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Event Notification Report for October 29, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/28/1999 - 10/29/1999

                              ** EVENT NUMBERS **

36358  36359  36360  36361  36362  36363  36364  36365  36366  36367  36368  36369 
36370  

+------------------------------------------------------------------------------+
|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:  10/28/1999|
|  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     |
|                                                |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 1134  10/28/1999 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).                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36359       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS              REGION:  4  |NOTIFICATION DATE: 10/28/1999|
|    UNIT:  [1] [] []                 STATE:  TX |NOTIFICATION TIME: 10:13[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        04/22/1999|
+------------------------------------------------+EVENT TIME:        21:00[CDT]|
| NRC NOTIFIED BY:  JIM MORRIS                   |LAST UPDATE DATE:  10/28/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHARLES MARSCHALL    R4      |
|10 CFR SECTION:                                 |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24-HOUR REPORT REQUIRED BY FACILITY OPERATING LICENSE                        |
|                                                                              |
| "24-hour Report regarding Violation of Operating License NPF-76 for          |
| performing Core Alterations in Unit 1 while Containment Equipment Hatch was  |
| open.                                                                        |
|                                                                              |
| "In accordance with Technical Specification 3.9.4, Containment Building      |
| Penetrations, the equipment hatch must be closed and held in place by at     |
| least four bolts during Core Alterations or movement of irradiated fuel      |
| within the containment.                                                      |
|                                                                              |
| "The South Texas Project Technical Specifications define Core Alterations as |
| the movement or manipulation of any component within the reactor pressure    |
| vessel with the vessel head removed and fuel in the vessel. The insertion of |
| the incore detector thimbles into the core is considered a Core Alteration.  |
|                                                                              |
| "It has been determined that during Unit 1 refueling outage 1RE08, between   |
| 2100 hours on April 22, 1999, and 0030 hours on April 23, 1999, the incore   |
| detector thimbles were inserted into the reactor core after the containment  |
| equipment hatch was opened. At this time all fuel assemblies had been        |
| reloaded into the reactor core and refueling cavity level had been reduced   |
| to permit setting the reactor vessel head.                                   |
|                                                                              |
| "This notification is being made pursuant to Operating License NPF-76        |
| Condition 2.G for operation or condition prohibited by Technical             |
| Specifications."                                                             |
|                                                                              |
| The licensee discovered this occurrence as the result of a review of a       |
| Condition Report.                                                            |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36360       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OCONEE                   REGION:  2  |NOTIFICATION DATE: 10/28/1999|
|    UNIT:  [1] [2] [3]               STATE:  SC |NOTIFICATION TIME: 10:54[EDT]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE:        10/28/1999|
+------------------------------------------------+EVENT TIME:        08:20[EDT]|
| NRC NOTIFIED BY:  PAULINE BEATTY               |LAST UPDATE DATE:  10/28/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MARK LESSER          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  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|3     N          Y       100      Power Operation  |100      Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FITNESS FOR DUTY EVENT                                                       |
|                                                                              |
| A licensed operator tested positive for illegal drug use during a random     |
| screening. The individual's site access has been suspended, and the          |
| individual will be referred to the Employee Assistance Program for           |
| evaluation. The NRC resident inspector has been informed of this event by    |
| the licensee. Contact the NRC Operations Center for additional details.      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36361       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ROBINSON                 REGION:  2  |NOTIFICATION DATE: 10/28/1999|
|    UNIT:  [2] [] []                 STATE:  SC |NOTIFICATION TIME: 11:14[EDT]|
|   RXTYPE: [2] W-3-LP                           |EVENT DATE:        10/28/1999|
+------------------------------------------------+EVENT TIME:        10:19[EDT]|
