Event Notification Report for May 17, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/16/2003 - 05/17/2003
Other Nuclear Material
Event Number: 39861
Rep Org: ILLINOIS DEPARTMENT OF NUC. SAFETY
Licensee: NELSON LEASING
Region: 3
City: WHEELING State: IL
County:
License #: IL-01828-01
Agreement: Y
Docket:
NRC Notified By: JOE KLINGER
HQ OPS Officer: ARLON COSTA
Licensee: NELSON LEASING
Region: 3
City: WHEELING State: IL
County:
License #: IL-01828-01
Agreement: Y
Docket:
NRC Notified By: JOE KLINGER
HQ OPS Officer: ARLON COSTA
Notification Date: 05/19/2003
Notification Time: 16:30 [ET]
Event Date: 05/17/2003
Event Time: 18:45 [CDT]
Last Update Date: 05/19/2003
Notification Time: 16:30 [ET]
Event Date: 05/17/2003
Event Time: 18:45 [CDT]
Last Update Date: 05/19/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
ANNE MARIE STONE (R3)
ANNE MARIE STONE (R3)
AGREEMENT STATE REPORT - STOLEN TROXLER MOISTURE DENSITY GAUGE
"On Saturday, May 17, at approximately 1845 hrs a Troxler moisture/density gauge Model # 3440, serial no. 21948, was stolen from a licensee's locked truck while it was parked in a parking lot at 105 N. Des Plaines, in Chicago. The licensee's technician stopped on his way home from work at this location and noticed, upon returning to his vehicle, that the rear hard cover, locked hatch had been broken into. Upon further inspection, the technician noticed that the locked and chained nuclear gauge had been taken. Immediately following this discovery, the Chicago Police Department was notified along with the licensee's Radiation Safety Officer/President, Scott R. Nelson. Scott Nelson mobilized to the crime scene. En route he notified the Illinois Department of Nuclear Safety's Radiological Duty Officer, Larry Haskell. Upon arrival at the scene, Mr. Nelson informed the police of the gauges operations, potential health issues and completed filing a police report. It apparently was evident that the truck was broken into. The police report number is HJ-369907. The station is Area 4."
"On Saturday, May 17, at approximately 1845 hrs a Troxler moisture/density gauge Model # 3440, serial no. 21948, was stolen from a licensee's locked truck while it was parked in a parking lot at 105 N. Des Plaines, in Chicago. The licensee's technician stopped on his way home from work at this location and noticed, upon returning to his vehicle, that the rear hard cover, locked hatch had been broken into. Upon further inspection, the technician noticed that the locked and chained nuclear gauge had been taken. Immediately following this discovery, the Chicago Police Department was notified along with the licensee's Radiation Safety Officer/President, Scott R. Nelson. Scott Nelson mobilized to the crime scene. En route he notified the Illinois Department of Nuclear Safety's Radiological Duty Officer, Larry Haskell. Upon arrival at the scene, Mr. Nelson informed the police of the gauges operations, potential health issues and completed filing a police report. It apparently was evident that the truck was broken into. The police report number is HJ-369907. The station is Area 4."
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 39855
Facility: COOK
Region: 3 State: MI
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRIAN BATES
HQ OPS Officer: ARLON COSTA
Region: 3 State: MI
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRIAN BATES
HQ OPS Officer: ARLON COSTA
Notification Date: 05/18/2003
Notification Time: 04:27 [ET]
Event Date: 05/17/2003
Event Time: 22:05 [EDT]
Last Update Date: 06/10/2003
Notification Time: 04:27 [ET]
Event Date: 05/17/2003
Event Time: 22:05 [EDT]
Last Update Date: 06/10/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
SONIA BURGESS (R3)
MICHAEL CASE (NRR)
SONIA BURGESS (R3)
MICHAEL CASE (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Refueling Shutdown | 0 | Refueling Shutdown |
DEGRADED CONDITION DUE TO CRACK INDICATIONS ON VESSEL HEAD
"At 18:00 on 5/15/03, craze cracking indications were found on a Reactor Pressure Vessel Head Penetration. At 22:05 on 5/17/03, it was determined that this condition was reportable as a prompt eight-hour report under 10 CFR 50.72(b)(3)(ii)(A).
"During the Unit 2 reactor head inspection, five small, shallow indications were found on the inside diameter of penetration #74. The indications are closely spaced and are approximately 3/8 inch below the J-groove weld region. Initial calculations showed a crack depth of 0.117 inches. All of the indications are bounded within an area that is one inch wide by 2.6 inches high. There was no through-wall leakage and the reactor coolant pressure boundary remains intact.
"These indications were previously identified during the last refueling outage in February 2002. They were evaluated as acceptable to leave in service for a full cycle at that time, and they have not shown any significant growth since then.
