ML20147H959
| ML20147H959 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 03/04/1988 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20147H963 | List: |
| References | |
| NUDOCS 8803090137 | |
| Download: ML20147H959 (3) | |
Text
4 INSTRUMENTATION BASES FIRE DETECTION INSTRUMENTATION (Continued) equipment and is an integral element in the overall facility fire protection program.
In the event that a portion of the fire detection instrumentation is inoperable, increasing the frequency of fire watch patrols in the affected areas in required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.
3/3.3.7.10 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent monitoring instrumentation is provided to monitor ana control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.
The alarm / trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFP. Part 20.
The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
3/4.3.7.11 RADIOACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.
The alarm / trip setpoints for these insruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.
This instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the waste gas holdup system.
The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
3/4.3.7.12 LOOSE-PART DETECTION SYSTEM The OPERABILITY of the loose part detection system ensures that sufficient capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components.
The allowable out-of-service times and surveillance requirements are consistent with the recom-mendations of Regulatory Guide 1.133, "Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors."
3/4.3.8 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION The feedwater/ main turbine trip system actuation instrumentation is provided to initiate the feedwater system / main turbine trip system in the event of reactor vessel water level equal to or greater than the level 8 setpoint as',ociated with a feedwater controller failure, to prevent overfilling the reactor vessel which may result in high pressure liquid discharge through the safety / relief valve discharge lines.
LA SALLE - UNIT 1 8 3/4 3-6 Amendment No.53 98898658888)ho P
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INSTRUMENTATION BASES FIRE DETECTION INSTRUMENTATION (Continued) stages.
Prompt detection of fires will reduce the potential for damage to safety-related equipment and is an integral element in the overall facility fire protection program.
In the event that a portion of the fire detection instrumentation is inoperable, increasing the frequency of fire watch patrols in the affected areas in required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.
3/3.3.7.10 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid offluents.
The alarm / trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.
The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50, 3/4.3.7.11 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.
The alarm / trip setpoints for these insruments shall be calculated in accordance with the procedures in the 00CM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.
This instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the waste gas holdup system.
The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
3/4.3.7.12 LOOSE-PART DETECTION SYSTEM The OPERABILITY of the loose part detection system ensures that sufficient capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components.
The allowable out-of-service times and surveillance requirements are consistent with the recom-mendations of Regulatory Guide 1.133, "Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors."
3/4.3.8 FEE 0 WATER / MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION The feedwater/ main turbine trip system actuation instrumentation is provided to initiate the feedwater system / main turbine trip system in the event of reactor vessel water level equal to or greater than the level 8 setpoint associated with a feedwater controller failure to prevent over-filling the reactor vessel which may result in high pressure liquid dis-charge through the safety / relief valve discharge lines.
LA SALLE - UNIT 2 B 3/4 3-6 Amendment No. 35
s INSTRUMENTATION TRAVERSING IN-CORE PROBE SYSTEM LIMITING CONDITION FOR OPERATION 3.3.7.7.
The traversing in-core probe system shall be OPERABLE with:
a.
Movable detectors, drives and readout equipment to map the core in the required measurement locations, and b.
Indexing equipment to allow all required detectors to be calibrated in-a common location.
APPLICABILITY:
When the traversing in-core probe is used for:
- a.
Recalibration of the LPRM detectors, and
- b.
Monitoring the APLHGR, LHGR, MCPR, or MFLPD.
ACTION:
With one or more TIP measurement locations inoperable, required measure-a.
ments may be performed as described in 1 and 2 below, provided the reactor core is operating in an octant symmetric control rod pattern, and the total core TIP uncertainty for the present cycle has been measured to be less than 8.7 percent.
1.
TIP data for an inocerable measurement location may be replacea by data obtained from that string's redundant (symmetric) counterpart if the substitute TIP data was obtained from an operable measurement location.
2.
TIP data for an inoperable measurement location may be replaced by data obtained from a 3-dimensional BWR core simulator code normalized with available operating measurements, provided the total number of simulated channels (measurement locations) does not exceed:
a)
All channels of a single TIP machine, or b)
A total of five channels if more than one TIP machine is involved.
b.
Otherwise, with the TIP system inoperable, suspend use of the system for the above applicable monitoring or calibration functions.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.7.7 The traversing in-core probe system shall be demonstrated OPERABLE by normalizing each of the above required detector outputs within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to use for the above applicable monitoring or calibration functions.
- 0nly the detectorTs) in tiie required measurement location (s) e e required to be OPERABLE.
LA SALLE - UNIT 2 3/4 3-73 Amendment No. 35
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