Text
ENCLOSURE 5
SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT RTD BYPASS MANIFOLD ELIMINATION TECHNICAL SPECIFICATION PAGES 9309070356 930827 PDR ADOCK 05000400 P
PDR
TABLE 2.2-1 (Continued)
TABLE NOTATIONS NOTE le OVERTEHPERATURE hT aT ~
(
)
C M
Mhere:
hT Heasured hT by RTD i o d Instrumentation>
~1+ r S Lead-lag compensator on measured ST; 1+ r2S
'ls '2 Time constants util.ised in lead-lag compensator for hT, Tl ~ 8 s, T2 3
SS 1+ x3S T3 hT Kl Lag compensator on measured hT; Time constants utilized in the lag compensator for hT, r3 Kg 0 ss Indicated hT at RATED THERMAL POMER; 1.17; 0.0224/'F;
~le r S
1 + t~S
'4s '5 1 + v6S The function generated by the lead"lag compensator for Tavg dynamic compensation; Time constants utilized in the lead-lag compensator for T, v4 ~ 20 ss Tg 4
ss Average temperature, F;
Lag compensator on measured T
avg'ime constant utilized in the measured T
lag compensator t6 ~ 0 sp avg S
LIHITING "SAFETY SYSTEM SETTINGS BASES Power Ran e, Neutron Flux (Continued)
The I.ow Setpoint trip may be manually blocked above P"10 (a power Level of approximately 10X of RATED THERMAL POWER) and is automatically reinstated below the P-10 Set po int.
Power Ran e, Neutron Flux, Hi h Rates The Power Range Positive Rate trip provides protection against rapid flux increases which are characteristic of a rupture of a control rod drive housing.
Specifically, this trip complements the Power Range Neutron FLux High and Low trips to ensure that the criteria are met for rod ejection from mid"power.
The Power Range Negative Rate trip provides protection for control rod drop accidents.
At high po~er a single or multipLe rod drop accident could cause local flux peaking which could cause an unconservative local DNBR to exist.
The Power Range Negative Rate trip will prevent this from occurring by tripping the reactors No credit is taken for operation of the Power Range Negative Rate trip for those control rod drop accidents for which DNBRs will be greater than the design DNBR vaLue.
Intermediate and Source Ran e
Neutron Flux The Intermediate and Source
- Range, Neutron Flux trips provide core protection during reactor startup to mitigate the consequences of an uncontrolled rod
'cluster controL assembly bank withdrawal from a subcritical condition.
These trips provide redundant protection to the Low Setpoint trip of the Power Rangef Neutron flux channels.
The Source Range channels will initiate a
Reactor trip at about 10 counts per second unless manually bLocked when P-6 becomes active'he Intermediate Range channels will initiate a
Reactor trip at a current Level equivalent to approximately 25X of RATED THERMAL POWER unless manualLy blocked when P-10 becomes active.
A~spo+f Pp RPQ )cl's/oA'xE'l~ dg Overtem erature dT The Overtemperature hT trip provides core protection to prevent
DNB for aLL combinations of pressure, po~er, coolant temperature, and axial po~er distribu-tion, provided that the
transient is slow with respect Co ra xt del s
o t
c e
o the temperature detectors (about 4 seconds and pressure is wxthxn the range between the Pressurizer High and Low Pressure trips.
The Set-point is automatically varied with:
(1) coolant temperature to correct for temperature induced changes in density and heat capacity of ~ater and includes dynamic compensation for a
m e
ore o the loop temperature detectors
, (2) pressurizer
- pressure, and (3) axiaL power distribution.
With normal axial power distribution, thi
Reactor trip limit is always below the core Safety Limit as shown in Figure 2. 1-1. If axial peaks are greater than
- design, as indicated by the differe ce between top and bottom po~er range nuclear detectors, the Reactor trip is automatically reduced according to the notations in Table 2.2"1.
fmuspopT do hue( 8E$~~ ~~~E~~
SHEARON HARRIS - UNIT 1
B 2-4 Amendment No.
LIMITING SAFETY SYSTEM SETTINGS BASES The Overpower hT trip provides assurance of fueL integrity (e.g.,
no fueL peLLet melting and Less than 1X cladding strain) under all possibLe overpower conditions, Limits the required range for Overtemperature AT trip, and provides a backup to the High Neutron Flux trip.
The Setpoint is automatically varied with:
(1) coolant temperature to correct for temperature induced changes in density and heat capacity of water, and (2) rate of change of temperature for dynamic compensation fdr x
x d
a ro th cor to the loop temperature detectors, to ensure that the aLlowable heat generation rate (kW/ft) is not exceeded.
The Overpower 4T trip provides protection to mitigate the consequences of various size steam breaks as reported in
WCAP-9226, "Reactor Core Response to Excessive Secondary Steam Releases."
