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Event Notification Report for November 2, 2006

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
11/01/2006 - 11/02/2006

** EVENT NUMBERS **


42935 42953 42954 42955

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General Information or Other Event Number: 42935
Rep Org: SC DIV OF HEALTH & ENV CONTROL
Licensee: MCLEOD REGIONAL MEDICAL CENTER
Region: 1
City: FLORENCE State: SC
County:
License #: 139
Agreement: Y
Docket:
NRC Notified By: MELINDA BRADSHAW
HQ OPS Officer: BILL GOTT
Notification Date: 10/26/2006
Notification Time: 17:34 [ET]
Event Date: 05/25/2006
Event Time: [EDT]
Last Update Date: 10/26/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JAMES NOGGLE (R1)
ROBERT PIERSON (NMSS)

Event Text

AGREEMENT STATE REPORT

The State provided the following information via facsimile:

"The SC Department of Health and Environmental Control was notified on Wednesday, October 18, 2006, by letter dated October 9, 2006, that a possible Medical Event involving a fetus took place in May 2006. According to a letter from the RSO at McLeod Regional Medical Center, a female patient was dosed with 14 microcuries of Iodine 131 on May 24, 2006, and 15 millicuries of Technetium 99m on May 25 as a prelude to a Nuclear Medicine Thyroid Therapy Ablation. The patient denied the possibility of pregnancy and signed an informed consent specifically addressing pregnancy and fetal exposure. This was following an explanation by the Radiologist of the exact procedure. A dose of Iodine 131 in the amount of 14.8 millicuries was then given the patient for the thyroid ablation.

"The patient's OB/GYN physician notified the radiology department as of October 9, 2006, that the patient is now approximately 32 to 34 weeks pregnant. A calculation is being done to determine the exposure dose to the fetus and fetal thyroid. This information is to be sent to the Department once completed. This is all the information available on this situation and determination has not been made that it is a medical event. The investigation is still ongoing. The incident will be updated once additional material is received."


A "Medical Event" may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.

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Power Reactor Event Number: 42953
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: DAVID LYNCH
HQ OPS Officer: STEVE SANDIN
Notification Date: 11/01/2006
Notification Time: 15:30 [ET]
Event Date: 11/01/2006
Event Time: 09:08 [EST]
Last Update Date: 11/01/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JOHN WHITE (R1)

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

Event Text

POTENTIAL DEGRADATION IN THE OFFSITE EMERGENCY SIREN NOTIFICATION SYSTEM

"A potential loss of the ENS Siren System occurred on 11/1/2006 due to a degradation of the Radio Transmitter System. A successful siren silent test was performed at 0925 on 11/1/2006 to verify full siren operation. The system was returned to full functionality at 1127 on 11/1/2006 by restoring normal transmission capability."

The licensee will inform Calvert, Dorchester and St. Mary's Counties and has informed the NRC Resident Inspector.

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Power Reactor Event Number: 42954
Facility: PALISADES
Region: 3 State: MI
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: DAN MALONE
HQ OPS Officer: STEVE SANDIN
Notification Date: 11/01/2006
Notification Time: 18:40 [ET]
Event Date: 11/01/2006
Event Time: 18:05 [EST]
Last Update Date: 11/01/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
MONTE PHILLIPS (R3)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 80 Power Operation

Event Text

UNIT SHUTDOWN REQUIRED DUE TO SERVICE WATER LEAK INVOLVING A CONTAINMENT AIR COOLER

"On November 1, 2006, at 1530 hours EST, a service water leak was identified in the cooling coil of Containment Air Cooler VHX-4. While this containment air cooler has no safety function for containment cooling, the breached cooling coil represents an inoperable containment boundary.

"In accordance with Technical Specification (T.S.) 3.6.1.B1&2, a shutdown was initiated at 1805 hours EST, following expiration of the completion time of 1 hour for restoring containment to operable per T.S. 3.6.1.A.1."

The licensee anticipates having the unit in mode 3 Hot Standby by 2205 hours EST, at which time an evaluation involving extent of condition for the required repairs will be performed. The leak is characterized at this time as 300 ml/minute.

The licensee informed the NRC Resident Inspector.

