ML19330B579
| ML19330B579 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/31/1980 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML19330B574 | List: |
| References | |
| NUDOCS 8008050065 | |
| Download: ML19330B579 (7) | |
Text
-
)
3 i
j i
.j}$
t
... _. F,. _ :.(-34.72.112')
(20.16,112)
- 110
. (-40.1 37)
I ACCEPIABLE.4 100
) -( W OO).
PUMP OPERATION 90 -.
. 4
_(-34.72,.84.48)
, (20.l16, 84.48)
[i 30 N
' ~
(-40, 79.48) j l
.. ACCEPT.A8L)E 3&4 70 i (39,72.48)
PWF OPE $ TION
. 80 i
~3 i
l W
58.
- E.
- g 40 i
'=
- 3 i
e
.......j.....-.
..l.
I g-28 8 j_
_.:.n_.p.:...
..u. '... :...
.g._. i f.
.8
... :u:_
i.
i
- 1g '
e GB
....i....
. _ =
1
=:
. -80
-50
-40
-34
-20
-18 I
+10
+20
+30
+40
+50
+60 l
-l..... _..
- a..
.-l l
...,,L 4
AXIAL POWER INALANCE, 1 I
FIGURE 2.1-2 REACTOR CORE SAFETY LIMIT I
CRYSTAL RIER - UNIT 3 2-3 l
8008050065
_TA8LE 2.2-1 REACTOR PROTECTION SYSTEM INSTRUE NTATION TRIP SETPOINTS 9a g
FUNCTIONAL UNIT TRIP SETPOINT ALLOWA8LE VALUES l
5 1.
Manual Reactor Trip Not Applicable Not Applicable
- 5i 2.
Nuclear Overpower
$105.5% of RATED THERMAL POWER 5105.5% of RATED THERMAL POWER with four pumps operating with four pumps operating E
Q
<77. 98% of RATED THERMAL POWER
<77.98% of RATED THERMAL POWER
~ with three pumps operating with three pumps operating w
3.
RCS Outlet Temperature-High (619'F
<619'F 4.
Nuclear Overpower Based on Trip Setpoint not to exceed the Allowable Values not to exceed RCS Flow gnq AXIAL POWER limit line of Figure 2.2-1 the limit line of Figure 2.2-1.
IMBALANCElli
{
5.
RCS Pressure-Low (1) 11800 psig 11800 psig 6.
RCS Pressure-High 12300 psig 12300 psig 7.
RCS Pressure-Variable Low (I) 1(11.80 Tout 'F -5209.2) psig 1(11.80 Tout *F -5209.2) psig 0
0 1
B I
.I10
.l
(-20.6, j04.4)
,(12,104.4)
E 10 0 _..
5._
i
(-2h,95)[AtlEPTABLE I
4 pump 90 l
, (29,90)
OPERATION
_(-20.6,77.9&).
80 (1,2, 77.S31 m
7g -
(-29,!68.58)
)(29,63.58)
. 50 i
ACCEPTABLE ;g i
3&4 PLN i
.CP& RATION
. 50 4
m I
i JE.
4 0 ___
=
~5 l
.ac _. 30
-.1-m' I
- g.. 20
~
3- - 10 E
i n
-50
-40 30
-20
-10 0
+10
+20
+30
+40 +50 AXIAL POWER IMBALANCE, %
FIGURE 2.2-1 TRIP SETPOINT FOR NUCLEAR OVERPOWER BASED ON RCS FLOW AW AXIAL POWER IMBALANCE CRYSTAL RIVER - UNIT 3 2-7
O LIMITING SAFETY SYSTEM SETTINGS BASES RCS Outlet Temperature - High The RCS Outlet Temperature High trip (619'F prevents the reactor outlet tem-perature from exceeding the design liinits and acts as a backup trip for all power excursion transients.
Nuclear Overpower Based on RCS Flow and AXIAL POWER IPEALANCE The power level trip setpoint produced by the reactor coolant system flow is based on a t'!ux-to-flow ratio ditch has been established to accomodate flow decreasing transients from high power.
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 protec-tion for all modes of pump operation.
For every flow rate there is a maxi-mum permissible power level, and for every power level there is a minimum permissible low flow rate.
Typical power level and low flow rate combina-tions for the pump situations of Table 2.2-1 are as follows:
1.
Trip would occur then four reactor coolant pumps are operating if power is >104.4% and reactor flow rate is 100%, or flow rate is
<95.78% and power level is 1001.
J 2.
Trip would occur when three reactor coolant pumps are operating if j
power is >77.98% and reactor flow rate is 74.7%, or flow rate is i
<71.84% anl power is 755.
For safety calculations the maximum calibration and instrumentation errors for the power level were used.
