| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
09/26/2003 - 09/29/2003 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 40193 | Rep Org: ARIZONA RADIATION REGULATORY AGENCY
Licensee: ARVISO ENGINEERING INC
Region: 4
City: YUMA State: AZ
County:
License #:
Agreement: Y
Docket:
NRC Notified By: AUBREY GODWIN
HQ OPS Officer: RICH LAURA | Notification Date: 09/23/2003
Notification Time: 13:00 [ET]
Event Date: 09/23/2003
Event Time: 10:00 [MST]
Last Update Date: 09/23/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG PICK (R4)
JOHN HICKEY (NMSS)
| Event Text ARIZONA AGREEMENT STATE REPORT FOR DAMAGED GAUGE
"On 23 September 2003, the licensee notified the Agency that a Humboldt Scientific moisture/density gauge, serial number 1136, had been run over by a roller at a construction site in the vicinity of interstate 8 and Avenue 3E in Yuma. The source was in the backscatter position at the time; however, the licensee was able to retract the source into its shielded position. A leak test is being performed. The Agency will continue to investigate. The gauge contains approximately 10 millicuries of cesium 137 and 40 millicuries of americium-beryllium. The NRC and Governor's office are being notified of this event. |
| Power Reactor | Event Number: 40198 | Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [3] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: TODD STRAYER
HQ OPS Officer: RICH LAURA | Notification Date: 09/26/2003
Notification Time: 01:25 [ET]
Event Date: 09/25/2003
Event Time: [EDT]
Last Update Date: 09/26/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
TODD JACKSON (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | | 3 | N | N | 0 | Refueling | 0 | Refueling | Event Text INITIATION OF A TECHNICAL SPECIFICATION REQUIRED SHUTDOWN AT PEACH BOTTOM 2
"On 09/25/03 @ 2210, while restoring reactor vessel instrumentation to service on Unit 3, an invalid ECCS actuation, (reactor vessel lo-lo-lo) occurred which caused all four (4) EDG to automatically start. All eight (8) 4 KV buses remained supplied from offsite sources. The Unit 3 ECCS pump auto starts were previously defeated per plant procedure and were not required to be operable per Tech Specs. The invalid ECCS initiation signal caused the offsite power Loss-of-Power instrumentation setpoints to transfer to the degraded voltage LOCA setpoints. With the degraded voltage LOCA setpoints initiated, the 4 KV E-bus fast transfer capability on a degraded voltage-NON-LOCA condition is defeated. With the inability to fast transfer the 4 KV E-buses on a degraded voltage NON-LOCA condition, both offsite sources are inoperable. Prior to restoring the reactor vessel level instrumentation, the E-2 diesel generator was inoperable. With both offsite source.; and one EDG inoperable, LCO 3.8.1 Required Action H.1 requires an entry into LCO 3.0.3 for Unit 2.
With Unit 3 in MODE 5, LCO 3.0.3 is not applicable.
"After one (1) hour, actions were taken to initiate a plant shutdown per LCO 3.0.3. No negative reactivity was added as the preparations were administrative in nature. At 09/26/03 @ 0006, the invalid ECCS initiation was removed. And all offsite Loss-of-Power instrumentation has been returned to OPERABLE status.
"Following the automatic start of all four (4) EDGs, E-1, E-3, and E-4 were successfully shutdown per plant procedures. E-2 could not be shutdown per plant procedures and was shutdown locally. The cause of the inability to shutdown E-2 per plant procedures is under investigation. E-2 EDG remains inoperable."
The NRC Resident Inspector was notified by the licensee. |
| Power Reactor | Event Number: 40200 | Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN RODEN
HQ OPS Officer: JOHN MacKINNON | Notification Date: 09/26/2003
Notification Time: 16:31 [ET]
Event Date: 09/26/2003
Event Time: 08:50 [EDT]
Last Update Date: 09/26/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
| Person (Organization):
CAUDLE JULIAN (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text GREATER THAN 1 PERCENT OF STEAM GENERATORS 1,2 & 4 TUBES INSPECTED INDICATE THAT THE INSPECTED TUBES REQUIRE PLUGGING.
