ML20215M979
| ML20215M979 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 10/29/1986 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20215M980 | List: |
| References | |
| NUDOCS 8611040120 | |
| Download: ML20215M979 (13) | |
Text
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UNITED STATES M
1.
NUCLEAR REGULATORY COMMISSION j
L/)e $
WASHINGTON, D. C. 20555 k
COMMONWEALTH EDIS0N COMPANY DOCKET N0. STN 50-454 BYRON STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE
~
Amendment No. 4 License No. NPR-37 1.
The Nuclear Regulatory Commission (the Comission) has found that:
.A.
The applications for amendment by Comonwealth Edison Company (thelicensee)datedJuly 30, 1986 and August 5, 1986 comply 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; 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 Comission'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 i~n accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements I
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. NPR-37 is hereby amended to read as follows:
8611040120 e61029 PDR ADOCK 05000454 P
- 4 (2) Technical Specifications The Technical Specifications contained in' Appendix A, as revised through Amendment No. 4, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental' Protection Plan.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR ATORY COMMISSION ff
. ve gai PWR Project Director t #3 Division of PWR Licen g-A, NRR
Attachment:
Changes to the Technical Specifications Date of Issuance: October 29, 1986 O
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WASHINGTON, D. C. 20555 ATTACHMENT TO LICENSE AMENDMENT NO. 4 FACILITY OPERATING LICENSE NO. NPR-37 DOCKET N0. STN 50-454 Revise Apoendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by
.the captioned amendment number and contain marginal lines indicating the area of change. Overleaf pages (*) have been provided to maintain document completeness.
Remove Pages
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Insert Pages 3/4 2-1*
3/4 2-2 3/4 2 3/4 2-7 3/4 2-7 3/4 2-8*
3/4 3-43*
3/4 3-44 3/4 3-44 3/4 7-3*
3/4 7-4 3/4 7-4 1
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SCALE FIGURE 5.1-2 LOW POPULATION ZONE (L.P.Z.)
PUBLIC FACILITIES AND INSTITUTIONS WITHIN 3 MILES OF THE SITE BYRON - UNITS 1 & 2 5-3 AMENDMENT N0. 4
DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall contain 193 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaloy-4.
Each fuel rod shall have a nominal active fuel-length of 144 inches.
The initial core loading shall have l
a maximum enrichment of less than 3.20 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.0 weight percent U-235.
CONTROL ROD ASSEMBLIES 5.3.2 The core shall cont'ain 53 full-length and no part-length control rod
' assemblies. The full-length control rod assemblies shall contain a nominal 142 inches of absorber material.
All control rods shall be hafnium, clad with
-stainless steel tubing.
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5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:
a.
In accordance with the Code requirements specified in Section 5.2 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
For a pressure of 2485 psig, and c.
For a temperature of 650'F, except for the pressurizer which is 680*F.
VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 12,257 cubic feet at a nominal T,yg of 588.4*F.
5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
BYRON - UNITS 1 & 2 5-4 AMENDMENT NO. 4
PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 At least two independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:
a.
One motor-driven auxiliary feedwater pump capable of being powered from an ESF Bus, and b.
One direct-driven ~ diesel auxiliary feedwater pump capable of being powered from a direct-drive diesel engine and an OPERABLE Diesel Fuel Supply System consisting of a day tank containing a minimum of 420 gallons of fuel.
APPLICABILITY:
MODES 1, 2, and 3.
ACTION:
a.
With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to.0PERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the'next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With both auxiliary feedwater pumps inoperable, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.1.2.1 Each auxiliary feedwater pump shall be demonstrated OPERABLE:
a.
At least once per 31 days on a STAGGERED TEST BASIS by:
1)
Verifying that the pump develops a differential pressure of greater than or equal to 1825 psid at a flow of greater than or equal to 85 gpm on the recirculation flow when tested pursuant to Specification 4.0.5; BYRON - UNITS 1 & 2 3/4 7-4 AMENDMENT NO. 4
f.
TABLE 3.7-2 STEAM l.INE SAFETY VALVES PER LOOP VALVE ~ NUMBER LIFT SETTING (11%)*
ORIFICE SIZE M5013(A-0) 1235 psig 16 in MS014(A-D) 1220 psig 16 in2 M5015(A-D) 1205 psig 16 in2 M5016(A-0) 1190 psig 16 in2 MS017(A-0) 1175 psig 16 inz 1
- The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
BYRON - UNITS 1 & 2 3/4 7-3
INSTRUMENTATION SEISMIC INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.3 The seismic monitoring instrumentation shown in Table 3.3-7 shall be OPERABLE.
