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Event Notification Report for October 27, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/26/1999 - 10/27/1999

                              ** EVENT NUMBERS **

36266  36267  36296  36314  36347  36348  36349  36350  36351  36352  36353  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36266       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 10/06/1999|
|    UNIT:  [1] [2] []                STATE:  PA |NOTIFICATION TIME: 18:15[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        10/06/1999|
+------------------------------------------------+EVENT TIME:        17:45[EDT]|
| NRC NOTIFIED BY:  DAUGHERTY                    |LAST UPDATE DATE:  10/26/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       90       Power Operation  |90       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ERROR FOUND IN LARGE BREAK LOCA ANALYSIS                                     |
|                                                                              |
| "Westinghouse Letter DLC-99-768 reported errors found in the Large Break     |
| LOCA analysis for both Beaver Valley units.  These errors resulted in        |
| calculated maximum Peak Clad Temperatures >2200F with out taking credit for |
| any other available margins.  Per 10CFR50.46.a.3.(ii), any change or error   |
| correction that results in a calculated ECCS performance (where Peak Clad    |
| Temperature is not maintained <2200F) Is reportable per 10CFR50.72          |
|                                                                              |
| "It should be noted that Westinghouse Letter DLC-99-768 proposed a more      |
| conservative restriction on FQ limits for both units, and a more             |
| conservative limit on Steam Generator tube plugging at unit 2 that would     |
| overcome the effects of the reported errors.  These limits are presently     |
| being met and have been met for the time periods of the present cycles at    |
| both units, so that the proposed analysis appears to be valid.  Engineering  |
| evaluation is pending for final approval of these proposals."                |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.                   |
|                                                                              |
| * * * Retraction on 10/26/99 at 1430 ET by C. Hynes taken by MacKinnon at    |
| 1458 ET * * *                                                                |
|                                                                              |
| Available design margins in FQ and steam generator tube plugging at Unit 2   |
| were sufficient to offset the increase in PCT due to the identified errors   |
| and maintain compliance with the ECCS Performance Criteria of 10 CFR 50.46.  |
| Utilizing these design margins has necessitated reduction of the FQ          |
| surveillance limits in the Core Operating Limits Report.  Administrative     |
| controls were implemented on 10/08/99 to achieve this reduction in the FQ    |
| surveillance limits.  A review of completed flux maps has shown that the     |
| reduced FQ limit has been met for the present operating cycle.  Current      |
| steam generator tube plugging levels were also confirmed to be less than the |
| reduced limit.  Subsequent engineering review has confirmed that the         |
| evaluations performed by Westinghouse show that all applicable safety        |
| analysis acceptance criteria continue to be met.  Recovery of available      |
| margin results in a PCT that has in the past and presently remains < 2000 F. |
| As such, the basis for retraction of the 10CFR50.72 notification on 10/06/99 |
| is that this condition does not place either Unit outside its design basis.  |
| However, this condition is applicable to the 30 day reporting criteria of 10 |
| CFR 50.46(a)(3)(ii). R1DO (David Lew) notified.                              |
|                                                                              |
| The NRC Resident Inspector was notified of this retraction by the licensee.. |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36267       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VERMONT YANKEE           REGION:  1  |NOTIFICATION DATE: 10/06/1999|
|    UNIT:  [1] [] []                 STATE:  VT |NOTIFICATION TIME: 18:28[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        10/06/1999|
+------------------------------------------------+EVENT TIME:        16:40[EDT]|
| NRC NOTIFIED BY:  DENNIS MAY                   |LAST UPDATE DATE:  10/26/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN KINNEMAN        R1      |
