Event Notification Report for July 16, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/15/2001 - 07/16/2001
Power Reactor
Event Number: 38143
Facility: MCGUIRE
Region: 2 State: NC
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BILL MASON
HQ OPS Officer: STEVE SANDIN
Region: 2 State: NC
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BILL MASON
HQ OPS Officer: STEVE SANDIN
Notification Date: 07/16/2001
Notification Time: 11:20 [ET]
Event Date: 07/16/2001
Event Time: 09:58 [EDT]
Last Update Date: 07/16/2001
Notification Time: 11:20 [ET]
Event Date: 07/16/2001
Event Time: 09:58 [EDT]
Last Update Date: 07/16/2001
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
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
JAY HENSON (R2)
JAY HENSON (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP DURING MAINTENANCE
"The channel 2 of the 2B streamline pressure was in test. The channel 3 of the 2B streamline pressure was taken out of service (transmitter). This resulted in meeting the logic for main streamline isolation (2/3). This resulted in a reactor trip on overtemperature delta temperature. Auxiliary feedwater autostarted due to decreasing steam generator water levels. This event started as a result of preventative maintenance of steam generator pressure 2B channel 2."
All rods fully inserted. Unit 2 is stable in mode 3 at 2235 psig and 556 degrees F with decay heat removal bypassing the main streamline isolation valves to the main condenser. Efforts are underway to restore main feedwater and secure the operating auxiliary feedwater pumps (both electrical and the turbine driven). During the transient all three primary PORVs lifted and reseated while secondary safety valves also cycled. There is no known primary-to-secondary tube leakage. All emergency equipment is available, if needed. The licensee informed the NRC resident inspector and does not plan a press release.
"The channel 2 of the 2B streamline pressure was in test. The channel 3 of the 2B streamline pressure was taken out of service (transmitter). This resulted in meeting the logic for main streamline isolation (2/3). This resulted in a reactor trip on overtemperature delta temperature. Auxiliary feedwater autostarted due to decreasing steam generator water levels. This event started as a result of preventative maintenance of steam generator pressure 2B channel 2."
All rods fully inserted. Unit 2 is stable in mode 3 at 2235 psig and 556 degrees F with decay heat removal bypassing the main streamline isolation valves to the main condenser. Efforts are underway to restore main feedwater and secure the operating auxiliary feedwater pumps (both electrical and the turbine driven). During the transient all three primary PORVs lifted and reseated while secondary safety valves also cycled. There is no known primary-to-secondary tube leakage. All emergency equipment is available, if needed. The licensee informed the NRC resident inspector and does not plan a press release.
Power Reactor
Event Number: 38144
Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DORMAN
HQ OPS Officer: CHAUNCEY GOULD
Region: 2 State: GA
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DORMAN
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 07/16/2001
Notification Time: 14:51 [ET]
Event Date: 07/16/2001
Event Time: 10:33 [EDT]
Last Update Date: 07/19/2001
Notification Time: 14:51 [ET]
Event Date: 07/16/2001
Event Time: 10:33 [EDT]
Last Update Date: 07/19/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JAY HENSON (R2)
JAY HENSON (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 |
PLANT HAD A MAJOR LOSS OF OFFSITE PUBLIC ALERTING SIREN SYSTEM
While performing the weekly siren test, 35 of 47 sirens failed to respond. The weekly test was performed at 1033 EDT. Preliminary investigation suggests a problem with the sirens electronic memory chip. Troubleshooting and repairs are in progress.
The NRC resident inspector has been notified.
***** UPDATE FROM JOHN C. WILLIAMS TO LEIGH TROCINE AT 1621 ON 07/19/01 *****
The following text is a portion of a facsimile received from the licensee:
"This is an Information Only follow-up notice to Event Notification #38144, submitted on 7-16-2001, regarding the loss of 35 out of 47 sirens in the Offsite Public Alerting Siren System."
"All sirens were tested and returned to service as of 1516 EDT on 7-18-2001. A vendor representative from Whelan Engineering Company has advised that cause of the problem was a software issue with a batch of 2020 logic control boards, revision E or prior, used in the siren controller. He further states that he knows of no other nuclear facilities that have these controller boards at this time."
The licensee notified the NRC resident inspector. The NRC operations officer notified the R2DO (Jay Henson).
While performing the weekly siren test, 35 of 47 sirens failed to respond. The weekly test was performed at 1033 EDT. Preliminary investigation suggests a problem with the sirens electronic memory chip. Troubleshooting and repairs are in progress.
The NRC resident inspector has been notified.
***** UPDATE FROM JOHN C. WILLIAMS TO LEIGH TROCINE AT 1621 ON 07/19/01 *****
The following text is a portion of a facsimile received from the licensee:
"This is an Information Only follow-up notice to Event Notification #38144, submitted on 7-16-2001, regarding the loss of 35 out of 47 sirens in the Offsite Public Alerting Siren System."
"All sirens were tested and returned to service as of 1516 EDT on 7-18-2001. A vendor representative from Whelan Engineering Company has advised that cause of the problem was a software issue with a batch of 2020 logic control boards, revision E or prior, used in the siren controller. He further states that he knows of no other nuclear facilities that have these controller boards at this time."
The licensee notified the NRC resident inspector. The NRC operations officer notified the R2DO (Jay Henson).
General Information or Other
Event Number: 38145
Rep Org: NORTECH ENVIRONMENTAL
Licensee: NORTECH ENVIRONMENTAL
Region: 4
City: FAIRBANKS State: AK
County:
License #:
Agreement: N
Docket:
NRC Notified By: CHEEK
HQ OPS Officer: CHAUNCEY GOULD
Licensee: NORTECH ENVIRONMENTAL
Region: 4
City: FAIRBANKS State: AK
County:
License #:
Agreement: N
Docket:
NRC Notified By: CHEEK
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 07/16/2001
Notification Time: 16:36 [ET]
Event Date: 07/16/2001
Event Time: 08:00 [YDT]
Last Update Date: 07/16/2001
Notification Time: 16:36 [ET]
Event Date: 07/16/2001
Event Time: 08:00 [YDT]
Last Update Date: 07/16/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
DAVID GRAVES (R4)
JOSEPHINE PICCONE (NMSS)
DAVID GRAVES (R4)
JOSEPHINE PICCONE (NMSS)
NORTECH ENVIRONMENTAL REPORTED THAT AN X-RAY FLUORESCENCE DEVICE WAS STOLEN FROM THEIR OFFICES
The device was stolen sometime this past weekend, but was just discovered this morning at 0800 YDT to be missing. The device was a Niton XL model 309 serial #U1002 containing 14 millicuries of cadmium-109 (serial #NR0853). This device was a hand held device used to analyze for lead in paint. The local police and Niton have been notified. The State will be notified.
The device was stolen sometime this past weekend, but was just discovered this morning at 0800 YDT to be missing. The device was a Niton XL model 309 serial #U1002 containing 14 millicuries of cadmium-109 (serial #NR0853). This device was a hand held device used to analyze for lead in paint. The local police and Niton have been notified. The State will be notified.