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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  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35961       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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.                            |
+------------------------------------------------------------------------------+