Event Notification Report for January 14, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
01/13/2000 - 01/14/2000
** EVENT NUMBERS **
36358 36547 36570 36585 36586 36587 36588 36589
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36358 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 10/28/1999|
| UNIT: [1] [2] [] STATE: PA |NOTIFICATION TIME: 03:45[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 10/28/1999|
+------------------------------------------------+EVENT TIME: 03:35[EDT]|
| NRC NOTIFIED BY: BENDER |LAST UPDATE DATE: 01/13/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |DAVID LEW R1 |
|10 CFR SECTION: |DAVID MATTHEWS NRR |
|AAEC 50.72 (a) (1) (I) EMERGENCY DECLARED |CHARLES MILLER IRO |
|DDDD 73.71 UNSPECIFIED PARAGRAPH |ROBERTA WARREN IAT |
|NOCM COMM ASST BRIEF |RICHARD ROSANO IAT |
| |GREG SMITH IAT |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 21 Power Operation |21 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNUSUAL EVENT DECLARED DUE TO BOMB THREAT |
| |
| Contact the NRC Operations Center for additional details. The NRC resident |
| inspector will be informed. |
| |
| * * * COMMISSIONERS' ASSISTANTS BRIEFING HELD AT 0630 EDT * * * |
| |
| Briefer: H. Miller. Participants: C. Miller (IRO), Adensam, Matthews (NRR), |
| Ten Eyck (NMSS), Beecher (OPA), Lohaus (OSP), Hauber (OIP), Madden (OCA), |
| Tschiltz (EDO), Paperiello (DEDE), Boyce, Olencz (Dicus), Sharkey |
| (McGaffigan), Castleman (Diaz), Doane (Merrifield), Rosano, Warren (IAT), |
| Screnci (R1PAO). |
| |
| * * * UPDATE AT 1134 ON 10/28/99 FROM JOHN HUNTER TAKEN BY STRANSKY * * * |
| |
| The licensee terminated the Unusual Event at 1124 EDT. Searches of the plant |
| protected area were completed without the discovery of any suspicious |
| devices. In addition, the threat, initially determined to be credible, has |
| been determined not to be credible. The NRC resident inspector has been |
| informed of this update by the licensee. Notified R1DO (Lew), NRR EO |
| (Lyons), FEMA (Sullivan). |
| |
| ******************** UPDATE AT 1712 ON 01/13/99 BY LEIGH TROCINE |
| ******************** |
| |
| This event notification is being updated to document the NRC's response to |
| this event. According to the NRC HOO Log and a time-line generated from |
| recordings of the event, the NRC entered the Monitoring Phase of Normal Mode |
| at 0454 EDT on 10/28/99, and the Monitoring Phase of Normal Mode was exited |
| at 0955 EDT on the same day. |
| |
| HOO NOTE: The bomb threat was made at approximately 0243 EDT, and the |
| Unusual Event was declared at |
| 0335 EDT. |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36547 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 12/29/1999|
| UNIT: [1] [] [] STATE: KS |NOTIFICATION TIME: 17:10[EST]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 12/29/1999|
+------------------------------------------------+EVENT TIME: 15:50[CST]|
| NRC NOTIFIED BY: ROBERT WALTERS |LAST UPDATE DATE: 01/13/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GARY SANBORN R4 |
|10 CFR SECTION: | |
|DDDD 73.71 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| 1-HOUR SECURITY REPORT INVOLVING HISTORICAL ACCESS AUTHORIZATION PROGRAM |
| VIOLATION |
| |
| "During performance of a Plant Evaluation Checklist (PEC OB 99-1157) on the |
| NRC Performance Indicator for [the] Physical Protection Area, a historical |
| error was discovered pertaining [to] access authorization. It was |
| discovered that unescorted access was authorized to an individual from |
| 11/10/95 to 01/16/96. However, on 01/11/96, information was received that, |
| had it been properly investigated, would have caused denial of unescorted |
| access at that time. |
| |
| "This event is reportable as a 1-hour report pursuant to 10 CFR 73.71 as an |
| Access Authorization (AA) program violation as stated in an NRC letter from |
| LeMoine J. Cunningham, Chief Safeguards Branch, USNRC to the NRC Regions |
| chief, dated 05/19/95. In the letter, Mr. Cunningham states that events |
| involving AA program failure are reportable and a 30-day written report |
| required." |
| |
| The licensee plans to inform the NRC resident inspector. |
| |
| * * * RETRACTION ON 01/13/00 AT 1022ET FROM BOB WALTER TAKEN BY MACKINNON * |
| * * |
| |
| Wolf Creek Nuclear Operating Corporation has further reviewed this event and |
| has determined in the information used to develop on 01/11/96 did not |
| provide a preponderance of evidence to require access screening to further |
| investigate the individual. Investigation conducted by access screening |
| identified that the Wolf Creek Nuclear Operating program for access |
| screening met the guidance of NUMARC 91-03 and that a program failure did |
