Event Notification Report for February 04, 2011
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/03/2011 - 02/04/2011
Power Reactor
Event Number: 46593
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: ROBERT ANDERSEN
HQ OPS Officer: DONALD NORWOOD
Region: 1 State: NY
Unit: [] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: ROBERT ANDERSEN
HQ OPS Officer: DONALD NORWOOD
Notification Date: 02/04/2011
Notification Time: 16:17 [ET]
Event Date: 02/04/2011
Event Time: 16:00 [EST]
Last Update Date: 04/11/2011
Notification Time: 16:17 [ET]
Event Date: 02/04/2011
Event Time: 16:00 [EST]
Last Update Date: 04/11/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JAMES DWYER (R1DO)
JAMES DWYER (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
LOSS OF EMERGENCY RESPONSE DATA SYSTEM DUE TO PLANNED REPLACEMENT OF PLANT PROCESS COMPUTER
"The implementation of a planned replacement of the Unit 3 plant process computer, also known as the Critical Function Monitoring System (CFMS), with a new Plant Integrated Computer System (PICS), resulted in the loss of the Emergency Response Data System (ERDS). The Meteorological Radiological Plant Data Acquisition System (MRPDAS), and Meteorological Information and Dose Assessment System (MIDAS) is also impacted. MIDAS will function but the automatic download of Unit 3 plant parameters will not be available and the MIDAS Operator (SM or Dose Assessor) will have to manually input this data to perform dose assessment. Meteorological data will remain available. All Unit 2 functions remain available. Other systems such as the Safety Parameter Display System (SPDS), the Radiological Emergency Communication System (RECS), and the Emergency Notification System (ENS) remain available. As a compensatory measure, a proceduralized backup method is available to FAX applicable data for ERDS and MRPDAS. As discussed in a letter to the NRC data October 6, 2010, the plant process computer is being replaced due to obsolescence. The new Unit 3 computer processors will be located in the Unit 2 Computer Room which will become the Computer Room for both the Unit 2 and Unit 3 Plant Computers. The new Unit 3 plant process computer work stations will be located in the Unit 3 Control Room. The new PICS was previously installed in the Unit 3 plant simulation facility. The modification was initiated on February 4, 2011 and is scheduled to be completed by March 6, 2011. The new PICS will not affect the transmitted data points nor affect the transmission format and computer communication protocol to ERDS. In accordance with the site reporting procedure, a loss of ERDS is reportable as a major loss of emergency assessment capability."
The licensee expects the duration of the ERDS outage to be from one to three weeks. The licensee notified the NRC Resident Inspector. The licensee also notified the following: New York State, Putnam County, Westchester County, Rockland County, and Orange County.
* * * UPDATE AT 0935 EDT ON 4/11/11 FROM CHARLES ROKES TO MARK ABRAMOVITZ * * *
"This notification is an update to the information previously provided on February 4, 2011. The replacement of the Unit 3 plant process computer with a new plant integrated computer system (PICS) has been completed. With the return of PICS to service the function of ERDS was also returned to service. A quarterly test with the NRC on April 5, 2011, verified ERDS is functional. The link to PICS for MRPDAS and MIDAS remains unavailable. The previously reported compensatory measure using a proceduralized backup method remains available to FAX applicable data for MRPDAS. Future upgrades will address the PICS data for MRPDAS and MIDAS."
The licensee notified the NRC Resident Inspector and will notify the state and local authorities.
Notified the R1DO (Henderson).
"The implementation of a planned replacement of the Unit 3 plant process computer, also known as the Critical Function Monitoring System (CFMS), with a new Plant Integrated Computer System (PICS), resulted in the loss of the Emergency Response Data System (ERDS). The Meteorological Radiological Plant Data Acquisition System (MRPDAS), and Meteorological Information and Dose Assessment System (MIDAS) is also impacted. MIDAS will function but the automatic download of Unit 3 plant parameters will not be available and the MIDAS Operator (SM or Dose Assessor) will have to manually input this data to perform dose assessment. Meteorological data will remain available. All Unit 2 functions remain available. Other systems such as the Safety Parameter Display System (SPDS), the Radiological Emergency Communication System (RECS), and the Emergency Notification System (ENS) remain available. As a compensatory measure, a proceduralized backup method is available to FAX applicable data for ERDS and MRPDAS. As discussed in a letter to the NRC data October 6, 2010, the plant process computer is being replaced due to obsolescence. The new Unit 3 computer processors will be located in the Unit 2 Computer Room which will become the Computer Room for both the Unit 2 and Unit 3 Plant Computers. The new Unit 3 plant process computer work stations will be located in the Unit 3 Control Room. The new PICS was previously installed in the Unit 3 plant simulation facility. The modification was initiated on February 4, 2011 and is scheduled to be completed by March 6, 2011. The new PICS will not affect the transmitted data points nor affect the transmission format and computer communication protocol to ERDS. In accordance with the site reporting procedure, a loss of ERDS is reportable as a major loss of emergency assessment capability."