|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       99       Power Operation  |99       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BOTH TRAINS OF LOW PRESSURE COOLANT INJECTION DECLARED INOPERABLE            |
|                                                                              |
| During periodic inspections, technicians discovered multiple loose battery   |
| terminal connections on both UPS-1A and UPS-1B batteries.  The licensee was  |
| uncertain of the operability of the batteries and conservatively declared    |
| both trains of low pressure coolant injection (LPCI) inoperable.  This put   |
| them in a 24-hour Technical Specification action statement (3.5.A.6) to      |
| bring the plant to hot shutdown.  Electrical maintenance is on site          |
| tightening connections and inspecting all battery connections.  The licensee |
| does not anticipate having to shutdown as electrical maintenance is working  |
| now.  An investigation into the event will follow up the event.              |
|                                                                              |
| The licensee notified the NRC Resident Inspector and the State of Vermont    |
| Nuclear Engineer.                                                            |
|                                                                              |
|                                                                              |
| * * * Retraction on 10/26/99 at 1639 ET by Mark Magnuson taken by MacKinnon  |
| * * *                                                                        |
|                                                                              |
| Vermont Yankee Design Electrical Engineering (EE) has since evaluated the    |
| as-found condition of the battery terminals (interconnection plate fasteners |
| at less than the required torque).  EE reviewed the as-found interconnection |
| resistance values.  Those resistance values showed that the total resistance |
| created by the battery connections in the as-found configuration was         |
| elevated by only 0.57%.  The as-found resistance's also showed that the      |
| highest resistance interconnection would, with running load placed upon the  |
| battery, have induced a voltage drop of less than 0.002% of rated battery    |
| voltage.  Additionally, the potential heating of the highest resistance      |
| interconnection plate assembly (under running load) was determined to be 0.6 |
| watt-hours.  This is not sufficient energy to cause overheating of the       |
| connection.                                                                  |
|                                                                              |
| EE's conclusion after a detailed assessment of the condition of the 2 UPS    |
| batteries, is that they were operational at all times they were considered   |
| operable.  Therefore, they were fully capable of supporting operation of the |
| LPCI system. Therefore, this event is being retracted by the licensee.       |
|                                                                              |
| R1DO (David Lew) notified.  The NRC Resident Inspector was notified by the   |
| licensee of the retraction of the event.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36296       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CRYSTAL RIVER            REGION:  2  |NOTIFICATION DATE: 10/15/1999|
|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 13:09[EDT]|
|   RXTYPE: [3] B&W-L-LP                         |EVENT DATE:        10/15/1999|
+------------------------------------------------+EVENT TIME:        10:00[EDT]|
| NRC NOTIFIED BY:  BILL BANDHAUSER              |LAST UPDATE DATE:  10/26/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CAUDLE JULIAN        R2      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| GREATER THAN 1% OF THE 'A' ONCE-THROUGH STEAM GENERATOR (OTSG) TUBES ARE     |
| DEFECTIVE.                                                                   |
|                                                                              |
| Plant personnel determined that the inspection of the 'A' OTSG found 10 of   |
| 528 tubes to have "indication of a defect" using the plus point probe        |
| inspection of the lower tube sheet secondary face ding/dent population.      |
|                                                                              |
| Because there is no qualified sizing technique for circumferential           |
| crack-like or volumetric indications in this region, it cannot be            |
| demonstrated that the through-wall depth penetration of these indications is |
| less than 40% of the tube wall.  Therefore, the tubes containing these       |
