Event Notification Report for May 06, 1999
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/05/1999 - 05/06/1999
EVENT NUMBERS
3568635687359383568235684
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 35686
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: MARTIN
HQ OPS Officer: CHAUNCEY GOULD
Region: 1 State: CT
Unit: [] [] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: MARTIN
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 05/06/1999
Notification Time: 18:44 [ET]
Event Date: 05/06/1999
Event Time: 18:00 [EDT]
Last Update Date: 06/04/1999
Notification Time: 18:44 [ET]
Event Date: 05/06/1999
Event Time: 18:00 [EDT]
Last Update Date: 06/04/1999
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):
JAMES LINVILLE (R1)
JAMES LINVILLE (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
VALVE FAILED LOCAL LEAK RATE TEST (LLRT).
VALVE 3QSS*V4 IS A CHECK VALVE IN THE QUENCH SPRAY SYSTEM, AND THE CAUSE OF THE LLRT FAILURE IS UNKNOWN AND BEING INVESTIGATED, BUT MOST LIKELY MAY BE DUE TO VALVE DEGRADATION. WHEN THE RESULTS OF ITS LLRT WERE ADDED TO THE OTHER CATEGORY "C" VALVES' RESULTS, THE TOTAL LEAKAGE EXCEEDED TECHNICAL SPECIFICATION ALLOWABLE LIMITS OF 43 SCFH (TOTAL MEASURED CATEGORY "C" WAS 335 SCFH); HOWEVER, THE TOTAL LEAKAGE OF EVERYTHING STILL DID NOT EXCEED THE 0.6 La VALUE. CORRECTIVE ACTION WILL BE TO REPAIR THE VALVE PRIOR TO STARTUP.
THE NRC RESIDENT INSPECTOR WAS NOTIFIED ALONG WITH STATE, LOCAL AND OTHER GOVERNMENT AGENCIES.
* * * UPDATE 1134 5/13/99 FROM STEVE LAWHEAD TAKEN BY STRANSKY * * *
Local leak rate testing of valve SIL*V6 (RHS Loop 1 Cold Leg Check Valve) found the leakage to be excessive. This leakage, when combined with the other known leakage, caused TS LCO 3.6.1.2.b to be exceeded. The TS requires a combined leakage rate of less than 0.6 La for all penetrations and valves subject to Type B and C tests, when pressurized to Pa. The NRC resident inspector has been informed of this update. Notified R1DO (Cowgill).
* * * RETRACTION 1633 EDT ON 6/4/99 BY DALE BRODSKY TO FANGIE JONES * * *
These conditions were conservatively reported as conditions outside the unit's design basis.
"A review has determined that the Combined Type B and C Leakage limit of 0.60 La and the Enclosure Building (Secondary Containment) Bypass Leakage limit of 0.042 La, (based upon ANSI/ANS 56.8-1994 and NUREG 1022, Rev. 1) should be based upon the As-Found limit measured on a Minimum Pathway Leakage Rate basis. Using this basis the measured total as-found leakage does not exceed either limit.
"These conditions are not reportable pursuant to 10 CFR 50.72(b)(1)(ii)(B) as conditions outside the design basis, or pursuant to 10 CFR 50.72(b)(2)(i) as events or conditions that may have resulted in an unanalyzed conditions and therefore, the Immediate Notification for these conditions is retracted."
The licensee notified the NRC Resident Inspector. The Headquarters Operations Officer notified the R1DO (Ronald Bellamy).
VALVE 3QSS*V4 IS A CHECK VALVE IN THE QUENCH SPRAY SYSTEM, AND THE CAUSE OF THE LLRT FAILURE IS UNKNOWN AND BEING INVESTIGATED, BUT MOST LIKELY MAY BE DUE TO VALVE DEGRADATION. WHEN THE RESULTS OF ITS LLRT WERE ADDED TO THE OTHER CATEGORY "C" VALVES' RESULTS, THE TOTAL LEAKAGE EXCEEDED TECHNICAL SPECIFICATION ALLOWABLE LIMITS OF 43 SCFH (TOTAL MEASURED CATEGORY "C" WAS 335 SCFH); HOWEVER, THE TOTAL LEAKAGE OF EVERYTHING STILL DID NOT EXCEED THE 0.6 La VALUE. CORRECTIVE ACTION WILL BE TO REPAIR THE VALVE PRIOR TO STARTUP.
THE NRC RESIDENT INSPECTOR WAS NOTIFIED ALONG WITH STATE, LOCAL AND OTHER GOVERNMENT AGENCIES.