The licensee expects the duration of the ERDS outage to be from one to three weeks. The licensee notified the NRC Resident Inspector. The licensee also notified the following: New York State, Putnam County, Westchester County, Rockland County, and Orange County.
* * * UPDATE AT 0935 EDT ON 4/11/11 FROM CHARLES ROKES TO MARK ABRAMOVITZ * * *
"This notification is an update to the information previously provided on February 4, 2011. The replacement of the Unit 3 plant process computer with a new plant integrated computer system (PICS) has been completed. With the return of PICS to service the function of ERDS was also returned to service. A quarterly test with the NRC on April 5, 2011, verified ERDS is functional. The link to PICS for MRPDAS and MIDAS remains unavailable. The previously reported compensatory measure using a proceduralized backup method remains available to FAX applicable data for MRPDAS. Future upgrades will address the PICS data for MRPDAS and MIDAS."
The licensee notified the NRC Resident Inspector and will notify the state and local authorities.
Notified the R1DO (Henderson).
Power Reactor
Event Number: 46724
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: BOB MURRELL
HQ OPS Officer: JOHN SHOEMAKER
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: BOB MURRELL
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 04/05/2011
Notification Time: 11:58 [ET]
Event Date: 02/04/2011
Event Time: 13:54 [CDT]
Last Update Date: 04/05/2011
Notification Time: 11:58 [ET]
Event Date: 02/04/2011
Event Time: 13:54 [CDT]
Last Update Date: 04/05/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
ROBERT DALEY (R3DO)
ROBERT DALEY (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
INVALID PRIMARY CONTAINMENT ISOLATION SYSTEM ACTUATION DUE TO A FAILED RELAY COIL
"This 60-day telephone notification is being made under reporting requirements specified by 10CFR50.73 (a)(2)(iv)(A) to describe an invalid actuation of a containment isolation signal affecting more than one system.
"At 1354 on February 4, 2011, with the Duane Arnold Energy Center (DAEC) operating at 100% power, an invalid Group 3 isolation on the 'B' side of the Primary Containment Isolation System occurred. Group 3 isolation signals were generated for Primary Containment Isolation Valves for Drywell and Torus Ventilation, and Purge, Containment Nitrogen Compressor Suction and Discharge, Recirculation Pump Seals, and Post Accident Sample System.
"This event was caused by a high resistance contact on relays in the trip circuitry for the 'B' Fuel Pool Exhaust Radiation Monitor logic.
"All equipment responded in accordance with the plant design. Specifically, all actuations were complete and successful.
"There were no safety consequences or impacts on the health and safety of the public. The event was entered into DAEC's corrective action program for resolution."
The licensee notified the NRC Resident Inspector.
"This 60-day telephone notification is being made under reporting requirements specified by 10CFR50.73 (a)(2)(iv)(A) to describe an invalid actuation of a containment isolation signal affecting more than one system.
"At 1354 on February 4, 2011, with the Duane Arnold Energy Center (DAEC) operating at 100% power, an invalid Group 3 isolation on the 'B' side of the Primary Containment Isolation System occurred. Group 3 isolation signals were generated for Primary Containment Isolation Valves for Drywell and Torus Ventilation, and Purge, Containment Nitrogen Compressor Suction and Discharge, Recirculation Pump Seals, and Post Accident Sample System.
"This event was caused by a high resistance contact on relays in the trip circuitry for the 'B' Fuel Pool Exhaust Radiation Monitor logic.
"All equipment responded in accordance with the plant design. Specifically, all actuations were complete and successful.
"There were no safety consequences or impacts on the health and safety of the public. The event was entered into DAEC's corrective action program for resolution."
The licensee notified the NRC Resident Inspector.