Pressurizer Pressure
~A44~A'f 7o A+d7 WESjoOHCgliPf'g In each of the pressurizer pressure
- channels, there are two independent bistables, each with its own trip setting to provide for a High and Low Pressure trip thus limiting the pressure range in which reactor operation is permitted.
The Low Setpoint trip protects against low pressure which could
Lead to
DNB by tripping the reactor in the event of a Loss of
reactor coolant pressure.
On decreasing power the Low Setpoint trip is automaticaLLy blocked by the
- Loss, of P-7 (a power level of approximately 10Z of RATED THERMAL POWER or turbine impulse chamber pressure at approximateLy LOZ of full power equivalent);
and on increasing power, automatically reinstated by P-7.
The High Setpoint trip functions in conjunction with the pressurizer reLief and safety valves to protect the
Reactor Coolant System against system overpressure.
Pressurizer Water Level The Pressurizer High Water Level trip is provided to prevent ~ater relief through the pressurizer safety valves.
On decreasing power the Pressurizer High Water Level. trip is automatically blocked by the loss of P"7 (a power LeveL of approximately LOX of RATED THERMAL POWER or a turbine impulse chamber pressure at approximately LOX of full power equivalent);
and on increasing power., automatically reinstated by P-7
~
Reactor Coolant Flow The
Reactor Coolant Low Flow trips provide core protection to prevent
DNB by mitigating the consequences of a loss of flow resulting from the Loss of one or more
reactor coolant pumps.
On increas'ing power above P-7 (a power Level of approximately LOZ of RATED THERMAL POWER or a turbine impulse chamber pressure at approximately 10Z of full po~er equivaLent),
an
automatic Reactor trip will occur if the flow in more than one loop drops below 90.5X of nominal full loop flow.
Above P-8 SHEARON HARRIS - UNIT 1
B 2"S Amendment No.
TABLE 4.3-1 (Continued)
TABLE NOTATIONS (Continued)
RESpoNSE djmZ.
(11)
CHANNEL CALIBRATION shall include the
RTD s
oo w r te (12) Verify that appropriate signals reach the
undervoltage and
shunt trip
- relays, for both the main and bypass
- breakers, from the manual reactor trip switch.
SHEARON HARRIS - UNIT 1
3/4 3-14a Amendment No.~
TABLE 2.2-1 Continued TABLE NOTATIONS NOTE 1:
OVERTEHPERATURE bT hT (I + r,S)
(I +
AS) 1+ r3S x hT, (I + r4S)
K) K2 (I + rsS) 1+ reS
+ K~(P Pi) fI(III)
Where:
hT Heasured hT by
RTD Instrumentation; 1+ r)S Lead-lag compensator on measured hT; 1+ r2S T) )
T2 Time constants utilized in lead-lag compensator for hT, r> = 8 s, r2 = 3 s; 1
+ r>S Lag compensator on measured hT; t
Time constants utilized in the lag compensator for bT, r3 = 0 s; Indicated hT at RATED THERHAL POWER; K,
K2 1.17; 0.0224/'F; 1+
T4S The function generated by the lead-lag compensator for T, dynamic compensation; 1+ rsS "4P "S
Time constants utilized in the lead-lag compensator for T,pg T4 20 s, rs = 4 s;
NOTE 1:
(Continued)
TABLE 2.2-1 Continued TABLE NOTATIONS Average temperature,
'F; I +
AS Lag compensator on measured
- Tzpg, Ks Time constant utilized in the measured Tgyg lag compensator,.
ra
= 0 s; z 588.8'F (Nominal T, at RATED THERMAL POWER);
0.001072/psig; p
Pressurizer
- pressure, psig; Pl 2235 psig (Nominal RCS operating pressure);
Laplace transform operator, s ~;
and f> (h,I) is a function of the indicated difference between top and bottom detectors of the power-range neutron ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that:
(1)
For q, -
q> between
-21.6% and +6.0%,
f> (h,I) = 0, where q, and q> are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and q, +
q> is total THERMAL POWER in percent of RATED THERMAL POWER; (2)
For each percent that the magnitude of q, -
q> exceeds
-21.6%, the hT Trip Setpoint shall be automatically reduced by 2.36% of its value at RATED THERMAL POWER; and (3)
For each percent that the magnitude of q, -
q> exceeds
+ 6.0%, the hT.-Trip Setpoint shall be automatically reduced by 1.57% of its value at RATED THERMAL POWER.
NOTE 2:
The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 2.1% h,T span.
i
LIMITING SAFETY SYST ETTINGS BASES Power Ran e
Neutron Flux Continued The Low Setpoint trip may be manually blocked above P-10 (a power level of approximately 10% of RATED THERMAL POWER) and is automatically reinstated below the P-10 Setpoint.
Power Ran e
Neutron Flux Hi h Rates The Power Range Positive Rate trip provides protection against rapid flux increases which are characteristic of a rupture of a
control rod drive housing.
