Event Notification Report for March 25, 1999
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/24/1999 - 03/25/1999
EVENT NUMBERS
36588355153551235513355083550935521
Power Reactor
Event Number: 36588
Facility: PERRY
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: STETSON
HQ OPS Officer: LEIGH TROCINE
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: STETSON
HQ OPS Officer: LEIGH TROCINE
Notification Date: 01/13/2000
Notification Time: 17:04 [ET]
Event Date: 03/25/1999
Event Time: 03:30 [EST]
Last Update Date: 02/03/2000
Notification Time: 17:04 [ET]
Event Date: 03/25/1999
Event Time: 03:30 [EST]
Last Update Date: 02/03/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(1)(ii)(B) - OUTSIDE DESIGN BASIS
10 CFR Section:
50.72(b)(1)(ii)(B) - OUTSIDE DESIGN BASIS
Person (Organization):
BRENT CLAYTON (R3)
BRENT CLAYTON (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 0 | Cold Shutdown |
DISCOVERY THAT A SINGLE PASSIVE FAILURE OF THE INCLINED FUEL TRANSFER SYSTEM FLAP VALVE MAY HAVE RESULTED IN A LOSS OF ECCS DURING A DESIGN BASIS LOCA (HISTORICAL EVENT)
The following text is a portion of a facsimile received from the licensee:
"With the Inclined Fuel Transfer System (IFTS) flange removed at power, a single passive failure of the IFTS flap valve may have resulted in a loss of Emergency Core Cooling System (ECCS) during a design basis Loss of Coolant Accident (LOCA). This was determined during an engineering review examining the effects on containment structural capability with the IFTS Blind Flange removed."
"An assumed single passive failure of the IFTS flap valve would have resulted in inventory loss from the upper containment pools with the IFTS gate removed. The postulated water inventory loss would reduce the inventory to less than required for the makeup to the suppression pool during a LOCA. Therefore, ECCS may not have met single failure criteria during the period when the IFTS Flange was removed at power."
"The IFTS flange was removed for approximately 3 days prior to the commencement of the seventh refueling outage. Administrative controls are in place to preclude removal of the IFTS flange at power until this issue is fully evaluated."
The licensee stated that this event was determined to be reportable approximately 10 minutes prior to the event notification.
The licensee notified the NRC resident inspector.
* * * UPDATE ON 02/03/00 AT 1312 BY STERLING SANFORD TAKEN BY STEVE SANDIN * * *
The licensee made an editorial correction to the event time to show 0330 hours instead of 1530 hours.
The licensee notified the NRC Resident Inspector. The NRC Operations Officer notified the R3DO Tony Vegel.
The following text is a portion of a facsimile received from the licensee:
"With the Inclined Fuel Transfer System (IFTS) flange removed at power, a single passive failure of the IFTS flap valve may have resulted in a loss of Emergency Core Cooling System (ECCS) during a design basis Loss of Coolant Accident (LOCA). This was determined during an engineering review examining the effects on containment structural capability with the IFTS Blind Flange removed."
"An assumed single passive failure of the IFTS flap valve would have resulted in inventory loss from the upper containment pools with the IFTS gate removed. The postulated water inventory loss would reduce the inventory to less than required for the makeup to the suppression pool during a LOCA. Therefore, ECCS may not have met single failure criteria during the period when the IFTS Flange was removed at power."
"The IFTS flange was removed for approximately 3 days prior to the commencement of the seventh refueling outage. Administrative controls are in place to preclude removal of the IFTS flange at power until this issue is fully evaluated."
The licensee stated that this event was determined to be reportable approximately 10 minutes prior to the event notification.
The licensee notified the NRC resident inspector.
* * * UPDATE ON 02/03/00 AT 1312 BY STERLING SANFORD TAKEN BY STEVE SANDIN * * *
The licensee made an editorial correction to the event time to show 0330 hours instead of 1530 hours.
The licensee notified the NRC Resident Inspector. The NRC Operations Officer notified the R3DO Tony Vegel.