| not occur as a result of this event. Because a program failure did not |
| occur based upon the reportability requirements as clarified by the 05/19/95 |
| Cunningham letter, this event is no longer considered to be a 1-hour |
| reporting event. Therefore, this event notification is being retracted. |
| |
| The NRC resident inspector was notified of this event retraction by the |
| licensee. The NRC operations officer notified the R4DO (Jeff Shackelford). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36570 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 01/07/2000|
| UNIT: [1] [] [] STATE: LA |NOTIFICATION TIME: 15:51[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 01/07/2000|
+------------------------------------------------+EVENT TIME: 12:00[CST]|
| NRC NOTIFIED BY: VERNON CARLSON |LAST UPDATE DATE: 01/13/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BLAIR SPITZBERG R4 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| OBSERVATION OF UNUSUAL CAVITATION NOISE AND VIBRATION OF THE HIGH PRESSURE |
| CORE SPRAY (HPCS) PUMP DURING QUARTERLY INSERVICE TESTING (IST) |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "During the quarterly IST surveillance on the high pressure core spray pump, |
| unusual cavitation noise and vibration was observed. Abnormal low suction |
| pressure alarms were also noted. These conditions could not be explained, |
| and therefore, the high pressure core spray pump was declared inoperable, |
| and plant engineering was contacted to investigate. The data collected on |
| the surveillance test was satisfactory including vibration readings. The |
| abnormal conditions were noted during system realignment for continuation of |
| the testing." |
| |
| The cause of the unusual cavitation noise and vibration of the high pressure |
| core spray pump is currently under investigation. In accordance with |
| Technical Specification 3.5.1, the reactor core isolation cooling system was |
| verified to be operable within one hour. Technical Specification 3.5.1 also |
| requires the licensee to restore the high pressure core spray system to an |
| operable status within 14 days or place the unit in Cold Shutdown. The |
| licensee stated that all other emergency core cooling systems are currently |
| operable. |
| |
| The licensee notified the NRC resident inspector. |
| |
| * * * UPDATE AT 1826 ON 01/13/00 FROM MARK FELTNER TO JOLLIFFE * * * |
| |
| Following the identification of the above condition, licensee actions were |
| taken to investigate the reported deficiency. A loop calibration was |
| performed on the HPCS pump suction transmitter with no abnormal conditions |
| identified. The HPCS pump was run in a variety of configurations including |
| the configuration that produced the original event, and all the data |
| obtained was satisfactory. During each of these runs no abnormal noise, |
| vibrations or pump characteristics were noted. |
| |
| Based on the observed condition and the additional data obtained, a |
| determination was made that the pump did not experience cavitation |
| conditions for more than a short period of time (5 to 8 seconds) if at all. |
| This, coupled with information obtained from the pump vendor, the subsequent |
| successful performance of multiple pump runs, successful calibration of the |
| suction pressure transmitter, and the lack of any abnormal noise or |
| vibration; provides assurance that the HPCS pump is capable of performing |
| its intended safety function. |
| |
| Based on this information, the licensee determined that this condition is |
| not reportable to the NRC and desires to retract this report. |
| |
| The licensee plans to notify the NRC resident inspector. The NRC Operations |
| Officer notified the R4DO Jeff Shackelford. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36585 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 01/13/2000|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 02:55[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/13/2000|
+------------------------------------------------+EVENT TIME: 00:59[CST]|
| NRC NOTIFIED BY: STEWART DRESSER |LAST UPDATE DATE: 01/13/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRENT CLAYTON R3 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 100 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SWITCHYARD FAULT RESULTED IN MAIN GENERATOR TRIP/TURBINE TRIP/REACTOR TRIP. |
| |
| At 0059CT, a Reactor Trip occurred on Unit 2. A fault in the switchyard |
| resulted in a Main Generator Trip which caused a Turbine Trip/Reactor Trip. |
| All rods fully inserted into the core. All other systems responded per |
| design with the following exceptions: |
| |
| 1). A Unit 1/Unit 2 Containment Ventilation Actuation occurred (caused by |
