Event Notification Report for July 28, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
07/27/1999 - 07/28/1999
** EVENT NUMBERS **
35961 35962 35963 35964 35965 35966
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|Power Reactor |Event Number: 35961 |
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+------------------------------------------------------------------------------+
| FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 07/27/1999|
| UNIT: [3] [] [] STATE: LA |NOTIFICATION TIME: 00:45[EDT]|
| RXTYPE: [3] CE |EVENT DATE: 07/26/1999|
+------------------------------------------------+EVENT TIME: 21:52[CDT]|
| NRC NOTIFIED BY: BILL CROWLEY |LAST UPDATE DATE: 07/27/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BILL JONES R4 |
|10 CFR SECTION: | |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
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| LICENSEE DETERMINED THAT UNDER CERTAIN METEOROLOGICAL CONDITIONS, THE |
| ULTIMATE HEAT SINK (DRY COOLING TOWERS) MAY NOT BE WITHIN THE LICENSING |
| BASIS OF THE FACILITY. |
| |
| "WATERFORD 3 IS NOT ABLE TO MEET LICENSING BASIS FOR ANALYZED RAINFALL |
| EVENTS. SPECIFICALLY, A SITE PROJECT STORM WITHOUT ANY DRY COOLING TOWER |
| SUMP PUMPS AVAILABLE AND A PROJECT MAXIMUM PRECIPITATION WITH ONLY ONE DRY |
| COOLING TOWER SUMP PUMP AVAILABLE. SINCE IT IS POSSIBLE THAT WATERFORD MAY |
| HAVE OPERATED IN A CONDITION WITH ONE DRY COOLING TOWER INOPERABLE AND THE |
| OTHER DRY COOLING TOWER HAVING ONLY ONE SUMP PUMP AVAILABLE, A PROJECT |
| MAXIMUM PRECIPITATION COULD HAVE INCAPACITATED THE OPERABLE DRY COOLING |
| TOWER. BASED ON THE CURRENT DRY COOLING TOWER SUMP PUMP CONFIGURATION AND |
| PREDICTED RAINFALL, BOTH DRY COOLING TOWERS REMAIN OPERABLE. THE PLAN IS TO |
| INSTALL A HIGH CAPACITY PORTABLE DIESEL SUMP PUMP IN EACH DRY COOLING AREA |
| WITHIN 24 HOURS." |
| |
| THE ABOVE CONDITION WAS DISCOVERED BY THE LICENSEE DURING A REVIEW OF A |
| DESIGN MODIFICATION. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35962 |
+------------------------------------------------------------------------------+
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| FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 07/27/1999|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 12:50[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 07/27/1999|
+------------------------------------------------+EVENT TIME: 08:50[CDT]|
| NRC NOTIFIED BY: WILLIAM B. GREEN |LAST UPDATE DATE: 07/27/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BILL JONES R4 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| INVALID HALF GROUP VII ISOLATION |
| |
| AT 0850 CDT 07/27/99, AN INVALID HALF GROUP VII ISOLATION OCCURRED ON THE |
| 'A" LOGIC. THIS ISOLATION IS NORMALLY CAUSED BY A LOW REACTOR WATER LEVEL |
| SIGNAL, GREATER THAN OR EQUAL TO -113 INCHES, OR A HIGH MAIN STEAM LINE |
| RADIATION SIGNAL, LESS THAN OR EQUAL TO 3 TIMES NORMAL FULL POWER |
| BACKGROUND. NEITHER OF THESE SIGNALS WERE PRESENT. REACTOR RECIRCULATION |
| AIR OPERATED VALVE #RR-AO-741, SAMPLE POINT 1 INBOARD ISOLATION VALVE, |
| CLOSED AS A RESULT OF THIS CONDITION. THIS ISOLATION RESULTED IN THE PLANT |
| ENTERING LCO 3.4.1, CONDITION "B", DUE TO THE INABILITY TO SAMPLE THE |
| REACTOR COOLANT. |
| |
| UNRELATED WORK WAS BEING PERFORMED IN THE GENERAL AREA OF THE ISOLATION |
| RELAY. A SPURIOUS ACTUATION OF THE RELAY OCCURRED, RESULTING IN THE VALVE |
| ISOLATION. AN INVESTIGATION OF THIS EVENT IS IN PROGRESS. THE RELAY WAS |
| RESET WITH STATION PERSONNEL PRESENT TO DETERMINE THAT THE RELAY HAD |