| NRC NOTIFIED BY:  DAVE BLAKENEY                |LAST UPDATE DATE:  10/28/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MARK LESSER          R2      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| SECURITY EVENT -                                                             |
|                                                                              |
| UNESCORTED ACCESS GRANTED INAPPROPRIATELY TO A CONTRACTOR EMPLOYEE.          |
| COMPENSATORY ACTIONS TAKEN IMMEDIATELY UPON DISCOVERY.  CONTACT THE NRC      |
| HEADQUARTERS OPERATIONS OFFICER FOR ADDITIONAL DETAILS.  THE LICENSEE        |
| NOTIFIED THE NRC RESIDENT INSPECTOR.                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36362       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI                    REGION:  3  |NOTIFICATION DATE: 10/28/1999|
|    UNIT:  [2] [] []                 STATE:  MI |NOTIFICATION TIME: 11:57[EDT]|
|   RXTYPE: [2] GE-4                             |EVENT DATE:        10/27/1999|
+------------------------------------------------+EVENT TIME:        17:00[EDT]|
| NRC NOTIFIED BY:  SANJEEV ARAB                 |LAST UPDATE DATE:  10/28/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MIKE JORDAN          R3      |
|10 CFR SECTION:                                 |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       97       Power Operation  |97       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - PLANT FIRE PROTECTION PROGRAM PROCEDURES DID NOT INCLUDE CERTAIN FIRE      |
| ZONES -                                                                      |
|                                                                              |
| During the performance of a licensee Fire Protection Audit, it was           |
| discovered that an error existed in plant procedures designed to shut the    |
| plant down in the event of a fire in plant areas where hot shorts could      |
| challenge safe plant operation.  In 1994, a new style air-operated HPCI/RCIC |
| test return valve was installed in the plant.  At the time, it was           |
| recognized that due to cable run locations, hot shorts could be created in   |
| the event of a fire in certain areas that would cause the valve to open      |
| inadvertently.  This would cause bypass of standby feedwater  flow to the    |
| condensate storage tank instead of the reactor pressure vessel (RPV) and     |
| challenge the ability to maintain RPV level.  Plant procedures for dedicated |
| shutdown were revised to isolate air to that valve to prevent this response  |
| for fires in specified zones.  However, during a recent licensee audit, it   |
| was discovered that hot shorts for the test valve could exist for fires in   |
| some plant zones not previously identified. This was discovered at 1700 on   |
| 10/27/99.  The procedure has since been corrected to add these zones.        |
|                                                                              |
| This event constitutes a non-compliance with the approved Fire Protection    |
| Program which could have adversely affected the plant's ability to achieve   |
| and maintain safe shutdown in the event of a fire.  This is reportable as a  |
| condition not in compliance with Fermi 2 Operating License NPF-43, License   |
| Condition 2.C.9.  This notification is required to be submitted within 24    |
| hours in accordance with NRC License NPF-43, Section 2.F.                    |
|                                                                              |
| The licensee plans to notify the NRC Resident Inspector.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36363       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SALEM                    REGION:  1  |NOTIFICATION DATE: 10/28/1999|
|    UNIT:  [1] [2] []                STATE:  NJ |NOTIFICATION TIME: 15:33[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        10/28/1999|
+------------------------------------------------+EVENT TIME:        15:00[EDT]|
| NRC NOTIFIED BY:  JOHN F. GARECHT              |LAST UPDATE DATE:  10/28/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVID LEW            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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       45       Power Operation  |45       Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OUTSIDE DESIGN BASIS BASED ON APPENDIX R ISSUE                               |
|                                                                              |
| During an ongoing review of the current Salem Post-fire Safe Shutdown        |
| Analysis a concern was identified with the 125 VDC control circuits for the  |
| 4KV circuit breakers in the post fire Alternate Shutdown Area.  Alternate    |
| Shutdown (ASD) is implemented in the event of a fire in the Control Room,    |
| Relay Room or the ceiling of the 460 V Switchgear room (ASD area).           |
| Operators implement the ASD methodology in accordance with procedures        |
| S1(2).OP-AB.CR-0002.  The procedures require that 125 VDC control power to   |
| required 4KV breakers be isolated by opening the main bus feeder breaker     |
| local to the switchgear.  The 4KV breakers are then manually operated at the |
| switchgear as necessary to shed and load the 4KV buses in the event of loss  |
| of offsite power.                                                            |
|                                                                              |
| In the event of a postulated fire in the ASD area, cables associated with    |
