ML20062F405
| ML20062F405 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/20/1990 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20062F406 | List: |
| References | |
| NUDOCS 9011270258 | |
| Download: ML20062F405 (6) | |
Text
_ _ _ _ _ _ _ _ _ _ _ - _ -. - _ _ _ _ _ _
9 CORRECTED P/,G,ES A
FACILITY CPERATING LICENSE NO, OPR-77 DOCKET N0_.,f 0-3,2,7 0
Ptvise the Appendix A Technical Specificctions by retcving the pages identified below and inserting the enclosed pages. The revised pages are 1&ntifitd by the captient.d 6tendment nurber and contain marginal lines indicating the area of change.
REMOVE INSERT B 2-3 B 2-3 3/4 2-10 3/4 P-10 3/4 3-8 3/4 3-8 3/4 3-22 3/4 3-22 3/4 3-32 3/4 3-32 9011 70 m 901ano FDR ADOCK 050003,.77 P
m 14#
l hFETYLIMITS BASES Manual Reactor Trip The Manual Reactor Trip is a redundant channel to the automatic protective instrumentation channels and provides manual reactor trip capability.
Power Range, Neutron Flux The Power Range, Neutron Flux channel high setpoint provides reactor core protection against reactivity excursions which are too rapid to be protected by temperature and pressure protective circuitry.
The low set point provides redundant protection in the power range for a power excursion beginning from low power.
The trip associated with the low setpoint may be manually bypassed when P-10 is active (two of the four power range channels indicate a power level of above approximately 10 percent of RATED THERMAL POWER) and is auto-matica11y reinstated when P-10 becomes inactive (three of the four channels indicate a power level below approximately 9 percent of RATED THERMAL POWER).
hwsrRange,NeutronFlux,HighRates The Power Range Positive Rate trip provides protection against rapid flux
.ncreases which are characteristic of rod ejection events from any power level.'
Specifically, this trip complements the Power Range Neutron Flux High and Low trips to ensure that the criteria are met for rod ejection from partial power.
The Power Range Negative Rate trip provides protection to ensure that the minimum DNBR is maintained above the safety analysis DNBR limit for control rod l
drop accidents.
At high power a single or multiple rod drop accident could cause local flux peaking which, when in conjunction with nuclear power being maintained equivalent to turbine power by action of the automatic rod control system, could cause an unconservative local DNBR to exist.
The Power Range Negative Rate trip will prevent this from occurring by tripping the reactor for all single or multiple dropped rods.
Intermediate and Source Range, Nuclear Flux The Intermediate and Source Range, Nuclear Flux trips provide reactor core protection during reactor startup.
These trips provide redundant protec-tion to.the low setpoint trip of the Power Range, Neutron Flux channels.
The 0
Source Range Channels will initiate a reactor trip at about 10 counts per second unless manually blocked when P-6 becomes active.
The Intermediate l
SEQUOYAH - UNIT 1 B 2-3 Amendment No. 138 Revised 08/18/87
4tj l
,,P0 WOR DISTRIBUTJON LIMITS 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR i
LIMITING CONDITION FOR OPERATION The Nuclear Enthalpy Hot Channel Factor, Ffg, shall be limited by the 3.2.3 following relationship:
Where:
Ffg51.55(1.0+0.3(1.0-P)]
a.
THERMAL POWER b.
P he,TED THERMAL POWER '
APPLICABILITY:
MODE 1 ACTION:
WithFfH exceeding its limit:
a.
Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Power Range Neutron Flux-High Trip Setpoints to 1 55% 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 />, Demonstratethruin-coremappingthatFfH b.
is within its limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding the limit or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, and c.
