ML20247E922
| ML20247E922 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 09/06/1989 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20247C462 | List: |
| References | |
| NUDOCS 8909180046 | |
| Download: ML20247E922 (11) | |
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ENCIDSURE 1 BRUNSWICK STEAM ELECTRIC PLANT CORRECTIONS TO RECENT LICENSE AMENDMENTS 1
AMENDMENT NOS. 130 AND 160 i
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8909180046 890906 PDR ADOCK 0500 4
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TABLE 3.3.4-1 (Continued)
CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION NOTES (a) The minimum number of OPERABLE CHANNELS may be reduced by one for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in one of the trip syste.as for maintenance and/or testing except for Rod Block Monitor function.
(b) This function is bypassed if detector is reading >100 cps or the IRM channels are on range 3 or higher.
(c) This function is bypassed when the associated IRM channels are on range 8 or higher.
(d) A total cf 6 IRM instruments must be OPERABLE.
(e) This function is bypassed when the IRM channels are on range 1.
(f) When THERMAL POWER is greater than or equal to 30% of RATED THERMAL POWER.
(g) With any control rod vithdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
(h) This signal is contained in the Channel A logic only.
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BRUNSWICK - UNIT 1 3/4 3-49 Amendment No.
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l-L TA,BLE 3.3.4-1 (Continued).
CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION 1
l NOTES (a) The minimum n mber of OPERABLE CHANNELS may be reduced by one for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in one of the trip systems for maintenance and/or testing except for Rod Block Monitor function.
l-(b) This function is oypassed if detector is reading >100 cps or the IRM channels are on range 3 or higher.
(c) This function is bypassed when the associated IRM channels are on range 8 or higher.
(d) A total.of 6 IRM instruments must be OPERABLE.
(e) Mais function is bypassed when the IRM channels are on range 1.
(f) When THERMAL POWER is greater than or equal to 30% of RATED THERMAL POWER.
(g) With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
(h) This signal is contained in the Channel A logic only.
l BRUNSWICK - UNIT 2 3/4 3-49 Amendment No.
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-E ENCLOSURE 2 BRUNSWICK STEAM ELECTRIC PIANT CORRECTIONS TO RECENT LICENSE AMENDMENTS 1
AMENDMENT NOS. 132 AND 162 1
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ENCIDSURE 3 BRUNSWICK STEAM ELECTRIC 'L/Mr CORRECTIONS TO RECENT LICENSE MENDMENTS AMENDMENT NO. 163 (UNIT 2)-
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. LIMITING CONDITIONS'FOR 0PERATION AND' SURVEILLANCE REQUIREMENTS
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SECTION PACE s
-3/4.3 INSTRUMENTATION
'3/4.3.1
' REACTOR PROTECTION: SYSTEM INSTRUMENTATION............
13/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION..................
3/4 3-10 3/4.3.3 EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION...................................-
3/4 3-33 3/4.3.4-CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION.........
3/4 3-47
~.3/4.3.5
. MONITORING INSTRUMENTATION
-Seismic Monitoring. Instrumentation...................
3/4 3-53 Remote Shutdown Monitoring Instrumentation...........
3/4 3-561 Accident Monitoring Instrumentation...................
3/4.3-59 Source Range Monitors................................
3/4 3-63 4
Chlorine Detection System............................
3/4 3-64
. Chloride Intrusion Monitors...........................
3/4 3-65.
' Fire Detection Instrumentation.......................
3/4 3-69 Radioactive Liquid Effluent Monitoring Instrumentation...................................
3/4 3-72' Radioactive Caseous Effluent Monitoring
-Instrumentation...................................
3/4 3-78 3/4.3.6 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION ATWS Recirculation Pump Trip (RPT) System Instrumentation....................................
3/4 3-83 l
Eud-of Cycle Recirculation Pump Trip System Instrumentation...e.............................r..
3/4 3-93 l
3/4.3.7 REACTOR CCRE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION...................................
3/4 3-99 i
3/4.4 F.EACTOR COOLANT SYSTEM 3/4,4.1 Rr: CIRC"LATION SYSTEM Recirculation Loops..................................
3/4 4-1 Jet Pumps............................................
3/4 4-2 Idle Recirculation Loop Start-up.....................
