Event Notification Report for July 10, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/09/2001 - 07/10/2001
EVENT NUMBERS
38126381273812838129
Power Reactor
Event Number: 38126
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: TERRY ARNETT
HQ OPS Officer: FANGIE JONES
Region: 1 State: CT
Unit: [] [] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: TERRY ARNETT
HQ OPS Officer: FANGIE JONES
Notification Date: 07/10/2001
Notification Time: 16:47 [ET]
Event Date: 07/10/2001
Event Time: 16:11 [EDT]
Last Update Date: 07/10/2001
Notification Time: 16:47 [ET]
Event Date: 07/10/2001
Event Time: 16:11 [EDT]
Last Update Date: 07/10/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
ANTHONY DIMITRIADIS (R1)
ANTHONY DIMITRIADIS (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 100 | Power Operation | 99 | Power Operation |
PLANT SHUTDOWN REQUIRED DUE TO FAILED CONTAINMENT LEAK RATE TEST
The licensee was conducting normal technical specification surveillance of containment leak rate and determined that the personnel access airlock has failed the surveillance. The plant commenced a technical specification required reactor shutdown to Mode 3 at 1611 EDT on 7/10/01. The licensee will remain in Mode 3 until the airlock is repaired.
The licensee has notified the NRC Resident Inspector and the State of Connecticut.
The licensee was conducting normal technical specification surveillance of containment leak rate and determined that the personnel access airlock has failed the surveillance. The plant commenced a technical specification required reactor shutdown to Mode 3 at 1611 EDT on 7/10/01. The licensee will remain in Mode 3 until the airlock is repaired.
The licensee has notified the NRC Resident Inspector and the State of Connecticut.
Hospital
Event Number: 38127
Rep Org: ST. LUKES MEDICAL CENTER
Licensee: ST. LUKES MEDICAL CENTER
Region: 3
City: MILWAUKEE State: WI
County:
License #: 48-01338-01
Agreement: N
Docket:
NRC Notified By: DOUGLAS SIMPKIN
HQ OPS Officer: FANGIE JONES
Licensee: ST. LUKES MEDICAL CENTER
Region: 3
City: MILWAUKEE State: WI
County:
License #: 48-01338-01
Agreement: N
Docket:
NRC Notified By: DOUGLAS SIMPKIN
HQ OPS Officer: FANGIE JONES
Notification Date: 07/10/2001
Notification Time: 17:33 [ET]
Event Date: 07/10/2001
Event Time: 14:30 [CDT]
Last Update Date: 07/10/2001
Notification Time: 17:33 [ET]
Event Date: 07/10/2001
Event Time: 14:30 [CDT]
Last Update Date: 07/10/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
35.33 - MED MISADMINISTRATION
10 CFR Section:
35.33 - MED MISADMINISTRATION
Person (Organization):
DAVID HILLS (R3)
ERIC LEEDS (NMSS)
DAVID HILLS (R3)
ERIC LEEDS (NMSS)
MEDICAL MISADMINISTRATION INVOLVING TREATMENT TO WRONG SITE
There were 2 patients prepared for treatment with a gamma knife. The wrong treatment package was used for the first patient. There were 4 of 8 shots administered to the wrong site before it was discovered that the wrong package was being used. The patient received approximately 13 gray over a short period to a small area. The consequences of the exposure are not known at this time and are being investigated and the patient's progress will be followed for some time. The patient received the correct treatment subsequently. The attending physician has been notified and the patient will be informed tomorrow.
There is a review and evaluation of procedures on going to determine how to insure this event is not repeated.
There were 2 patients prepared for treatment with a gamma knife. The wrong treatment package was used for the first patient. There were 4 of 8 shots administered to the wrong site before it was discovered that the wrong package was being used. The patient received approximately 13 gray over a short period to a small area. The consequences of the exposure are not known at this time and are being investigated and the patient's progress will be followed for some time. The patient received the correct treatment subsequently. The attending physician has been notified and the patient will be informed tomorrow.
There is a review and evaluation of procedures on going to determine how to insure this event is not repeated.