| FUNCTIONED PROPERLY. THE HALF GROUP ISOLATION HAS BEEN RESET AND VALVE |
| #RR-AO-741 HAS BEEN REOPENED. LCO 3.4.1 HAS BEEN EXITED DUE TO THE SAMPLING |
| FUNCTION BEING RETURNED TO SERVICE. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35963 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 07/27/1999|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 13:25[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 07/27/1999|
+------------------------------------------------+EVENT TIME: 11:45[EDT]|
| NRC NOTIFIED BY: PETE GARDNER |LAST UPDATE DATE: 07/27/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN KINNEMAN R1 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| RESIDUAL HEAT REMOVAL (RHR) PUMP RECEIVED A START SIGNAL DURING A |
| SURVEILLANCE TEST. |
| |
| AT 1145 ON 07/27/99, DURING PERFORMANCE OF A SURVEILLANCE TEST FOR REMOTE |
| SHUTDOWN PANEL OPERABILITY (#ST-2-088-321-2), THE "2A" RHR PUMP RECEIVED A |
| START SIGNAL. AT THE TIME, CONTROL OF THE PUMP HAD BEEN TRANSFERRED TO THE |
| REMOTE SHUTDOWN PANEL. THE PUMP START WAS UNEXPECTED AND THUS, IS BEING |
| REPORTED AS AN ESF ACTUATION UNDER THE GUIDANCE OF LIMERICK REPORTABILITY |
| MANUAL (F-02). THE TRANSFER SWITCH WAS BEING CLEANED AND CYCLED DURING THE |
| PUMP START AND AT THIS TIME IT IS BELIEVED THAT A CONTACT HAD INADVERTENTLY |
| MADE UP. THE CAUSE OF THE EVENT IS BEING INVESTIGATED AND THE "2A" RHR PUMP |
| AND THE REMOTE SHUTDOWN PANEL HAVE CONSERVATIVELY BEEN DECLARED INOPERABLE |
| UNTIL THE INVESTIGATION IS COMPLETE. THE RHR PUMP WAS REMOVED FROM SERVICE |
| AFTER RETURNING CONTROL POWER VIA THE REMOTE SHUTDOWN TRANSFER SWITCH. |
| |
| ALL OTHER EMERGENCY CORE COOLING SYSTEMS ARE FULLY OPERABLE, IF NEEDED. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 35964 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: UNITED STATES AIR FORCE |NOTIFICATION DATE: 07/27/1999|
|LICENSEE: UNITED STATES AIR FORCE |NOTIFICATION TIME: 16:58[EDT]|
| CITY: WASHINGTON DC REGION: 1 |EVENT DATE: 07/26/1999|
| COUNTY: STATE: DC |EVENT TIME: 10:00[EDT]|
|LICENSE#: 42-23539-01AF AGREEMENT: N |LAST UPDATE DATE: 07/27/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |ROBERT HAAG R2 |
| |BILL JONES R4 |
+------------------------------------------------+CHARLEY HAUGHNEY NMSS |
| NRC NOTIFIED BY: MAJOR HICKS | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAE1 20.2202(b)(1) PERS OVEREXPOSURE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| USAF PERSON INHALED DEPLETED URANIUM DUST |
| |
| THE USAF RADIOISOTOPE COMMITTEE, BOLLING AIR FORCE BASE, REPORTED THE |
| FOLLOWING INCIDENT WHICH OCCURRED AT ROBINS AIR FORCE BASE, GEORGIA . |
| |
| AT 1000 ON 07/26/99, USAF PERSONNEL WERE PERFORMING MAINTENANCE ON A C-141 |
| CARGO AIRCRAFT AILERON. A TECHNICIAN WAS FOUND USING A HAMMER AND CHISEL TO |
| REMOVE INSTALLED DEPLETED URANIUM COUNTERWEIGHTS FROM THE AILERON. THIS |
| PROCESS PRODUCED DUST AND DEBRIS WHICH WAS SCATTERED BY A NEARBY FAN. THE |
| TECHNICIAN USING A HAMMER AND CHISEL ON THE DEPLETED URANIUM WAS IN |
| VIOLATION OF SEVERAL RULES. |
| |
| UPON DISCOVERY OF THIS ACTIVITY, THE TECHNICIAN WAS TOLD TO IMMEDIATELY STOP |
| WORK . THE AREA HAS BEEN SECURED AND DECONTAMINATION PROCEDURES INITIATED. |
| HEALTH PHYSICS SUPPORT HAS BEEN REQUESTED FROM BROOKS AIR FORCE BASE, SAN |
| ANTONIO, TEXAS. BIOASSAYS OF THE TECHNICIAN AND OTHER WORKERS IN THE AREA |
| HAS BEEN INITIATED. |
| |
| CONTAMINATION LEVELS IN THE ROOM WHERE THE MAINTENANCE WAS BEING PERFORMED |
| WERE FOUND TO BE ABOVE BACKGROUND (NUCLEAR RESEARCH CORPORATION MODEL |