| indications must be classified as "Defective."                               |
|                                                                              |
| Since more than 1% of the sample size was determined to be defective, the    |
| inspection result is classified as "C-3" as defined in paragraph             |
| 5.6.2.10.2.f of the Crystal River Unit 3 Improved Technical Specifications   |
| (ITS).                                                                       |
|                                                                              |
| Table 5.6.2-2 of Crystal River Unit 3 ITSs requires that this "C-3" result   |
| be reported to the NRC per 10 CFR 50.72.                                     |
|                                                                              |
| This condition is considered to be a serious degradation of a principal      |
| safety barrier (Reactor Coolant System) discovered while shutdown.           |
|                                                                              |
| Prior to the current Crystal River Unit 3 plant shutdown on 10/01/99, the    |
| actual primary to secondary leakage through the 'A' OTSG was significantly   |
| below the allowable limit of ITS 3.4.12.d (less that 150 gallons per day).   |
|                                                                              |
| The NRC Resident Inspector was notified of this event notification by the    |
| licensee.                                                                    |
|                                                                              |
| * * * Update by Bandhauer on 10/26/99 at 1507ET taken by MacKinnon * * *     |
|                                                                              |
|                                                                              |
| Upon further review, Florida Power Corporation (FPC) has determined that     |
| none of the 10CFR50.72 reporting criteria applies to the results of this     |
| inspection.  Therefore, the basis for this notification is revised to        |
| "require by ITS Table 5.6.2-2 and ITS 5.7.2.d."                              |
|                                                                              |
| The OTSG Tube Surveillance Program is completed. Additional "C-3"            |
| classifications are now being declared where more than 1% of sampled tubes   |
| were determined to be defective.  The inspected areas involve the "A" and    |
| "B" OTSG upper roll transition/tube ends and the "B" OTSG sleeved tubes.     |
| FPC has determined that none of the 10CFR50.72 reporting criteria applies to |
| the results of these inspections.  Therefore, this supplemental notification |
| is being made because it is required by ITS Table 5.6.2-2 and ITS  5.7.2.d.  |
|                                                                              |
| Further information concerning the OTSG Tube Surveillance Program inspection |
| results will be provided in Mode 4 Report required by ITS 5.7.2.c. R2DO      |
| (Mark Lesser) was notified.                                                  |
|                                                                              |
| The NRC Resident Inspector was notified of this Update by the licensee.      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36314       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  MISSISSIPPI DIV OF RAD HEALTH        |NOTIFICATION DATE: 10/20/1999|
|LICENSEE:  PRITCHARD ENGINEERING INC            |NOTIFICATION TIME: 09:40[EDT]|
|    CITY:  STARKVILLE               REGION:  2  |EVENT DATE:        10/19/1999|
|  COUNTY:                            STATE:  MS |EVENT TIME:        17:45[CDT]|
|LICENSE#:  MS-865-01             AGREEMENT:  Y  |LAST UPDATE DATE:  10/26/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |KERRY LANDIS         R2      |
|                                                |SCOTT MOORE     EO   NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  NELSON                       |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE MISSISSIPPI DIVISION OF RADIOLOGICAL HEALTH REPORTED A LOST MOISTURE     |
| DENSITY GAUGE.                                                               |
|                                                                              |
| PRITCHARD ENGINEERING INC. LOST A MOISTURE DENSITY GAUGE WHEN IT FELL OUT OF |
| THE BACK OF A TRUCK IN STARKVILLE, MS.  THE GAUGE IS A CAMPBELL-PACIFIC      |
| MODEL 131 SERIAL # MD80804480 CONTAINING 10 MILLICURIES OF CESIUM-137 AND 50 |
| MILLICURIES OF AMERICIUM-241/BERYLLIUM.  THE DEVICE SHOULD BE LOCKED IN AN   |
| ORANGE CONTAINER AND ALSO LOCKED AT THE GAUGE HANDLE.  THE LOCAL SHERIFF AND |