APPLICABILITY:
At all times.
ACTION:
a.
With one or more of the above required seismic monitoring instruments inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrumr_.it(s) to OPERABLE status.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
' SURVEILLANCE REQUIREMENTS 4.3.3.3.1 The seismic monitoring instrumentation shall be determined OPERABLE:
a.
At least once per 31 days byJverifying operable status indications of the seismic monitoring instrumentation.
b.
At least once per 92 days by verifying that:
1)
The triaxial acceleration sensors and the time-history accelero-graphs properly process the equipment internal test signals.
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2)
The response spectrum analyzer properly executes its diagnostic routine.
c.
At least once per 184 days by verifying that the triaxial acceleration sensors and the time-history accelerographs properly record the equipment internal test signals.
The test may be performed in lieu of the test required by Specification 4.3.3.3.1.b.1), and d.
At least once per 18 months by:
1)
Verifying the electronic calibration of the time-history accelerographs.
2)
Installing fresh magnetic recording plates in the triaxial peak accelerographs.
4.3.3.3.2 Upon actuation of the seismic monitoring instruments, the equipment listed in Table 3.3-7 shall be restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following the seismic event.
Data shall be retrieved from actuated instruments and analyzed to determine the magnitude of the vibratory ground motion.
A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 14 days describing the magnitude, frequency spectrum and resultant effect upon facility features important to safety.
BYRON - UNITS 1 & 2 3/4 3-44 AMENDMENT NO. 4
INSTRUMENTATION MOVABLE INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The Movable Incore Detection System shall be OPERABLE with:
.a.
At least 75% of the detector thimbles, b.
A minimum of two detector thimbles per core quadrant, and Sufficient movable detectors, drive, and readout equipment to map c.
these thimbles.s APPLICABILITY: When the Movable Incore Detection System is used for:
Recalibration of the excore neutron flux detection system, or a.
b.
Monitoring the QUADRANT POWER TILT RATIO, or c.
Measurement of F H, F (Z) and F q
xy.
ACTION:
With the Movable Incore Detection System inoperable, do not use the system for the above applicable monitoring or calibration functions.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.2 The Movable Ir, core Detection System shall be demonstrated OPERABLE at least onco per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by normalizing each detector output when required for:
Recalibration of the Excore Neutron Flux Detection System, or a.
b.
Monitoring the QUADRANT POWER TILT RATIO, or N
c.
Measurement of F
, F (Z), and F q
xy.
BYRON - UNITS 1 & 2 3/4 3-43
POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)
P 2)
When the F is less than or equal to the F limit for the appropriate measured core plane, additional power distribution P
maps shall be taken and F compared to F and F at least once per 31 EFPD.
The F,y limits for RATED THERMAL POWER (F P) shall be 1.71 for all e.
core planes containing Bank "D" control rods and 1.55 for all unrodded core planes; f.
The F limits f Specification 4.2.2.2e., above, are not applicable xy in the following core planes regions as measured in percent of core height from the bottom of the fuel:
1)
Lower core region from 0 to 15%, inclusive, 2)
Upper core region from 85 to 100%, inclusive, 3)
Within i 2% of grid plane regions such that no more than 20% of the total core height in the center core region is affected, and 4)
Core plane regions within i 2% of core height (1 2.88 inches) about the bank demand position of the Bank "D" control rods.
g.
With F exceeding Fx, the effects of F on F (Z) shall be xy g
evaluated to determine if F (1) is within its limits.
q 4.2.2.3 When F (Z) is measured for other than F determinations, an overall g
xy measured F (Z) shall be obtained from a power di,stribution map and increased g
by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.
BYRON - UNITS 1 & 2 3/4 2-7 AMENDMENT NO. 4 s
POWER DISTRIBUTION LIMITS 3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR LIMITING CONDITION FOR OPERATION 3.2.3 Indicated Reactor Coolant System (RCS) total flow rate and F shall be H
maintained as follows for four loop operation.
.a.
RCS Total Flowrate > 390,400 gpm, and b.
F
$ 1.55 [1.0 + 0.3 (1.0-P)]
H where:
Measured values of F are obtained by using the movable incore H
detectors.
An appropriate uncertainty of 4% (nominal) or greater sha'll then be applied to the measured value of F before it is g
compared to the requirements, and THERMAL POWER p, RATED THERMAL POWER APPLICABILITY: MODE 1.
