ML18093A214
| ML18093A214 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/02/1987 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML18093A212 | List: |
| References | |
| NUDOCS 8707110021 | |
| Download: ML18093A214 (8) | |
Text
ATTACHMENT
~
SALEM UNIT 1 ~ DELETION OF REACTOR TRIP ON TURBINE TRIP BELOW P-9 _
TECHNICAL SPECIFICATION MARK-UPS 8707110021 870702------~,
PDR ADOCK 05000272 p
TABLE 3.3-1 (Continued)
ACTION 9 - With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s* or be in HOT STANDBY within the next 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />s: however, one channel associated with an operating loop 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 /> tor s.u.rveillance testing per Specifi_cation 4.3.1.1.
ACTION 10 - With one channel inoperable, restore the inoperable channel to OPERABLE status 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 below P-8 within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Operation below P~8 may continue pursuant to ACTION 11.
ACTION 11 - With less than the Minimum Number of Channels OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
ACTION 12 - 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 hpurs and/or open the reactor trip breakers.
DESIGNATION P-6 P-.7 SALEM - UNIT 1 REACTOR TRIP SYSTEM INTERLOCKS CONDITION AND SETPOINT With 2 of 2 Intermediate Range Neutron Flux Channels < 6 x 10 amps.
With 2 of 4 Power Range Neutron Flux Channels > 11% of RATED THERMAL POWER or 1 of 2 Turbine impulse chamber pressure channels L. a pressure equivalent to 11% of RATED THERMAL POWER.
3/4 3-7 FUNCTION P-6 prevents or def eats the manual block of source range reactor trip.
P-7 prevents or defeats the automatic block of react.or trip on:
Low flow in more than one primary coolant loop, reactor coolant pump under-voltage and under-frequency, pressurizer low pressure, and pressurizer high level.
1
e e
DESIGNATION P-8 P-9*
P-10 TABLE 3.3-1 (Continued)
CONDITION AND SETPOINT With 2 of 4 Power Range Neutron Flux channels 2. 36% of RATED THERMAL POWER.
With 2 of 4 Power Range neutron flux channels> 50% of RATED THERMAL POWER.-
With 3 of 4 Power range neutron flux channels < 9% of RATED THERMAL POWER.
FUNCTION P-8 prevents or def eats the automatic block of reactor trip on low coolant flow in a single loop (and reactor trip on turbine trip*).
P-9* prevents or def eats the automatic block of reactor trip on turbine trip.
P-10 prevents or defeats the manual block of:
Power range low setpoint reactor trip, Intermediate range reactor trip, and intermediate range rod stops.
Provides input to P-7.
- The P-9 interlock will prevent or defeat the automatic block of reactor trip on turbine trip after the start of Cycle 9.
The P-8 interlock will prevent or defeat the automatic block of reactor trip on turbine trip during Cycle 8 only, unless the P-9 hardware is installed during a Cycle 8 shutdown, then the P-9 interlock will prevent or defeat the automatic block of reactor trip on turbine trip thereafter.
SALEM -UN IT 1 3/4 3-8
LIMITING SAFETY SYSTEM SETTINGS BASES reliability of the Reactor Protection System.
This trip is redundant to the Steam Generator Water Level Low-Low trip.
The Steam/Feedwater Flow Mismatch portion of this trip is activated when the steam flow exceeds the feedwater flow by 2. 1.42 x 10s lbs/hour.
The Steam Generator Low Water level portion of the trip is activated when the water level drops below 25 percent, as indicated by the narrow range instrument.
These trip values include sufficient allowance in excess of normal operating values to preclude spurious trips but will initiate a reactor trip before the steam generators are dry.
Therefore, the required capacity and starting time requirements of the auxiliary feedwater pumps are reduced and the resulting thermal transient on the Reactor Coolant System and steam generators is minimized.
Undervoltage and Underfrequency - Reactor Coolant Pump B11sses The Undervoltage and Underfrequency Reactor Coolant Pump bus trips provide reactor core protection against DNB as a result of loss of voltage or underfrequency to more than one reactor coolant pump.
The specified set points assure a reactor trip signal is generated before the low flGw trip set point is reached.
Time delays are incorporated in the underfrequency and undervoltage trips to prevent spurious reactor trips from momentary electrical power transients.
For undervoltage, the delay is set so that the time required for a signal to reach the reactor.
trip breakers following the simultaneous trip of two or more reactor coolant pump bus circuit breakers shall not exceed 0.9 seconds.
For underfrequency*, the delay is set so that the time required for a signal to reach the reactor trip breakers after the underfrequency trip setpoint is reached shall not exceed 0.3 seconds.
Turbine Trip A Turbine Trip causes a direct reactor trip when operating above P-9.
Each of the turbine trips provide turbine protection and reduce the severity of the ensuing transient.
No credit was taken in the accident analyses for operation of these trips. Their functional capability at the specified trip settings is required to enhance the overall reliability of the Reactor Protection System.