| MISSISSIPPI HEALTH DEPARTMENT HAVE BEEN NOTIFIED.  THEY ARE CURRENTLY        |
| LOOKING FOR THE DEVICE.                                                      |
|                                                                              |
|                                                                              |
| *** UPDATE ON 10/26/99 @ 0945 BY NELSON TO GOULD ***                         |
|                                                                              |
| THE GAUGE WAS FOUND ON 10/25/99 BY A SEARS SERVICEMAN ON A ROAD IN           |
| MASHULAVILLE, MS.  THE DEVICE WAS INTACT WITH ONLY MINOR DAMAGE TO THE CASE. |
| THE SEARS SERVICEMAN NOTIFIED THE MISSISSIPPI DEPARTMENT OF TRANSPORTATION   |
| TO LOCATE AND RETURN THE DEVICE TO THE OWNER.  THE OWNER TOOK POSSESSION OF  |
| THE DEVICE LAST NIGHT.                                                       |
|                                                                              |
| THE REG 2 RDO(LANDIS) AND NMSS EO(PICCONE) WERE NOTIFIED.                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36347       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FT CALHOUN               REGION:  4  |NOTIFICATION DATE: 10/26/1999|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 03:06[EDT]|
|   RXTYPE: [1] CE                               |EVENT DATE:        10/26/1999|
+------------------------------------------------+EVENT TIME:        01:32[CDT]|
| NRC NOTIFIED BY:  LARRY LEES                   |LAST UPDATE DATE:  10/26/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          ALE                   |DAVID LOVELESS       R4      |
|10 CFR SECTION:                                 |BRUCE BOGER          NRR     |
|AAEC 50.72 (a) (1) (I)   EMERGENCY DECLARED     |JOSEPH GIITTER       IRO     |
|                                                |CANUPP               FEMA    |
|                                                |PERKINS              DOE     |
|                                                |TURMAN               EPA     |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| UNIT 1 REPORTED ENTERING AND EXITING CONDITIONS REQUIRING AN ALERT           |
| DECLARATION                                                                  |
|                                                                              |
| "AT 0132CDT, WHEN ATTEMPTING TO TRANSFER STATION LIGHTING, VITAL BUSES 1A3   |
| AND 1A4 WERE DEENERGIZED.  [BOTH] DIESEL GENERATORS [DG-1 AND DG-2]  WERE IN |
| 'OFF-AUTO' FOR MODE 5 CONDITIONS.  WHEN THE DIESEL GENERATORS WERE TAKEN TO  |
| 'AUTO,' THE DIESEL  GENERATORS AUTOSTARTED AND ENERGIZED VITAL BUSES 1A3 AND |
| 1A4, AT 0134CDT.  SHUTDOWN COOLING WAS LOST FOR APPROXIMATELY [TWO] 2        |
| MINUTES AND RESTORED WHEN THE DIESEL GENERATORS WERE PLACED ON THE BUS.      |
| SHUTDOWN COOLING TEMPERATURE INDICATED [ZERO] 0 DEGREES FAHRENHEIT           |
| TEMPERATURE RISE IN THE [TWO] 2 MINUTES THAT SHUTDOWN COOLING WAS LOST.      |
| WHEN THE EMERGENCY PLAN WAS ENTERED, VITAL BUSES WERE ALREADY RE-ENERGIZED.  |
| AN ALERT WAS REPORTED UNDER EAL 4.3 BUT NOT DECLARED.  OFFSITE POWER WAS     |
| ALWAYS AVAILABLE, AND AS OF THIS TIME IS ON VITAL BUS 1A3."                  |
|                                                                              |
| OFFSITE POWER WAS RESTORED TO BUSES 1A3 AND 1A4 AT 0159CDT AND 0209CDT,      |
| RESPECTIVELY.  INITIAL RCS TEMPERATURE WAS 103 DEGREES FAHRENHEIT.  SHUTDOWN |
| COOLING TRAIN "A" WAS PLACED IN-SERVICE TO REPLACE THE OPERATING TRAIN "B"   |
| WHICH WAS DEENERGIZED.  THE    ELECTRICAL MAINTENANCE HAS LOOKED AT          |
| TRANSFORMERS INSIDE AND OUTSIDE THE PLANT AND FOUND NO APPARENT FAILURE.     |
|                                                                              |
| THE LICENSEE NOTIFIED BOTH STATE AND LOCAL AGENCIES AND WILL INFORM THE NRC  |
| RESIDENT INSPECTOR.                                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36348       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  FEDERAL BUREAU OF INVESTIGATION      |NOTIFICATION DATE: 10/26/1999|
|LICENSEE:  UNKNOWN                              |NOTIFICATION TIME: 10:08[EDT]|
|    CITY:  WASHINGTON               REGION:  1  |EVENT DATE:        10/26/1999|
|  COUNTY:                            STATE:  DC |EVENT TIME:        09:30[EDT]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  10/26/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |DAVID LEW            R1      |
|                                                |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  GARTEN                       |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE FBI REPORTED A STOLEN TROXLER GAUGE WAS RECOVERED.                       |
