ML18005A448
| ML18005A448 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 06/01/1988 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML18005A447 | List: |
| References | |
| NUDOCS 8806080111 | |
| Download: ML18005A448 (9) | |
Text
ENCLOSURE 3 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400 OPERATING LICENSE NPF-63 REQUEST FOR LICENSE AMENDMENT MOVABLE INCORE DETECTORS TECHNICAL SPECIFICATION PA ES 8806080111 880601 PDR ADOCK 05000400 i
P l3CD
POWER QISTRIBUTION LIMITS SURVEILLANCE REQUIRB!EHTS
~ ~
ge 1'l o
3 Gl N
lG Gl Gl U
C Ul.~
Gl Gl
~a 6
tg m
nu<
'rl C
~4
., II(
Gl 0
GI ul" C.
m+
ul Q.
Gl.
~ ill Gl N Gl 3E.~ l
+I m
w tg C C+
Gl m
~~e 34' Comparing the F
computed (F
) obtained in Spe'cification 4.2.2.2b.,
above to:
XyJ L.
The F
limits for RATED THERMAL POWER (F
) for the XJJ
~
Xy measured core planes given in Specification 4.2.2.ge.
- below, and appropriate and f.,
2.
The relationship:
F
= F t:1+O.2(L-P)3, XJJ Where F
is the limit for fractianal THERMAL POWER operation XJJ expressed.
as a function of F-" and P is the fraction of RATED
. XyJ THERMAL POWER at which F was measured.
- d. 'emeasuring F
according to the fallowing schedule:
L.
When F
is greater than the F
limit for the appropriate Xy measured core plane but less than. the F
relationship, additional c
Power distribution maPs shall be taken and F
comPared to Fxy L.
Xy and F 'ither:
a)
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding by 20 of RATED THERMAL POWER or greater, the THERMAL POWER at which F was last' determined, or b)
At least once per 31 Effective Full Power Oays (EFPO) whichever occurs first.
4.2.2.1 The provisions of Specificatian. 4.0.4 are not applicable.
4.2.2.2 F
shall be evaluated ta determine if F~(Z) is within its limit by:
a.
Using the movable incare detectors ta obtain a power distributiori
~ at any THERMAL POWER greater than 5", of RATED THERMAL POWER, b.
Increasing the measured F'omponent of the power distribution map by 3 ta account for manufacturing talerances and further increasing the value by 5 to accaunt for measurement uncertainties, See footnote on paqe 3/4 ~-56 for limitation SHEARON HARRIS - UNIT 1 3/4 2-6
POWER DISTRIBUTION LIMITS SURVEILLANCE REOUIREMENTS Continued) 2.
When the F
is less than or equal to the F
limit for the appropriate measured core plane, additional power dis~ribution maps shall be taken and F
compared to r and F't least
~
C
.L once per 31 ErPD.
.The F
limits for RATED THERMAL POWER (F
) shall be provided for Xff all core planes containing Bank "D" control rods and all unrodded core planes in a Radial Peaking Factor Limit Report per Specifica-tion 6.9.1.6; The F
limits of Specification 4.2.2.2e.,
- above, are not applicable 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, Z.
Upper core region from 85 to 100, inclusive, 3.
Grid plane regions at 17.8 '~ 2, 32.1 t 2, 46.4 t 2, 60-6 ~ 2, and 74.9 4 2", inclusive, and 4..
Core plane regions within t 2 of core height ~ 2.88 inches about the bank demand position of the Bank "D" control rods.
g.
With F exceeding F, the effects of F on F~(Z) shall be evaluated XJJ
....to determine if F~(Z) is within its limits.
4.2.2.3 When F~(Z) is measured for other than F
determinations, an overall Xy measured F~(Z) shall be obtained from a power distribution map and increased by 3 to account for manufacturing tolerances and further increased by N to account for measurement uncertainty..
When the number of OPERABLE movable incore thimbles
<T) is fewer than 38, the measurement uncertainty'(/) shall be increased to C5 + (38 T)/6.53.
See footnote on paqe 3/4 3-56 for limitation SHEARON HARRIS - UNIT 1 3/4 2-7
POWER OHNIBUTION LIMITS 3/4.2.3 RCS FLOW RATE ANO NUCLEAR ENTHALPY RISE HQT CHANNEL FACTOR LIMITING CONOITION FQR OPERATION 3.2.3 The indicated Reactor Coolant Sys em (RCS) total flow rate'nd F~
shall be maintained as follows:
a.