"The industry guidance on projected flaw growth rates has been revised since these indications were discovered in 2002. As a result, the new projections for these indications result in less than a full fuel cycle before reaching the limit for remaining in service. Therefore, repairs will be needed. Current plans are to perform an excavation of the affected area, under existing code guidance."
The NRC Resident Inspector has been notified.
* * * UPDATE AT 0811 EDT ON 6/10/03 FROM HACKMAN TO CROUCH * * *
The following information was obtained from the licensee via facsimile:
"Following evaluation of the condition reported in EN# 39855, it has been determined that the craze cracking indications in penetration 74 of the Unit 2 Reactor Pressure Vessel Head do not represent a seriously degraded principal safety barrier of the nuclear power plant.
"As stated in the initial ENS report, the flaw was on the inside diameter of the penetration approximately 3/8 inch below the J-groove weld. The flaw evaluation concluded that no growth occurred from the last inspection and at least one effective full power year of operation would pass prior to the crack growing to an unacceptable depth (75 percent through wall). Accordingly, Cook Nuclear Plant withdraws EN# 39855.
"Additionally, as part of the withdrawal, a correction to the information contained in EN# 39855 is being made. EN# 39855 stated that repairs were required this refueling outage due to changes in the industry guidance on projected flaw growth rates. The flaw evaluation performed for the 2002 refueling outage was based on growth charts in the flaw evaluation handbook (WCAP 14118, Rev 5) using the depth of the cracking without considering the length. The flaw evaluation for this outage was conservatively calculated considering both depth and length, which resulted in less than a cycle of operation prior to growing 75 percent through wall. The decision to repair the penetration allows Unit 2 to operate for a full fuel cycle. There was no change in industry guidance that compelled a repair for this outage."
The crack was repaired during the current refueling outage. The longest crack length identified was 2.1 inches with a depth of .117 inches in the penetration inside diameter of 2.75 inches. Wall thickness of penetration is nominally 0.625 inches.
The NRC Resident Inspector was notified of the retraction by the licensee.
Notified R3DO (Hills) and NRR EO (Reis).
"At 18:00 on 5/15/03, craze cracking indications were found on a Reactor Pressure Vessel Head Penetration. At 22:05 on 5/17/03, it was determined that this condition was reportable as a prompt eight-hour report under 10 CFR 50.72(b)(3)(ii)(A).
"During the Unit 2 reactor head inspection, five small, shallow indications were found on the inside diameter of penetration #74. The indications are closely spaced and are approximately 3/8 inch below the J-groove weld region. Initial calculations showed a crack depth of 0.117 inches. All of the indications are bounded within an area that is one inch wide by 2.6 inches high. There was no through-wall leakage and the reactor coolant pressure boundary remains intact.
"These indications were previously identified during the last refueling outage in February 2002. They were evaluated as acceptable to leave in service for a full cycle at that time, and they have not shown any significant growth since then.
"The industry guidance on projected flaw growth rates has been revised since these indications were discovered in 2002. As a result, the new projections for these indications result in less than a full fuel cycle before reaching the limit for remaining in service. Therefore, repairs will be needed. Current plans are to perform an excavation of the affected area, under existing code guidance."
The NRC Resident Inspector has been notified.
* * * UPDATE AT 0811 EDT ON 6/10/03 FROM HACKMAN TO CROUCH * * *
The following information was obtained from the licensee via facsimile:
"Following evaluation of the condition reported in EN# 39855, it has been determined that the craze cracking indications in penetration 74 of the Unit 2 Reactor Pressure Vessel Head do not represent a seriously degraded principal safety barrier of the nuclear power plant.
"As stated in the initial ENS report, the flaw was on the inside diameter of the penetration approximately 3/8 inch below the J-groove weld. The flaw evaluation concluded that no growth occurred from the last inspection and at least one effective full power year of operation would pass prior to the crack growing to an unacceptable depth (75 percent through wall). Accordingly, Cook Nuclear Plant withdraws EN# 39855.
"Additionally, as part of the withdrawal, a correction to the information contained in EN# 39855 is being made. EN# 39855 stated that repairs were required this refueling outage due to changes in the industry guidance on projected flaw growth rates. The flaw evaluation performed for the 2002 refueling outage was based on growth charts in the flaw evaluation handbook (WCAP 14118, Rev 5) using the depth of the cracking without considering the length. The flaw evaluation for this outage was conservatively calculated considering both depth and length, which resulted in less than a cycle of operation prior to growing 75 percent through wall. The decision to repair the penetration allows Unit 2 to operate for a full fuel cycle. There was no change in industry guidance that compelled a repair for this outage."
The crack was repaired during the current refueling outage. The longest crack length identified was 2.1 inches with a depth of .117 inches in the penetration inside diameter of 2.75 inches. Wall thickness of penetration is nominally 0.625 inches.
The NRC Resident Inspector was notified of the retraction by the licensee.
Notified R3DO (Hills) and NRR EO (Reis).