|                                                                              |
| THE FBI RECOVERED A STOLEN TROXLER GAUGE MODEL 3411-B SERIAL # 4311 ON SOUTH |
| CAPITAL ST IN WASHINGTON D.C.  IT WAS RECOVERED FROM AN INDIVIDUAL THAT WAS  |
| TRYING TO SELL IT.                                                           |
| THE DEVICE APPEARED TO BE INTACT, BUT THE PLASTIC CASE WAS OPEN.  THE        |
| READINGS MEASURED WAS 1.18 MILLIREM AND THE PAGER-S READ 8.  THE FBI HAS THE |
| DEVICE IN ITS POSSESSION.                                                    |
|                                                                              |
| *** UPDATE ON 10/26/99 @ 1104 BY NELSON TO GOULD ***                         |
|                                                                              |
| THE FBI HAVE LOCATED THE OWNER OF THE STOLEN TROXLER GAUGE.  EBA ENGINEERING |
| OF BALTIMORE, MD. IS THE OWNER OF THE DEVICE AND THEY BELIEVE IT WAS STOLEN  |
| LAST NIGHT.                                                                  |
| THE FBI HAS NOT YET RETURNED  THE DEVICE TO THE OWNER.                       |
|                                                                              |
| NOTIFIED REG 1 RDO(LEW) AND NMSS EO(HICKEY)                                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   36349       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  MERCY HOSPITAL                       |NOTIFICATION DATE: 10/26/1999|
|LICENSEE:  MERCY HOSPITAL                       |NOTIFICATION TIME: 11:00[EDT]|
|    CITY:  PORT HURON               REGION:  3  |EVENT DATE:        10/26/1999|
|  COUNTY:                            STATE:  MI |EVENT TIME:        03:45[EDT]|
|LICENSE#:  211563801             AGREEMENT:  N  |LAST UPDATE DATE:  10/26/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MIKE JORDAN          R3      |
|                                                |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  SMITH                        |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|LADM 35.33(a)            MED MISADMINISTRATION  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MEDICAL MISADMINISTRATION AT THE MERCY HOSPITAL IN PORT HURON, MI            |
|                                                                              |
| A PATIENT AT THE HOSPITAL WAS UNDERGOING TREATMENT WITH A WIRE OF IRIDIUM    |
| SEEDS(33 @ .923 MILLICURIES/SEED) INSERTED INTO A CATHETER, HOWEVER, THE     |
| WIRE CAME OUT PRIOR TO THE TIME IT WAS SCHEDULED TO BE REMOVED.  TREATMENT   |
| TIME WAS TO BE 48 HOURS  BEGINNING  @ 1015 ON 10/25/99, HOWEVER THE WIRE     |
| CAME OUT @ 0330 ON 10/26/99 RESULTING IN THE PATIENT ONLY RECEIVING 36% TO   |
| 38% OF HIS PRESCRIBED TREATMENT.  THE NURSE RESPONDED TO THE PATIENT'S CALL  |
| WITHIN A MINUTE AND REMOVED THE SOURCES FROM THE PROXIMITY OF THE PATIENT    |
| AND CALLED THE AUTHORIZED USER AND THE RSO.  HOWEVER ,WHEN THE NURSE ENTERED |
| THE PATIENT'S ROOM, SHE FOUND THE PATIENT HOLDING THE WIRE IN HIS HANDS.     |
| THEY CALCULATED THE DOSE TO THE PATIENT'S FINGERS TO BE 5 RADS.  THE         |
| PATIENT'S PHYSICIAN HAS NOT YET BEEN NOTIFIED.                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36350       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  TECHNOLOGY for ENERGY CORP.          |NOTIFICATION DATE: 10/26/1999|
|LICENSEE:  TECHNOLOGY for ENREGY CORP.          |NOTIFICATION TIME: 13:48[EDT]|
|    CITY:  KNOXVILLE                REGION:  2  |EVENT DATE:        10/26/1999|
|  COUNTY:                            STATE:  TN |EVENT TIME:        13:48[EDT]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  10/26/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MARK LESSER          R2      |
|                                                |VERN HODGE           NRR     |
+------------------------------------------------+DAVID LEW            R1      |
| NRC NOTIFIED BY:  JEFF LOLLAR                  |MIKE JORDAN          R3      |
|  HQ OPS OFFICER:  JOHN MacKINNON               |DAVID LOVELESS       R4      |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| RTV SEALANT USED IN THE TEC VALVE FLOW MONITORING SYSTEM CANNOT BE           |
| DEMONSTRATED TO MEET THE CONTAINMENT QUALIFICATION CONDITIONS.               |
|                                                                              |
| 10 CFR Part 21 Interim Report submitted by Technology for Energy Corporation |
| (TEC), located in Knoxville, TN.                                             |
|                                                                              |