| electrical spike in the switchyard). This is not an Engineered Safety |
| feature (ESF) Actuation because all the Containment Ventilation Isolation |
| valves were already closed. |
| |
| 2). A Fuel Handling Building Ventilation ESF Actuation occurred (caused by |
| the electrical spike in the switchyard). |
| |
| 3). An 'A'-Train Main Control Room Makeup Air Filter Unit ESF Actuation |
| occurred (caused by the electrical spike in the switchyard). |
| |
| All Emergency Core Cooling Systems and the Emergency Diesel Generators are |
| fully operable if needed. At this time, the Motor-Driven Auxiliary |
| Feedwater Pump is maintaining proper Steam Generator Water Levels with |
| T(ave) being maintained at a no load temperature of 557�F. |
| |
| The switchyard fault is being investigated. |
| |
| The NRC Resident Inspector will be notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36586 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 01/13/2000|
| UNIT: [1] [2] [] STATE: SC |NOTIFICATION TIME: 04:21[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/13/2000|
+------------------------------------------------+EVENT TIME: 03:26[EST]|
| NRC NOTIFIED BY: JIM BURGESS |LAST UPDATE DATE: 01/13/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ROBERT HAAG R2 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| ENTERED TECHNICAL SPECIFICATION 3.0.3 FOR 17 MINUTES DUE TO LOW DIFFERENTIAL |
| PRESSURE BETWEEN THE CONTROL ROOM AND THE AUXILIARY BUILDING. |
| |
| A LOW CONTROL ROOM VENTILATION SYSTEM DIFFERENTIAL PRESSURE WAS DISCOVERED |
| WHILE A CONTROL ROOM VENTILATION SYSTEM AND AUXILIARY BUILDING VENTILATION |
| SYSTEM COMPENSATORY ACTION WAS IN EFFECT DUE TO AUXILIARY BUILDING |
| VENTILATION SYSTEM WORK. THE LICENSEE ENTERED TECHNICAL SPECIFICATION 3.0.3 |
| AT 0326ET. AT 0333ET, THE LICENSEE SECURED THE '2A' AUXILIARY BUILDING |
| VENTILATION FILTER EXHAUST FAN. TECHNICAL SPECIFICATION 3.0.3 WAS EXITED AT |
| 0343ET AFTER CONTROL ROOM DIFFERENTIAL PRESSURE WAS VERIFIED ABOVE THE |
| MINIMUM LIMIT. |
| |
| THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36587 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 01/13/2000|
| UNIT: [] [] [3] STATE: CT |NOTIFICATION TIME: 09:39[EST]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 01/12/2000|
+------------------------------------------------+EVENT TIME: 17:49[EST]|
| NRC NOTIFIED BY: D. LATZ/ WILSON |LAST UPDATE DATE: 01/13/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LAWRENCE DOERFLEIN R1 |
|10 CFR SECTION: |CHARLES MILLER IRO |
|HFIT 26.73 FITNESS FOR DUTY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 N Y 100 Power Operation |100 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| FITNESS-FOR-DUTY REPORT INVOLVING A LICENSED EMPLOYEE |
| |
| A licensed employee was arrested offsite by the Security force for |
| possession of a controlled substance. The licensed employee was released on |
| his own recognizance. The licensed employee notified his supervisor of his |
| arrest, and his access to the protected area was suspended. The licensed |
| employee took a drug test, and the results of the test have not been |
| completed. |
| |
| (Refer to the HOO Log for further details.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36588 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 01/13/2000|
| UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 17:04[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 03/25/1999|
+------------------------------------------------+EVENT TIME: 15:30[EST]|
| NRC NOTIFIED BY: STETSON |LAST UPDATE DATE: 01/13/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRENT CLAYTON R3 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 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. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36589 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 01/13/2000|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 17:41[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 01/13/2000|
+------------------------------------------------+EVENT TIME: 10:15[CST]|
| NRC NOTIFIED BY: STEVE JOBE |LAST UPDATE DATE: 01/13/2000|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JEFF SHACKELFORD R4 |
|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 N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| FITNESS-FOR-DUTY REPORT - |
| |
| A NON-LICENSED EMPLOYEE SUPERVISOR (PLANT EMPLOYEE) WAS DETERMINED TO BE |
| UNDER THE INFLUENCE OF ALCOHOL DURING A FOR-CAUSE TEST. THE SUPERVISOR'S |
| PLANT ACCESS AUTHORIZATION HAS BEEN REVOKED. THE LICENSEE INFORMED THE NRC |
| RESIDENT INSPECTOR. CALL TO THE NRC OPERATIONS OFFICER FOR ADDITIONAL |
| DETAILS. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021