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The purpose of this report is to provide a … The purpose of this report is to provide a telephone notification under 10CFR50.73(a)(2)(iv)(A) for an invalid actuation of the Emergency Core Cooling Systems and the Emergency AC Electrical Power Systems. As allowed by 10CFR50.73(a)(1) this notification is being made via an ENS phone call.</br>On October 7, 2004, James A. Fitzpatrick (JAF) was in a refueling outage with the reactor cavity flooded and the spent fuel pool gates removed. At approximately 2055, during the performance of an instrument surveillance procedure (ISP-5-7) for 'Remote Shutdown Reactor Vessel Pressure Indicator Calibration' a pressure perturbation was introduced to the sensing lines while returning 02-3PI-60A to service. The pressure perturbation resulted in an invalid actuation of the Emergency Core Cooling Systems (ECCS) and Emergency Diesel Generator (EDG) initiation logic. The initiation logic functioned as designed, 'A' and 'B' Core Spray Pumps and 'A', 'B', 'C', and 'D' RHR pumps started and injected into core, and EDGs 'A', 'B', 'C' and 'D' started but did not close to the emergency buses since there was no loss of off site power.</br>Operations personnel verified plant conditions, secured ECCS injection and secured the EDGs. The event was entered in the plant corrective action program via Condition Report CR-JAF-04-04457. Preliminary investigation has identified valve manipulation to restore pressure indicator 02-3PI-60A to service as the cause of a pressure perturbation in a shared sensing line, which caused the level transmitters sharing the same line to detect a low reactor water level condition. All systems that actuated operated per their design. </br>As a result of the injection, water overflowed to the skimmer surge tanks and into the reactor building drain system as designed, resulting in contamination of sections of the reactor building. No personnel contaminations or unexpected exposures occurred as a result. A recovery plan was developed and implemented to minimize the impact and to recover the affected plant areas.</br>In addition, signals were received for HPCI and RCIC initiation, SBGT initiation, Recirc pump trip and Alternate Rod Insertion (ARI). Due to outage activities, these systems were removed from service and protective tagged, and thus the systems did not respond. Although not required by 10 CFR 50.73 JAF will submit a voluntary LER to address this event in greater detail.</br>The NRC Sr. Resident Inspector was notified.</br>The licensee also informed the State of New York.ensee also informed the State of New York.
01:55:00, 8 October 2004 +
41,214 +
14:38:00, 22 November 2004 +
01:55:00, 8 October 2004 +
The purpose of this report is to provide a … The purpose of this report is to provide a telephone notification under 10CFR50.73(a)(2)(iv)(A) for an invalid actuation of the Emergency Core Cooling Systems and the Emergency AC Electrical Power Systems. As allowed by 10CFR50.73(a)(1) this notification is being made via an ENS phone call.</br>On October 7, 2004, James A. Fitzpatrick (JAF) was in a refueling outage with the reactor cavity flooded and the spent fuel pool gates removed. At approximately 2055, during the performance of an instrument surveillance procedure (ISP-5-7) for 'Remote Shutdown Reactor Vessel Pressure Indicator Calibration' a pressure perturbation was introduced to the sensing lines while returning 02-3PI-60A to service. The pressure perturbation resulted in an invalid actuation of the Emergency Core Cooling Systems (ECCS) and Emergency Diesel Generator (EDG) initiation logic. The initiation logic functioned as designed, 'A' and 'B' Core Spray Pumps and 'A', 'B', 'C', and 'D' RHR pumps started and injected into core, and EDGs 'A', 'B', 'C' and 'D' started but did not close to the emergency buses since there was no loss of off site power.</br>Operations personnel verified plant conditions, secured ECCS injection and secured the EDGs. The event was entered in the plant corrective action program via Condition Report CR-JAF-04-04457. Preliminary investigation has identified valve manipulation to restore pressure indicator 02-3PI-60A to service as the cause of a pressure perturbation in a shared sensing line, which caused the level transmitters sharing the same line to detect a low reactor water level condition. All systems that actuated operated per their design. </br>As a result of the injection, water overflowed to the skimmer surge tanks and into the reactor building drain system as designed, resulting in contamination of sections of the reactor building. No personnel contaminations or unexpected exposures occurred as a result. A recovery plan was developed and implemented to minimize the impact and to recover the affected plant areas.</br>In addition, signals were received for HPCI and RCIC initiation, SBGT initiation, Recirc pump trip and Alternate Rod Insertion (ARI). Due to outage activities, these systems were removed from service and protective tagged, and thus the systems did not respond. Although not required by 10 CFR 50.73 JAF will submit a voluntary LER to address this event in greater detail.</br>The NRC Sr. Resident Inspector was notified.</br>The licensee also informed the State of New York.ensee also informed the State of New York.
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00:00:00, 22 November 2004 +
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45.488 d (1,091.72 hours, 6.498 weeks, 1.495 months) +
01:55:00, 8 October 2004 +
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