Identify and correct the cause of the out of limit condition arior 1
to increasing THERMAL POWER above the reduced limit required ay a.
or b. above; subsequent POWER OPERATFN may proceed provided that l
Ffg is demonstrated through in-core mapping to be within its limit at a nominal 50% of RATED THERMAL POWER prior to exceeding this l
THERMAL POWER, at a nominal 75% of RATED THERMAL POWER prior to exceeding this THERMAL POWER and within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after attaining 95% or greater RATED THERMAL POWER.
l l
SEQUOYAH - UNIT 1 3/4 2-10 Amendment No. 19, 138
M a
TABLE 3.3-1 (Continued)
ACTION 11 -
With the numbe.' of OPERABLE channels one less than the Total Number of Channals, STARTUP and/or POWER OPERATION may proceed provided that wi'hin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, for the affected protection set, the Steam Generator Water Level - Low-Low (EAM) channels trip setpoint is adjus;ed to the same value as Steam Generator Water Level - Low-Low (Adverse)
ACTION 12 -
With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1.1 provided the other channel is OPERABLE.
ACTION 13 -
With the number of OPERABLE channels one less than the Total Number of Channels and with the THERMAL POWER level above the P-7 (Block of Low Power Reactor Trips) setpoint, place the inoperable channel in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, i
operation may continue until performance of the next required CHANNEL FUNCTIONAL TEST.
ACTION 14 -
With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 15 -
With one of the diverse trip features (undervoltage or shunt trip attachment) inoperable, restore it 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 declare the breaker inoperable and apply ACTION 12.
The breaker shall not be bypassed while one of the diverse trip features is inoperable except for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for performing maintenance to restore the breaker to OPERABLE status.
ACTION 16 -
With the number of OPERABLE channels one less than 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 open the reactor trip breakers l
l within the next hour.
l l
t SEQUOYAH - UNIT 1 3/4 3-8 Amendment No. 54, 141
TABLE 3.3-3 (Continued)
TABLE NOTATION
- rip function may be bypassed in this MODE below P-11 (Pressurizer T
Pressure Block of Safety Injection) setpoint.
,, Trip function automatically blocked above P-11 and may be blocked below
,,,when Safety Injection on Steam Line Pressure-Low is not blocked.
The channel (s) associated with the protective functions derived from the
,out of service Reactor Coolant Loop shall be placed in the tripped mode.
The provisions of Specification 3.0.4 are not applicable.
ACTION STATEMENTS ACTION 15 -
With the number of OPERABLE Channels one less than the Total Number of Channels, be in at least HOT STANDBY within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.2.1.1 provided the other channel is OPERABLE.
ACTION *.6 -
Deleted.
ACTIM 17 -
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 the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.
The Minimum Channels OPERABLE requirements is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.2.1.1.
ACTION 18 -
With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met; one addi-tional channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> fr+
surveillance testing per Specification 4.3.2.1.1.
ACTION 19 -
With less than the Minimum Channels OPERABLE, operation may continue provided the containment ventilation isolation valves are maintained closed.
ACTION 20 -
With the number of OPERABLE Channels one less than the Total Number of Channels.. 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 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 in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SEQUOYAH - UNIT 2 3/4 3-22 Amendment No. 63, 141
sh TABLE 3.3-5 (Continued)
ENGINEERED SAFtTY FEATURES RESPONSE TIMES INITIA UNG SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 10.
Station Blackout a.
Auxiliary feedwater Pumps 1 60(11) 11.
Trip of Main Feedwater Pumps a.
Auxiliary Feedwater Pumps 1 60(11) 12.
Loss of Power o.
6.9 kv Shutdown Board - Degraded
< 10(10)
~
Voltage or Loss of Voltage 13.
RWST Level-Low Coincident with Containment Sump Level-High and Safety Injection a.
Automatic Switchover to Containment Sump i 250 14.
Containment Purge Air Exhaust Radioactivity - High a.
Containment Ventilation Isolation 1 10(6) 15.
Containment Gas Monitor Radioactivity High a.
Containment Ventilation Isolation 1 10(6) 16.
Containment Particulate Activity High a.
Containment Ventilation Isolation 1 10(6)
SEQUOYAH - UNIT 2 3/4 3-32 Amendment No. 29, 77, 82
.