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Power Reactor Event Number: 42955
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: SHAWN ZANDER
HQ OPS Officer: STEVE SANDIN
Notification Date: 11/01/2006
Notification Time: 19:10 [ET]
Event Date: 11/01/2006
Event Time: 18:37 [EST]
Last Update Date: 11/01/2006
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(iv)(A) - ECCS INJECTION
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
CAROLYN EVANS (R2)
STUART RICHARDS (NRR)
MELVYN LEACH (IRD)
TOM BARNES (DHS)
TODD KUZIA (FEMA)

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

Event Text

UNIT 2 DECLARED AN UNUSUAL EVENT DUE TO LOSS OF OFFSITE POWER TO THE 4KV EMERGENCY BUSES

At 1823 EST, Unit 2 was manually scrammed due to a loss of offsite power from the Startup Auxiliary Transformer to both 4KV Emergency (E) buses. Both Emergency Diesel Generators (EDGs) 3&4 autostarted and re-energized the affected electrical buses. At 1823 EST, an Unusual Event was declared based on EAL 06.01.01, "Inability to power either 4KV E bus from offsite power."

Unit 2 is currently stable in mode 3, Hot Shutdown, with MSIVs closed and HPCI controlling pressure and RPV Water Level. All control rods fully inserted following the manual reactor scram. The licensee determined that no emergency facilities will be activated and that no offsite assistance is needed at this time.

The licensee informed both state and local agencies and will inform the NRC Resident Inspector.

* * * UPDATE PROVIDED BY JOEL LEVINER TO JEFF ROTTON AT 2214 EST ON 11/01/06 * * *

"On 11/01/06 at approximately 18:23 (EST) Brunswick Unit 2 experienced a loss of the unit's Startup Auxiliary Transformer and a loss of reactor forced circulation. A manual reactor scram was performed as required by station Abnormal Operating Procedures. Due to the loss of the Startup Auxiliary Transformer and subsequent manual reactor scram, a loss of Offsite Power resulted to the unit's power buses when unit shutdown was completed. All control rods properly inserted when the manual reactor scram was performed. All four site emergency diesels started and diesels 3 and 4 are supplying the Unit 2 emergency buses. Reactor water level reached low level 1 (LL1) and low level 2 (LL2) as result of the reactor scram and loss of offsite power. The LL1 signal resulted in Group 2 (floor and equipment drain isolation valves), Group 6 (monitoring and sampling isolation valves) and Group a (shutdown cooling isolation valves) isolation signals. All low level 1 isolations occurred as designed. The LL2 resulted in a Reactor Core Isolation Cooling (RCIC) system actuation, High Pressure Coolant Injection (HPCI) system actuation, Group 3 (reactor water cleanup valves) isolation signal, a secondary containment isolation signal, a Standby Gas Treatment (SBGT) initiation signal, a Control Room Emergency Ventilation (CREV) initiation signal, and an Alternate Rod Insertion (ARI) actuation signal. All isolation and actuations occurred as designed with the exception the CREV initiation and ARI actuation. CREV initiation and ARI actuations were performed by manual actions. The failure of the CREV and ARI initiation/actuations are under investigation. The RCIC and HPCI systems were used to restore reactor water level to the normal operation band. Reactor vessel pressure is being controlled in the normal band with manual operation of Safety Relief Valves (SRV), and HPCI/RCIC in pressure control mode. The Main Steam Isolation Valves (MSIVs) (Group 1) and the drywell pneumatic isolation valves (Group 10) closed on the loss of power. The plant is a stable condition. Troubleshooting activities are in progress to determine the cause of the event.

"At 1910, the NRC was previously notified of the Unusual Event declaration.

"Initial Safety Significance Evaluation: The safety significance of this event is minimal and Unit 2 is in a stable condition. All control rods properly inserted when the manual scram was performed. Plant safety systems responded as required with the exception of the CREV and ARI systems which did not automatically initiate but functioned properly when manually actuated. All four emergency diesels started and Unit 2 diesels 3 and 4 are supplying the Unit 2 emergency buses. Reactor pressure and level are being controlled per procedure, with HPCI and RCIC. Actions are in progress to re-establish off site power supply to emergency buses 3 and 4 via backfeed through the Unit Auxiliary Transformer (UAT).

"Corrective Actions: Actions are in progress to re-establish offsite power supply to emergency buses 3 and 4 via backfeed through the UAT. Investigations are in progress to determine the cause of the SAT failure and the failure of CREV and ARI to auto-initiate."

The licensee has notified the NRC Resident Inspector and the State and local emergency agencies.

Update provided also added the following reportable notifications due to the event: 10CFR50.72(b)(2) (iv)(A) and(iv)(B) and 10CFR50.72(b)(3)(iv)(A). Notified R2DO (Evans).

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Friday, March 30, 2012