3/4 4-3 l
l 3/4.4.2 SAFETY / RELIEF VALVES.................................
3/4 4-4 3/4.4.3 REACTOR COOLANT SYSTEM LEAKACE Leakage Detection Systems............................
3/4 4-5 Operational Leakage..................................
3/4 4-6 1
l BRUNSWICK - UNIT 2 V
Amendment No.
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.h' ENCLOSURE 4 BRUNSWICK STEAM ELECTRIC PIANT CORRECTIONS TO RECENT LICEdSE AMENDMENTS AMENDMENT NOS. 136 AND 166
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CONTAINMENT SYSTEMS BASES 3 / 4. 6 '.1. 3 PRIMARY CONTAINMENT AIR LOCKS The limitations on closure and leak rate'for the containment air' locks are
- required to meet the restrictions on PRIMARY CONTAINMENT' INTEGRITY and leak rate given in Specifications 3.6.1.1 and 3.6.1.2.
The specification makes allowances for the fact that there may.be long periods of time when the air locks will be in a. closed and secured position during' reactor operation'. Only one. closed' door in each air lock is required to maintain the integrity of the containment. 'In.the event of an inoperable door interlock, locking shut the inner door will ensure containment integrity while permitting access to the lock for maintenance and surveillance testing.
3/4.6.1.4' PRIMARY CONTAINMENT STRUCTURAL INTEGRITY This. limitation ensures'that the structural integrity of the primary containment steel vessel will be maintained comparable to the original design 4
standards for the life of the facility. Structural integrity is required to ensure that.the vessel will withstand the maximum pressure of 49 psig in the-event of.a LOCA. A visual inspection in conjunction with Type A leakage tests is sufficient to demonstrate this capability..
3/4.6.1.5 PRIMARY CONTAINMENT INTERNAL PRESSURE The limitations of primary containment internal pressure ensure'that the containment. peak pressure of 49 psig does not exceed the design pressure.of 62 psig during LOCA conditions. The limit of 1.75 psig, for initial positive containment pressure. rill limit the total pressure to 49 psig, which is less than the design' pressure and is consistent with the accident. analyses.
3/4.6.1.6' PRIMARY CONTAINMENT AVERACE AIR TEMPERATURE The limitatien in containment average air teraperature ensures that the containment peak air temperature does not exceed the design temperature of 500*F during LOCA conditions and is consistent with the accident analyses.
1 3
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BRUNSWICK - UNIT 1 B 3/4 6-2 Amendment No.
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CONTAINMENT SYSTEMS BASES 3/4.6.1.3 ' PRIMARY CONTAINMENT AIR LOCKS U
The limitations on closure and leak rate for the containment: air locks are required to meet the restrictions on PRIMARY CONTAINMENT INTEGRITY and leak ~
rate given-in Specifications 3.6.1.1 and 3.6.1.2.
The specification makes
. allowances for the fact.that there may be long periods of-time when the air l
locks will be in a' closed and secured position during reactor operation. Only one closed door in each air lock is required to maintain the integrity of the containment. In the event of an inoperable door interlock, locking shut the-inner door will ensure. containment integrity while permitting access to the lock.for maintenance and surveillance testing.
3/4.6.1.4 PRIMARY CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the primary containment steel vessel will be maintained comparable to the. original design standards for the life'of the facility. Structural integrity is required to ensure that the vessel will' withstand the maximum pressure of 49 psig in the event of a LOCA.- A visual inspection in conjunction with Type A leakage tests is sufficient to. demonstrate this capability.
3/4.6.1.5 PRIMARY CONTAINMENT INTERNAL PRESSURE.
The limitations of primary containment internal pressure ensure that the containment peak pressure of'49 psig does not exceed the design pressure of 62 psig.during LOCA conditions. The limit of 1.75 psig, for. initial positive containment pressure will limit the total pressure to'49 psig, which is less than the design pressure and is consistent with the accident analyres.
1 3/4.6].5 L, MARY _ CONTAINENT AVER 4.CE AIR TEMFERATJRJ The liraitation' in containment average air temperature ensures that the
. containment peak air temperature does not exceed the design temperature of
'300*F during LOCA conditions and it consistent with the accident analyses.
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BRUNSWICK - UNIT 2 B 3/4 6-2 Amendment No.
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