ACTION:
With RCS total flow rate or F outside the region of acceptable operation:
g a.
Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either:
Restore RCS total flow rate and F"" to within the above limits, 1.
0 or 2.
Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER and redJce the Power Range Neutron Flux-High Trip Setpoint to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
BYRON - UNITS 1 & 2 3/4 2-8
LIMITING CONDITION FOR OPERATION ACTION (Continued)
With the indicated AFD outside of the above required targ t b c.
more than l' hour of cumulative penalty deviation time during th
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e and for previou's 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and with THERMAL POWER less than 50%
e than 15% of RATED THERMAL POWER, the THERMAL POWER shall reater increased equal to or greater than 50% of RATED THERMAL PO not be the. indicated AFD is within the above required target b until and.
SURVEILLANCE REQUIREMENTS 4.2.1.1 POWER OPERATION above 15% of RATED THERMAL P s during' Monitoring the indicated AFD for each OPERABLE excore ch a.
1).
At least once per 7 days when the AFD Monitor Alarm is OP annel:
and 2)
At least once per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after rest the AFD Monitor Alarm to'0PERABLE status.oring b.
Monitoring and logging the indicated AFD for each'0PERABLE once per 30 minutes thereafter, when the AFD M excore ast inoperable.
The logged values of the indicated AFD shall be assumed to exist during the interval preceding each logging 4.2.1.2 when two or more OPERABLE excore channels are ind the target band.
rget band shall be accumulated on a time basis of: Penalty deviation outside 'of the ab to be outside One minute penalty deviation for each 1 minute of POWER OPER a.
outside of the target band at THERMAL POWER levels equal to or N
50% of RATED THERMAL POWER, and ve b.
One-half minute penalty deviation for each 1 minute of POWER O outside of the target band at THERMAL POWER levels between 15%
RATION 50% of RATED THERMAL POWER.
nc 4.2.1.3 determined by measurement at least once per 92 EffectiThe ta The provisions of Specification 4.0.4 are not applicableve Full Power Days.
shall-be 4.2.1.4 31 Effective Full Power Days by either determining the tarTh pursuant to Specification 4.2.1.3 above or by linear interpol ti r
get flux difference most recently measured value and the predicted value at the a on between the life.
The provisions of Specification 4.0.4 are not applicable end of the cycle l
. BYRON - UNITS 1 & 2 3/4 2-2 AMENDMENT NO. 4
i 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE LIMITING CONDITION FOR OPERATION 3.2.1 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within the following target band (flux difference units) about the target flux difference:
a.
15% for Cycle 1 core average accumulated burnup of less than or equal to 5000 MWD /MTU, and b.
+ 3%,~ -9% for Cycle 1 core average accumulated burnup of greater than 5000 MWD /MTU, and c.
+ 3%, -12% for each subsequent cycle.
The indicated AFD nay deviate outside the above required target band at greater than or equal to 50% but less than 90% of RATED THERMAL POWER provided the indi-cated AFD is within the Acceptable Operation Limits of Figure 3.2-1 and the cumulative penalty deviation time does not exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The indicated AFD may deviate outside the above required target band at greater than 15% but less than 50% of RATED THERMAL POWER provided the cumulative penalty deviation time does not exceed.1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
APPLICABILITY:
MODE I above 15% of RATED THERMAL PCWER*.
ACTION:
a.
With the indicated AFD outside of the above required target band and with THERMAL POWER greater than or equal to 90% of RATED THERMAL POWER, within 15 minutes, either:
1.
Restore the indicated AFD to within the above required target band limits, or 2.
Reduce THERMAL POWER to less than 90% of RATED THERMAL POWER.
b.
With the indicated AFD outside of the above required target band for more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of cumulative penalty deviation time during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or outside the Acceptable Operation Limits of Figure 3.2-1 and with THERMAL POWER less than 90% but equal to or greater than 50% of RATED THERMAL POWER, reduce:
1.
THERMAL POWER to less than 50% of RATED THERMAL POWER within 30 minutes, and 2.
The Power Range Neutron Flux - High Setpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- See Special Test Exceptions Specification 3.10.2.
MSurveillance testing of the Power Range Neutron Flux channel may be performed pursuant to Specification 4.3.1.1 provided the indicated AFD is maintair.ed within the Acceptable Operation Limits of Figure 3.2-1.
A total of 16 noers operation may be accumulated with the AFD outside of the above required target band during testing without penalty deviation.
BYRON - UNITS 1 & 2 3/4 2-1 x
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