| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
06/16/2004 - 06/17/2004 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 40807 | Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: FLOWSERVE US INC
Region: 1
City: RALEIGH State: NC
County:
License #: 092-0121-1
Agreement: Y
Docket:
NRC Notified By: JAMES D. ALBRIGHT
HQ OPS Officer: ARLON COSTA | Notification Date: 06/11/2004
Notification Time: 14:36 [ET]
Event Date: 06/10/2004
Event Time: 15:00 [EDT]
Last Update Date: 06/11/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
CHRISTOPHER CAHILL (R1)
JOHN GREEVES (NMSS)
| Event Text AGREEMENT STATE NC - NOTIFICATION OF EQUIPMENT FAILURE DUE TO METAL FATIGUE
"The licensee [Flowserve US Inc.] performing Booth IR has an automatic IR setup that uses source switches to stop the extension of the source for IR operations. The source switch at the end of the guide tube failed and the source [Ir-192] extended beyond the end of the guide tube and got stuck. The licensee contacted Amersham (the manufacturer of the camera) for advice. By following Amersham's suggestions the licensee was able to remotely retract the source back into the guide tube, and from there to retract the source back into the camera in the fully shielded position. The licensee intends to have the source leak tested as soon as possible and said they would submit a complete report within 30 days."
No one was injured or overexposed during this incident. |
| General Information or Other | Event Number: 40812 | Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: ADCO SERVICES
Region: 3
City: TINLEY PARK State: IL
County:
License #: IL-0134701
Agreement: Y
Docket:
NRC Notified By: DAREN PERRERO
HQ OPS Officer: MIKE RIPLEY | Notification Date: 06/14/2004
Notification Time: 10:13 [ET]
Event Date: 06/14/2004
Event Time: [CDT]
Last Update Date: 06/14/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
PATRICK LOUDEN (R3)
ROBERTO TORRES (NMSS)
JIM WHITNEY (TAS)
| Event Text ILLINOIS AGREEMENT STATE REPORT - SOURCE MISSING IN SHIPMENT
One of five packages being shipped on 6/3/04 from Honeywell Corporation in Phoenix, AZ did not arrive at the licensee's facility as scheduled on 6/4/04. The package consisted of a 7-10 gallon steel drum containing 10 Curies of Pm-147 as sealed sources. The sources were removed from industrial gauging devices being disposed of.
* * * UPDATE ON 6/14/04 AT 1542 EDT FROM D. PERRERO TO A. COSTA * * *
Fed-Ex located the missing shipment in Pittsburgh and arrangements are being made to forward it to ADCO Services Inc, at Tinley Park, IL. Notified NMSS (Essig), R3DO(Louden) and TAS (Whitney). |
| Power Reactor | Event Number: 40820 | Facility: NORTH ANNA
Region: 2 State: VA
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: MIKE GUILL
HQ OPS Officer: JEFF ROTTON | Notification Date: 06/16/2004
Notification Time: 10:11 [ET]
Event Date: 06/16/2004
Event Time: 09:45 [EDT]
Last Update Date: 06/16/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
ROBERT HAAG (R2)
|
| 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 LOSS OF EMERGENCY ASSESSMENT CAPABILITY
"At 0945 on 6/16/04, the uninterruptible power supply to the Technical Support Center was removed from service for pre-planned maintenance. As a result, the plant Safety Parameter Display System (SPDS) and the Technical Support Center (TSC) computer system are inoperable. This event is a major loss of emergency assessment capability and is reportable under 10CFR50.72(b)(3)(xiii). The expected duration of the maintenance is between 4 and 8 hours."
This pre-planned maintenance also made the ERDS inoperable.
The Licensee has notified the NRC Resident Inspector.
* * * UPDATE ON 06/16/04 @ 1707 BY MIKE GUILL TO C GOULD * * * UPDATE
SPDS and the TSC computer were returned to service at 17:04 on 06/16/04.
