ML20212F462
| ML20212F462 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 10/23/1997 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20212F466 | List: |
| References | |
| NUDOCS 9711040290 | |
| Download: ML20212F462 (10) | |
Text
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t UNITED STATES g
j NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 2006H001 o
%*ess /
e SOU THERN NUCLEAR OPERATING COMPANY. WCL ALABAMA POWER COMPANY DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 131 License No. NPF-2 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
1 he application for amendment by Southern Nuclear Operating Company, Inc.
(Scuthern Nuclear), dated September 3,1997, 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 v,ill operate in conformity with the application, the provisions of the Act, and the ru!ss 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 license amendment will not be inim. ' : D the common defense anu security or to the health and safety of the public; anc E.
The issuance of this amendment is in accorc'ance 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 ps.ragraph 2.C.(2) of Facility Operating License No. NPF-2 is hereby amended to read as follows:
9711040290 971023
~
PDR ADOCK 05000348 P
2 (2)
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised -
through Amendment ' o.131, are hereby incorporated in the license. Southem N
Nuclear shall operate the facility in accordance with the Technical Specifications.
3.
Thld license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
' FOR THE NUCLEAR REGULATORY COMMISSION h
da H rt N. Berkow, Director roject Directorate ll 2 Division of Retctor Projects.1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of lasuance:
October 23, 1997
ATTACHMENT TO LICENSE AMENDMENT NO.131 TO FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginallines.
Remove Paoes _
insert Paoes 3/4 2-4 3/4 2-4 3/42-6 3/4 2-6 3/4 3-42 3/4 3-42 B 3/4 2-2 B 3/4 2-2 B 3/4 2-4 B 3/4 2-4 B 3/4 3-2a B 3/4 3-2a a
l-
POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)
- _ _ _ -Determining the computed heat flux hot channel f actor Fo'(Z),
b.
as follows:
^ Increase the measured Fo(Z) obtained from the power.
distribution map by 3% to account for manufacturing tolerances and further increase the value by 5% to account for measurement uncertainties when the um; is taken with more than 37 OPERABLE detector thimbles.
For Unit 1, Cycle 15 only, with 25 to 37 OPERADLE thimbles the measurement uncertainty is determined from the following algorithm:
Fo measurement uncertainty = 5% + [2(3-(T/12.5))),
where T = the number of OPERABLE thimbles.
C c.
Verifying that lia (Z), obtained in Specification 4.2.2.2b above, satisfies the relationship in Specification 3.2.2.
d.
Satisfying the following relationships F"*"
x K(Z)
C 0
F0(Z) 5 for P
0.5 P
x W(Z)
F
x K(Z)
C F0(Z) 5 for P
0.5 0.5 x W(Z)
Where r (1) is obtained in Specification 4.2.2.2b above, Fo"' is c
o the Fo limit, K(Z) is the normalized Fo(Z) as a function cf core h31ght, P is the fraction of RATED THERMAL POWER, and W(2) is tne cycle dependent function that accounts for power distribution transients encountered during normal operation.
Fo"', K ( Z ), and W(Z) are specified in the COLR as per Specification 6.9.1.11.
e.
Measuring Fo(Z) according to the following schedule 1.
Upon achieving equilibrium conditions after exceeding by 20% or more of RATED THERMAL POWER, the THERMAL PCWER at which Fo(Z) was last deternined*, rr 2.
At least once per-31 Effective Full Power Days, whichever occurs first.
- During power escalation af ter each fuel loading, power level may be increased until equilibrium conditions'at any power level greater than or equal to 50% of RATED THERMAL 20WER have been achitived and a power distribution map-obtained.
FARLEY-UNIT 1 3/4 2-4 AMENDMENT NO.
131
POWER DISTRIBUTION LIMITS i
SURVEILINICE REQUIREMENTS (Continued) h.
The limits specified in Specification 4.2.2.2c are applicable in all core plane regions, i.e.,
0 - 100%, inclusive.
i.
The limits specified~in Specifications 4.2.2.2d, 4.2.2.2f, and 4.2.2.2g above are not applicable in the following core plane regions:
1)
Lower core region from 0 to.15%, inclusive 2)
Upper core region from 85 to 100%, inclusive.
4.2.2.3 When Fg(Z) is measured for reasons other than meeting the requirements of Specification 4.2.2.2, an overall measured Fo(Z) shall be obtained from a rower distribution map and increased by 3% to account for manufacturing tolerances and further increased to account for measurement uncertainty.- When the map is taken with more than 37 OPERABLE detector thimbles, the measurement uncertainty is 5%.
