ML20155C306
ML20155C306 | |
Person / Time | |
---|---|
Site: | Saint Lucie ![]() |
Issue date: | 10/29/1998 |
From: | FLORIDA POWER & LIGHT CO. |
To: | |
Shared Package | |
ML17229A894 | List: |
References | |
NUDOCS 9811020187 | |
Download: ML20155C306 (5) | |
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TABLE 2.2-1 (Continued)
REACTOR PROTECTIVE' INSTRUMENTATION TRIP SETPOINT LIMITS E
O FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES g
9.
Thermal Margin / Low Pressure-(l)
=
C Four Reactor Coolant Pumps Trip setpoint adjusted to not Trip 'setpoint adjusted to not exceed the limit lines of Operating exceed the limit lines of Figures 2.2-3 and 2.2-4.
Figures 2.2-3 and 2.2-4.
9a. Steam Generator Pressure
'1 135.psid 1 135 psid Difference liigh (1)
(IbgicinTM/LP)
- 10. Loss of Turbine -- Ilydraulic
> 800 psig
> 800 psig FluidPressure-Low (3) 1 2.49 decades per minute
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- 11. Rate of Change of Power - liigh (4) 1 2.49 decades per minute Wide Range Logarithmic Neutron Flux power TABLE NOTATION Trip may be bypassed below 1% of RATED TilERMAL POWER; bypass shall. be automatically removed
% (1) when!;;ERyi.rCTRis>1%ofRATEDTilERMALPOWER.
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lo-(2) Trip may be manually bypassed below 685 psig; bypass shall be automatically removed at or above 685 psig.
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'(3) Trip may be bypassed below 15% of RATED TilERMAL POWER; bypass shall be autbmatically removed when TllCrg"i 7%T is > 15% of RATED THERMAL POWER.
g (4) Trip may be bypassed below 10~4% and above 15% of RATED TilERMAL P,0WE%
mm Power Range Neutron Flux power 9811020187 981029 PDR ADOCK 05000335 P
TABLE 3.3-1 (Continued)
TABLE NOTATION With the protective system trip breakers in the closed position and
, he CEA drive system capable of CEA withdrawal.
t
- The provisions of Specification 3.0.4 are not applicable.
(a) Trip may be bypassed below 1% of RATED THERMAL POWER; bypass shall' be automatically removed when -T:C ha:", is > 1% of RATED
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^^U THERMAL POWER.
(b) Trip may be manually bypassed below 685 psig; bypass shall be automatically removed at or above 685 psig.
(c) Trip may be bypassed below 15% of RATED THERMAL POWER; bypass 4
shall be automatically removed when " ~.". ^^%:.1 is > 15% of RATED THERMAL POWER.
g (d) Trip may be bypassed below 10" % and above 15% of RATED THERMAL POWER; bpass shall be automatically removed when is >-
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< 15% of RATED THERMAL POWER.
7 Wide Range Logarithmic Neutron Flux power (e) Deleted Power Range Neutro (f) There shall be at least two decades of overlap between the Wide Range Logarithmic Neutron Flux Monitorinp Channels and the Power Range Neutron Flux Monitoring Channels.
4 ACTION STATEMENTS ACTION 1 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
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and/or open the protective system trip: breakers.
ACTION 2' With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
a.
The inoperable channel is placed in either the bypassed or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. For the purposes of testing and maintenance, the inoperable channel may be bypassed for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> from time of initial loss of OPERABILITY; however, the inoperable channel shall then be either restored to OPERABLE status or placed in the tripped condition.
ST. LUCIE - UNIT 1 3/4 3-4 Aniendment No.15, 27, #
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St. Lucie Unit 1 and Unit 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments RPS Trio Bvoasses ATTACHMENT 4 to FPL Letter L-98-270 ST. LUCIE UNIT 2 MARKED-UP TECHNICAL SPECIFICATION PAGES Page 2-6 l
l Page 3/4 3-3
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4 TABLE 2.2-1 (Continued)
M REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS r-g Wide Range Logarithmic Neutron Flux power '
N TABLE NOTATION i
g (1) Trip may be manually bypassed below 0.5% of RATED THERMAL POWER during testing pursuant to Spectal Test Exception 3.10.3; bypass shall be automatically removed when the !:i%7.' ? Z O is greater p
than or equal to 0.5% of RATED THERMAL POWER.
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(2) Trip may be manually bypassed below 705 psig; bypass shall be automatically removed at or above 705 psig.
(3) % of the narrow range ste.am generator level indication. '
(4) Trip may be bypassed below 10 4% and above 15% of RATED THERMAL POWER; bypass shall be automatically i
T "" '" " "
< 15% of RATED THERMAL POWER.
removed when d... = " is > 1 Mr
, Power Rang +e Neutron Flux power
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s (5) Trip may be bypassed below 15% of RATED THERMAL POWER; bypass shall be automatically removed when
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rf, T;107 47 Z 0 is greater than or equal to 15% of RATED THERMAL POWER.
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ower Range Neutron Flux power E
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de Range Logarithmic Neutron Flux power t
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l TABLE 3.3-1 (Continued)
TABLE NOTATION Wide Range Loga, With the protective system trip breakers in the closed position, the CEA drive system capable of CEA withdrawal, and fuel in the reactor vessel.
1 0
l The provisions of Specification 3.0.4 are not applicable.
(a) Trip may be manually bypassed below 0.5% of RATED THERMAL POWER in con-l l
junction with (d) below; bypass shall be automatically removed when l
T.:g.LPCU: is greater than or equal to 0.5% of RATED THERMAL POWER.
l (b) Trip may be manually bypassed below 705 psig; bypass shall be l
automatically removed at or above 705 psig.
i (c) Trip may be bypassed below 15% of RATED THERMAL POWER; bypass shall be l
automatically removed when -T ::P "(. TCU:7. is greater than or e uiIo'n al to 15%
of RATED THERMAL POWER.
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l-(d) Trip may be bypassed during testing pursuant to Special Test Exception 3.10.3.
l (e) Trip may be bypassed below 10N and above 15% of RATED THERMAL POWER; j
bypass shall be automatically removed when ". F"'
- n
- r is > 10 % *
$ 15% of RATED THERMAL POWER.~
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(f) Each channel shall be comprised of two trip breakers; actual trip logic I
shall be one-out-of-two taken twice.
(g) There shall be at least two decades of overlap between the Wide Range Logarithmic Neutron Flux Monitoring Channels and the Power Range Neutron
)
l Flux Monitoring Channels.
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ACTION STATEMENTS With the number of channels OP.ERABLE one less than required by ACTION 1 the Minimum Channels OPERABLE requirement, restore the inoperable-channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in i4 at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the j
protective system trip breakers.
ET Wide Range Logarithm Power Range Neutro a
ST. LUCIE - UNIT 2 3/4 3-3 dienderfeM o.
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