Fuel Cycle Facility
Event Number: 38128
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: ERIC SPAETH
HQ OPS Officer: FANGIE JONES
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: ERIC SPAETH
HQ OPS Officer: FANGIE JONES
Notification Date: 07/10/2001
Notification Time: 20:56 [ET]
Event Date: 07/10/2001
Event Time: 09:10 [EDT]
Last Update Date: 07/10/2001
Notification Time: 20:56 [ET]
Event Date: 07/10/2001
Event Time: 09:10 [EDT]
Last Update Date: 07/10/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
DAVID HILLS (R3)
ERIC LEEDS (NMSS)
DAVID HILLS (R3)
ERIC LEEDS (NMSS)
24 HOUR REPORT - NRC BULLETIN 91-01
The following text is a portion of a facsimile received from PORTSMOUTH:
At 0910 on 07/10/2001 it was identified that control #5 of NCSA-0705_076.A03 was not being maintained for two filter press plates covered in plastic. NCSA-0705_076.A03 requires that no inadvertent containers that could contain greater than 2.5 liters of solution be permitted in any areas in which uranium bearing solution could be accumulated in the inadvertent container. The loose plastic wrapped on the filter press plates had the potential to deform into a container that would exceed the maximum criteria identified in the NCSA. This constitutes a loss of one control (geometry) of the double contingency control principle identified in NCSA-0705_076.A03. No fissile material leaked in the area while the plastic wrap was present.
NCSA-0705_076.A03 compliance was reported restored at 1010 hours.
SAFETY SIGNIFICANCE OF EVENTS:
The safety significance is low because at the time of the event there was no uranium bearing material present that could leak into the inadvertent container. The area in question is designated an 'Inadvertent Container Area' due to the presence of the Complexing Hand table. However. the Hand table is not currently in operation. The next nearest fissile material operation is Microfiltration which is currently in operation, but is more than 15 feet from the location of the plastic wrap in question. Nevertheless, the presence of an inadvertent container at that location is a violation of NCS controls and one leg of the double contingency principle described in NCSE-0705_076.E03.
POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO[S] OF HOW CRITICALITY COULD OCCUR):
For a criticality to occur, the following events would be required: The complexing Hand table would have to be in operation and be processing uranium bearing liquid with an unknown or high concentration of uranium. Then a leak in this system must occur such that an unsafe amount of liquid sprays (presumably under pressure) from the Hand table system onto the plastic wrap in question. The liquid would then have to collect and deform the plastic wrap such that more than 2.5 liters collects to a depth greater than 1.5 inches forming an unsafe geometry.
CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.):
Inadvertent containers are controlled based upon volume (2.5 liters maximum) or geometry (1.5 inches in depth or 4 inches in diameter. Flexible material (e.g., plastic wrap) is specifically controlled such that solution cannot pool to a depth grater than 1.5 inches,
ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS LIMIT AND % WORST CASE OF CRITICAL MASS):
No uranium bearing material was involved in this event. There were no leaks of uranium bearing material in the area while the inadvertent container was present. The event involves the presence of an unsafe geometry container that could collect solution in the event of a spill.
NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION OF THE FAILURES OR DEFICIENCIES:
Loose plastic wrap placed over filter press plates in an inadvertent Container Area was not configured or secured such that it cannot be deformed into an inadvertent container with an unsafe accumulation potential. This is a violation of control #5 of NCSA-0705_076.A03. Use of Inadvertent Containers
CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED:
Requirements of an NCS Anomalous condition entered. At the direction of an NCS engineer, the condition was corrected.
Portsmouth personnel notified the NRC Resident Inspector.
The following text is a portion of a facsimile received from PORTSMOUTH:
At 0910 on 07/10/2001 it was identified that control #5 of NCSA-0705_076.A03 was not being maintained for two filter press plates covered in plastic. NCSA-0705_076.A03 requires that no inadvertent containers that could contain greater than 2.5 liters of solution be permitted in any areas in which uranium bearing solution could be accumulated in the inadvertent container. The loose plastic wrapped on the filter press plates had the potential to deform into a container that would exceed the maximum criteria identified in the NCSA. This constitutes a loss of one control (geometry) of the double contingency control principle identified in NCSA-0705_076.A03. No fissile material leaked in the area while the plastic wrap was present.
