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Event Notification Report for October 19, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/18/2000 - 10/19/2000

                              ** EVENT NUMBERS **

37354  37429  37435  37436  37437  37438  37439  

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|General Information or Other                     |Event Number:   37354       |
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| REP ORG:  SCIENTECH/NUSI                       |NOTIFICATION DATE: 09/20/2000|
|LICENSEE:  SCIENTECH/NUSI                       |NOTIFICATION TIME: 07:42[EDT]|
|    CITY:  GAITHERSBURG             REGION:  1  |EVENT DATE:        09/14/2000|
|  COUNTY:                            STATE:  MD |EVENT TIME:             [EDT]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  10/18/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |WILLIAM RULAND       R1      |
|                                                |VERN HODGE           NRR     |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  BOOSKA                       |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| PART 21 RELATED TO DEFECTS IN DELTA T TIME DOMAIN MODULES SUPPLIED TO GINNA  |
| STATION                                                                      |
|                                                                              |
| SCIENTECH Inc.'s subsidiary NUS Instruments, Inc. (NUSI) has determined that |
| a Basic Component, supplied to Rochester Gas & Electric Ginna Station        |
| Nuclear Plant under RG&E purchase order NQ-l5877-A-JW, may contain a defect  |
| that is reportable under 10CFR21.  NUSI became aware of this potential       |
| defect September 14, 2000.  SCIENTECH, Inc. President was informed September |
| 19, 2000.  RG&E is aware of this problem and the affected components have    |
| been modified to remove any undesirable effects on their systems. A formal   |
| written report will be provided within 30 days of this notification.  The    |
| components, DELTA T Time Domain Modules, M/N: TMD500-08/08/08/08-15-08-01/2, |
| P/N: MBA-E062PA-l, Rev. 0 (4 ea.), were manufactured by NUSI.  These         |
| components have been supplied to no other utility for use in Safety Related  |
| Systems.  NUSI has opened a 10CFR21 file concerning this component and has   |
| numbered it as 21-00-01.                                                     |
|                                                                              |
| * * * UPDATE 1343EDT on 10/18/00 from Marty Booska to S. Sandin * * *        |
|                                                                              |
| The licensee submitted a formal copy of the Part 21 via fax with a hard copy |
| being sent by mail tomorrow.  Notified R1DO(Cook) and NRR(Vern Hodge) via    |
| fax.                                                                         |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37429       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER                   REGION:  4  |NOTIFICATION DATE: 10/14/2000|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 05:14[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        10/14/2000|
+------------------------------------------------+EVENT TIME:        03:24[CDT]|
| NRC NOTIFIED BY:  WILLIAM GREEN                |LAST UPDATE DATE:  10/18/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVE LOVELESS        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     A/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR SCRAM DUE TO A MAIN GENERATOR TRIP FOR UNKNOWN REASONS     |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "At 0324 [CDT], a reactor scram occurred due to a main generator trip.       |
| Group isolations 2, 3[, and] 6 occurred due to low reactor water level.  The |
| lowest [reactor water] level recorded was -20 inches on [the] wide range     |
| level recorder.  Reactor water level recovered, and both reactor [feedwater] |
| pumps tripped on high reactor water level.  Group isolations have been       |
| verified and reset.  [The] 'A' reactor [feedwater] pump has been returned to |
| service and is being used to control water level.  [High pressure coolant    |
| injection] and [reactor core isolation cooling] did not inject and were not  |
| needed to control reactor water level.  The plant will be placed in Cold     |
| Shutdown.  The electrical grid is stable."                                   |
|                                                                              |
| The licensee stated that all control rods fully inserted and that all        |
| systems functioned as required.  The licensee also stated that alternate rod |
| insertion initiated as a result of high pressure due to the transient.  The  |
| highest pressure observed was 1,085 psi.  None of the relief valves lifted,  |
| and the main steam isolation valves remained open throughout the event.      |
| Steam is currently being dumped to the condenser.                            |
|                                                                              |
| In addition, the licensee stated that the cause of the main generator trip   |
| is currently under investigation.  There were no related surveillance or     |
| maintenance activities ongoing at the time of the event.                     |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| * * * UPDATE  on 10/18/00 at 0428 ET by Myers taken by MacKinnon * * *       |
|                                                                              |
| A detailed review of the plant response to the scram has been conducted.     |
| This review indicated the following clarification to the initial report are  |
| needed:                                                                      |
|                                                                              |
| Alternate Rod Insertion initiated on low level, rather than high pressure.   |