* * * UPDATE 1134 5/13/99 FROM STEVE LAWHEAD TAKEN BY STRANSKY * * *
Local leak rate testing of valve SIL*V6 (RHS Loop 1 Cold Leg Check Valve) found the leakage to be excessive. This leakage, when combined with the other known leakage, caused TS LCO 3.6.1.2.b to be exceeded. The TS requires a combined leakage rate of less than 0.6 La for all penetrations and valves subject to Type B and C tests, when pressurized to Pa. The NRC resident inspector has been informed of this update. Notified R1DO (Cowgill).
* * * RETRACTION 1633 EDT ON 6/4/99 BY DALE BRODSKY TO FANGIE JONES * * *
These conditions were conservatively reported as conditions outside the unit's design basis.
"A review has determined that the Combined Type B and C Leakage limit of 0.60 La and the Enclosure Building (Secondary Containment) Bypass Leakage limit of 0.042 La, (based upon ANSI/ANS 56.8-1994 and NUREG 1022, Rev. 1) should be based upon the As-Found limit measured on a Minimum Pathway Leakage Rate basis. Using this basis the measured total as-found leakage does not exceed either limit.
"These conditions are not reportable pursuant to 10 CFR 50.72(b)(1)(ii)(B) as conditions outside the design basis, or pursuant to 10 CFR 50.72(b)(2)(i) as events or conditions that may have resulted in an unanalyzed conditions and therefore, the Immediate Notification for these conditions is retracted."
The licensee notified the NRC Resident Inspector. The Headquarters Operations Officer notified the R1DO (Ronald Bellamy).
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 35687
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: NACOSTE
HQ OPS Officer: CHAUNCEY GOULD
Region: 2 State: AL
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: NACOSTE
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 05/06/1999
Notification Time: 20:33 [ET]
Event Date: 05/06/1999
Event Time: 16:14 [CDT]
Last Update Date: 06/04/1999
Notification Time: 20:33 [ET]
Event Date: 05/06/1999
Event Time: 16:14 [CDT]
Last Update Date: 06/04/1999
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):
CHRIS CHRISTENSEN (R2)
CHRIS CHRISTENSEN (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 23 | Power Operation | 0 | Hot Shutdown |
THE REACTOR WAS MANUALLY SCRAMMED FROM 23.5% POWER.
DURING STARTUP FOLLOWING A REFUELING OUTAGE, THE UNIT EXPERIENCED A STEAM LEAK ON THE INLET SIDE OF THE OFFGAS PREHEATER (ASME CLASS 2 PIPING). TECHNICAL REQUIREMENTS MANUAL (TMR) SECTION 3.4.3 REQUIRES THAT THE AFFECTED COMPONENT BE ISOLATED IMMEDIATELY, REQUIRING THAT THE MAIN STEAM ISOLATION VALVES (MSIVs) BE CLOSED. THE MAIN TURBINE WAS TRIPPED FROM 23.5 % POWER IN ANTICIPATION OF THE INSERTION OF A MANUAL SCRAM WHICH OCCURRED AT 1614 CST. THE MANUAL SCRAM CAUSED REACTOR VESSEL WATER LEVEL TO GO BELOW THE LOW SETPOINT LEVEL, WHICH GENERATED A REDUNDANT SCRAM SIGNAL AND INITIATED THE PCIS ISOLATIONS OF GROUPS 2 (PRIMARY CONTAINMENT), 3 (RWCU), 6 (SECONDARY CONTAINMENT), AND 8 (TIP SYSTEM). ALL RODS FULLY INSERTED, NO ECCS INJECTION OCCURRED, AND NO RELIEF VALVES LIFTED. THE MSIVs WERE CLOSED AT 1632.
THE RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT.
* * * RETRACTED AT 1434 EDT ON 6/4/99 BY CHRIS VAUGHN TO FANGIE JONES * * *
This event is retracted after review and determination that as a planned manual reactor trip, it was not reportable under 10CFR50.72.2.ii per NUREG 1022.
The licensee notified the NRC Resident Inspector. The Headquarters Operations Officer notified the R2DO (Kenneth Barr).
