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Event Notification Report for April 22, 2011

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/21/2011 - 04/22/2011

** EVENT NUMBERS **


46645 46773 46774 46775

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 46645
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JEFF MIELL
HQ OPS Officer: BILL HUFFMAN
Notification Date: 02/26/2011
Notification Time: 12:16 [ET]
Event Date: 02/26/2011
Event Time: 09:48 [CST]
Last Update Date: 04/21/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
DAVID HILLS (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

Event Text

HIGH PRESSURE COOLANT INJECTION SYSTEM INOPERABLE

"High Pressure Coolant Injection (HPCI) system declared inoperable due to Flow Indicating Controller process value indicating 542 gpm while in standby readiness condition. This condition could impact the system response time in developing flow for events it was credited in mitigating.

"HPCI declared inoperable per TS 3.5.1 Condition F which allows 14 days to restore to operable status.

"Preliminary cause is air intrusion into instrument sensing lines following pre-planned maintenance where system draining was performed. Troubleshooting is in progress.

"All remaining ECCS and RCIC are operable and available. Grid stability has been verified."

The NRC senior resident has been notified.

* * * RETRACTION AT 1216 ON 4/21/2011 FROM BOB MURRELL TO MARK ABRAMOVITZ * * *

"The purpose of this notification is to retract a previous report made on 2/26/2011 at 1216 (EDT) (EN 46645). Notification of the event to the NRC was initially made as a result of declaring High Pressure Coolant Injection (HPCI) system inoperable due to Flow Indicating Controller process value indicating 542 gpm while in standby readiness condition. This condition could have impacted the system response time in developing flow for events it was credited to mitigate.

"Subsequent to the initial report, NextEra Energy Duane Arnold (NextEra) has determined that the HPCI system was capable of performing its safety function.

"NextEra concluded that the erroneous Flow Indicator Controller indication was due to air entrainment in the instrument sensing line. A detailed engineering analysis has concluded that the HPCI system was capable of providing design required flow rates with the flow offset.

"This event is not considered a Safety System Functional Failure and is not reportable to the NRC as a Licensee Event Report (LER) per 10 CFR 50.73.

"The NRC Senior Resident Inspector has been notified."

Tech spec required flow is 2700 gpm. Calculations show that a margin of 600 gpm exists between the tech spec flow rate, and the HPCI automatic flow setpoint, therefore, with an error of 542 gpm, the required flow is met.

Notified the R3DO (Phillips).

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Power Reactor Event Number: 46773
Facility: OCONEE
Region: 2 State: SC
Unit: [1] [2] [3]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: BOB MEIXELL
HQ OPS Officer: VINCE KLCO
Notification Date: 04/21/2011
Notification Time: 16:57 [ET]
Event Date: 04/21/2011
Event Time: 14:05 [EDT]
Last Update Date: 04/21/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
JONATHAN BARTLEY (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Refueling 0 Refueling
2 N Y 100 Power Operation 100 Power Operation
3 N Y 100 Power Operation 100 Power Operation

Event Text

OFFSITE NOTIFICATION DUE TO INADVERTENT SEWAGE DISCHARGE

"On [Thursday], 4/21/2011, at 1405 [EDT], Oconee Nuclear Station notified the South Carolina Department of Health and Environmental Control (SCDHEC) that sanitary sewage had been collected and inadvertently discharged without processing through the sanitary sewage system. The event was identified at 0730 [EDT] on 4/21/2011. The suspected cause is plumbing blockage. It is estimated that intermittent discharges over approximately three months resulted in a total discharge of approximately 4500 gallons. The Oconee NRC Senior Resident Inspector was notified. This event notification is being made pursuant to 10 CFR 50.72 (b)(2)(xi) due to notification of SCDHEC.

"Immediate corrective action was taken to isolate the affected portion of the sanitary sewage system.

"This event has no significance with respect to the health and safety of the public."