| the 4KV breaker 125 VDC control circuits could experience a hot short on the |
| positive side of the open/close coils.  Such a short occurring in            |
| combination with multiple grounds (occurring due to the postulated fire on   |
| negative 125 VDC circuit legs could result in energization of the closing or |
| trip coils.  This effectively bypasses the isolation provided by opening the |
| control power breaker.  This fire induced circuit failure (due to a          |
| combination of one hot short and two shorts to ground) could result in the   |
| inability to locally operate one or more 4KV breakers as required for        |
| alternate shutdown unless the hot short is removed.  This scenario could     |
| lead to loss of vital buses (worst case).  This event is applicable to 460 V |
| Switchgear room and relay room.  It is not applicable to the fire in control |
| room because the affected cables are not routed in the control room.  This   |
| condition does not satisfy the 10CFR50 Appendix R performance goal of        |
| providing necessary electrical support functions for post fire safe          |
| shutdown.                                                                    |
|                                                                              |
| Immediate corrective action is an hourly roving fire watch established in    |
| accordance with the fire protection program.  Long term corrective action    |
| includes evaluating plant modifications and/or licensing/design basis        |
| changes, and a review of other components relied upon for ASD of the plant   |
| to determine if there are any other ungrounded DC control circuits which     |
| could malfunction in the same manner.                                        |
|                                                                              |
| The licensee will notify the NRC resident inspector.                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36364       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 10/28/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 16:16[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        10/27/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        17:05[CDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  10/28/1999|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |MIKE JORDAN          R3      |
|  DOCKET:  0707001                              |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  W.F. CAGE                    |                             |
|  HQ OPS OFFICER:  DOUG WEAVER                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| Safety System Actuation                                                      |
|                                                                              |
| At  1705 CDT on 10/27/99, the Plant Shift Superintendent's (PSS) office was  |
| notified that a primary condensate alarm was received on the C-360 position  |
| 2 autoclave Water Inventory Control (WIC) System.  The WIC system is         |
| required to be operable while heating in mode 5 according to TSR 2.1.4.3.    |
| The autoclave was checked according to the alarm response procedure, removed |
| from service and declared inoperable by the PSS. Troubleshooting was         |
| initiated and is continuing in order to determine the reason for the alarm.  |
|                                                                              |
| The safety system actuation is reportable to the NRC as required by Safety   |
| Analysis Report, section 6.9, table 1 criteria J.2, Safety System actuation  |
| due to a valid signal as a 24-hour event notification.                       |
|                                                                              |
| The NRC resident inspector has been notified.                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   36365       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  COGEMA MINING, INC.                  |NOTIFICATION DATE: 10/28/1999|
|LICENSEE:  COGEMA MINING, INC.                  |NOTIFICATION TIME: 16:29[EDT]|
|    CITY:  LINCH                    REGION:  4  |EVENT DATE:        10/28/1999|
|  COUNTY:                            STATE:  WY |EVENT TIME:             [MDT]|
|LICENSE#:  SUA-1341              AGREEMENT:  N  |LAST UPDATE DATE:  10/28/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CHARLES MARSCHALL    R4      |
|                                                |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  CRAIG TOAL                   |                             |
|  HQ OPS OFFICER:  DOUG WEAVER                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MONITOR WELL IN EXCURSION STATUS                                             |
|                                                                              |
| A routine biweekly water sample collected on 10/26/99 from monitor well      |
| #6MW21 exceeded all three of its upper control limits (UCLs).  A             |
| confirmation sample was collected on 10/26/99 and it also exceeded all three |
| of its UCLs.  Well #6MW21 has been placed in excursion status per license    |
| Section 11.2 and its sampling frequency increased to weekly.  Well #6MW21 is |
| a perimeter ore zone monitor well located approximately 300 feet south of    |
| the Mine Unit 6 boundary at the Christensen Mine, Campbell County, Wyoming.  |
| The nearest community is Lint, Wyoming, approximately 15 miles to the        |
