ML20125A658
| ML20125A658 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 06/07/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19319A602 | List: |
| References | |
| NUDOCS 7908090680 | |
| Download: ML20125A658 (17) | |
Text
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ATTACHMENT TO LICENSE AMENDMENT NO.16 FACILITY OPERATING LICENSE NO. NPF 3 DOCKET NO. 50-346 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
Pages 2-3 2-5 2-7 2-8 B 2-5 3/4 2-14 3/4 4-1 5-8 7908 9"**
W
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e.
9'
+ 20.0 120
-35.0 120 112.0 112.0 1
100
+30.0
+ 20.0 98.0 45.0 85.5 85.5 55.0 80 85.0 2
+30.0 71.5 3
60 55.0
+30.0 5
58.5 z
58.5 E
9 go k
E E
h E
40 K
o O
g U
$m m
0 m$
g 20 uo u
e u
4 g
2 2
3 3
60 40 20 0
+20
+40
+60 0
AX1 AL POWER IMBALANCE. %
CURVE REACTOR COOLANT FLOW (GPM) 1 387,200 2
290,100 3
191,000 Figure 2.12 Reactos Core Safety Limit DAVIS-BESSE,INIT1 2-3 Amendment NO. XX,16 s.
4
TABLE 2.2-1 k
REACTOR PROTECTION SYSTEM INSTRUMENTATION TRIP SETPOINTS m
l En FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES w"
,m 1.
Manual Reactor Trip Not Applicable Not Applicable EJ 2.
High Flux
< 105.5% of RATED THERMAL POWER
< 105.6% of RATED THERMAL POWER Z
Eith four pumps operating with four pumps operating #
< 78.3% of RATED THERMAL POWER
< 78.4% of RATED THERMAL POWER With three pumps operating With three pumps operating #
3
< 50.6% of RATED THERMAL POWER with
< 50.7% of RATED THERMAL POWER with one pump operating in each loop one pump operatincj in each loop #
3.
RC High Temperature
< 619 F
< 619.08 F Flux - a Flux-Flow (I)
Trip Setpoint not to Allowable Values not to exceed 7
4.
exceed the limit line of the limit line of Figure 2.2-2.#
Figure 2.2-1.
5.
RC Low Pressure (I)
> 1985 psig
> 1984.0 psig*
> 1976.5 psig**
6.
RC High Pressure 1 2355 psig i 2356.0 psig*
1 2363.5 psig**
'7.
RC Pressure-Temperature (I)
> (16.25 T F - 7873) psig
> (16.25 T F - 7873.64) psig#
out out l
g 9
an 1
D
~
b l
l M
l l
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120
% RATED THERMAL POWER 22.0
+ 11.5 105.5 105.5 100 FOUR PUMP LIMIT LINES
+ 20.0 92.0 40.0 22.0
+ 11.5 80 84.0 78.3 78.3 EE-THREE PUMP h2 LIMIT LINES,
+ 20.0 2
P 64.7 0
60 p
C 40.0 22.0
+11.5 56.7 50.5 50.6 ' ~
E0 m.O w
J w
2 z
a p
+ 20.0
< c.
37.6 n.
u
-40.0 TWO PUMP b$
u N
29.0 LIMIT LINES Oo z
g 3
wWo 2
3 20 gwp
<u<
k EE am wu22 oOO
<wo 0
-60 40 20 s 0
+20
+40
+60 AX1 AL POWE R IMBALANCE, %
Figure 2.21 Trip Setpoint for Flux.1 Flux-Flow 4
DAVIS-BESSE, UNIT.1 2-7 Amendment NO. 11,I8
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LIMITING SAFETY SYSTEM SETTINGS BASES RC High Temperature The RC High Temperature trip <_ 619'F prevents the reactor outlet temperature from exceeding the design limits and acts as a backup trip for all power excursion transients.
Flux - A Flux-Flow The power level trip setpoint produced by the reactor coolant system flow is based on a flux-to-flow ratio which has been established to accommodate flow decreasing transients from high power where pro-tection is not provided by the High Flux / Number of Reactor Coolant Pumps On Trips.
The power level trip setpoint produced by the power-to-flow ratio provides both high power level and low flow protection in the event the reactor power level increases or the reactor coolant flow rate decreases.
The power level setpoint produced by the power-to-flow ratio provides overpower DNB protection for all modes of pump operation.
For every ~
flow rate'there is a maximum permissible power level, and for every power level there is a minimum pennissible low flon rate.