Measured RCS flow rate
> 292,800 gpm x (1.0 + Cz),
and b.
Measured F~ < 1.49 L1.0 + 0.2{1.0-P)g Where:
THERMAL. POWER RATED THERMAL POWER F~ =
Measured values of F~ obtained by using the movable incore detectors to obtain a power distribution map, ea47he measured values of F shall be used for comparison above Cq =
Measurement uncertainty for core flow as described in the Bases.
APPLICABILITY:
MQOE 1.
ACTION:
With RCS totaI fimv rate or F~ outside the above limits:
a.
Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either.
1.
Restore RCS total flow rate and F~ to within the above limits, or 2.
Reduce THERMAL POWER to less than 50 of RATED THERMAL POWER and reduce the Power Range Neutron Flux - High Trip Setpoint to less, than or equal to 5& 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 />.
when the number of OPERABLE movable detector thimbles (T) is gr eater than ar equal to ~8, since the 1A9 value above accounts far the standard 4% allawance an incare measurements af F~ ~ When the number of OPERABLE movable detector.thimbles is fewer than i8
~ the measured value of F shall be increased by a-factor af D. + <~8 T)/13003.
See footnote an page 3/4 3-56 for limitation SHEARON HARRIS - UNIT 1 3/4 2-9
INSTRUMENTATION MOVABLE INCORE O~i CTORS LIMITING CONOITION FOR OPERATION 3.3.3.2 The Movable Incore Oetection System shall be OPERABLE with:
a.
At least 38 detector thimbles, b.
minimum of two detector thimbles per core quadrant; ~
c.
Sufficient movable detectors,
- drive, and readout equipment to map these thimbles.
APPLICABILITY: When, the Movable Incore Oetection Sys em is used for:
a.
Recalibration of the Excore Neutron Flux Oetection Sys em, or b.
Monitoring the gUAORANT POWER TILT RATIO, or c.
Measurement of F~
F~(Z) and F N
xy, ACTION:
With the Movable Incore Oetection System inoperable, do not use the system for the above applicable monitoring or calibration func~ion's..
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.3.3.2 The Movable 'Incore Oetection System shall be demonstrated OPERABLE; within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to use, by irradiating each detector used and deter mining the acceptability of its voltage curve when required for:
a.
Recallbration of the Excore Neutron Flux Oetection
- System, or b.
Monitoring the gUAORANT POWER TILT RATIO, or c.
Measurement of F~
F~(Z) and F
1 or, with less than 38 detector, thimbles, a minimum of three detector thimbles per core quadrant,
~here two sets of quadrants are defined by:
(i) quadrants formed by the vertical and horizontal a:is of the core, and (2) quadrants formed by the two core diagonal aves.
These quadrant are defined such that a detector thimble located along the aves dividing the quadrants is included in both of those adjacent quadrants as a whole thimble.
The minimum number of detector thimbles may'e reduced to 25 for the remainder of fuel Cycle l, after which, the limit returns to i8.
SHEARON HARRIS - UNIT 1 3/4 3-56
POWER OISTRIBUTION LIMITS BASFS IJi I
i+
<<I Ul A.
Gl J3 E
~
C i"l Illca 0
~ 41
~pl c
Gl Gl Ill l
Q. W Q
Gl L J1 Q.
CL Gl tg IG
~tN Gl ~
.m u m
0 l
Q "u
Gl g
Gl Gl Lu 0 or a lJl,
'0 LL
<<L U Gl a
CL 5
Jl6
~
eQJ" HEAT'LUX HOT CHANNEL FACTOR.
ANO RCS FLOM RATE ANO NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR Continuea)
I c.
The controI rod insertion limits of Specifications 3.1.3.5 and 3.1.3.6 are maintained; and d.
The axial power distribution, expressed in terms of AXIAL FLUX OIFFERENCE, is maintained within the limits.
F~ will be maintained within its limits provicfed Conditions a.
through d.
above are maintained.
The combination of the RCS flow requirement and the measurement of F~ ensures that the calculated ONBR will not be below the design.ONBR value.
The relaxation of F~ as a function of THERMAL POWDER allows changes in the radial power shape for all permissible rod insertion limits.
F~ is evaluated as being less than or equal to 1.49.
This value is used in the various accident analyses where F~ influences parameters other than
- ONBR, e.g. peak clad temperature, and thus is the maximum "as measured" value allowed.
Fuel rod bowing reduces the value of ONB ratio.
Credit is available to offset this reduction in the generic margin.