Specifically, this trip complements the Power Range Neutron Flux High and Low trips to ensure that the criteria are met for rod ejection from mid-power.
The Power Range
Negative Rate trip provides protection for
control rod drop accidents.
At high power a single or multiple rod drop accident could cause local flux peaking which could cause an unconservative local
DNBR to exist.
The Power Range
Negative Rate trip will prevent this from occurring by tripping the reactor.
No credit is taken for operation of the Power Range
Negative Rate trip for those
control rod drop accidents for which
DNBRs will be greater than the design
DNBR value.
Intermediate and Source Ran e
Neutron Flux The Intermediate and Source
- Range, Neutron Flux trips provide core protection during reactor startup to mitigate the consequences of an uncontrolled rod cluster control assembly bank withdrawal from a subcritical condition.
These trips provide redundant protection to the Low Setpoint trip of the Power
- Range, Neutron Flux channels.
The Source Range channels will initiate a
Reactor trip at about 10 counts per second unless manually blocked when P-6 becomes active.
The Intermediate Range channels will initiate a
Reactor trip at a current level equivalent to approximately 25% of RATED THERMAL POWER unless manually blocked when P-10 becomes active.
Overtem erature hT The Overtemperature hT trip provides core protection to prevent
DNB for all combinations of pressure, power, coolant temperature, and axial power distribution, provided that the
transient is slow with respect to transport to and response time of the temperature detectors (about 4 seconds),
and pressure is within the range between the Pressurizer High and Low Pressure trips.
The Setpoint is automatically varied with: (1) coolant temperature to correct for temperature induced changes in density and heat capacity of water and includes dynamic, compensation for transport to and response time of the loop temperature detectors, (2) pressurizer
- pressure, and (3) axial power distribution.
With normal axial power distribution, this
Reactor trip limit is always below the core Safety Limit as shown in Figure 2. 1-1. If axial peaks are greater than design, as indicated by the difference between top and bottom power range nuclear detectors, the
Reactor trip is automatically reduced according to the notations in Table 2.2-1.
SHEARON HARRIS - UNIT 1
B 2-4 Amendment No.
LIMITING SAFETY SYST ETTINGS BASES Over ower BT The Overpower hT trip provides assurance of fuel integrity (e.g.,
no fuel pellet melting and less than 1% cladding strain) under all possible overpower conditions, limits the required range for Overtemperature bT trip, and provides a backup to the High Neutron Flux trip.
The Setpoint is automatically varied with: (1) coolant temperature to correct for temperature induced changes in density and heat capacity of water, and (2) rate of change of temperature for dynamic compensation for transport to and response time of the loop temperature detectors, to ensure that the allowable heat generation rate (kW/ft) is not exceeded.
The Overpower hT trip provides protection to mitigate the consequences of various size steam breaks as reported in
WCAP-9226, "Reactor Core Response to Excessive Secondary Steam Releases."
Pressurizer Pressure In each of the pressurizer pressure
- channels, there are two independent bistables, each with its own trip setting to provide for a High and Low Pressure trip thus limiting the pressure range in which reactor operation is permitted.
The Low Setpoint trip protects against low pressure which could
lead to
DNB by tripping the reactor in the event of a loss of
reactor coolant pressure.
On decreasing power the Low Setpoint trip is automatically blocked by the loss of P-7 (a power level of approximately 10% of RATED THERMAL POWER or turbine impulse chamber pressure at approximately 10% of full power equivalent);
and on increasing power, automatically reinstated by P-7.
The High Setpoint trip functions in conjunction with the pressurizer relief and safety valves to protect the
Reactor Coolant System against system overpressure.
Pressurizer Water Level The Pressurizer High Water Level trip is provided to prevent water relief through the pressurizer safety valves.
On decreasing power the Pressurizer High Water Level trip is automatically blocked by the loss of P-7 (a power level of approximately 10% of RATED THERMAL POWER or a turbine impulse chamber pressure at approximately 10% of full power equivalent);
and on increasing power, automatically reinstated by P-7.
Reactor Coolant Flow The
Reactor Coolant Low Flow trips provide core protection to prevent
DNB by mitigating the consequences of a loss of flow resulting from the loss of one or more
reactor coolant pumps.
On increasing power above P-7 (a power level of approximately 10% of RATED THERMAL POWER or a turbine impulse chamber pressure at approximately 10% of full power equivalent),
an
automatic Reactor trip will occur if the flow in more than one loop drops below 90.5% of nominal full loop flow.
Above P-8 SHEARON HARRIS - UNIT 1
B 2-5 Amendment No.
TABLE 4.3-1 Continued TABLE NOTATIONS Continued (ll)
CHANNEL CALIBRATION shall include the
RTD response time.
(12)
Verify that appropriate signals reach the
undervoltage and
shunt trip relays, for both the main and bypass
- breakers, from the manual reactor trip switch.
SHEARON HARRIS - UNIT 1
3/4 3-14a Amendment No.