Typical power level and low flow rate combinations for the pump situations of Table 2.2-1 are as follows:
Trip would occur when four reactor coolant pumps are operating 1.
if power is 105.5% and reactor flow rate is 100%, or flow rate is 94.6% and power level is ~100%.
Trip would occur when three reactor coolant pumps are operating 2.
if power is 78.3% and reactor flow rate is 74.7%, or flow rate is 70.9% and power is 75%.
Trip would occur when one reactor coolant pump is operating in 3.
each loop (total of two pumps operating) if the power is 50.6%
and reactor flow rate is 49.0% or flow rate is 46.3% and the power level is 49.0%.
For safety calculations the maximum calibration.and instrdmentation errors for the power level were used.
Amendment'No. I 6 B 2-5 DAVIS-BESSE, UNIT 1
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POWER DISTRIBUTION LIMITS
'ONB PARAMETERS LIMITING CONDITION FOR OPERATION 3.2.5 The following DNB related parameters shall be maintained within the limits shown on Table 3.2-1:
a.
Reactor Coolant Hot Leg Temperature.
b.
Reactor Coolant Pressure c.
Reactor Coolant Flow Rate APPLICABILITY: MODE 1.
ACTION:
With any of the above i,arameters exceeding its limit, restore the param-eter to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 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 />.
SURVEILLANCE REQUIREMENTS 4.2.5.1 Each of the parameters of Table 3.2-1 shall be verified to be within their limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
l l<
4.2.5.2 The Reactor Coolant System total flow rate shall be determined to be within its limit by measurement at least once per 18 months.
DAVIS-BESSE, UNIT 1 3/4 2-13 t
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3/4.4 REACTOR COOLANT SYSTEM
' REACTOR COOLANT LOOPS LIMITING CONDITION FOR OPERATION 3.4.1 Both reactor coolant loops and both reactor coolant pumps in each loop shall be in operation.
i APPLICABILITY: As noted below, but excluding MODE 6.*
ACTION:
j MODES 1 and 2:
l With one reactor coolant pump not in operation, STARTUP and a.
POWER OPERATION may be initiated and may proceed provided THERMAL POWER is restricted to less than 78.3% of RATED THERMAL POWER and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the setpoints for the following trips have been reduced to the values specified in Specification 2.2.1 for operation with three reactor coolant pumps operating:
~
1.
High Flux 2.
Flux-AFlux-Flow b.
With one reactor coolant pump in each loop not in operation, STARTUP and POWER OPERATION may be initiated and may proceed provided THERMAL POWER is restricted to less than 50.6% of RATED THERMAL POWER and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the setpoints for the following trips have been reduced to the values specified in Specification 2.2.1 for operation with one reactor coolant pump operating in each loop:
1.
High Flux 2.
Flux-aFlux-Flow t
- See Special Test Exception 3.10.3.
DAVIS-BESSE, UNIT 1 3/4 4-1 AmendmentFNo.16
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TABLE 5.7-1
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COMPONENT CYCLIC OR TRANSIENT LIMITS Component or System Cycle or Transient Limit Design Cycle or Transient 1.
. Reactor Coolant 240 Heatup and Cooldown 70 F to 557 F System Cycles 557 F to 70 F 2.
Reactor Coolant 160 Step Load Reduction 100% to 8% RTP* :
System Cycles (Resulting from turbine trip) 3.
Reactor Coolant 150 Step' Load Reduction 100% to 8% RTP*
System Cycles (Resulting from electrical load rejection) 4.
Reactor Coolant 40 Reactor Trip Cycles Reactor Trip System (Resulting from loss of electric power to all RC pumps) 5.
Reactor Coolant 160 Reactor Trip Cycles Reactor Trip SystE n (Resulting from turbine trip without automatic control action).
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6.
Reactor Coolant 40 Reactor Trip Cycles Reactor Trip System (Resulting from rod withdrawal ac.cident) 7.
Once Through 88 Reactor Trip Cycles Reactor Trip l
Stean Generator (Resulting from complete l
loss of all main feed-l water) 8.
Once Through 40 Reactor Trip Cycles Reactor Trip Steam Generator (Resulting from loss of station power) 9.
Once Through 20 Reactor Trip Cycles Reactor Trip l
Steam Generator (Resulting from loss of feedwater to one steam genera tor)
- RATED THERitAL POWER DAVIS-BESSE. UNIT 1 5-7 i
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