The generic margins, totaling 9.1 ONBR completely offset any rod bow penalties (less than 3
for the worst case which occurs at. a burnup of 33,000 MMO/MTU).
This margin includes the following:
a.
Qesign limit ONBR of 1.30 vs 1.28;
=
b.
, Grict Spacing (K ) of 0.046 vs 0.059, c.
Thermal Oiffusion Coefficient of 0.038 vs 0.059, d.
ONBR Multiplier of 0.86 vs 0.8&, ancf e.
,Pitch reduction.
'Men an F~ measurement is taken, an allowance f'r both experimentaI error and manufacturing tolerance must be made.
An allowance of 5" is appropriate for a full-core map taken with the Encore Oetector flux Mapping System, ~>
8 3 allowance is appropriate for manufacturing tolerance.
The Radial Peaking Factor, F
(Z), fs measurecf perioctically to provide assur Xy ance that the Hot Channel
- Factor, F~(Z), remains ~ithin its limit.
The Fxy limit for RATEO THERMAL POWER (F
) as providect in the Ractial Peaking Factor xy Limit Report per Specification 6.9.1.6 was determirred from expected power control manuevers over the full range of burnup conditions in the core-SHEARON HARRIS - UNIT 1 B 3/4 2-4
POWER OISTRIBUTION LIMITS BASES HEAT FLUX HOT CHANNEL FACTOR.
ANO RCS FLOW RATE ANO NUCLEAR ENTHALPY RISE HOT HANN L AC OR Continued
'eE +
~L-c m
~
Ill dmn mN g)
U crmc le Q
ill m
i~
0 c
m m ~a mme e ~
c zc Ql
.0 -<a m
omU
~
L. 0 m N 0
U m ~
m 4J ~
i6 0 Ul ~ i~
Ig CL ig
~ e 0 c
m
~ a E
~ 4J
~w L. C Gl Q
U m
w c<
CLUE When RCS flow rate and F~ are measured, no additional allowances are neces-sary prior to comparison with the limits of Specification 3.2.3>
A measurement error of 4X for F~ has been allowed for in determination of the design ONBR value, and a normal RCS flowrate error of 2.0 will be included in Cz, which vill be modified as discussed below.
The measurement error for RCS total f1ow rate is based'upon performing a precision heat balance and using the result to calibrate the RCS flow rate indicators.
Potential fouling of the feedwatar venturi which might not be detected could 'bias the result from the precision heat balance in a non-conservative manner.
Therefore, a penalty of 0.1~ for undetected fouling of the feedwatar venturi, raises the nominal flow measurement allowance, C<, to 2.3X for no venturi fouling.
Any fouling which might bias the RCS <<low rate measurement greater than O.L" can be detected by monitoring and trending various plant performance parameters.
If detected, action shal,l be taken before performing subsequent preci'sion heat balance measurements, i.e., either
, the effect of the fouling shall be quantified.and compensated for in the RCS flow rate measurement or the venturi shall be cleaned to eliminate the fouling.
The 12-hour periodic survei11ance of indicated RCS f1ow is sufficient to detect only f1ow degradation that could lead to operation outside the accept-able region of operation.
3/4.2.4 OUAORANT POWER TILT RATIO The gUAORANT POWER TILT RATIO limit assures that the radial power distribution satisfies the design values used in the power capability analysis.
Radial power distribution measurements are made during STARTUP testing and period-ically during power operation.
The limit of 1.02, at which corrective action is required,. provides ONB and linear heat generation rate protection with x-y plane power tilts.
A limiting tilt of 1.025 can be tolerated before the margin for uncertainty in F~ is depleted.
A limit of 1.02 was selected to provide an allowance for the uncertainty associated with the indicated power tilt.
The 2-hour time allowance for operation with a tilt condition greater than 1.02 but, less than 1.09 is provided to allow identification and correction of a dropped or misaligned control rod.
In the event such action does not correct the tilt, the margin for uncertainty on F is reinstated by reducing the, maximum allowed power by 3
for each percent of tilt in excess of l.
SHEARON HARRIS - UNIT 1 B 3/4 2"5
ENCLOSURE 4 SHEARON HABRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400 OPERATING LICENSE NPF-63 REQUEST FOR LICENSE AMENDMENT MOVABLE INCORE DETECTORS CORE THIMBLE EDUCT ON STUDY
ENCLOSURE 5 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400 OPERATING LICENSE NPF-63 REQUEST FOR LICENSE AMENDMENT MOVABLE INCORE DETECTORS OPR ETARY INFORMATION NOTICE