ML20134N921
| ML20134N921 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/18/1996 |
| From: | SOUTHERN NUCLEAR OPERATING CO. |
| To: | |
| Shared Package | |
| ML20134N903 | List: |
| References | |
| NUDOCS 9611270155 | |
| Download: ML20134N921 (3) | |
Text
_
F N P U nit 1 Technical Specifications Changed Page Unit 1 Revision B 3/4 2-5 Replace 9611270155 961118 PDR ADOCK 05000348 P _.
-. - ~ -. _. - ~
I POWER DISTRIBUTION LIMITS
.j
- BASES-3/4.2.4 NMRANT PNER TILT RATIO l
The quadrant power tilt ratio limit assures that the radial power distribution
~
satisfies the design values used.in the power capability analysis. Radial l
power distribution measurements are made during startup testing and t
periodically.during power operation, i
-The limit of 1.02, at which corrective action is required, provides DNB and linear heat generation rate protection with x-y plane power tilts.
The two 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 j
dropped or misaligned control rod.
In the event such action does not correct is reinstated by reducing the-the tilt,-the margin for uncertainty on FO maximum allowed power by 3 percent for each percent of tilt in excess of 1.0.
For purposes of monitoring QUADRANT POWER TILT RATIO when one encore detector
'is inoperable, the movable incore detectors are used to confirm that the
. normalized symmetric power distribution is consistent with the QUADRANT POWER TILT RATIO..The incore detector monitoring is done with a full incore flux map i
.or two' sets.of four symmetric thimbles. The two sets of four symmetric thimbles is-a unique set of eight detector locations. These locations are C-8, E-5, E-11, H-3, H-13, L-5, L-11, and N-8.
3/4.2.5-DNB PARAMETERS l
The limits on the DNS related parameters assure that each of the parameters are maintained within the normal steady state envelope of operation assumed in the transient ~and accident analyses. The limits are consistent with the initial FSAR assumptions and have been analytically demonstrated adequate to meet the The indicated T J
DNB design criterion throughout each analysed transient.value of 580.7'F is based on the average of; indication uncertainty of 2.5*F.
The indicated pressure value of 2205 psig is based on the average of two control board readings and an indication uncertainty of 20 pai. The indicated total RCS flow rate is based on two elbow tap measurements from each loop and an uncertainty of 2.4% flow (0.1% flow is included for feedwater venturi fouling).
and pressuriser pressure through the control The12hoursurveillanceofTv$ensurethattheparametersarerestored a
board readings are sufficient t within their limits following load changes and other expected transient operation.
The 18 month surveillance of the total RCS flow rate may be performed by one of two alternate methods. One method is a precision calorimetric performed at the beginning'of each fuel cycle. The other method is based on the Ap measurements from the cold leg elbow taps, which are correlated to past precision heat balance measurements. Correlation of the flow indication channels with selected precision loop flow calorimetrics for this method is documented in WCAP-14750.
Use of the elbow tap Ap measurement method removes the requirement for performance of a precision RCS flow calorimetric measurement for that cycle. The monthly surveillance of the total RCS flow rate is a reverification of the RCS flow requirement using process computer indications of loop elbow tap measurements that j
are correlated either to the precision RCS flow measurement or the elbow tap j
measurement at the beginning of.the fuel cycle. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> RCS flow surveillance is a qualitative verification of significant flow degradation using the control j
board indicators fed by elbow tap measurements.
Revised by NRC letter
.FARLEY-UNIT 1 5 3/4 2-5 dated:
FNP Unit 2 Technical Specifications Changed Pagg Unit 2 Revision B 3/4 2-5 Replace i
1
0 r
e POWER DISTRIBUTION LIMITS BASES 3/4.2.4 OUADRANT POWER TILT RATIO The quadrant 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 periodically during power operation.
The limit of 1.02, at which corrective action is required, provides DNB and linear heat generation rate protection with x-y plane power tilts.
The two 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 Fg is reinstated by reducing the maximum allowed power by 3 percent for each percent of tilt in excess of 1.0.
For purposes of monitoring QUADRANT POWER TILT RATIO when one excore detector is inoperable, the movable incore detectors are used to confirm that the normalized symmetric power distribution is consistent with the QUADRANT POWER TILT RATIO. The incore detector monitoring is done with a full incore flux map or two sets of four symmetric thimbles. The two sets of four symmetric thimbles is a unique set of eight detector locations. These locations are C-8, E-5, E-11, H-3, H-13, L-5, L-11, and N-8.
3/4.2.5 DNB PARAMETERS The limits on the DNB related parameters assure that each of the parameters are maintained within the normal steady state envelope of operation asogmed in the transient and accident analyses. The limits are consistent with gm initial FSAR assumptions and have been analytically demonstrated adequate py meet the DNB design criterion throughout each analyzed transient. The indic04ed T value of 580.7'F is based on the average of two control board readings and'2n indication uncertainty of 2.5'F.
The indicated pressure value of 2205 psig is based on the average of two control board readings and an indication uncertainty of 20 psi.
The indicated total RCS flow rate is based on two elbow tap measurements from each loop and an uncertainty of 2.4% flow (0.1% flow is included for feedwater venturi fouling).
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> surveillance of T and pressurizer pressure through the control boardreadingsaresufficientt$ensurethattheparametersarerestored ay within their limits following load changes and other expected transient operation.
The 18 month surveillance of the total RCS flow rate may be performed by one of two alternate methods. One method is a precision calorimetric performed at the beginning of each fuel cycle. The other method is based on the Ap measurements from the cold leg elbow taps, which are correlated to past precision heat balance measurements. Correlation of the flow indication channels with selected precision loop flow calorimetries for this method is documented in WCAP-14750.
Use of the i
elbow tap Ap measurement method removes the requirement for performance of a l
precision RCS flow calorimetric measurement for that cycle.
The monthly surveillance of the total RCS flow rate is a reverification of the RCS flow requirement using process computer indications of loop elbow tap measurements that are correlated either to the precision RCS flow measurement or the elbow tap measurement at the beginning of the fuel cycle.
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> RCS flow surveillance is a qualitative verification of significant flow degradation using the control board indicators fed by elbow tap measurements.
1 Revised by NRC letter FARLEY-UNIT 2 8 3/4 2-5 dated
..