DURING STARTUP FOLLOWING A REFUELING OUTAGE, THE UNIT EXPERIENCED A STEAM LEAK ON THE INLET SIDE OF THE OFFGAS PREHEATER (ASME CLASS 2 PIPING). TECHNICAL REQUIREMENTS MANUAL (TMR) SECTION 3.4.3 REQUIRES THAT THE AFFECTED COMPONENT BE ISOLATED IMMEDIATELY, REQUIRING THAT THE MAIN STEAM ISOLATION VALVES (MSIVs) BE CLOSED. THE MAIN TURBINE WAS TRIPPED FROM 23.5 % POWER IN ANTICIPATION OF THE INSERTION OF A MANUAL SCRAM WHICH OCCURRED AT 1614 CST. THE MANUAL SCRAM CAUSED REACTOR VESSEL WATER LEVEL TO GO BELOW THE LOW SETPOINT LEVEL, WHICH GENERATED A REDUNDANT SCRAM SIGNAL AND INITIATED THE PCIS ISOLATIONS OF GROUPS 2 (PRIMARY CONTAINMENT), 3 (RWCU), 6 (SECONDARY CONTAINMENT), AND 8 (TIP SYSTEM). ALL RODS FULLY INSERTED, NO ECCS INJECTION OCCURRED, AND NO RELIEF VALVES LIFTED. THE MSIVs WERE CLOSED AT 1632.
THE RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT.
* * * RETRACTED AT 1434 EDT ON 6/4/99 BY CHRIS VAUGHN TO FANGIE JONES * * *
This event is retracted after review and determination that as a planned manual reactor trip, it was not reportable under 10CFR50.72.2.ii per NUREG 1022.
The licensee notified the NRC Resident Inspector. The Headquarters Operations Officer notified the R2DO (Kenneth Barr).
General Information or Other
Event Number: 35938
Rep Org: OREGON RAD PROTECTION SERVICES
Licensee: MERLE WEST MEDICAL CENTER
Region: 4
City: KLAMATH FALLS State: OR
County:
License #: ORE-90442
Agreement: Y
Docket:
NRC Notified By: TERRY LINDSEY
HQ OPS Officer: DOUG WEAVER
Licensee: MERLE WEST MEDICAL CENTER
Region: 4
City: KLAMATH FALLS State: OR
County:
License #: ORE-90442
Agreement: Y
Docket:
NRC Notified By: TERRY LINDSEY
HQ OPS Officer: DOUG WEAVER
Notification Date: 07/20/1999
Notification Time: 13:06 [ET]
Event Date: 05/06/1999
Event Time: 12:00 [PDT]
Last Update Date: 07/20/1999
Notification Time: 13:06 [ET]
Event Date: 05/06/1999
Event Time: 12:00 [PDT]
Last Update Date: 07/20/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
ELMO COLLINS (R4)
JOSIE PICCONE (NMSS)
ELMO COLLINS (R4)
JOSIE PICCONE (NMSS)
AGREEMENT STATE REPORT - MEDICAL MISADMINISTRATION
A patient received 97 mCi of Sm-153 instead of 62 mCi based on a dosage of 1 mCi per Kg of body weight.
This event occurred at the Merle West Medical Center in Klamath Falls, OR. Sm-153 is used to alleviate bone pain in cancer patients. The error was discovered by the chief technician. No other information was immediately available.
A patient received 97 mCi of Sm-153 instead of 62 mCi based on a dosage of 1 mCi per Kg of body weight.
This event occurred at the Merle West Medical Center in Klamath Falls, OR. Sm-153 is used to alleviate bone pain in cancer patients. The error was discovered by the chief technician. No other information was immediately available.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 35682
Facility: SUMMER
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: JIM PROPER
HQ OPS Officer: LEIGH TROCINE
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: JIM PROPER
HQ OPS Officer: LEIGH TROCINE
Notification Date: 05/06/1999
Notification Time: 07:34 [ET]
Event Date: 05/06/1999
Event Time: 06:45 [EDT]
Last Update Date: 05/07/1999
Notification Time: 07:34 [ET]
Event Date: 05/06/1999
Event Time: 06:45 [EDT]
Last Update Date: 05/07/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
Person (Organization):
CHRIS CHRISTENSEN (R2)
CHRIS CHRISTENSEN (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
ATTEMPTED INTRODUCTION OF CONTRABAND INTO THE PROTECTED AREA (1-hour report in accordance with 10CFR73.71, Appendix G)
The licensee reported an attempted introduction of contraband into the protected area. Immediate compensatory measurements were taken upon discovery. (Contact the NRC Operations Officer for additional details and for a site contact telephone number.)
The licensee notified the NRC Resident Inspector.