For unit 1, Cycle 15 only, with 25 to 37 OPERABLE thimbles the measurement uncertainty is determined from the following algorithm.
To measurement uacertainty = 5% + [2(3-(T/12.5))],
where T = the nt.mber of OPERABLE thimbles.
FARLEY-UNIT 1 3/4 2-6 AMENDMENT NO. 131
I i
POWER DISTRIBUTION LIKITS SURVEILLANCE REQUIREMENTS
_4.2.1.1 F$Hshallbedeterminedtobewithinitslimitbyusingthe movable incore detectors to obtain a power distribution maps a.
Prior to operation above 75% of RATED THERMAL POWER after each fuel loading, and b.
At least once per 31 Effective Full Power Days.
c.
The provisions of Specification 4.0.4 are not applicable.
4.2.3.2 ThemeasuredF5Hof4.2.3.1above, shall be ucreased by 4% for measurement uncertainty when the map is taken with more than 37 OPERABLE detector thimbles.
For Unit 1, Cycle 15 only, with 25 to 37 OPEPABLE thimbles the measurement uncertainty is determined from the following algorithm.
Fa measurement uncertainty = 4% + [1.5(3-(T/12.5))),
where T = the number of OPERABLE thimbles.
'FARLEY-UNIT 1 3/4 2-9 AMENDMENT No. 131 4
h n
INSTRUMENTATION MOVAB',E INCORE DETECTORS
.IMITING CONDITION FOR OPERATION 3.3.3.2 The movable incore detection system shall be OPERABLE with a.
At least 75%* of the detector thimbles, b.
A minimum of 2* detector thimbles per core quadrant, and c.
Sufficient movable detectors, drive, and readout equipment to map these thimbles.
APPLICABILITY:
When the movable incore detection system is used fort a.
Recalibration of the excore neutre, flux detection system, b.
Monitoring the QUADRANT POWER TILT RATIO, or MeasurementofF$g* Fg(Z) and F c.
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 REQUIREMD4TS 4.3.3.2 The movable incore detection system shall be demonstrated OPERABLE, by normalizing each detector output during use when required for:
a.
Recalibr& tion of the excere neutron flux detection system, or b.
Monitoring the QUADRANT POWER TILT RATIO, or MeasurementofF$g, Fg (Z) and F c.
xy.
- For Unit 1, Cycle 15 only, at least 50% of the detector thimbles are required..With less than 75% of the detector thimbles, a minimwm of 3
-detectors thlmbles-per core quadrant are required, where quadrant includes both the horizontal-vertical quadrant and diagonally bound quadrants (eight quadrants total).
EARLEY-UNIT 1 3/8 3-42 AMENDMENT NO.
131
POWER DISTRIBUTION LIMITS BASES 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR, NUCLEAR ENTHALPY HOT CHANNEL FACTOR The limits on heat flux hot channel factor, and nuclear enthalpy rise hot channel factor ensure that 1) the design limit on peak local power density is not exceeded, 2) the DNB design criterion is met, and 3) in the event of a LOCA the peak fuel clad temperature will not exceed the 2200'F ECCS acceptance criteria limit.
Each of these is measurable but will normally only be determined periodically as specified in Specifications 4.2.2 and 4.2.3.
This periodic surveillance is suf ficient to insure that the 1.imits are maintained provided:
a.
Control rods in a single group nave together with no individual rod snsertion differing by more than i 12 steps, indicated, i.
fro:a tne group demand position.
b.
Control rod banks are sequenced with overlapping groups as described in Specification 3.1.3.6.
c.
The control rod insertion limits of Specifications 3.1.3.5 and 3.1.3.6 are maintained, d.
The axial power distribution, expressed in terms of AXIAL FLUX DIFFERENCE, is maintained within the limits.
F$gwillbemaintainedwithinitslimitsprovidedconditionsa.
through d. above are maintained. TherelaxationofF$Hasafunctionof THERMAL PCWER allows changes in the radial power shape for all permissible rod insertion liraits.
When an Fg measurement is taken, an allowance fer both experimental error end manufacturing tolerance must be made.
An allowance of 5% is appropriate for a full core map taken with the incore detector flux napping system with more than 37 OPERABLE detector thimbles. With 25 to 37 OPERABLE detector thimbles, the allowance for measurement uncertainty is calculated b1 the algorithm in 4.2.2.2.b.
for Unit 1, Cycle 15 only. A 3%
allowance is appropriate for manufacturing tolerance.
