s 140% of Rated Steam Flow 4
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2 Main Steam Line Leak s 40 F above max ambient 4
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Detection High Temperature 4
Reactor Cleanup System Equipment s 40 F above max ambient 8
C Area High Temperature i
2 Low Condenser Vacuum 2 8' Hg. Vac (7)(B) 4 B
Closes MSIV's i
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Amendment No.1[, [, %, f, Q,1[3,1 f9, If, if5,2f3 b
207 64 t
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I JAFNPP BELE 3.2-1 (Cont'd)
INSTRUMENTATION THAT INITIATES PRIMARY CONTAINMENT ISOLATION NOTES FOR TABLE 3.2-1 1.
Whenever Primary Containment integrity is required by Section 3.7, there shall be two operable or tripped trip systems for each function.
2.
From and after the time it is found that the first column cannot be met for one of the trip systems, that trip system shall be tripped or the appropriate action listed below shall be taken.
A.
Place the reactor in the cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B.
Isolate the main steam lines within eight hours.
C.
Isolate Reactor Water Cleanup System within four hours.
D.
Isolate shutdown cooling within four hours.
l E.
Isolate the main steam line drain valves, the recirculation loop sample valves, l
and the mechanical vacuum pumps, within eight hours.
3.
Deleted 4.
Deleted 5.
Two required for each steam line.
6.
These signals also start SBGTS arid initiate secondary containment isolation.
. 7.
Only required in run mode (interlocked with Mode Switch).
8.
Bypassed when mode switch is not in run mode and turbine stop valves are closed.
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Amendment No. /. [8, f, f,1[2,1f9,1f2 207 65 l
JAFNPP TABLE 4.2-1 MINIMUM TEST AND CALIBRATION FREQUENCY FOR PCIS Instrument Channel (8) instrument Functional Test Calibration Frequency Instrument Check (4) 1)
Reactor High Pressure (1)
Once/3 months None (Shutdown Cooling Permissive) 2)
Reactor Low-Low-Low Water Level (1)(5)
(15)
Once/ day 3)
Main Steam High Temp.
(1)(5)
( 5)
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 High Temp.
(1)
Once/3 months None 7)
Condenser Low Vacuum (1)(5)
(15)
Once/ day l8)
Main Steam Line High Radiation (1)(5)
(11)
Once/ day Logic System Functional Test (7) (9)
Frequency 1)
Main Steam Line isolation Valves Once/6 months Main Steam Une Drain Valves Reactor Water Sample Valves 2)
RHR - Isolation Valve Control Once/6 months Shutdown Cooling Valves 3)
Reactor Water Cleanup Isolation Once/6 months 4)
Drywell isolation Valves Once/6 months TIP Withdrawal l
Atmospheric Control Valves 5)
Standby Gas Treatment System Once/6 months Reactor Building Isolation i
NOTE: See notes foi!owing Table 4.2-5.
Amendment No. f, p,1[6,1f1,1%, if0 207 78
JAFNPP NOTES FOR TABLES 4.2-1 THROUGH 4.2-5 1.
Initially once every month until acceptance failure rate data are 7.
Simulated automatic actuation shall be performed once each available; thereafter, a request may be made to the NRC to operating cycle. Where possible, all logic system functional change the test frequency. The compilation of instrument tests will be performed using the test jacks.
failure rate data may include data obtained from other boiling water reactors for which the same design instruments operate 8.
Reactor low water level, and high drywell pressure are not in a environment similar to that of JAFNPP.
included on Table 4.2-1 since they are listed on Table 4.1-2.
2.
Functional tests are not required when these instruments are 9.
The logic system functional tests shall include a calibration of not required to be operable or are tripped. Functional tests time delay relays and timers necessary for proper functioning of sha 1 be performed within seven (7) days prior to each startup.
the trip systems.
3.
Calibrations are not required when these instruments are not
- 10. At least one (1) Main Stack Dilution Fan is required to be in required to be operable or are tripped. Calibration tests shall operation in order to isokinetically sample the Main Stack.
be performed within seven (7) days prior to each stadup or prior to a pre-planned shutdown.
- 11. Perform a calibration once per operating cycle using a radiation source. Perform an instrument channel alignment once every 3 4.
Instrument checks are not required when these instruments months using the built-in current source.
are not required to be operable or are tripped.
- 12. (Deleted) 5.
This instrumentation is exempt from the functional test definition. The functional test will consist of injecting a
- 13. Calibration and instrument check surveillance for SRM and IRM simulated electrical signal into the measurement channel.
Instruments are as specified in Tables 4.1 -1, 4.1 -2, 4.2-3.
6.
These instrument channels will be calibrated using simulated
- 14. Functional test is performed once each operating cycle.
electrical signals once every three months.
- 15. Sensor calibration once per operating cycle. Master / stave trip unit calibration once per 6 months.
Amendment No. p, h, 5//,89,181 207 84
NOTES FOR TABLE 3dQ-2 (a)
Functional tests, calibrations and instrument checks need not be performed when these instruments are not required n be operable or are tripped.
(b)
Instrument checks shall be performed at least once per day during these periods when the instruments are required to be operable.
(c)
A source check shall be performed prior to each release.
(d)
Uquid radwaste effluent line instrumentation surveillance requirements need not be performed when the instruments are not required as the result of the discharge path i
not being utilized.
(e)
An instrument channel calibration shall be performed with known radioactive sources standardized on plant equipment which has been calibrated with NBS traceable standards.
(f)
Simulated automatic actuation shall be performed once each operaliag cycle. Where j
possible, all logic system functional tests will be performed using the test Jacks.
(g)
Refer to Appendix A for instrument channel functional test and instrument channel l
calibration requirements (Table 4.2-1). These requirements are performed as part of main steam high radiation monitor surveillances.
(h)
The logic system functional tests shall include a calibration of time delay relays and timers necessary for proper functioning of the trip systems.
4 (i)
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.
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Amendment No. h 207 l
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