CRYSTAL RIVER - UNIT 3 8 2-5 1
L'IMITING SAFETY SYSTEM SETTINGS BASES r
The AXIAL POWER IPEALANCE boundaries are established in ortier to prevent reactor thermal limits from being exceeded.
These thermal limits are ei-ther power peaking kw/ft limits or DNBR limits.
The AXIAL POWER IMBALANCE reduces the power level trip produced by the flux-to-flow ratio such that the boundaries of Figure 2.2-1 are produced. The flux-to-flow ratio nduc-es the power level trip and associated reactor power-reactor power-imbalance boundaries by 1.044% for a 1% flow reduction.
RCS Pressure - Low. High and Variable Low The High and Low trips are provided to limit the, pressure range in dich reactor operation is permitted.
During a slow reactivity insertion startup accident from low power or a slow reactivity insertion from high power, the RCS Pressure-High setpoint is reached before the Nuclear Overpower Trip Setpoint.
The trip setpoint for RCS Pressure-High, 2300 psig, has been established to maintain the sys-tem pressure below the safety limit, 2750 psig, for any design transient.
The RCS Pressure-High trip is backed up by the pressurized code safety valves for RCS over pressure protection, and is therefore set lower than the set pressure for these valves, 2500 psig.
The RCS Pressure-High trip also backs up the Nuclear Overpower trip.
3 The RCS Pressure-Loir, 1800
- psig, and RCS Presssure-Variable
- Low, (11.80 Tout *F-5209.2) psig, Trip Setpoints have been established to main-tain the DNS ratio Feater than or equal to 1.30 for those design accidents that result in a pressure reduction.
It also prevents reactor operation at pressures below the valid range of DNB correlation limits, protecting against DNB.
Due to the calibration and instrumentation errors, the safety analysis used i
a RCS Pressure-Variable Low Trip Setpoint of (11.80 Tout *F-5249.2) psig.
i 1
CRYSTAL RIVER - UNIT 3 8 2-6
'3/4.4 REACTOR COOLANT SYSTEM REACTOR COOLANT LOOPS LIMITING CONDITION FOR OPERATION 3.4.1 Both reactor coolant lwps and both reactor coolant pumps in each loop shall be in operation.
APPLICABILITY: As noted below, but excluding MODE 6.*
ACTION:
MODES I and 2:
With one reactor coolant pump not in operation, STARTUP and POWER OPERATION may be initiated and may proceed provided THERMAL POWER is restricted to less than 77.98% 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 setpoint for the Nuclear Overpower trip has been reduced to the value specified in Specification 2.2.1 for operation with three reactor coolant pumps operating; MODES 3, 4 and 5 a.
Operation may proceed provided at least one reactor coolant icop
{
is in operation with an associated reactor coolant pump or decay i
heat removal pump.
1 1
b.
The provisions of Specifications 3.0.3 and 3.0.4 are.not i
applicable.
SURVEILLANCE REQUIREMENTS 4.4.1 The Reactor Protective Instrumentation channe?s specified in the applicable ACTION statement above shall be verified to have had their j
trip setpoints changed to the values specified in Specification 2.2.1 for the applicable number of reactor coolant pumps operating either:
a.
Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after switching to a different pump combination if the switch is made dile operating, or b.
Prior to reactor criticality if the switch is made while shut down.
<l'!
- See Special Test Exception 3.10.3.
CRYSTAL RIVER - UNIT 3 3/4 4-1 j
REACTIVITY, CONTROL SYSlEMS BORATED WATER SOURCES - SliUT.)0WN i
LIMITING CONDITION F0P OPERATION 3.1.2.8 As a minimum, one of the following borated water sources shall be OPERABLE:
A concentrated boric aci.I storage system and associated heat a.
tracing with:
1.
A minimum contained borated water volume of 6615 gallons, 2.
Between 11,60') and 14,000 ppm of boron, and 3.
A minimum sol; tion temperature of 105'F.
b.
The borated water storage tank (BWST) with:
1.
A minimum cortained borated water volute o' 13,500 gallons.
2.
A minimum bor on con:entration of 2270 ppa, and j
3.
A minimum sol Jtion temperature of 40'F.
a 6
APPLICABILITY:
MODES 5 and 5.
)
ACTION:
1 f
i With no borated water sources OPER\\BLE, suspend all operatiens in.a!ving CORE ALTERATION or positive reacti<ity changes until at least on. aora: e1 water source is restored to 3PERAB'.E status.
s i'
SURVEILLANCE REQUIREMENTS 4.1.2.8 The above required oorated water source shall be demenst ated OPERABLE:
a.
At least once per 7 days by:
1.
Verifying the boron concentration of the water.
2.
Verifying the contained borated water volui 2 of t is tar ;.,
)
and
-l CP.YSTAL RIVER - UNIT 3 3/4 1-14 L
1 Amendment No. 2 0 t.
,_