NCSA-0705_076.A03 compliance was reported restored at 1010 hours.
SAFETY SIGNIFICANCE OF EVENTS:
The safety significance is low because at the time of the event there was no uranium bearing material present that could leak into the inadvertent container. The area in question is designated an 'Inadvertent Container Area' due to the presence of the Complexing Hand table. However. the Hand table is not currently in operation. The next nearest fissile material operation is Microfiltration which is currently in operation, but is more than 15 feet from the location of the plastic wrap in question. Nevertheless, the presence of an inadvertent container at that location is a violation of NCS controls and one leg of the double contingency principle described in NCSE-0705_076.E03.
POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO[S] OF HOW CRITICALITY COULD OCCUR):
For a criticality to occur, the following events would be required: The complexing Hand table would have to be in operation and be processing uranium bearing liquid with an unknown or high concentration of uranium. Then a leak in this system must occur such that an unsafe amount of liquid sprays (presumably under pressure) from the Hand table system onto the plastic wrap in question. The liquid would then have to collect and deform the plastic wrap such that more than 2.5 liters collects to a depth greater than 1.5 inches forming an unsafe geometry.
CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.):
Inadvertent containers are controlled based upon volume (2.5 liters maximum) or geometry (1.5 inches in depth or 4 inches in diameter. Flexible material (e.g., plastic wrap) is specifically controlled such that solution cannot pool to a depth grater than 1.5 inches,
ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS LIMIT AND % WORST CASE OF CRITICAL MASS):
No uranium bearing material was involved in this event. There were no leaks of uranium bearing material in the area while the inadvertent container was present. The event involves the presence of an unsafe geometry container that could collect solution in the event of a spill.
NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION OF THE FAILURES OR DEFICIENCIES:
Loose plastic wrap placed over filter press plates in an inadvertent Container Area was not configured or secured such that it cannot be deformed into an inadvertent container with an unsafe accumulation potential. This is a violation of control #5 of NCSA-0705_076.A03. Use of Inadvertent Containers
CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED:
Requirements of an NCS Anomalous condition entered. At the direction of an NCS engineer, the condition was corrected.
Portsmouth personnel notified the NRC Resident Inspector.
Power Reactor
Event Number: 38129
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: BRAD ELLISON
HQ OPS Officer: FANGIE JONES
Region: 3 State: MN
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: BRAD ELLISON
HQ OPS Officer: FANGIE JONES
Notification Date: 07/11/2001
Notification Time: 14:47 [ET]
Event Date: 07/10/2001
Event Time: 15:30 [CDT]
Last Update Date: 07/11/2001
Notification Time: 14:47 [ET]
Event Date: 07/10/2001
Event Time: 15:30 [CDT]
Last Update Date: 07/11/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
DAVID HILLS (R3)
DAVID HILLS (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 |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
16 OF 17 FLOOD PANELS FOUND TO BE NON-FUNCTIONAL
"A second quarter 2001 inspection per Procedure PM-3586-10 identified miscellaneous deficiencies (e.g., deteriorated gasket material, obstructions, deficient bolting) with flood panels such that 16 of 17 are considered non-functional. There is no current operability concern due to the river level and the analyzed need for both snow melt and heavy rains to require the use of these panels. We are currently working on a plan to correct deficiencies. Reference: USAR Section 2.4.3.5"
The licensee noted that this report was due yesterday. However, the licensee determined this afternoon (7/11/2001) that a report should have been made.
The licensee intends to notify the NRC Resident Inspector.
"A second quarter 2001 inspection per Procedure PM-3586-10 identified miscellaneous deficiencies (e.g., deteriorated gasket material, obstructions, deficient bolting) with flood panels such that 16 of 17 are considered non-functional. There is no current operability concern due to the river level and the analyzed need for both snow melt and heavy rains to require the use of these panels. We are currently working on a plan to correct deficiencies. Reference: USAR Section 2.4.3.5"
The licensee noted that this report was due yesterday. However, the licensee determined this afternoon (7/11/2001) that a report should have been made.
The licensee intends to notify the NRC Resident Inspector.