| TEC is reporting a potential defect in Valve Flow Monitoring Systems         |
| provided by TEC to the nuclear power industry.  Further evaluation is        |
| required to determine if the subject condition constitutes a defect as       |
| defined in  10CFR21.3.                                                       |
|                                                                              |
| The RTV-738 sealant used in the TEC Valve Flow Monitoring System cannot be   |
| demonstrated to meet the containment qualification conditions.               |
|                                                                              |
| During discussions with customers concerning the application of RTV-738      |
| sealant at the accelerometer connection to hardline cable, it was discovered |
| that the recommended installation procedure was not specified during the     |
| qualification test (1980).  One witness to the qualification test confirm    |
| that the RTV-738 was present but further stated it had been removed and      |
| replaced between qualification stages (aging, irradiation, seismic, and      |
| LOCA).  Records cannot confirm if this was the test condition, but a set of  |
| cable resistance measurements suggest the RTV-738 was removed in order to    |
| perform the resistance testing.  This uncertainty impacts the qualified life |
| of the Valve Flow Monitoring System since the accelerometer to hardline      |
| cable could be exposed to LOCA conditions and the RTV-738 is applied to seal |
| the junction between these components.  Internal Corrective Action Report #  |
| 0026 has been initiated to track this condition.                             |
|                                                                              |
|                                                                              |
| After confirming that documentation was not available to conclusively        |
| demonstrate the qualified test conditions, a new qualification test plan was |
| generated and has started.  This testing is designed to demonstrate if the   |
| accelerometer to hardline cable junction can be qualified not only using     |
| RTV-738 , but also without RTV-738 and with Raychem heat shrink.  Thermal    |
| aging is complete without failure and irradiation is now underway.  The full |
| test is expected to be completed by December 10, 1999 with the final LOCA    |
| testing phase scheduled to start on November 8, 1999.                        |
|                                                                              |
| There have been no reported failures of the accelerometer to hardline cable  |
| junction except due to physical damage during outages.  Therefore, no action |
| is recommended at this time pending verification of the qualified assembly   |
| both with and without the RTV-738 sealant.                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36351       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES              REGION:  3  |NOTIFICATION DATE: 10/26/1999|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 16:44[EDT]|
|   RXTYPE: [1] GE-3,[2] GE-3                    |EVENT DATE:        08/25/1999|
+------------------------------------------------+EVENT TIME:        10:20[CDT]|
| NRC NOTIFIED BY:  K HILL                       |LAST UPDATE DATE:  10/26/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MIKE JORDAN          R3      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR CORE ISOLATION COOLING (RCIC) DECLARED INOPERABLE ON 08/26/99        |
|                                                                              |
| The licensee is reviewing events from the past couple of years in which RCIC |
| was declared inoperable. Control Room personnel were notified they should    |
| have  reported events to the NRC over the last couple of years(per           |
| 10CFR50.72(b)(2)(iii)(D)) when RCIC  was declared inoperable.                |
|                                                                              |
| On 08/25/99 at 1020CT, while conducting post maintenance testing to return   |
| Unit 2 RCIC to operable status, the RCIC system turbine tripped on           |
| overspeed. RCIC was subsequently repaired and made operable on 08/26/99 at   |
| approximately 1500 hours.  All Emergency Core Cooling Systems were fully     |
| operable during the time period RCIC  was inoperable.                        |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36352       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 10/26/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 20:37[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        10/26/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        03:59[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  10/26/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |MIKE JORDAN          R3      |
