ML20078R602
| ML20078R602 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 02/13/1995 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20078R600 | List: |
| References | |
| NUDOCS 9502230045 | |
| Download: ML20078R602 (4) | |
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Unit 2-j PBAPS i
LIMITINC CounITIONS FOR OPERATION SURVEILIANCE REOUIREMENTS 3.5.C HPCI Subsystem (cont'd.)
4.5.C HPCI-Subsystem (cont'd.)
l lt;ma Frequency (b) Pump Once/ month Operability (c) Motor Operated Once/ month Valve Operability (d) Flow Rate at Once/3 months approximately 1030 psig Reactor Steam Pressure (e) Verify, with Once/ operating i
reactor pressure cycle 5175 psig, the HPCI pump can develop a flow i
rate 25000 gpa against a system head correspod-l ing to reactor pressure.*
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- 2. From and after the date that
-The HPCI purp shall deliver the HPCI Subsystem is made or at least 5000 gom for a system found to be inoperable for head correspondin5 te a reactor any reason, continued reactor
' pressure of approximately 1030 to f
operation is permissible only 150 psig.
during the succeeding seven days unless such subsystem is
- 2. DELETED l
sooner made operable, provi-ding that during such seven days all active components of j
the ADS subsystem, the RCIC system, the LPCI subsystem i
and both core spray subsys-tems are operable.
- 3. If the requirements of 3.5.C cannot be met, an orderly shut-down shall be initiated and the reactor shall be in a Cold Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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- Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.
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PDR. ADOCK 05000277 P
PDR l
Unit 3 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILIANCE REOUIREMENTS 3.5.C HPCI Subsystem (cont'd.)
4.5.C HPCI Subsystem (cont'd.)
ligg Frecuency (b) Pump Once/ month Operability (c) Motor Operated Once/ month Valve Operability (d) Flow Rate at once/3 months approximately 1000 psig Reactor Steam Pressure (e) Verify, with Once/ operating reactor pressure cycle 5175 psig, the HPCI pump can develop a flow rate 25000 gpm against a system head correspod-ing to reactor pressure.*
- 2. From and after the date that The HPCI p g shall deliver the HPCI Subsystem is made or at least 5000 gpm for a system found to be inoperable for head corresponding to a reactor any reason, continued reactor pressure of 1000 to 150 psig.
operation is permissible only during the succeeding seven
- 2. DELETED days unless such subsystem is sooner made operable, provi-ding that during such seven days all active components of the ADS subsystem, the RCIC system, the UCI subsystem and both core spray subsys-tems are operable.
- 3. If the requirements of 3.5.C cannot be met, an orderly shut-down shall be initiated and the reactor shall be in a Cold Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.
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Unit.2
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PBAPS-
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L4.5 88511.
Core and Containment Coolina Systems Surveillance Freauencies
- The performance.of individual emergency core cooling systems. (HPCI, LPCI, Core Spray and ADS) and.the integrated performance of the emergency core cooling systems are described in analyses referenced in Section-6.5 of the Updated Final Safety Analysis Report.
Periodic surveillance of pumps and valves is performed in accordance with ASME 4
Code,Section XI, to the extent described in the-Inservice Testing Plan, to verify that the systems will provide the flow rates required by the respective analyses. HPCI and RCIC flow tests are performed at.two pressures so that the systems' capability to provide rated flow over their operating range is verified.
Reactor steam pressure must be 51030 and 1920'psig to perform the high pressure test and greater than or equal to the Electro-Hydraulic Control (EHC) System minimum pressure set-with the EHC System controlling pressure (EHC System begins controlling-pressure at a nominal 150 psig) and $175 psig to perform TS 4.5.C.I.e.
To avoid damaging Core Spray system valves during Core Spray pump flow testing, throttling is not normally performed to obtain a system head
-i corresponding to a reactor pressure of 2105 psig.
Pump curves are used to determine equivalent values for flow rate and test pressure for the Core Spray pumps in order to meet he Surveillance Requirements. HPSW flow tests verify that rated flow ccn be delivered to the RHR heat exchangers.
i The testing interval for the core and containment cooling systems is based un industry practice, sound engineering judgment and practicality.