Power Reactor
Event Number: 35515
Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: JOEY CLARK
HQ OPS Officer: FANGIE JONES
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: JOEY CLARK
HQ OPS Officer: FANGIE JONES
Notification Date: 03/25/1999
Notification Time: 21:11 [ET]
Event Date: 03/25/1999
Event Time: 16:40 [CST]
Last Update Date: 03/25/1999
Notification Time: 21:11 [ET]
Event Date: 03/25/1999
Event Time: 16:40 [CST]
Last Update Date: 03/25/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(ii) - ESF ACTUATION
10 CFR Section:
50.72(b)(2)(ii) - ESF ACTUATION
Person (Organization):
CHARLES CAIN (R4)
CHARLES CAIN (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 78 | Power Operation | 78 | Power Operation |
ESF ACTUATION RESULTING IN ISOLATION OF A DIVISION 2 VALVE
"An invalid ESF actuation resulted in the isolation of Division 2 primary containment isolation valve RHSAOV62 SUPPRESSION POOL CLEANUP (SPC) SYSTEM SUCTION.
"During outage preparation activities in the Reactor Building Dryer storage pool, level in the pool was inadvertently lowered approximately three and one-half inches, resulting in a non-ESF isolation signal from the division 2 dryer pool level indicator. The level change was caused by a siphon effect that was created through a vacuum hose being staged between the Dryer Pool and Refueling Cavity for pool cleanup.
"The lowering level was terminated upon identification and all systems responded as designed."
The siphon action was started during 'bump' testing of the vacuuming system during setup due to the differences in pool levels of about one foot. Work has been terminated until an investigation is completed and necessary changes to the work are made.
The licensee notified the NRC Resident Inspector.
"An invalid ESF actuation resulted in the isolation of Division 2 primary containment isolation valve RHSAOV62 SUPPRESSION POOL CLEANUP (SPC) SYSTEM SUCTION.
"During outage preparation activities in the Reactor Building Dryer storage pool, level in the pool was inadvertently lowered approximately three and one-half inches, resulting in a non-ESF isolation signal from the division 2 dryer pool level indicator. The level change was caused by a siphon effect that was created through a vacuum hose being staged between the Dryer Pool and Refueling Cavity for pool cleanup.
"The lowering level was terminated upon identification and all systems responded as designed."
The siphon action was started during 'bump' testing of the vacuuming system during setup due to the differences in pool levels of about one foot. Work has been terminated until an investigation is completed and necessary changes to the work are made.
The licensee notified the NRC Resident Inspector.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 35512
Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TOM BEAUDIN
HQ OPS Officer: FANGIE JONES
Region: 4 State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TOM BEAUDIN
HQ OPS Officer: FANGIE JONES
Notification Date: 03/25/1999
Notification Time: 17:37 [ET]
Event Date: 03/25/1999
Event Time: 16:04 [CST]
Last Update Date: 04/13/1999
Notification Time: 17:37 [ET]
Event Date: 03/25/1999
Event Time: 16:04 [CST]
Last Update Date: 04/13/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
Person (Organization):
CHARLES CAIN (R4)
CHARLES CAIN (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 |
PHYSICAL SECURITY REPORT
Unescorted access granted inappropriately to contract employee. Immediate compensatory measures taken upon discovery.
The licensee notified the NRC Resident Inspector.
Refer to the HOO Log for additional details.
*** UPDATE ON 04/12/99 @ 1418 BY HARRIS TO GOULD *** RETRACTION
THE LICENSEE IS RETRACTING THIS EVENT. REFER TO HOO LOG FOR ADDITIONAL INFORMATION.
THE RESIDENT INSPECTOR WILL BE NOTIFIED.
THE REG 4 RDO(SMITH) WAS NOTIFIED.
Unescorted access granted inappropriately to contract employee. Immediate compensatory measures taken upon discovery.
The licensee notified the NRC Resident Inspector.
Refer to the HOO Log for additional details.
*** UPDATE ON 04/12/99 @ 1418 BY HARRIS TO GOULD *** RETRACTION
THE LICENSEE IS RETRACTING THIS EVENT. REFER TO HOO LOG FOR ADDITIONAL INFORMATION.
THE RESIDENT INSPECTOR WILL BE NOTIFIED.
THE REG 4 RDO(SMITH) WAS NOTIFIED.