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Power Reactor Event Number: 46774
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MATTHEW MOG
HQ OPS Officer: VINCE KLCO
Notification Date: 04/21/2011
Notification Time: 19:16 [ET]
Event Date: 04/21/2011
Event Time: 16:01 [EDT]
Last Update Date: 04/21/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
WILLIAM COOK (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 90 Power Operation 0 Hot Standby

Event Text

MANUAL REACTOR TRIP DUE TO CIRCULATING WATER PUMPS OUT OF SERVICE

"A manual trip of Salem Unit 1 was initiated due to a loss of circulating water pumps from heavy grassing at the circulating water intake. All rods fully inserted on the trip and all systems responded as designed with decay heat being removed via the steam dump system. All Auxiliary Feed Water (AFW) pumps auto started as expected on low steam generator levels from the trip.

"During a period of heavy grassing with one circulating water pump out of service for maintenance and another out of service for water box cleaning, a third circulating water pump's screen stopped and this circulating water pump was emergency tripped. When this circulating water pump was emergency tripped, the adjacent circulating water pump received a large intake of grass and automatically tripped.

"The abnormal operating procedure provides guidance to trip the plant if less than three circulating water pumps are in service and power is above P-10. At this point the manual reactor trip was initiated.

"The crew entered EOP-TRIP-1, appropriately transitioned to EOP-TRlP-2 and stabilized the plant at no load conditions.

"Salem Unit 1 is currently in mode 3. Reactor Coolant System temperature is 547F with pressure at 2235 psig. All ECCS and ESF Systems are available. Salem Unit 2 is currently defueled in a planned refueling outage and there is no impact to Salem Unit 2.

"No personnel injuries have occurred as a result of the trip.

"This event is reportable per 10CFR50.72(b)(3)(iv)(A) due to the auto start of the AFW pumps.

"This event is reportable per 10CFR50.72(b)(2)(iv)(B) due to the manual reactor trip."

The plant is aligned with a normal electrical line-up from offsite power sources.

The Licensee has notified the NRC Resident Inspector. The Licensee will notify Lower Alloways Creek Township and the States of New Jersey and Delaware.

* * * UPDATE FROM MATTHEW MOG TO VINCE KLCO ON 4/21/2011 AT 2241 EDT * * *

"During the post-trip data review for the manual reactor trip that occurred on April 21, 2011 at 1601 [EDT], 2 additional automatic Auxiliary Feedwater (AFW) pump start signals were identified. Operators were controlling AFW level to maintain steam generator levels within the band required by the emergency operating procedures. At approximately 1615 [EDT] the 13 steam generator level had cleared the low level setpoint but subsequently dipped below the low level setpoint at 1623 [EDT]. At approximately 1640 [EDT], the 14 steam generator had recovered above the low level setpoint and subsequently dipped below the low level setpoint. The Unit 1 reactor had been previously tripped at 1601 [EDT] and all AFW pumps had automatically started. The 13 turbine driven AFW pump was stopped at approximately 1625 [EDT]. The two motor driven AFW pumps continued to run throughout this event. Low level in one steam generator generates an automatic start of the motor driven AFW pumps and is reportable per 10CFR50.72(b)(3)(iv)(A)."

The licensee notified the NRC Resident Inspector and will notify Lower Alloways Creek Township and the States of New Jersey and Delaware.

Notified the R1DO (Cook).

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Power Reactor Event Number: 46775
Facility: GINNA
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: DAN DEAN
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 04/21/2011
Notification Time: 19:32 [ET]
Event Date: 04/21/2011
Event Time: 17:00 [EDT]
Last Update Date: 04/21/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
WILLIAM COOK (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation

Event Text

POTENTIAL INADVERTANT ACTIVATION OF ONE EMERGENCY SIREN

"On April 20, 2011, several hours after a severe lightning storm in the early morning hours, RE Ginna Nuclear Power Plant received a report that a siren may have activated. There was no specific location provided in the report. A review of the siren computer history showed no indication of any siren activation during that time frame. During the daily silent test of the siren system, one siren was determined to have failed due to loss of its AC power.

"During an inspection of the siren on April 21, 2011, it was reported that the siren appeared to have been struck by lightning. A number of electronic components in the siren had to be replaced and as a result the technicians were unable to determine if the siren had activated. As such. there is a potential that the siren may have been the source of the initial report. The siren has been tested and returned to service.

"The NRC Resident Inspector was notified by the licensee."

The licensee notified the Public Utilities Commission and Wayne and Monroe Counties.

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Thursday, March 29, 2012