ML20043A250
| ML20043A250 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/16/1990 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20043A251 | List: |
| References | |
| NUDOCS 9005210086 | |
| Download: ML20043A250 (4) | |
Text
,_ _ _
7 m,.,
.A.,.
.c CORRECTED PNGES' FACILITY OPERATION LICENSE NO. DPR-77=
DOCKET N0? 50-327, i
1 Revised the Appendix 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-line indicating: the area of change.
REMOVE
= INSERT-
'I
+
3/4 2-7a
-3/4 5.3/4 5 '.
B 3/4-2 B;3/4~2-1; t!
B 3/4 2 B:3/4'2 l r
a i
'i l
l'
\\
i
\\
- l l..
l l
l, L
l
.9005210086 900516 P-PDR ADOCK 05000327
.P PDC 1
y
.,y 3
l4
-l l i:
L.-
EAERGENCYCORE'COOLINGSYSTEMS:(ECCSI'
-SURVEILLANCE-REQUIREMENTS'(Continued)'
l r
Va'lve Number-Valve Function Valve Position 2 f
~
a.
FCV-63 -RHR Suction from RWST open-b.
FCV-63-22 ISIS Discharge to; Common Piping-open a
l
- b.
.At least once peri 31 days by:'
-1 1.
Ver.ifyingLthat-the ECCS piping isLfull of water.by1 venting thel
. j ECCS pump. casings.and. accessible discharge piping high points,--
and a
2.
Verifying:that each valve-(manual,. power operated or automatic)'
l in the flow path-that is not locked, sealed,:or otherwise lJ secured in position, is?in its cor' rect position.
1 4
c.
.By a ' visual inspection whichl verifies:that' no. loose debris (rags, trash,' clothing,ietc.)-is_present in-the containment which could be-a transported to.the' containment. sump'and'cause restriction of the pump suctions during LOCA conditions.
This visual inspectionishall-
'be performed:
1.
For all accessible areas of theLeontainment prior to I
establishing CONTAINMENT INTEGRITY,:and' 2.
Of the areas affected within containment at the completion of I
each containment entry when CONTAINMENT INTEGRITY.is established.
t d.
At least once per 18 months by:
1.
Deleted.
t
'b 2.
A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and-that the sump components (trash racks, screens, etc.) show no evidence.of structural distress or corrosion.
,(
l e.
At least once per 18 months, during shutdown, by:
4 o
i 1.
Verifying that each automatic valve in the flow path actuates
'!1 to its correct position on a safety injection test signal ard 1
automatic switchover to containment sump test signal.
o 4
SEQUOYAH - UNIT 1 3/4 5-5 Amendment No. 92,139,-140
'I Correction letter of 1-22-89 1
-Correction Letter of.5-16-90
i 3/4.2 POWER DISTRIBUTION LIMITS BASFS The specifications of this section provide assurance of fuel integrity j
during Condition I (Normal Operation) and II (Incidents of Moderate Frequency) i events by:
(a) maintaining the calculated DNBR in the core at or above design during normal operation and in short term transients, and (b) limiting the i
fission gas release, fuel pellet temperature and cladding mechanical properties to within assumed design criteria.
In addition, limiting the peak linear power density during Condition I events provides assurance that the initial J
conditions assumed for the LOCA analyses are met and the ECCS acceptances i
criteria limit of 2200*F is not exceeded.
The definitions of certain hot channel and peaking factors as used in these specifications are as follows:
F (Z)
Heat Flux Hot Channel Factor, is defined as the maximum local 0
heat flux on the-surface of a fuel rod at core elevation Z divided by the everage fuel rod heat flux, allowing for manufacturing tolerances on fuel pellets and rods.
F Nuclear Enthalpy Rise Hot Channel Factor is defined as the ratio of the g
integral of linear power alona the rod with the highest integrated power to the average rod puwer.
3/4.2.1 AXIAL FLUX DIFFERENCE (AFD)
The limits on AXIAL FLUX OlFFERENCE assure that the F (Z) upper bound 9
envelope of 2.32 times the normalized axial peaking factor is not exceeded l
during either normal operation or in the event of xenon redistribution follow-ing power changes.
1 Provisions for monitoring the AFD on an automatic basis are derived from the plant process computer through the AFD Monitor Alarm.. The computer deter-mines the one minute average of each of the OPERABLE excore detector outputs and provides an alarm message immediately if the AFD for at least 2 of 4 or 2 of 3 OPERABLE excore channels are outside the allowed AI-Power operating space and the THERMAL POWER is greater than 50 percent of RATED THERMAL POWER.
3/4.2.2 and 3/4.2.3 HEAT FLUX AND NUCLEAR ENTHALPY HOT CHANNEL FACTORS The limits on the heat flux hot channel factor and the nuclear enthalpy rise hot channel factor ensure that 1) the design limits on peak local power density and minimum DNBR are not exceeded and 2) in the event of a LOCA the peak fuel clad temperature will not exceed the 2200'F ECCS acceptance criteria limit.
Amendment Nc., 19, 138 CorrectionLetterof$140 SEQUOYAH - UNIT 1 B 3/4 2-1 16 1
l..
t POWER DISTRIBUTION LIMITS l
l BASES 5
Each of these' hot channel factors is measurable but will normally only be
. determined periodically as specified in Specifications 4.2.2'and 4.2.3.
-This periodic surveillance is sufficient to insure that the limits are maintained l
provided:
a.
Contro1' rods in a single group move together with no individual rod insertion dif fering by more than + 13 steps from the group demand
- position, j
i
-b.
Control rod groups 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.
The F limit as a function of THERMAL POWER allows changes in the radial H
power shwa for all permissible rod insertion limits.
F will be maintained j
H within m lin;ts provided conditiuns a thru d above, are maintained.
When an F measurement is taken, both experimental error and' manufacturing 0
tolerance must be allowed for.
The 5% is the appropriate allowance for a full core map taken with the incore detector flux mapping system and 3% is the appropriate allowance for manuf acturing tolerance.
N When an F is measured, experimental error must be allowed for and 4% is g
the appropriate allowance for a full core map taken with the incore detection system.
ThespecifiedlimitforFfg also contains an 8% allowance for uncertainties which mean that normal operation will= result in F H i 1.55/1.08.
The 8% allowance is based on the following considerations.
a.
abnormal perturbatios in the radial power shape, such as from rod misalignment, effect F more directly than F.
H q
b.
although rod movement has a direct influence upon limiting F to q
within its limit, such control is not readily available to limit F H, and c.
errors in prediction for control power shape detected during startup physics test can be compensated for in F by restricting axial flux q
distribution.
This compensation for F is less readil' available.
H y
i SEQUOYAH - UNIT 1 B 3/4 2-2 Amendment No. 19, 138 Correction letter. of 5-16-90
--