Fuel Cycle Facility
Event Number: 35513
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: J. B. HALCOMB
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: J. B. HALCOMB
HQ OPS Officer: FANGIE JONES
Notification Date: 03/25/1999
Notification Time: 18:16 [ET]
Event Date: 03/25/1999
Event Time: 10:03 [EST]
Last Update Date: 03/29/1999
Notification Time: 18:16 [ET]
Event Date: 03/25/1999
Event Time: 10:03 [EST]
Last Update Date: 03/29/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
MELVYN LEACH (R3)
ROBERT PIERSON (NMSS)
MELVYN LEACH (R3)
ROBERT PIERSON (NMSS)
VALID ACTUATION OF A 'Q' SAFETY SYSTEM
"At 1003 hours on March 25, 1999, during normal charging of cell 31-3-3 prior to placing onstream, an Operations
Front Line Manager was investigating a Cascade Automatic Data Processing smokehead alarm from this cell when a second smokehead alarmed. He than saw what appeared to be smoke above the Stage 6 area.
"All personnel in the area immediately evacuated, implemented the 'See & Flee' Procedure, activated the building recall system, and notified Emergency Response Forces. The cell was taken offstream and cell pressure was reduced below atmosphere.
"All airborne and surface contamination sample results were less than detectable and there was no release of
Hazardous/Radioactive material or Radioactive/Radiological contamination exposure as a result of this event."
The facility notified the NRC Resident Inspector and the DOE Site Manager.
* * * UPDATE 1112 3/29/1999 FROM VANDERPOOL TAKEN BY STRANSKY * * *
The original report was reissued with the following change to the third paragraph above:
"All airborne and surface contamination sample results were less than detectable, and there was no Radioactive/Radiological contamination exposure as a result of this event."
HOO notified R3DO (Ring).
"At 1003 hours on March 25, 1999, during normal charging of cell 31-3-3 prior to placing onstream, an Operations
Front Line Manager was investigating a Cascade Automatic Data Processing smokehead alarm from this cell when a second smokehead alarmed. He than saw what appeared to be smoke above the Stage 6 area.
"All personnel in the area immediately evacuated, implemented the 'See & Flee' Procedure, activated the building recall system, and notified Emergency Response Forces. The cell was taken offstream and cell pressure was reduced below atmosphere.
"All airborne and surface contamination sample results were less than detectable and there was no release of
Hazardous/Radioactive material or Radioactive/Radiological contamination exposure as a result of this event."
The facility notified the NRC Resident Inspector and the DOE Site Manager.
* * * UPDATE 1112 3/29/1999 FROM VANDERPOOL TAKEN BY STRANSKY * * *
The original report was reissued with the following change to the third paragraph above:
"All airborne and surface contamination sample results were less than detectable, and there was no Radioactive/Radiological contamination exposure as a result of this event."
HOO notified R3DO (Ring).
Power Reactor
Event Number: 35508
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GRANT FERNSLER
HQ OPS Officer: JOHN MacKINNON
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GRANT FERNSLER
HQ OPS Officer: JOHN MacKINNON
Notification Date: 03/25/1999
Notification Time: 02:34 [ET]
Event Date: 03/25/1999
Event Time: 01:30 [EST]
Last Update Date: 03/25/1999
Notification Time: 02:34 [ET]
Event Date: 03/25/1999
Event Time: 01:30 [EST]
Last Update Date: 03/25/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - DEG/UNANALYZED COND
10 CFR Section:
50.72(b)(2)(i) - DEG/UNANALYZED COND
Person (Organization):
JACK MCFADDEN (R1)
JACK MCFADDEN (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Refueling | 0 | Refueling |
LOCAL LEAK RATE TEST PERFORMED ON THE "A" LOOP FEEDWATER CONTAINMENT PENETRATION FAILED.
An Appendix "J" Local Leak Rate Test was performed on the "A" Loop Feedwater containment penetration. The penetration piping was unable to be pressurized and therefore the leakrate exceeded Tech Spec limits. The penetration is isolated and the condition does not represent an immediate threat to the public health or safety.
The NRC Resident Inspector will notified of this event by the licensee.
An Appendix "J" Local Leak Rate Test was performed on the "A" Loop Feedwater containment penetration. The penetration piping was unable to be pressurized and therefore the leakrate exceeded Tech Spec limits. The penetration is isolated and the condition does not represent an immediate threat to the public health or safety.
The NRC Resident Inspector will notified of this event by the licensee.