**** UPDATE AT 1314 ON 05/07/99 FROM RICE TO GOULD **** EVENT RETRACTION
THE LICENSEE HAS INVESTIGATED THIS EVENT FURTHER AND HAS DETERMINED THAT THE EVENT IS NOT REPORTABLE SINCE THERE WAS NO DELIBERATE INTENT TO INTRODUCE CONTRABAND INTO THE PROTECTED AREA. A BACKGROUND CHECK CONFIRMED NO CRIMINAL HISTORY FOR THE INDIVIDUAL.
THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.
THE NRC OPERATIONS OFFICER NOTIFIED THE R2DO CHRIS CHRISTENSEN.
The licensee reported an attempted introduction of contraband into the protected area. Immediate compensatory measurements were taken upon discovery. (Contact the NRC Operations Officer for additional details and for a site contact telephone number.)
The licensee notified the NRC Resident Inspector.
**** UPDATE AT 1314 ON 05/07/99 FROM RICE TO GOULD **** EVENT RETRACTION
THE LICENSEE HAS INVESTIGATED THIS EVENT FURTHER AND HAS DETERMINED THAT THE EVENT IS NOT REPORTABLE SINCE THERE WAS NO DELIBERATE INTENT TO INTRODUCE CONTRABAND INTO THE PROTECTED AREA. A BACKGROUND CHECK CONFIRMED NO CRIMINAL HISTORY FOR THE INDIVIDUAL.
THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.
THE NRC OPERATIONS OFFICER NOTIFIED THE R2DO CHRIS CHRISTENSEN.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 35684
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [2] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: DON SMITH
HQ OPS Officer: BOB STRANSKY
Region: 2 State: AL
Unit: [1] [2] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: DON SMITH
HQ OPS Officer: BOB STRANSKY
Notification Date: 05/06/1999
Notification Time: 09:51 [ET]
Event Date: 05/06/1999
Event Time: 08:35 [CDT]
Last Update Date: 05/06/1999
Notification Time: 09:51 [ET]
Event Date: 05/06/1999
Event Time: 08:35 [CDT]
Last Update Date: 05/06/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(1)(v) - EMERGENCY SIREN INOP
10 CFR Section:
50.72(b)(1)(v) - EMERGENCY SIREN INOP
Person (Organization):
CHRIS CHRISTENSEN (R2)
CHRIS CHRISTENSEN (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
| 2 | N | N | 0 | Startup | 0 | Startup |
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
EMERGENCY SIRENS INOPERABLE DUE TO WEATHER
The licensee reported that 35 of 100 emergency sirens are currently inoperable due to adverse weather conditions. The plant is required to maintain at least 70 sirens operable at any time. The licensee is attempting to restore the sirens, but stated that the adverse weather is expected to continue throughout the day. The NRC resident inspector has been informed of this notification.
***UPDATE ON 5/6/99 @ 1552 BY SMITH TO GOULD *** EVENT RETRACTION
THE LICENSEE IS RETRACTING THIS EVENT SINCE IT WAS DETERMINED THAT ONLY 1 SIREN WAS
INOPERABLE OUT OF 35. THE ABILITY TO VERIFY OPERABILITY OF THE OTHER 34 SIRENS WAS MASKED BY THE 1 INOPERABLE SIREN. THE INOPERABLE SIREN WAS RETURNED TO SERVICE AT 1300CST.
THE RESIDENT INSPECTOR WAS NOTIFIED.
REG 2 RDO(CHRISTENSEN) WAS NOTIFIED.
The licensee reported that 35 of 100 emergency sirens are currently inoperable due to adverse weather conditions. The plant is required to maintain at least 70 sirens operable at any time. The licensee is attempting to restore the sirens, but stated that the adverse weather is expected to continue throughout the day. The NRC resident inspector has been informed of this notification.
***UPDATE ON 5/6/99 @ 1552 BY SMITH TO GOULD *** EVENT RETRACTION
THE LICENSEE IS RETRACTING THIS EVENT SINCE IT WAS DETERMINED THAT ONLY 1 SIREN WAS
INOPERABLE OUT OF 35. THE ABILITY TO VERIFY OPERABILITY OF THE OTHER 34 SIRENS WAS MASKED BY THE 1 INOPERABLE SIREN. THE INOPERABLE SIREN WAS RETURNED TO SERVICE AT 1300CST.
THE RESIDENT INSPECTOR WAS NOTIFIED.
REG 2 RDO(CHRISTENSEN) WAS NOTIFIED.