| ADM-300 DETECTOR WITH A PANCAKE PROBE WAS USED TO SURVEY THE AREA). THE |
| AREA OF CONTAMINATION HAS BEEN CONFINED TO THE BUILDING 180 MAINTENANCE |
| BAY. |
| |
| A FOLLOWUP REPORT BY THE USAF RADIOISOTOPE COMMITTEE WILL BE MADE TO NRC |
| REGION 4 BY 08/27/99. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35965 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 07/27/1999|
| UNIT: [] [3] [] STATE: NY |NOTIFICATION TIME: 19:57[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 07/27/1999|
+------------------------------------------------+EVENT TIME: 19:00[EDT]|
| NRC NOTIFIED BY: STEPHEN DAVIS |LAST UPDATE DATE: 07/27/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN KINNEMAN R1 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|3 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| A MODIFIED CONNECTION BETWEEN TWO CONTAINMENT ISOLATION VALVES WAS FOUND TO |
| LEAK WHICH PLACED UNIT 3 OUTSIDE ITS DESIGN BASIS. |
| |
| DURING THE RETURN OF PIPING PENETRATIONS TO SERVICE FOLLOWING THE |
| INSTALLATION OF A MODIFICATION TO THE ISOLATION VALVE SEAL WATER SYSTEM, IT |
| WAS DETERMINED THAT A MODIFIED CONNECTION BETWEEN CONTAINMENT ISOLATION |
| VALVES #WD-AOV-1723 AND #WD-AOV-1728 LEAKED. UPON INVESTIGATION, AT 1727, |
| IT WAS DETERMINED THAT CONTAINMENT INTEGRITY WAS NOT ESTABLISHED. THE |
| AFFECTED PENETRATIONS WERE ISOLATED AT 1810, BY DEACTIVATING INNER AIR |
| OPERATED VALVES OR BY LOCKED CLOSED MANUAL VALVES. AT 1900, IT WAS |
| DETERMINED THAT UNIT 3 HAD BEEN POTENTIALLY OUTSIDE ITS DESIGN BASIS |
| BETWEEN 1610, WHEN THE PIPING PENETRATIONS WERE RETURNED TO SERVICE, AND |
| 1810, WHEN THE PENETRATIONS WERE ISOLATED. DURING THE PERIOD WHEN THE |
| PIPING PENETRATION WERE UNISOLATED, A POSTULATED SINGLE FAILURE COULD HAVE |
| RESULTED IN A DIRECT PATHWAY FROM CONTAINMENT ATMOSPHERE TO PRIMARY |
| AUXILIARY BUILDING ATMOSPHERE. |
| |
| THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35966 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 07/27/1999|
| UNIT: [1] [2] [] STATE: MI |NOTIFICATION TIME: 21:10[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/27/1999|
+------------------------------------------------+EVENT TIME: 18:45[EDT]|
| NRC NOTIFIED BY: SAM PARTIN |LAST UPDATE DATE: 07/27/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GEOFFREY WRIGHT R3 |
|10 CFR SECTION: | |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
|2 N N 0 Refueling |0 Refueling |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| ALL FOUR EMERGENCY DIESEL GENERATORS (EDGs) DECLARED INOPERABLE BUT |
| FUNCTIONAL.. |
| |
| DURING THE RECENT EXPANDED SYSTEM READINESS REVIEW, IT WAS IDENTIFIED THAT |
| THE EDG COMBUSTION AIR INTAKE AND EXHAUST STRUCTURES AND THE EDG ROOM |
| VENTILATION INTAKE AND EXHAUST STRUCTURES MAY NOT MEET THE DESIGN CRITERIA |
| SPECIFIED IN THE UFSAR. IT IS APPARENT THAT THESE STRUCTURES MAY NOT BE |
| CAPABLE OF WITHSTANDING THE EFFECTS OF TORNADO GENERATED MISSILES. THE |
| LICENSEE CURRENTLY DOES NOT HAVE REASONABLE ASSURANCE THAT, WHILE THE |
| REACTOR WAS IN OPERATION, THE EDGs WOULD HAVE PERFORMED THEIR SAFETY |
| FUNCTION DURING A TORNADO EVENT. |
| |
| FURTHER EVALUATIONS ARE IN PROCESS TO DETERMINE THE CORRECTIVE ACTIONS |
| NEEDED TO RESTORE THE EDGs TO OPERABLE STATUS. |
| |
| UNIT 1 IS IN MODE 5 AND UNIT 2 IS DEFUELED. ALL EDGs ARE FUNCTIONAL. THE |
| LICENSEE IS PURSUING JUSTIFICATION TO ALLOW THE START OF OFFLOADING THE UNIT |
| 1 CORE. BOTH UNITS HAVE BEEN SHUTDOWN SINCE 09/12/97. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
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