Power Reactor
Event Number: 35509
Facility: CRYSTAL RIVER
Region: 2 State: FL
Unit: [3] [] []
RX Type: [3] B&W-L-LP
NRC Notified By: SERGIO ORTIZ
HQ OPS Officer: JOHN MacKINNON
Region: 2 State: FL
Unit: [3] [] []
RX Type: [3] B&W-L-LP
NRC Notified By: SERGIO ORTIZ
HQ OPS Officer: JOHN MacKINNON
Notification Date: 03/25/1999
Notification Time: 08:52 [ET]
Event Date: 03/25/1999
Event Time: 08:12 [EST]
Last Update Date: 03/25/1999
Notification Time: 08:52 [ET]
Event Date: 03/25/1999
Event Time: 08:12 [EST]
Last Update Date: 03/25/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(vi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(vi) - OFFSITE NOTIFICATION
Person (Organization):
MARK LESSER (R2)
MARK LESSER (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION MADE TO THE FLORIDA DEPARTMENT OF ENVIRONMENTAL PROTECTION CONCERNING A KEMPS RIDLEY SEA TURTLE BEING FOUND IN THE INTAKE STRUCTURE.
A SUB-ADULT KEMPS RIDLEY SEA TURTLE WAS FOUND IN THE PLANT'S INTAKE STRUCTURE. THE LIVE KEMPS RIDLEY SEA TURTLE WAS TRANSPORTED TO THE MARICULTURE CENTER FOR DISPOSITION/EVALUATION. THE TURTLE WILL BE TRANSPORTED TO THE CLEARWATER MARINE SCIENCE CENTER FOR REHABILITATION. THE FLORIDA DEPARTMENT OF ENVIRONMENTAL PROTECTION WAS NOTIFIED BY THE LICENSEE OF THIS EVENT.
THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE.
A SUB-ADULT KEMPS RIDLEY SEA TURTLE WAS FOUND IN THE PLANT'S INTAKE STRUCTURE. THE LIVE KEMPS RIDLEY SEA TURTLE WAS TRANSPORTED TO THE MARICULTURE CENTER FOR DISPOSITION/EVALUATION. THE TURTLE WILL BE TRANSPORTED TO THE CLEARWATER MARINE SCIENCE CENTER FOR REHABILITATION. THE FLORIDA DEPARTMENT OF ENVIRONMENTAL PROTECTION WAS NOTIFIED BY THE LICENSEE OF THIS EVENT.
THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE.
General Information or Other
Event Number: 35521
Rep Org: ILLINOIS DEPT OF NUCLEAR SAFETY
Licensee: PROVENA- ST JOSEPH MED CTR
Region: 3
City: JOLIET State: IL
County:
License #: IL-01326-01
Agreement: Y
Docket:
NRC Notified By: PATRICIA LARKINS (OSP)
HQ OPS Officer: BOB STRANSKY
Licensee: PROVENA- ST JOSEPH MED CTR
Region: 3
City: JOLIET State: IL
County:
License #: IL-01326-01
Agreement: Y
Docket:
NRC Notified By: PATRICIA LARKINS (OSP)
HQ OPS Officer: BOB STRANSKY
Notification Date: 03/29/1999
Notification Time: 08:57 [ET]
Event Date: 03/25/1999
Event Time: 00:00 [CST]
Last Update Date: 03/29/1999
Notification Time: 08:57 [ET]
Event Date: 03/25/1999
Event Time: 00:00 [CST]
Last Update Date: 03/29/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
PATRICK HILAND (R3)
LARRY CAMPER (NMSS)
PATRICK HILAND (R3)
LARRY CAMPER (NMSS)
AGREEMENT STATE REPORT
The following is a compilation of information sent to the Operations Center by the Office of State Programs:
The RSO from the Provena-St. Joseph Medical Center reported that a decay error involving an HDR source resulted in a 31% underdose to three patients (53 year old female, 43 year old female, and 60 year old male). The apparent cause was the use of the certificate activity instead of the current activity for the dose planning. The device was a Nucletron Microselectron HDR with an Ir-192 source. The source had recently been replaced by Nucletron.
The following is a compilation of information sent to the Operations Center by the Office of State Programs:
The RSO from the Provena-St. Joseph Medical Center reported that a decay error involving an HDR source resulted in a 31% underdose to three patients (53 year old female, 43 year old female, and 60 year old male). The apparent cause was the use of the certificate activity instead of the current activity for the dose planning. The device was a Nucletron Microselectron HDR with an Ir-192 source. The source had recently been replaced by Nucletron.