Event Notification Report for March 13, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/12/2001 - 03/13/2001
Other Nuclear Material
Event Number: 37832
Rep Org: PENNSYLVANIA STATE UNIVERSITY
Licensee: PENNSYLVANIA STATE UNIVERSITY
Region: 1
City: UNIVERSITY PARK State: PA
County:
License #:
Agreement: N
Docket:
NRC Notified By: ERIC BOELDT
HQ OPS Officer: FANGIE JONES
Licensee: PENNSYLVANIA STATE UNIVERSITY
Region: 1
City: UNIVERSITY PARK State: PA
County:
License #:
Agreement: N
Docket:
NRC Notified By: ERIC BOELDT
HQ OPS Officer: FANGIE JONES
Notification Date: 03/13/2001
Notification Time: 11:39 [ET]
Event Date: 03/13/2001
Event Time: 00:00 [EST]
Last Update Date: 03/13/2001
Notification Time: 11:39 [ET]
Event Date: 03/13/2001
Event Time: 00:00 [EST]
Last Update Date: 03/13/2001
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):
PETE ESELGROTH (R1)
JOHN HICKEY (NMSS)
PETE ESELGROTH (R1)
JOHN HICKEY (NMSS)
MISSING TRITIUM TUBE FROM EXIT SIGN
During removal of tritium exit signs from the campus, one of the signs in the Academic Projects Building was found to be missing one of four tubes of tritium. The tube originally contained a maximum of 6 Curies in April, 1983 and 2.3 Curies today, it is not considered a hazard to the public. The licensee does not know if the tube was missing when the sign was installed or has been removed since. The sign was originally in a different building. The sign is a Everglow Safety Sign, model #710-1 and serial #14867. The licensee will contact NRC Region 1 (Thompson).
During removal of tritium exit signs from the campus, one of the signs in the Academic Projects Building was found to be missing one of four tubes of tritium. The tube originally contained a maximum of 6 Curies in April, 1983 and 2.3 Curies today, it is not considered a hazard to the public. The licensee does not know if the tube was missing when the sign was installed or has been removed since. The sign was originally in a different building. The sign is a Everglow Safety Sign, model #710-1 and serial #14867. The licensee will contact NRC Region 1 (Thompson).
Fuel Cycle Facility
Event Number: 37833
Facility: PORTSMOUTH GASEOUS DIFFUSION PLANT
Region: 3 State: OH
Unit: [] [] []
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
NRC Notified By: JOE HALCOMB
HQ OPS Officer: STEVE SANDIN
Region: 3 State: OH
Unit: [] [] []
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
NRC Notified By: JOE HALCOMB
HQ OPS Officer: STEVE SANDIN
Notification Date: 03/13/2001
Notification Time: 17:18 [ET]
Event Date: 03/13/2001
Event Time: 14:15 [EST]
Last Update Date: 03/13/2001
Notification Time: 17:18 [ET]
Event Date: 03/13/2001
Event Time: 14:15 [EST]
Last Update Date: 03/13/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
76.120(c)(2) - SAFETY EQUIPMENT FAILURE
10 CFR Section:
76.120(c)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
GEOFFREY WRIGHT (R3)
JOHN HICKEY (NMSS)
GEOFFREY WRIGHT (R3)
JOHN HICKEY (NMSS)
SAFETY EQUIPMENT FAILURE RELATED TO STEAM LEAK ON AUTOCLAVE #3
"At 1415 hours on 3/13/01 after questioning by the Senior NRC Resident Inspector concerning a steam leak on autoclave (A/C) #3 in the X-344, it was discovered that an as found reading (pressure decay test) was not performed on A/C #3 prior to the Maintenance department replacing the o-ring during the evening of 3/12/01. Without performing the pressure decay test there is no possible method to verify if the o-ring would have performed its safety function. This test would have been used to determine if an observed steam leak on A/C #3 that occurred at 1050 hours during the early phase of an applicable heating mode on 3/12/01 would have been classified as a Safety Equipment Failure per the plant's NRC Event reporting Criteria.
"Since the As Found Reading (pressure decay test) was not performed, the failure of the o-ring as observed by the steam leak on A/C #3 in the X-344 building, is being reported as a 'Safety Equipment Failure' per table 6.9.1 section J of the SAR."
