ML20236U418
| ML20236U418 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 11/25/1987 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20236T809 | List: |
| References | |
| NUDOCS 8712030028 | |
| Download: ML20236U418 (3) | |
Text
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OUa0 C!?!t$
OPR-29 I
' operable tenedtately. 'fne RCIC' system shall be demonstrated to be operable daily thereafter.
Ostly demonstration of the auto-tactic pressure relief subsystem operattitty is not required-provided that two feedwater pumps are operating at' levels..
above 390 Mde: and one feedwater provided that during such 7 days pump.is operating as normally all active camponents of the required with one additional automatic prassure relief sub- '
resowater pump operable at power systems, the core spray sub-lovels less than 300 peas.
i Systems. LPCI mode of the RNR system. and the RCIC system are operable.
3.
If the reeutrements of
$pecif1Catton 3.5.C cannot be Y
met. an orderly shutchun shall be inittated, and the reactor
'l pressure shall be reduced to 90 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
automatic Pressure Relief Subsystems
- 0. LAutomatic Pressure Relief Subsystems 1
0.
Surveillance of the automatte pressure relief subsystem shall be performed ac fellows:
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The fellowing surveillance shall 1.
The aut matic pressure relief subsystem shall be 09erable be carried out on a sis-eenth whenever the reactor pressure is surveillance interval:
greater than 90 pstg. trradiated fuel ts in the reactor vessel a.
With the reactor at pressure 4
and prior te reactor startup each reitet. valve shall be from a cold condition.
manually opened. Relief valve opening shall be verified by a cenpensating thrbine bypass valve or contral valve closure.
2.
A logic system functional test 2.
From and after the date that two' r,.. of the five rettef shall be performed each
/ relief subsysten are made orvalves of the automatic pressure refueltng outage.
3.
& Simulated automatic initiation found to be snoperable d en the reactor is pressurtaed above 90 d ich opens all pilot valves p
psig with trradiated fuel in the shall be performed each re-reactor vessel. reactor fueling outage.
operation is permissible only during the succeeding 7 days unless repairs are made and A.
m en it ts determineel that two.
provided that during such tien the HPCI subsystem is operable.
[7
- i. valves of the automatic, l
ressure relief subsystem are 3.
If the requirements of $pectft-inoperabi.. ene mi shan be cation 3.5.0 cannot be met, an demonstrated to be operable orderly shutdown shall be initi-taunediately.
ated and the reactor pressure shall be reduced to 90 psig 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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07038 3.5/4.5-5 Amendment No.
8712030028 871125 PDR ADOCK 05000254'-
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Altachment_B Rod Block Monitor Setpoint Clippi,n3 As discussed in Reference (a), operating in the Increased Core Flow region requires a change to the Rod Block Monitor flow-biased trips to maintain consistency with the Rod Withdrawal Error analysis. The change required is to clip the rod block setpoint above 100% flow such that the RBM rod block occurs at the same power level (local power normalized to APRM average power) as if the reactor were at 100% flow.
Although there are several ways this can be accomplished, one straightforward method is to use the backup rod block function in the trip reference circuitry. The backup circuit is currently set at a high value so it does not interfere with the normal rod block. The backup circuit includes a portion which permits the reference signal to be clipped, 1.
e.,
even with increasing flow the reference signal will no longer increase. The backup circuit can be set so that the reference signal increases with flow like the normal signal, but then stops increasing when the flow is at or above the recirculation drive flow corresponding to 100% rated core flow.
This will accomplish the clipping required with Increased Core Flow (ICF).
This clipping method makes use of plant equipemnt as installed, i.e. only adjustment of the installed equipment is required.
Therefore, the RBM clipping to accommodate ICF can be performed without any equipment modification.
This is the method which will be utilized at Quad Cities. To avoid the use of different RBM settings for the two units during the approximately four months between the Unit 1 Cycle 10 startup and the Spring, 1988 Unit 2 outage, the station plans to defer the setpoint adjustment until Unit 2 shuts down in April, 1988.
In the interim, the current procedural limitations restricting operation to less than or equal to 100% rated core flow will be maintained.
Operation in the Increased Core Flow region will not be allowed until the RBM setpoint adjustment and associated procedural changes are implemented, i
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Attachment C pore Plate Differential Pressure Surveillance
.i As a means to monitor. jet pump, integrity and as connaitted to for 4-the Quad cities Unit 2 Cycle 9 reload approval, the station will continue to perform the Core Plate Differential Pressure Surveillance during single loop' operation (as required by existing procedures) for Quad cities Unit 1 as well.
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