Event Notification Report for February 11, 1999
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/10/1999 - 02/11/1999
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 35364
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: ROBERT POWERS
HQ OPS Officer: JOHN MacKINNON
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: ROBERT POWERS
HQ OPS Officer: JOHN MacKINNON
Notification Date: 02/11/1999
Notification Time: 23:31 [ET]
Event Date: 02/11/1999
Event Time: 19:45 [CST]
Last Update Date: 03/01/1999
Notification Time: 23:31 [ET]
Event Date: 02/11/1999
Event Time: 19:45 [CST]
Last Update Date: 03/01/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iii)(C) - POT UNCNTRL RAD REL
10 CFR Section:
50.72(b)(2)(iii)(C) - POT UNCNTRL RAD REL
Person (Organization):
GARY SHEAR (R3)
GARY SHEAR (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
TORQUE VALUE USED ON THE MSIVs FOUND TO BE LESS THAN REQUIRED BY SEISMIC ANALYSES
"During an evaluation of the torque values for the Main Steam Isolation Valve's (MSIV) actuator cylinder yoke
upper flange studs, Clinton Power Station discovered that the torque value for the lower flange bolts as specified
by the vendor manual and plant procedure is much smaller [than] that used in the seismic qualification of the MSIV actuators. The Vendor manual specifies 200 ft-lbs while plant procedures specify 200 to 240 ft-lbs. However, the GE seismic qualification document NEDE-30725 uses 620 ft-lbs.
"A review of the seismic qualification indicated that the minimum applied torque of 200 ft-lbs is acceptable for
mode 4 (cold shutdown), the plant's current mode of operation.
" This condition during a seismic event could cause the valve stem to bind which could have prevented MSIV
operation. Thus, a notification is being made per 10 CFR 50.72(b)(2)(iii)(c) [because] this condition could have
prevented the fulfillment of the safety function of systems that are needed to control the release of radioactive
material."
The licensee notified the NRC Resident Inspector.
*** UPDATE ON 3/1/99 @ 1817 BY POWERS TO GOULD *** EVENT RETRACTION
FURTHER EVALUATION OF THIS CONDITION HAS DETERMINED THAT THIS EVENT IS NOT REPORTABLE. THE TORQUE VALUE OF 200 FT-LBS HAS BEEN EVALUATED IN NUCLEAR STATION ENGINEERING DEPT. CALCULATION IP-Q-0438, REVISION 0, AND FOUND TO NOT AFFECT THE SEISMIC QUALIFICATION OF THE MSIV ACTUATORS. HOWEVER, ENGINEERING CHANGE NOTICE 31374 HAS BEEN ISSUED TO CHANGE THE DESIGN SPECIFIED TORQUE VALUE FOR THE AFFECTED FASTENERS TO 400 FT-LBS (+/-10% LUBRICATED).
THE RESIDENT INSPECTOR WAS NOTIFIED. REG 3 RDO(JORGENSEN) WAS NOTIFIED.
"During an evaluation of the torque values for the Main Steam Isolation Valve's (MSIV) actuator cylinder yoke
upper flange studs, Clinton Power Station discovered that the torque value for the lower flange bolts as specified
by the vendor manual and plant procedure is much smaller [than] that used in the seismic qualification of the MSIV actuators. The Vendor manual specifies 200 ft-lbs while plant procedures specify 200 to 240 ft-lbs. However, the GE seismic qualification document NEDE-30725 uses 620 ft-lbs.
"A review of the seismic qualification indicated that the minimum applied torque of 200 ft-lbs is acceptable for
mode 4 (cold shutdown), the plant's current mode of operation.
" This condition during a seismic event could cause the valve stem to bind which could have prevented MSIV
operation. Thus, a notification is being made per 10 CFR 50.72(b)(2)(iii)(c) [because] this condition could have
prevented the fulfillment of the safety function of systems that are needed to control the release of radioactive
material."
The licensee notified the NRC Resident Inspector.
*** UPDATE ON 3/1/99 @ 1817 BY POWERS TO GOULD *** EVENT RETRACTION
FURTHER EVALUATION OF THIS CONDITION HAS DETERMINED THAT THIS EVENT IS NOT REPORTABLE. THE TORQUE VALUE OF 200 FT-LBS HAS BEEN EVALUATED IN NUCLEAR STATION ENGINEERING DEPT. CALCULATION IP-Q-0438, REVISION 0, AND FOUND TO NOT AFFECT THE SEISMIC QUALIFICATION OF THE MSIV ACTUATORS. HOWEVER, ENGINEERING CHANGE NOTICE 31374 HAS BEEN ISSUED TO CHANGE THE DESIGN SPECIFIED TORQUE VALUE FOR THE AFFECTED FASTENERS TO 400 FT-LBS (+/-10% LUBRICATED).