"At 0850 EST on September 26, 2003, with Watts Bar Nuclear Plant Unit 1 defueled, steam generator inspections were being performed in accordance with Technical Specification (TS) 5.7.2.12, 'Steam Generator Tube Surveillance Program.' The results of the inspections performed on Steam Generator Numbers 1, 2, and 4 indicated that greater than 1% of the inspected tubes require plugging. Based on TS 5.7.2.12, this determination results in the classification of C-3. The current inspection results do not meet the criteria specified for steam generator tube degradation in Revision 2 of NUREG 1022, Event Reporting Guidelines 10 CFR 50.72 and 10 CFR 50.73. However, for classification C-3, WBN TS Table 5.7.2.12-1, 'SG Tube Inspection Supplemental Sampling Requirements, 'requires that the results of the inspection be reported under 10 CFR 50.72. At this time, the submittal of the Licensee Event Report in accordance with 10 CFR 50.73 is not planned."
The NRC Resident Inspector was notified of this event by the licensee. |
| Power Reactor | Event Number: 40202 | Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JOHN TWAROG
HQ OPS Officer: STEVE SANDIN | Notification Date: 09/27/2003
Notification Time: 10:52 [ET]
Event Date: 09/27/2003
Event Time: 07:40 [EDT]
Last Update Date: 09/27/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
TODD JACKSON (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 15 | Power Operation | Event Text TECH SPEC REQUIRED SHUTDOWN DUE TO RCS LEAKAGE INCREASE GREATER THAN 2 GPM
"Initiated Plant shutdown required by the Technical Specifications. TS 3.6.C.1.b limits unidentified primary containment leakage to a 2 gpm increase in any 24 hour period. Leakage increased by approximately 3.6 gpm."
The licensee will inform the NRC Resident inspector. |
| Power Reactor | Event Number: 40203 | Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [1] [2] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: WAYNE AHO
HQ OPS Officer: JOHN MacKINNON | Notification Date: 09/27/2003
Notification Time: 16:08 [ET]
Event Date: 09/27/2003
Event Time: 15:08 [CDT]
Last Update Date: 09/27/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
GREG PICK (R4)
|
| 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 | N | 0 | Refueling | 0 | Refueling | Event Text SAFETY PARAMETER DISPLAY SYSTEM (SPDS)
"Unit 2 will be down powering inverter 2Y-26 for pre-planned maintenance during the Unit 2 refueling outage. This will result in the loss of power to the Safety Parameter Display System (SPDS). This constitutes a major loss of emergency assessment capability for both Unit 1 and Unit 2. The expected SPDS outage duration is 2 hours."
State and the NRC Resident Inspector will be notified of this event by the Licensee. |
| Power Reactor | Event Number: 40204 | Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [1] [ ] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: BLAKE HOQUE
HQ OPS Officer: MIKE RIPLEY | Notification Date: 09/28/2003
Notification Time: 03:02 [ET]
Event Date: 09/28/2003
Event Time: 00:13 [CDT]
Last Update Date: 09/28/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
GREG PICK (R4)
|
| 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 OFFSITE NOTIFICATION DUE TO REPORT OF EMERGENCY SIREN ACTUATION
"At 00:13 on 9/28/03, the Unit 1 Control Room received an offsite call from the Pope County 911 office stating that two local individuals had reported the actuation of emergency sirens in the Russellville area. The Arkansas Department of Health, who controls the actuation of the sirens, was contacted; but they had no indication of the sirens alarming at the time that they were notified. The actuation of the sirens has not been confirmed.
"This report is being made in accordance with SAF 4.1 'News Release or Government Agency Notification' and
10CFR50.72(b)(2)(xi) since there was a notification of state/county agencies of inadvertent actuation of part of the public notification system."
The licensee will inform the state and has informed the NRC Resident Inspector. | |