|  DOCKET:  0707002                              |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JIM MCCLEERY                 |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NCFR                     NON CFR REPORT REQMNT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| RECEIVED A CASCADE AUTOMATIC DATA PROCESSING (CADP) SMOKEHEAD ALARM.         |
|                                                                              |
| On 10/26/99 at 0359 hours, operations personnel received a CADP smokehead    |
| alarm for system 31-3 smoke head S-16 located in Cascade Facility X-330.  A  |
| valving operation was in progress when the alarm was received. Operations    |
| immediately stopped the operation and isolated the piping.  Radiological air |
| samples and visual observations did not indicate a release of Uranium        |
| Hexafluoride. Smokehead detector can be activated by dust, smoke , Uranium   |
| Hexafluoride, etc.                                                           |
|                                                                              |
| A graphic plot of the firing voltage (voltage drop) from the CADP system of  |
| the alarming smokehead gave indication that the CADP system received a valid |
| signal. The certificate holder does not know what activated the smokehead.   |
|                                                                              |
|                                                                              |
| This is reportable as an activation of a Q safety system per Safety Analysis |
| Report (SAR) section 6.9 table 6.9-1.                                        |
|                                                                              |
| There was no loss of hazardous/radioactive material or                       |
| radioactive/radiological contamination exposure as a result of this event.   |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the certificate     |
| holder.                                                                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36353       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CLINTON                  REGION:  3  |NOTIFICATION DATE: 10/26/1999|
|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 22:51[EDT]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        10/26/1999|
+------------------------------------------------+EVENT TIME:        19:20[CDT]|
| NRC NOTIFIED BY:  MARSHALL FUNKHOUSER          |LAST UPDATE DATE:  10/26/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MIKE JORDAN          R3      |
|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                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE CORE SPRAY (HPCS) DECLARED INOPERABLE DUE TO ITS MINI FLOW     |
| VALVE FAILING TO FULLY OPEN.                                                 |
|                                                                              |
|                                                                              |
| Clinton Power Station is presently performing a planned Division 3 (HPCS     |
| Diesel ) outage.  The plant has been in a limited condition for operation    |
| allowed by Technical Specifications for this outage since 0230 CT on         |
| 10/26/99.  At 1920 hours on 10/26/99 during performance of a High Pressure   |
| Spray System Surveillance the HPCS Minimum Flow Valve (1E22-F012) failed to  |
| operate properly.  During an open stroke of the Minimum Flow valve, power    |
| was lost due to a breaker trip and the valve failed to fully open.  This     |
| valve provides a minimum amount of flow through the system to ensure that    |
| the pump does not overheat.  The Plant's Technical Specification provides    |
| allowances for this condition but 10CFR50.72(b)(2)(iii)(D) requires that a   |
| component failure that could have prevented an independent safety system     |
| from performing its function be reported. This system may have failed to     |
| perform its safety function due to the failure of this valve, thus, this     |
| report is being made.  The licensee entered Technical Specification 3.5.1    |
| (14 days Limiting Condition of Operation). The Reactor Core Isolation        |
| Cooling and all other Emergency Core Cooling Systems are fully operable if   |
| needed.  The Electrical Grid is Stable and Division 1 and 2 Emergency Diesel |
| Generators a fully operable.                                                 |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+