ML20217G782

Special Rept:On 970227,ECCS Sys Was Actuated & Injected Water in Rcs.Declared HPCI Subsystem Operable Following Restoration of Subsystem to Normal Standby Lineup

ML20217G782
Person / Time
Site:	Quad Cities
Issue date:	07/22/1997
From:	Pearce L COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LWP-97-076, LWP-97-76, NUDOCS 9708080041
Download: ML20217G782 (2)

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(:ortlin a. II,6121/ O':40 la sm.s. 22 o LWP-97-076 July 22,1997 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Document Control Desk This Special Report is submitted in accordance with Quad Cities Unit I and 2 Technical Specifications 3.5.A and 6.9.B.

Technical Specification 3.5.A Action 7 requires that "In the event an ECCS system is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.B within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value

• of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0,70."

At 0242 hours0.0028 days <br />0.0672 hours <br />4.001323e-4 weeks <br />9.2081e-5 months <br /> on February 27,1997, with Unit Two in Mode One at approximately 95% power, the Instrument Maintenance (IM) Department was performing Quad Cities Instrument Maintenance Procedure (QCIPM) 0100-10, " Refuel Outage ECCS Instrumentation Check Prior To ECCS Logic Test," to test the High Pressure Coolant Injection (HPCI) containment j pressure Emergency Core Cooling System (ECCS) initiation logic. A HPCI initiation signal was produced when performance of procedural steps satisfied ,

[v j the actuation logic for HPCI High Drywell pressure. License Event Report '

(LER) 2-97-001 Supplement 1 provides the full details of this event, including the failuie to submit this special report within 90 days of the injection event.

' y When Control Room personnel noted the HPCI turbine starting sequence and associated alarms, they verified that the HPCI initiation was not iequired and tripped the turbine approximately 27 seconds after the initiation signal was received. The crew reviewed control room indications and determined there was no evidence of change in reactor power, pressure, or level. The investigation team later determined that the subsystem injected less than 300 gallons of water into the reactor vessel during this event. The HPCI subsystem was declared operable at 0521 hours0.00603 days <br />0.145 hours <br />8.614418e-4 weeks <br />1.982405e-4 months <br /> on February 27,1997, following restoration of the subsystem to its normal standby lineup.

9708080041 970722 PDR S

ADOCK 05000265 PDR ,

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• U. S. NRC LWP-97-076 2 July 22,1997 Due to the limited amount of cold water (<300 gallons) injected by the 11PCI subsystem, feedwater was not cooled below 240 degrees. A partial loss of feedwater heating is define,i to be a change of feedwater temperature where the temperature stays above 240 degrees F. To dete there have been eighteen (18) partial loss of feedwater heating events on Quad Cities Unit 2. The reactor remains within the designed number of vessel cycles (80) for a partial loss of feedwater heating. The usage factor for the feedwater nozzles remains below 0.70. This is based on the current accumulated cycles for all events are less than that allowed in UFSAR Tables 3.9-1 and 3.9-2.

If there are any questions or comments concerning this ietter, please refer them to Charles Peterson, Regulatory Affairs Manager at 309-654-2241, ext. 3609. Respectfully, COMMONWEALTII EDISON COMPANY QUAD CITIE NUCLEAR POWER STATION

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L. W. Pearce am Station Manager s LWP/CP/pim cc: A. B. Beach, Regional Administrator, Region III R. M. Pulsifer, Project Manager, NRR C. G. Miller, Senior Resident inspector, Quad Cities W. D. Leech, MidAmerican Energy Company D. C. Tubbs, MidAmerican Energy Company F. A. Spangenberg, Regulatory AfTairs Manager, Dresden INPO Records Center Oflice of Nuclear Facility Safety, IDNS DCD License (both electronic and hard copies) M. E. Wagner, Licensing, Comed}}