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> July 1
Event Notification Report for July 1, 2005
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U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
06/30/2005 - 07/01/2005
** EVENT NUMBERS **
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| General Information or Other |
Event Number: 41806 |
Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: ENERGIZER
Region: 1
City: ASHEBORO State: NC
County:
License #: 076-1755-0G
Agreement: Y
Docket:
NRC Notified By: J. MARION EADDY III
HQ OPS Officer: PETE SNYDER
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Notification Date: 06/28/2005
Notification Time: 17:06 [ET]
Event Date: 06/28/2005
Event Time: [EDT]
Last Update Date: 06/28/2005
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Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
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Person (Organization):
JOHN WHITE (R1)
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Event Text
AGREEMENT STATE REPORT LOST / MISSING SOURCE
The State provided the following information via facsimile:
"The North Carolina Radioactive Materials branch was made aware of the loss [of] a Po-210 static elimination source from the Energizer facility in Asheboro, NC today.
"The agency interviewed the Staff Environmental Coordinator this afternoon via telephone. The information for the missing source is as follows:
Isotope: Po-210
Activity: 20 millicuries as of 3 March 2004 (decay corrected to 2.38 mCi at time of loss)
Make: NRD LLC
Model: P-2031-1000
Serial No.: A2DP844
"The licensee continues to search for the missing source. North Carolina Radioactive Materials Branch continues to monitor the situation and will dispatch health physicists to investigate as necessary." |
| Power Reactor |
Event Number: 41813 |
Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAVID VINEYARD
HQ OPS Officer: JOHN MacKINNON
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Notification Date: 06/30/2005
Notification Time: 11:52 [ET]
Event Date: 06/30/2005
Event Time: 08:00 [EDT]
Last Update Date: 06/30/2005
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Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
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Person (Organization):
BRIAN BONSER (R2)
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| 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
ALERT NOTIFICATION RADIO TRANSMITTER DISCOVERED INOPERABLE
"During daily maintenance check of alert notification siren system, a siren technician discovered that the radio transmitter used to communicate with the sirens was not available. Investigation revealed that an encoder that utilizes a T1 phone line to send signals from a siren encoder to the transmitter had failed. This failure produced a signal to key the transmitter. After the transmitter is keyed for approximately 15 seconds the transmitter will lock out and therefore not be available for use. Since the transmitter was unavailable this rendered all offsite sirens inoperable. This notification is made under 10CFR50.72(b) because of a significant loss off offsite public notification capability.
"This failure was promptly diagnosed, corrected, and the system tested satisfactorily within approximately 62 minutes from time of discovery of 0800 Eastern Time.
"The tone alert radio portion of the alert notification system was available for notification during this event."
The NRC Resident Inspector and Burke County was notified of this event by the licensee. |
| Power Reactor |
Event Number: 41814 |
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: JAMES HURCHALLA
HQ OPS Officer: JOHN KNOKE
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Notification Date: 06/30/2005
Notification Time: 16:16 [ET]
Event Date: 06/30/2005
Event Time: 09:30 [EDT]
Last Update Date: 06/30/2005
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Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
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Person (Organization):
BRIAN BONSER (R2)
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| 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
NON-LICENSED SUPERVISOR FAILED FITNESS FOR DUTY TEST FOR DRUGS
A non-licensed employee supervisor had a confirmed positive for illegal drugs during a random fitness-for-duty tests. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details |
| Power Reactor |
Event Number: 41815 |
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: NICHOLAS AVRALOTOS
HQ OPS Officer: JOHN KNOKE
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Notification Date: 06/30/2005
Notification Time: 19:49 [ET]
Event Date: 06/30/2005
Event Time: 19:29 [EDT]
Last Update Date: 06/30/2005
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Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
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Person (Organization):
JOHN WHITE (R1DO)
CYNTHIA CARPENTER (NRR)
MELVYN LEACH (IRD)
STEINDURF (FEMA)
CRAIG (DHS)
B.HOLIAN (R1)
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| 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
PRIMARY CONTAINMENT INOPERABLE DUE TO SMALL CRACK IN TORUS
The licensee has determined that the small weep hole (x in shape) crack is in a position which requires the plant to initiate a normal shutdown to cold shutdown conditions. The crack is located about 5 feet below the waterline and just below the HPCI exhaust pipe discharge. Due to the location of this crack the licensee's engineering staff showed via analysis that it would be prudent to restrict the number of thermal cycles the crack receives. The plant is in a 1 hour Technical Specification LCO shutdown action statement. At 19:50 the licensee commenced the Technical Specification shutdown to cold shutdown conditions.
As an additional item, one of the four Emergency Diesel Generators was deemed inoperable at the time of the event, and continues to be in a LCO action statement.
The licensee made notifications to the State and local agencies, and will notify the NRC Resident Inspector.
*** UPDATE ON 06/30/05 AT 22:24 EDT FROM T. PAGE TO J. KNOKE ***
"With the plant operating at 100% on June 27, 2005 during RCIC Torus Suction piping inspection per ST-24H, inspectors discovered a TORUS leak in the vicinity of a TORUS Support between Bays A and P. The leak was quantified as slight weepage with streaking and a small puddle below leak. This was captured in the plant corrective action program on CR-JAF-2005-02593. Subsequent non destructive examination determined that the leakage was from a small through wall crack. The condition was discussed with the NRC Staff at that time. Initial evaluation at that time determined that there was reasonable expectation of operability, an Operational Decision Making Instruction (ODMI) was prepared and implemented to monitor the leakage while further engineering evaluation was conducted. On June 30,2005 further engineering analysis determined that operability of the primary containment was not assured and at 19:29 on June 30, 2005 the Shift Manager declared Primary Containment Inoperable and entered Technical Specification LCO 3.6.1.1 Condition A, Primary Containment Inoperable, and declared an Unusual Event under EAL 9.1.2. Preparations were made for a reactor shutdown and the shutdown was commenced at 20:00.
"At the time of the event the A Train of EDGs was out of service for a planned maintenance LCO. At this time the NRC Resident has been informed."
The A Train EDG is not available nor operable if needed.
The R1DO (White) and NRR EO (Carpenter) have been notified. |
| Power Reactor |
Event Number: 41816 |
Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: PATRICK FALLON
HQ OPS Officer: ARLON COSTA
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Notification Date: 07/01/2005
Notification Time: 00:08 [ET]
Event Date: 06/30/2005
Event Time: 19:31 [EDT]
Last Update Date: 07/01/2005
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Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
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Person (Organization):
JAMNES CAMERON (R3)
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| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 2 |
N |
N |
0 |
Cold Shutdown |
0 |
Cold Shutdown |
Event Text
UNANALYZED CONDITION RELATED TO THE STANDBY FEEDWATER PUMPS AND CONTROL CIRCUITS
"During an NRC Triennial Fire Protection Audit the Inspector identified a fuse coordination issue between 130DC supply circuit and breaker trip circuit fuses for the Standby Feedwater (SBFW) Pump switchgear. The coordination ratio was found to be too low to support requirements for fire related safe shutdown equipment under Generic Letter 81-12. Impacted equipment is SBFW Pumps A & B and control circuits required for Appendix R Alternative Shutdown auxiliary equipment. This event is being reported as an unanalyzed condition that significantly degraded plant safety under 10CFR50.72(b)(3)(ii)(B).
"The impacted equipment has been declared inoperable and a team is currently working on design changes to change fuse sizes for the breaker trip circuit/supply circuit to meet the requirements of Generic Letter 81-12."
The licensee notified the NRC Resident Inspector. |
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