The heat flux hot channel f actor Eb(3) ic measured perioe: ally and increased by a cycle and height dependent power factor appropriate to RAOC operation, W(Z), to provide acsurance that the lindt on the heat flux hot channel f actor Fb(Z) is met.
W(Z)' accounts for the effects of normal operational transients within the AFD limits and was determined from expected power control maneuvers over the full range of burnup conditions in the core.
The W(Z) function for normal operation and the AFD limita are provided in the COLR per Specification 6.9.1.11.
FARLEY-UNIT 1 B 3/4 2-2 AMENDMENT NO. 131
l POWER DISTRIBUTION LIMITS BASES WhenFfgismeasured, experimental error must be allowed for and 4%
4 is the appropriate allowance for a full core map taken with the incore detection system with more than 37 OPERABLE detector thimbles. With 25 to 37 OPERABLE detector thimbles, the allowance for measurement uncertainty is calculated by the algorithm defined by 4.2.3.2 for Unit 1, cycle 15 only.
The specified limit for F$g contains a ~4% allowance for nanufacturing uncertainties.
The total uncertainty allowance is based on the following considerations:
a, Abnornal perturbations in the radial power shape, such as from rod nd s alignment, affectF$gmoredirectlythanF, g
b.
Although rod movement has a direct influence upon limiting Fg to within its limit, suchcontrolisnotreadilyavailabletolimitF$g, and c.
Errors in prediction for control power shape detected during startup physics tests can be compensated for in Fg by restricting axial flux distribution.
ThiscompensationforF$H is less readily available.
If F$H exceeds its lindt, the unit will be allowed 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to restore F$H to within its lind t s.
This restoration may, for example, involve realigninganymisalignedrodsorreducingpowerenoughtobringFNHwithin its power dependent limit. WhentheF$H limit la exceeded, the DNBR limit is not likely violated in steady state operation, because events that could significantlyperturbtheF$gvalue, e.g.,
static control rod udsalignment, are considered in the safety analyses.
However, the DNBR limit may be violated if a DNB limiting avent occurs while F$g is above its limit. The increased allowed action time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> provides an acceptable time to restoreF$gtowithinitslimitswithoutallowingtheplanttoremaininan unacceptable condition for an extended period of time.
Once corrective action has been taken, e.g.,
realignment of misaligned rods or reduction of power, an incore flux map murt be obtained and the measured value of F$g verified not to exceed the allowed limit.
Twenty additional hours are provided to perform this task above the tour hours allowed by Action Statement 3/4.2.3.a.
The completion time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is acceptable because of the low probabilir'/ of having a DNB limiting event within this 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period and, in the eve.;L that power is reduced, an increase in DNB margin is obtained at lower power levels. Additionally, operating experience 'ias indicated that this completion time is suf ficient to obtain the incore flux map, perform the required calculations, and evaluateF$H' 4
FARLEY-UNIT 1 D 3/4 2-4 AMCNDMENT No. 131 l
-INSTRUMENTATION BASES ^
RADIATION MONITORING INSTRUMENTATION (continued)
The alarm / trip setpoint for the fuel storage pool area has been l
established based on a flow rato of 13,000 scfm; a_ release in which Xe-133 and Kr-85 are tho predominant isotopes, on concentration values equal-to or less than the effluent concentration limits stated in 10 CFR 20, Appendix B,-(to paragraphs 20.1001 - 20.2s01), Table 2, Column 1 for these isotopes, and on a X/O of 5.6 x 10-6,,ef,: at the site boundary.
3/4.3.3.2 MOVABLE INCORE DETECTORS
'The' OPERABILITY of the movable incore detectors with the specified
' minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distrjbution of the reactor core. The OPERABILITY f this system is demonstreted by irradiating each detector used and determining the acceptability of its voltage curve.
For the purpose of rneasuring Fg(Z), F$H, and F a full in: ore flux map is used.
Quarter-core flux maos, asdefinedinWbP-8648, June 1976, x
nay be used in recalibration of the ex: ore neutron flux detection system.
For Unit 1 Cycle 15 only, the definition of quadrents includes both the horizontal-vertical quadrant and diagonally bound quadrants (eight quadrants total) as defined in Westinghouse Report CAA-97-234.. Full Ancore flux maps or synunetric incore thimbles may be used for monitoring the QUADRANT POWER TILT RATIO when one Power Range Channel is inoperable.
FARLEY-UNIT 1 B 3/4 3-2a AMENDMENT NO.131
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