The NRC Resident Inspector will be returned to service. |
| Power Reactor | Event Number: 40821 | Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: STEVEN BENEDICT
HQ OPS Officer: CHAUNCEY GOULD | Notification Date: 06/16/2004
Notification Time: 15:52 [ET]
Event Date: 06/16/2004
Event Time: 14:00 [EDT]
Last Update Date: 06/16/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
| Person (Organization):
PATRICK LOUDEN (R3)
|
| 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 24 HOUR NOTIFICATION OF PLANT EXCEEDING ITS POWER LIMIT
At 1400 hours on June 16, 2004, it was confirmed that the plant had operated in excess of its licensed maximum power limit of 3758 megawatts thermal by about two (2) megawatts thermal. The power limit was determined to have been exceeded due to a feedwater temperature RTD being replaced on May 24, 2004, without having installed a matching transmitter. This error caused a non-conservative input into the core power calculation resulting in a small error. The error allowed the power to be about two (2) megawatts above the limit while indicating that it was within requirements. This condition occurred during two periods on 06/14/04 and 06/15/04. On 06/14/04 the first occurrence lasted for approximately 7 hours. The second occurrence lasted for 16 hours commencing on 06/14/04 and terminating on 06/15/04. The licensee identified this condition on 06/15/04 @ 1130 and the condition was corrected on 06/15/04 @ 1315.
This notification is being submitted in accordance with PNPP Operating License Condition 2.F, as a potential violation of the Maximum Power Level specified in PNPP Operating License
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 40822 | Facility: POINT BEACH
Region: 3 State: WI
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: MIKE MEYER
HQ OPS Officer: CHAUNCEY GOULD | Notification Date: 06/16/2004
Notification Time: 18:27 [ET]
Event Date: 06/16/2004
Event Time: 14:59 [CDT]
Last Update Date: 06/16/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
PATRICK LOUDEN (R3)
HERB BERKOW (NRR)
TOM ANDREWS (IRO)
|
| 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 EMERGENCY SIRENS INADVERTENTLY ACTIVATED
During a weekly growl test of the Point Beach Nuclear Plant (PBNP) emergency sirens on June 16, 2004, the Manitowoc County sirens were inadvertently activated at 1459 CDT. PBNP is investigating the cause of this event. The sirens were activated for approximately one minute. As a result of the inadvertent actuation, the Village of Mishicot, the City of Two Rivers, Manitowoc County, and Kewaunee County, Wisconsin were notified. There was no impact to the plant as a result of the activation of the sirens. The alert notification system remains operable. This report is being submitted in accordance with 10 CFR 50.72(b)(2)(xi) as a result of the notifications made.
The Resident Inspector was notified |
| Power Reactor | Event Number: 40823 | Facility: SALEM
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RICHARD DeSANCTIS
HQ OPS Officer: DICK JOLLIFFE | Notification Date: 06/17/2004
Notification Time: 03:38 [ET]
Event Date: 06/17/2004
Event Time: 00:22 [EDT]
Last Update Date: 06/17/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
ANTHONY DIMITRIADIS (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 48 | Power Operation | Event Text TECH SPEC REQUIRED PLANT SHUTDOWN DUE TO EMERGENCY CORE COOLING SYSTEM INOPERABLE
At 0338 EDT on 06/17/04, the licensee reported that at 0321 EDT on 06/14/04, the licensee identified that the Salem Unit 1 #12 charging pump was declared inoperable due to an inoperable discharge check valve. Repairs to the check valve are not expected to be completed by 0321 EDT on 06/17/04. At 0022 EDT on 06/17/04, the licensee commenced a shutdown of Salem Unit 1 from 100% power to comply with Tech Spec 3.5.2, Emergency Core Cooling System Inoperable (72 hour LCO). #15 service water pump and #11 auxiliary building exhaust fan have been declared inoperable for scheduled maintenance.
There were no personnel injuries or radiological occurrences associated with this event.
This event has no effect on Salem Unit 2 which is at 100% power.
The licensee notified the NRC Resident Inspector and plans to notify State and Local officials. | |