| southeast.                                                                   |
|                                                                              |
| Analysis:                                                                    |
| Date                          Chloride                                       |
| Conductivity               Alkalinity                        Uranium         |
| Sampled                  (mg/I)                                              |
| (umhos/cm2)             (mg/l)                              (mg/I U-308)     |
|                                                                              |
| UCL 120.0                              UCL 1576                     UCL 95.2 |
| UCL none                                                                     |
| 10-26-99                    32.2                                             |
| 1800                              329.4                                0.5   |
| 10-28-99                    29.2                                             |
| 1746                              305.8                                0.5   |
|                                                                              |
| Health and Environmental Hazards:                                            |
| None                                                                         |
|                                                                              |
| Corrective Action:                                                           |
| Over-recovery pumping of the wellfield area nearest Mine #6MW21              |
|                                                                              |
| Written Notification:                                                        |
| A written notification will be submitted to NRC Uranium Recovery Branch      |
| Chief within 7 days.                                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36366       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DIABLO CANYON            REGION:  4  |NOTIFICATION DATE: 10/28/1999|
|    UNIT:  [1] [2] []                STATE:  CA |NOTIFICATION TIME: 18:20[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        10/28/1999|
+------------------------------------------------+EVENT TIME:        13:59[PDT]|
| NRC NOTIFIED BY:  JOY SKAGGS                   |LAST UPDATE DATE:  10/28/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHARLES MARSCHALL    R4      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     M/R        Y       70       Power Operation  |0        Hot Standby      |
|2     M/R        Y       30       Power Operation  |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIPS OF BOTH UNITS                                           |
|                                                                              |
| UNIT 1:  Manual reactor trip initiated due to loss of both circulating water |
| pumps during heavy sea conditions.  Following the reactor trip, auxiliary    |
| feedwater pumps 2-2 and 2-3 auto started.  Auxiliary feedwater pump 2-1 was  |
| already running for a scheduled surveillance test.  A feedwater isolation    |
| actuation occurred on reactor trip with low T-avg signal.  The reactor is    |
| currently stable in hot standby with the MSIVs closed.  All control rods     |
| fully inserted on the trip and reactor coolant pumps continued to run        |
| throughout the event.  Decay heat is being removed by steaming the           |
| generators through the atmospheric dumps.  The unit will remain in hot       |
| standby until heavy sea conditions have subsided.                            |
|                                                                              |
| UNIT 2:  Manual reactor trip initiated due to loss of both circulating water |
| pumps during heavy sea conditions.  Following the reactor trip, all          |
| auxiliary feedwater pumps auto started, a feedwater isolation actuation      |
| occurred on reactor trip with low T-avg signal, and emergency diesel         |
| generators 1-1 and 1-3 auto started but did not load.  The reactor is        |
| currently stable in hot standby with MSIVs closed.  All control rods fully   |
| inserted on the trip and reactor coolant pumps continued to run throughout   |
| the event.  Decay heat is being removed by steaming the generators through   |
| the atmospheric dumps.  The unit will remain in hot standby until heavy sea  |
| condition have subsided.                                                     |
|                                                                              |
| The licensee notified the NRC resident inspector, the San Luis Obispo        |
| Sheriff's Office and the California State Office of Emergency Services.      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   36367       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  QUEENS MEDICAL CENTER                |NOTIFICATION DATE: 10/28/1999|
|LICENSEE:  QUEENS MEDICAL CENTER                |NOTIFICATION TIME: 19:18[EDT]|
|    CITY:  HONOLULU                 REGION:  4  |EVENT DATE:        10/27/1999|
|  COUNTY:                            STATE:  HI |EVENT TIME:        16:16[HST]|
|LICENSE#:  53-16533-02           AGREEMENT:  N  |LAST UPDATE DATE:  10/28/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CHARLES MARSCHALL    R4      |
|                                                |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ALAN CASSADY                 |                             |