- The P-9 interlock will enable a reactor trip on turbine trip after the start of Cycle 9.
The P-8 interlock will enable a reactor trip during Cycle 8 only, unless the P-9 hardware is installed during a Cycle 8 shutdown, then the P-9 interlock will enable a reactor trip on turbine trip thereafter.
SALEM - UNIT 1 B 2-7
t ATTACHMENT. 4-. - ---
SALEM UNIT 2 - DELETION OF REACTOR-TRIP ON TURBINE TRIP BELOW P-9 TECHNICAL SPECIFICATION MARK-UPS.
ACTION 9 ACTION 10 ACTION 11 ACTION 12 DESIGNATION P-6 P-7 SALEM - UN IT 2 TABLE 3.3.1 (Continued)
With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 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 />; however, one channel associated with an operating loop 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.
With one channel inoperable, restore the inoperable channel to OPERABLE status 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 below the P-8 (Low Reactor Coolant Pump Flow and Reactor Coolant Pump Breaker Position) setpoint, within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Operation below the P-8 (Low Reactor Coolant Pump Flow and Reactor Coolant Pump Breaker Position) setpoint, may continue pursuant to ACTION 11.
With less than the Minimum Number of Channels OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
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 /> and/or open the reactor trip breakers.
REACTOR TRIP SYSTEM INTERLOCKS CONDITION AND SETPOINT With 2 of 2 Intermediate Range Neutron Flux Channels < 6 x 10 amps.
With 2 of 4 Power Range Neutron Flux Channels~ 11% of RATED THERMAL POWER or 1 of 2 Turbine impulse chamber pressure channels
- 2. a pressure equivalent to 11% of RATED THERMAL POWER.
3/4 3-7 FUNCTION P-6 prevents or def eats the manual block of source range reactor trip.
P-7 prevents or defeats the automatic block of reactor trip on:
Low flow in more than one primary coolant loop, reactor coolant pump under-voltage and under-frequency, pressurizer low pressure, and pressurizer high level.
DESIGNATION P-8 P-9 P-10 SALEM - UNIT 2 TABLE 3.3-1 (Continued)
CONDITION AND SETPOINT With 2 of 4 Power Range Neutron Flux channels > 36% of RATED THERMAL POWER.
With 2 of 4 Power range neutron flux channels > 50% of RATED THERMAL POWER.
With 3 of 4 Power range neutron flux channels < 9% of RATED THERMAL POWER.
3/4 3-8 FUNCTION
- P-8 prevents or defeats the automatic block of reactor trip on low coolant flow in a single loop.
P-9 prevents or def eats the automatic block of reactor trip on turbine trip.
P-10 prevents or defeats the manual block of:
Power range low setpoint reactor trip, Intermediate range reactor trip, and intermediate range rod stops.
Provides input to P-7.
LIMITING SAFETY SYSTEM SETTINGS BASES Undervoltage and Underfreguency - Reactor Coolant Pump Busses The Undervoltage and Underfrequency Reactor Coolant Pump bus trips provide reactor core protection against DNB as a result of loss of voltage or under-frequency to more than one reactor coolant pump.
The specified set points assure a reactor trip signal is generated before the low flow trip set point is reached.
Time delays are incorporated in the underfrequency and undervoltage trips to prevent spurious reactor trips from momentary electrical power transients.
For undervoltage, the delay is set so that the time required for a signal to reach the reactor trip breakers following the simultaneous trip of two or more reactor coolant pump bus circuit breakers shall not exceed 0.9 seconds.
For underfrequency. the delay is set so that the time required for a signal to reach the reactor trip breakers after the underfrequency trip setpoint is reached shall not exceed 0.3 seconds.
urbine Tri A Turbine Trip causes a direct reactor trip when operating above P-9.
l Each of the turbine trips provide turbine protection and reduce the severity of the ensuing transient.
No credit was taken in the accident analyses for operation of these trips. Their functional capability at the specified trip settings is required to enhance the overall reliability of the Reactor Protection System.
Safety Injection Input from ESF If a reactor trip has not already been generated by the reactor protective instrumentation, the ESF automatic actuation logic channels will initiate a reactor trip upon any signal which initiates a safety injection. This trip is provided to protect the core in the event of a LOCA.
The ESF instrumentation channels which initiate a safety injection signal are shown in Table 3.~-3.
Reactor Coolant Pump Breaker Position Trip_
The Reactor Coolant Pump Breaker Position Trips are anticipatory trips which provide reactor core protection against DNB resulting from the opening of any one pump breaker above P-8 or the opening of two or more pump breakers below P-8.
These trips are blocked below P-7.
The open/close position trips assure a reactor trip signal is generated before the low flow trip set point is reached.
No credit was taken in the accident analyses for operation of these trips. Their functional capability at the open/close position.settings is required to enhance the overall reliability of the Reactor Protection System.
SALEM -- UNIT 2 B 2-7