Operations has informed the NRC resident inspector and the DOE site representative.
"At 1415 hours on 3/13/01 after questioning by the Senior NRC Resident Inspector concerning a steam leak on autoclave (A/C) #3 in the X-344, it was discovered that an as found reading (pressure decay test) was not performed on A/C #3 prior to the Maintenance department replacing the o-ring during the evening of 3/12/01. Without performing the pressure decay test there is no possible method to verify if the o-ring would have performed its safety function. This test would have been used to determine if an observed steam leak on A/C #3 that occurred at 1050 hours during the early phase of an applicable heating mode on 3/12/01 would have been classified as a Safety Equipment Failure per the plant's NRC Event reporting Criteria.
"Since the As Found Reading (pressure decay test) was not performed, the failure of the o-ring as observed by the steam leak on A/C #3 in the X-344 building, is being reported as a 'Safety Equipment Failure' per table 6.9.1 section J of the SAR."
Operations has informed the NRC resident inspector and the DOE site representative.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 37834
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: JOHN HODDY
HQ OPS Officer: STEVE SANDIN
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: JOHN HODDY
HQ OPS Officer: STEVE SANDIN
Notification Date: 03/13/2001
Notification Time: 18:07 [ET]
Event Date: 03/13/2001
Event Time: 14:45 [EST]
Last Update Date: 05/11/2001
Notification Time: 18:07 [ET]
Event Date: 03/13/2001
Event Time: 14:45 [EST]
Last Update Date: 05/11/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
PETE ESELGROTH (R1)
PETE ESELGROTH (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 |
HIGH PRESSURE COOLANT INJECTION (HPCI) DECLARED INOPERABLE DUE EXCESSIVE MOISTURE IN LUBE OIL
"At approximately 1100 hours, operators observed oil puddled around the HPCI lube oil sump vents and observed a slightly higher than normal sump level. The system engineer was consulted and recommended lowering sump level and sampling for moisture.
"At 1445, water was observed in the sample taken from the HPCI lube oil sump. The amount of water observed (approximately 1/2 gallon) was such that compliance with a maximum recommended lube oil moisture content of 5% could not be assured. A conservative decision was made to declare HPCI inoperable. The system is inoperable but available. The plant is in a 7-day LCO per T.S. 3.5.C."
The licensee informed the NRC resident inspector.
***** RETRACTION RECEIVED AT 0933 ON 05/11/01 FROM ART ZAREMBA TO LEIGH TROCINE *****
The initial notification regarded the HPCI system being declared inoperable because of an unknown quantity of water in the lube oil sump. The licensee subsequently drained, cleaned, and refilled the lube oil sump and determined exactly how much water intrusion had occurred. The licensee's engineering evaluation determined that the technical requirements were not exceeded (based on the acceptance criteria for the percentage of water in the system) and that the HPCI system was in fact operable. Therefore, the licensee is retracting this event notification.
The licensee notified the NRC resident inspector. The NRC operations officer notified the R1DO (Cook).
"At approximately 1100 hours, operators observed oil puddled around the HPCI lube oil sump vents and observed a slightly higher than normal sump level. The system engineer was consulted and recommended lowering sump level and sampling for moisture.
"At 1445, water was observed in the sample taken from the HPCI lube oil sump. The amount of water observed (approximately 1/2 gallon) was such that compliance with a maximum recommended lube oil moisture content of 5% could not be assured. A conservative decision was made to declare HPCI inoperable. The system is inoperable but available. The plant is in a 7-day LCO per T.S. 3.5.C."
The licensee informed the NRC resident inspector.
***** RETRACTION RECEIVED AT 0933 ON 05/11/01 FROM ART ZAREMBA TO LEIGH TROCINE *****
The initial notification regarded the HPCI system being declared inoperable because of an unknown quantity of water in the lube oil sump. The licensee subsequently drained, cleaned, and refilled the lube oil sump and determined exactly how much water intrusion had occurred. The licensee's engineering evaluation determined that the technical requirements were not exceeded (based on the acceptance criteria for the percentage of water in the system) and that the HPCI system was in fact operable. Therefore, the licensee is retracting this event notification.
The licensee notified the NRC resident inspector. The NRC operations officer notified the R1DO (Cook).