|  HQ OPS OFFICER:  DOUG WEAVER                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|LADM 35.33(a)            MED MISADMINISTRATION  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MEDICAL MISADMINISTRATION                                                    |
|                                                                              |
| A patient received a fractional dose to the wrong area because of problems   |
| with the measuring device used to locate the dose.  The reference point used |
| was 950 mm, but it should have been 995 mm.  The error resulted from the     |
| measuring device "snagging" on a kink in the cable, thus preventing complete |
| insertion.  The net result was an error of approximately 4.5 cm.  The 380    |
| cGy fraction was delivered to the end of the nose vice further in as         |
| prescribed.  The fraction was one of four planned with a total intended dose |
| of 1520 cGy.   The source involved was 6.8 Ci of Ir-192.                     |
|                                                                              |
| The patient and doctor have been informed of the error.  No adverse          |
| consequences are expected for the patient.                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36368       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES              REGION:  3  |NOTIFICATION DATE: 10/28/1999|
|    UNIT:  [1] [2] []                STATE:  IL |NOTIFICATION TIME: 19:45[EDT]|
|   RXTYPE: [1] GE-3,[2] GE-3                    |EVENT DATE:        09/10/1999|
+------------------------------------------------+EVENT TIME:        14:45[CDT]|
| NRC NOTIFIED BY:  DARYL CLARK                  |LAST UPDATE DATE:  10/28/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MIKE JORDAN          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  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OUTSIDE DESIGN BASIS - HIGH CONTROL ROOM EMERGENCY FILTRATION SYSTEM FLOW    |
|                                                                              |
| On September 10, 1999, while performing the Control Room Emergency           |
| Filtration System monthly surveillance, the system flow rate was found to be |
| 2317 scfm.  The required Tech Spec flow rate is 2000 scfm +/-10%.  The       |
| condition was immediately corrected at the time of discovery by              |
| repositioning the ventilation damper.  This event is still being evaluated   |
| by the licensee.                                                             |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36369       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 10/29/1999|
|    UNIT:  [1] [] []                 STATE:  FL |NOTIFICATION TIME: 02:14[EDT]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        10/29/1999|
+------------------------------------------------+EVENT TIME:        01:29[EDT]|
| NRC NOTIFIED BY:  EMLING                       |LAST UPDATE DATE:  10/29/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MARK LESSER          R2      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC TURBINE TRIP/REACTOR TRIP DUE TO LOSS OF MAIN TURBINE BEARING OIL  |
| PRESSURE                                                                     |
|                                                                              |
| The reactor automatically tripped from 100% power when the main turbine      |
| tripped due to low bearing oil pressure. All control rods inserted           |
| completely, and all systems functioned as expected. The auxiliary feedwater  |
| system automatically started to feed the steam generators.                   |
|                                                                              |
| The licensee reported that a main turbine low bearing oil pressure alarm had |
| been received in the control room several minutes before the trip. An        |
| operator had just been dispatched to investigate the cause of the alarm when |
| the main turbine automatically tripped.                                      |
|                                                                              |
| The NRC resident inspector will be informed of this event by the licensee.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36370       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DUANE ARNOLD             REGION:  3  |NOTIFICATION DATE: 10/29/1999|
|    UNIT:  [1] [] []                 STATE:  IA |NOTIFICATION TIME: 04:41[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        10/29/1999|
+------------------------------------------------+EVENT TIME:        02:45[CDT]|
| NRC NOTIFIED BY:  MIKE DAVIS                   |LAST UPDATE DATE:  10/29/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MIKE JORDAN          R3      |
|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          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| STANDBY DIESEL GENERATOR AUTOSTART DUE TO LIGHTNING STRIKE                   |
|                                                                              |
| The licensee reported that one of the standby diesel generators autostarted, |
| but did not load, due to a lightning strike. The load dispatcher informed    |
| the site that numerous strikes were also taken on the electrical grid in the |
| vicinity of the site, causing some breaker repositioning. However, the site  |
| was unaffected, except for the autostart of the diesel generator.            |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+