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Event Notification Report for April 24, 2007

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/23/2007 - 04/24/2007

** EVENT NUMBERS **


43307 43313 43315

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General Information or Other Event Number: 43307
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: CARDINAL HEALTH 200 INC.
Region: 4
City: EL PASO State: TX
County:
License #: 02407
Agreement: Y
Docket:
NRC Notified By: LATISCHA HANSON
HQ OPS Officer: JASON KOZAL
Notification Date: 04/18/2007
Notification Time: 13:05 [ET]
Event Date: 03/12/2007
Event Time: [CDT]
Last Update Date: 04/18/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RUSSELL BYWATER (R4)
GREG MORELL (FSME)

Event Text

AGREEMENT STATE REPORT - IRRADIATOR WATER CONDUCTIVITY GREATER THAN LIMIT

"On March 13, 2007, the Agency was notified by the licensee that their source pool conductivity had exceeded 100 microsiemens per centimeter (uS/cm). The facility had completed a source replacement the week of February 21, 2007 and had regenerated their ion exchange resin on March 9, 2007. On March 11, 2007, the water conductivity was found to be 269.1 uS/cm. The licensee conducted an investigation and found that the system used to control the regeneration of their ion exchange resins, had failed to operate properly due to a power outage. The purification resins were replaced and the conductivity was reported to be 69.34 uS/cm on March 30, 2007 and 1 uS/cm on April 4, 2007. The licensee has upgraded the control system and is measuring conductivity twice a day to prevent a reoccurrence."

Texas report number - I - 8402

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Power Reactor Event Number: 43313
Facility: VOGTLE
Region: 2 State: GA
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MARK SLIVKA
HQ OPS Officer: STEVE SANDIN
Notification Date: 04/23/2007
Notification Time: 11:25 [ET]
Event Date: 04/23/2007
Event Time: 10:24 [EDT]
Last Update Date: 04/23/2007
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):
JOEL MUNDAY (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 A/R Y 53 Power Operation 0 Hot Standby

Event Text

AUTOMATIC REACTOR TRIP DUE TO GENERATOR GROUND RELAY ACTUATION

"Vogtle Unit 2 tripped from 53% power due to a turbine trip /P9 reactor trip RPS actuation during power ascension following completion of refueling outage 2R12. Initial investigation indicates that a generator neutral ground relay actuated causing an automatic main generator turbine trip. No visual damage is apparent on any plant equipment.

"All systems responded as expected. Both motor driven auxiliary feedwater pumps and the turbine driven started on lo-lo steam generator level and AMSAC.

"The NRC Resident Inspector was notified."

All control rods fully inserted upon RPS actuation, the atmospheric relief valves lifted momentarily and reseated as expected, and no safety valves lifted. After the trip, steam generator level was being maintained with auxiliary feed pumps and steam was being dumped to the condenser. The plant was placed in the normal shutdown electrical lineup.

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Power Reactor Event Number: 43315
Facility: LIMERICK
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: NED DENNIN
HQ OPS Officer: STEVE SANDIN
Notification Date: 04/24/2007
Notification Time: 04:04 [ET]
Event Date: 04/24/2007
Event Time: 02:10 [EDT]
Last Update Date: 04/24/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(2)(iv)(A) - ECCS INJECTION
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
JAMES TRAPP (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 A/R Y 100 Power Operation 0 Hot Shutdown

Event Text

AUTOMATIC REACTOR SCRAM WITH ECCS INJECTION ON LOWERING REACTOR VESSEL WATER LEVEL

"Limerick Unit 2 automatically shutdown on low reactor water level (+12.5 inches) at 0210 on 4/24/07. The cause is under investigation at this time.

"All control rods inserted as required. HPCI and RCIC initiated, injected and restored reactor water level. Lowest reactor water level noted was -73 inches.

"Primary containment isolation signals on +12.5 inches and -38 inches occurred. All isolations completed as required."

"The plant is currently in hot shutdown maintaining normal reactor level with feedwater in service."

Approximately 16000 gallons was injected in 4 minutes. There was no indication of RCS leakage. The licensee is investigating whether a feedwater runback had occurred. No SRVs lifted with the highest pressure observed at 1050 psi. The main condenser remains in service for decay heat removal. All EDGs are available, if needed.

The licensee informed the NRC Resident Inspector and will inform both the State and Local authorities.

Page Last Reviewed/Updated Thursday, March 29, 2012
Thursday, March 29, 2012