The core cooling systems have not been designed to be fully testable j
during operation. For example, in the case of the HPCI, automatic initiation during power operation would result in pumping cold water I
into the reactor vessel which is not desirable. Complete ADS testing during power operation causes an undesirable loss-of-coolant inventory.
To increase the availability of the core and containment cooling systems, the components which make up the system; i.e., instrumentation, pumps, valves, etc., are tested frequently. The pumps and motor operated injection valves are also tested each month to assure their l
operability. A simulated automatic actuation test once each cycle combined with frequent tests of the pumps and injection valves is deemed
-l to be adequate testing of these systems.
The flow path piping of the emergency core cooling systems (ECCS) has the potential to develop voids and pockets of entrained air.
Maintaining the pump discharge lines of the HPCI system, Core Spray f
system, and LPCI subsystems full of water ensures that the ECCS will L
perform properly, injecting its full capacity into the reactor pressure vessel upon demand. This will also prevent a water hammer following an i
ECCS initiation signal. One acceptable method of ensuring that the lines are full is to vent at the high points. An acceptable method of ensuring the LPCI and Core Spray system discharge lines are full is to verify the absence of the associated " keep fill" system accumulator alarms.
j While the reactor is in the Cold Condition one low pressure ECCS j
subsystem can maintain adequate reactor vessel water level. To provide redundancy, a minimum of two low pressure ECCS subsystems are required to be OPERABLE with the reactor in the Cold Condition.
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PBAPS I
'4.5 B&EE _
Core and Containment Coolina Systems Surveillance Freauencies The performance of-individual emergency core cooling systems (HPCI, LPCI, Core. Spray and ADS) and the integrated performance of the emergency core cooling systems are described in analyses referenced in Section 6.5 of the Updated Final Safety Analysis Report.- Periodic surveillance of pumps and valves is performed in accordance with ASME Code,Section XI, to the extent described in the Inservice Testing Plan, to verify that the systems will provide the flow rates required by the respective analyses. HPCI and RCIC flow tests are performed at two i
pressures so that the systems' capability to provide rated flow over
- their operating range is verified. Reactor steam pressure must be $1030 and 2920 psig to perform the high pressure test and greater than or equal to the Electro-Hydraulic Control (EHC) System minimum pre'ssure set with the EHC System controlling pressure (EHC System begins controlling pressure at a nominal 150 psig) and 5175 psig to perform TS 4.5.C.I.e.
To avoid damaging Core Spray system valves during Core Spray pump flow testing, throttling is not normally performed to obtain a system head correspending to a reactor pressure of 2105 psig.
Pump curves are used to determine equivalent values for flow rate and test pressure for the Core Spray pumps in order to meet the Surveillance Requirements. HPSW flow tests verify that rated flow can be delivered to the RHR heat exchangers.
The testing interval for the core and containment cooling systems is l
based on industry practice, sound engineering judgment and practicality.
The core cooling systems have not been designed to be fully testable during operation.
For example, in the case of the HPCI, automatic initiation during power operation would result in pumping cold water into the reactor vessel which is not desirable. Complete ADS testing i
during power operation causes an undesirable loss-of-coolant inventory.
To increase the availability of the core and containment cooling systems, the components which make up the system; i.e., instrumentation, pumps, valves, etc., are tested frequently. The pumps and motor operated injection valves are also tested each month to-assure their operability. A simulated automatic actuation test once each cycle l
combined with frequent tests of the pumps and injection valves is deemed l
to be adequate testing of these systems.
l The flow path pipin) of the emergency core cooling systems (ECCS) has the potential to develop voids and pockets of entrained air.
Maintaining the puup discharge lines of the HPCI system, Core Spray j
system, and LPCI sobsystems full of water ensures that'the ECCS will perform properly, injecting its full capacity into the reactor pressure vessel upon demand. This will also prevent a water hammer following an l
ECCS initiation signal. One acceptable method of ensuring that the lines are full is to vent at the high points. An acceptable method of l
ensuring the LPCI and Core Spray system discharge lines are full is to verify the absence of the associated " keep fill" system accumulator alarms.
i While the reactor is in the Cold Condition one low pressure ECCS l
subsystem can maintain adequate reactor vessel water level. To provide redundancy, a minimum of two low pressure ECCS subsystems are required to be OPERABLE with the reactor in the Cold Condition.
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