THE RESIDENT INSPECTOR WAS NOTIFIED. REG 3 RDO(JORGENSEN) WAS NOTIFIED.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 35365
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DAVID JENKINS
HQ OPS Officer: JOHN MacKINNON
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DAVID JENKINS
HQ OPS Officer: JOHN MacKINNON
Notification Date: 02/11/1999
Notification Time: 23:56 [ET]
Event Date: 02/11/1999
Event Time: 22:49 [EST]
Last Update Date: 03/03/1999
Notification Time: 23:56 [ET]
Event Date: 02/11/1999
Event Time: 22:49 [EST]
Last Update Date: 03/03/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iii)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(2)(iii)(D) - ACCIDENT MITIGATION
Person (Organization):
THOMAS DECKER (R2)
THOMAS DECKER (R2)
| 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) SYSTEM DECLARED INOPERABLE DUE TO INABILITY TO ESTABLISH REFERENCE FLOW CONDITIONS.
HPCI SYSTEM WAS DECLARED INOPERABLE DUE TO INABILITY TO ESTABLISH REFERENCE FLOW CONDITIONS DURING PERFORMANCE OF THE QUARTERLY OPERABILITY TEST. THESE CONDITIONS ARE NORMALLY ESTABLISHED AT 2,500 REVOLUTIONS/MINUTE AND 4,550 GALLONS/MINUTE. DURING THIS PERFORMANCE OF THE TEST, A FLOW OF 4,450 GALLONS/MINUTE WAS OBTAINED WITH REFERENCE TURBINE SPEED.
THE HPCI SYSTEM IS A SINGLE TRAIN EMERGENCY CORE COOLING SYSTEM. ACCORDINGLY, EMERGENCY HIGH PRESSURE INJECTION IS NOT AVAILABLE AT THIS TIME. THE HIGH PRESSURE REACTOR CORE ISOLATION COOLING (RCIC) REMAINS OPERABLE, AND THE AUTOMATIC DEPRESSURIZATION SYSTEM (BACKUP SYSTEM FOR HPCI) ALSO REMAINS OPERABLE. PLANT TECHNICAL SPECIFICATIONS SECTION 3.5 ALLOWS CONTINUED OPERATION FOR 14 DAYS WITH HPCI SYSTEM INOPERABLE.
ENGINEERING AND MAINTENANCE PERSONNEL ARE WORKING TO DETERMINE THE CAUSE OF THIS EVENT. ONCE THE CAUSE IS UNDERSTOOD, A CORRECTIVE ACTION PLAN WILL BE DEVELOPED.
THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE.
* * * RETRACTED AT 1123 EST ON 3/3/99 BY STEVE TABOR TO FANGIE JONES * * *
The licensee has determined that the HPCI system was capable of performing its design basis function. The declaration on inoperability was conservative based on initial indications. However, after a calibration check of the flow instrumentation, which indicated the need for calibration, the flow instrument was calibrated. The HPCI flow test was performed again with satisfactory results, showing that no flow degradation had occurred. Thus, this event notification is retracted.
The licensee notified the NRC Resident Inspector.
The NRC Operations Officer notified the R2DO (Claude Julian).
HPCI SYSTEM WAS DECLARED INOPERABLE DUE TO INABILITY TO ESTABLISH REFERENCE FLOW CONDITIONS DURING PERFORMANCE OF THE QUARTERLY OPERABILITY TEST. THESE CONDITIONS ARE NORMALLY ESTABLISHED AT 2,500 REVOLUTIONS/MINUTE AND 4,550 GALLONS/MINUTE. DURING THIS PERFORMANCE OF THE TEST, A FLOW OF 4,450 GALLONS/MINUTE WAS OBTAINED WITH REFERENCE TURBINE SPEED.
THE HPCI SYSTEM IS A SINGLE TRAIN EMERGENCY CORE COOLING SYSTEM. ACCORDINGLY, EMERGENCY HIGH PRESSURE INJECTION IS NOT AVAILABLE AT THIS TIME. THE HIGH PRESSURE REACTOR CORE ISOLATION COOLING (RCIC) REMAINS OPERABLE, AND THE AUTOMATIC DEPRESSURIZATION SYSTEM (BACKUP SYSTEM FOR HPCI) ALSO REMAINS OPERABLE. PLANT TECHNICAL SPECIFICATIONS SECTION 3.5 ALLOWS CONTINUED OPERATION FOR 14 DAYS WITH HPCI SYSTEM INOPERABLE.
ENGINEERING AND MAINTENANCE PERSONNEL ARE WORKING TO DETERMINE THE CAUSE OF THIS EVENT. ONCE THE CAUSE IS UNDERSTOOD, A CORRECTIVE ACTION PLAN WILL BE DEVELOPED.
THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE.
* * * RETRACTED AT 1123 EST ON 3/3/99 BY STEVE TABOR TO FANGIE JONES * * *
The licensee has determined that the HPCI system was capable of performing its design basis function. The declaration on inoperability was conservative based on initial indications. However, after a calibration check of the flow instrumentation, which indicated the need for calibration, the flow instrument was calibrated. The HPCI flow test was performed again with satisfactory results, showing that no flow degradation had occurred. Thus, this event notification is retracted.
The licensee notified the NRC Resident Inspector.
The NRC Operations Officer notified the R2DO (Claude Julian).