Event Notification Report for February 12, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/11/1999 - 02/12/1999
** EVENT NUMBERS **
35362 35363 35364 35365
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|Power Reactor |Event Number: 35362 |
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+------------------------------------------------------------------------------+
| FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 02/10/1999|
| UNIT: [1] [] [] STATE: GA |NOTIFICATION TIME: 21:59[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/10/1999|
+------------------------------------------------+EVENT TIME: 20:30[EST]|
| NRC NOTIFIED BY: W. R. DUNN |LAST UPDATE DATE: 02/11/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |THOMAS DECKER R2 |
|10 CFR SECTION: | |
|HFIT 26.73 FITNESS FOR DUTY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - FITNESS-FOR-DUTY REPORT - |
| |
| A LICENSED OPERATOR WAS DETERMINED TO BE UNDER THE INFLUENCE OF ALCOHOL |
| DURING A RANDOM FITNESS FOR DUTY TEST. THE EMPLOYEE'S ACCESS AUTHORIZATION |
| TO THE PLANT HAS BEEN DEACTIVATED. REFER TO THE HOO LOG FOR ADDITIONAL |
| DETAILS. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
| |
| ***UPDATE ON 02/11/99 AT 0925ET FROM C. MEYER TAKEN BY MACKINNON**** |
| |
| A URINE SAMPLE WAS TAKEN ON 02/10/99 AT 2000 HOURS, BUT THE SAMPLE HAS NOT |
| BEEN ANALYZED. THE LICENSED OPERATOR FAILED A BREATHALYZER TEST (TESTED |
| POSITIVE FOR ALCOHOL). THE INDIVIDUAL FAILED A SECOND BREATHALYZER TEST FOR |
| ALCOHOL FROM A DIFFERENT BREATHALYZER MACHINE. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS CENTER |
| NOTIFIED THE R2DO (TOM DECKER). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35363 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 02/11/1999|
| UNIT: [] [2] [3] STATE: CA |NOTIFICATION TIME: 04:48[EST]|
| RXTYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 02/10/1999|
+------------------------------------------------+EVENT TIME: 11:37[PST]|
| NRC NOTIFIED BY: CLAY WILLIAMS |LAST UPDATE DATE: 02/11/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN PELLET R4 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Refueling |0 Refueling |
|3 N Y 100 Power Operation |100 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| During a postulated seismic event, Component Cooling Water (CCW) isolation |
| valves which separate the CCW critical loops from the non-critical loop may |
| not operate. |
| |
| "At 1137 PST on February 10, 1999, with Unit 2 in a refueling outage and |
| Unit 3 at about 100 percent power, SCE concluded that isolation valves which |
| separate CCW critical loops [loops to safety-related equipment] from the |
| non-Critical Loop (NCL) may not have operated during a postulated seismic |
| event. |
| |
| "The CCW system is required to perform its intended safety function during a |
| seismic event concurrent with a Loss of Coolant Accident. These valves |
| (28-inch Fisher Type-9241 air/nitrogen-operated butterfly valves) close on a |
| CCW surge tank low-low level alarm or when a Containment Isolation Actuation |
| Signal (CIAS) is received. These isolation valves are normally actuated with |
| non-seismically qualified instrument air and normal nitrogen. During a |
| postulated seismic event, the air and nitrogen systems are assumed to fail. |
| A seismically qualified accumulator tank provides the motive force to close |
| the isolation valves during such events. This actuation occurs through the |
| pressurization and venting of pneumatic tubing. |
| |
| "During outage testing [first time the test has been performed this way] of |
| the Train A CCW isolation valves, the valves would not stroke closed within |
| the required time when actuated by the accumulators only. SCE's |
| Air-Operated Valve diagnostic testing determined the pneumatic tube sizing |
| provided insufficient venting to properly actuate the valves, which cause |
| the isolation valves to stroke slower than desired. When the isolation |
| valves between one CCW critical loop and the non-critical loop are opened, |
| SCE now considers that CCW critical loop to be inoperable. |
| |
| "During past plant operation, it is possible that one CCW critical loop was |
| out of service while the remaining critical loop was not isolated from the |
| non-critical loop. If a seismic event were to have occurred in this |
| configuration, it is possible the plant would not have had an operable train |
| of CCW. Consequently, SCE is reporting this occurrence in accordance with |
| 10CFR50.72(b)(2)(iii)(D). |
| |
| "Currently, Unit 2 is in Mode 6 in a refueling outage; there is no safety |
| function requiring the valves to close in this mode. At Unit 3, both CCW |
| trains are functional with the isolation valves for one train closed. In |
| this configuration, Unit 3 is in a 72-hour action statement. SCE plans to |
| modify the valve actuator design within 72 hours to correct this |
| condition." |
| |
| The licensee said that the isolation valves mentioned above should normally |
| close within 10 to 15 seconds. During testing of the valve, the licensee |
| believed that it took approximately 47 seconds for the valves to close. |
| |
| The NRC resident inspector was notified of this event by the licensee. |
| |
| * * * UPDATE AT 2002 EST ON 02/11/99 BY CLAY WILLIAMS TO FANGIE JONES * * * |
| |
| The licensee noted a typographical error in the original report as reported. |
| The time reported in the first quoted paragraph should be 1137 PM or 2337 |
| PST. |
| |
| The R4DO (John Pellet) was notified by the NRC Operations Officer. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35364 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 02/11/1999|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 23:31[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 02/11/1999|
+------------------------------------------------+EVENT TIME: 19:45[CST]|
| NRC NOTIFIED BY: ROBERT POWERS |LAST UPDATE DATE: 02/11/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GARY SHEAR R3 |
|10 CFR SECTION: | |
|AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 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. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35365 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 02/11/1999|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 23:56[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 02/11/1999|
+------------------------------------------------+EVENT TIME: 22:49[EST]|
| NRC NOTIFIED BY: DAVID JENKINS |LAST UPDATE DATE: 02/12/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |THOMAS DECKER R2 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 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. |
| |
| 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. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021