| The low level was not in long enough to trip the Recirculation pumps.  The   |
| pumps trip after a 9 second delay, and the low level signal was only in for  |
| ~ 7 seconds.                                                                 |
|                                                                              |
| Initial indications were that reactor pressure had reached 1085 psig, based  |
| on pressure recorder LRPR97, the highest reading of the pressure recorders.  |
| Additional pressure recorders and the plant computer indicate  pressure      |
| reached a maximum of ~ 1068 psig.  Evaluation of the recorder indicates it   |
| is in calibration, and the "overshoot" of indicated pressure is due to       |
| mechanical characteristics of the recorder linkage.  NRC R4DO (John Pellet)  |
| notified.                                                                    |
|                                                                              |
| The NRC Resident Inspector was informed of this update by the licensee.      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37435       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 10/18/2000|
|    UNIT:  [] [2] []                 STATE:  FL |NOTIFICATION TIME: 12:00[EDT]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        10/18/2000|
+------------------------------------------------+EVENT TIME:        10:52[EDT]|
| NRC NOTIFIED BY:  ALAN T. HALL                 |LAST UPDATE DATE:  10/18/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CAUDLE JULIAN        R2      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO LOCAL FIRE DEPARTMENT FOR FIRE ON OWNER CONTROLLED   |
| POPERTY                                                                      |
|                                                                              |
| "REFERENCE NUREG  [1022 - SECTION] 3.3.7:                                    |
|                                                                              |
| NOTIFICATION OF CONTACT OF ST. LUCIE '911' (FIRE) TO REQUEST OFFSITE FIRE    |
| DEPARTMENT TO EXTINGUISH A SMALL GRASS FIRE EAST OF PLANT BETWEEN DUNE LINE  |
| AND MANGROVES, IN A GRASS COVERED PARKING AREA.  TOTAL TIME FROM DISCOVERY   |
| UNTIL NOTIFICATION OF 'FIRE IS OUT' WAS 38 MINUTES.  NO E-PLAN ACTIVATION    |
| WAS REQUIRED.  FIRE [WAS] NOT ON PLANT SITE."                                |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND LOCAL AUTHORITIES.      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37436       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEQUOYAH                 REGION:  2  |NOTIFICATION DATE: 10/18/2000|
|    UNIT:  [1] [2] []                STATE:  TN |NOTIFICATION TIME: 13:47[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        10/18/2000|
+------------------------------------------------+EVENT TIME:        12:00[EDT]|
| NRC NOTIFIED BY:  TOM RYAN                     |LAST UPDATE DATE:  10/18/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CAUDLE JULIAN        R2      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|2     N          Y       78       Power Operation  |78       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE AGENCIES NOTIFIED OF INADVERTENT ACTUATION OF OFFSITE SIRENS DURING  |
| "SILENT TEST"                                                                |
|                                                                              |
| "At approximately, 1200 on 10/18/2000, the Prompt Notification System (PNS)  |
| sirens were inadvertently actuated during a 'Silent Test' of the PNS system  |
| by the Hamilton County Emergency Management Agency (HCEMA). The Corporate    |
| Emergency Planning (EP) personnel were in contact with the HCEMA and         |
| Tennessee Emergency Management Agency (TEMA) Staff at the time of the test   |
| and immediately canceled the activation of PNS system at approximately 1201. |
| The Corporate Operations Duty Specialist (ODS) notified the Sequoyah         |
| Operations Shift Manager at approximately 1205. Tennessee Valley Authority   |
| (TVA) Public Information personnel notified the media.  Due to heightened    |
| public and media interest and notifications, this incident is being reported |
| under 10CFR 50.72(b)(2)(vi)."                                                |
|                                                                              |
| The licensee informed state/local agencies, local media and the NRC resident |
| inspector.                                                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37437       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK              REGION:  1  |NOTIFICATION DATE: 10/18/2000|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 15:04[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        10/18/2000|
+------------------------------------------------+EVENT TIME:        14:00[EDT]|
| NRC NOTIFIED BY:  JOSEPH KLEVORN               |LAST UPDATE DATE:  10/18/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |WILLIAM COOK         R1      |
|10 CFR SECTION:                                 |                             |
|ADAS 50.72(b)(2)(i)      DEG/UNANALYZED COND    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LICENSEE IDENTIFIED DURING SURVEILLANCE TESTING THAT THE CONTAINMENT LEAK    |
| RATE EXCEEDS THE ALLOWABLE LEAK RATE                                         |
|                                                                              |
| "PRIMARY CONTAINMENT AS-FOUND MINIMUM PATHWAY LEAK RATE EXCEEDED THE         |
| ALLOWABLE LEAK RATE OF 1.5%/DAY DURING REFUELING OUTAGE 14.  THE MAJOR       |
| CONTRIBUTOR TO TOTAL CONTAINMENT LEAKAGE WAS THE 'D' MAIN STEAM LINE WHOSE   |
| LEAK RATE WAS NOT ABLE TO BE QUANTIFIED."                                    |
|                                                                              |
| THE LICENSEE HAS APPROXIMATELY 35 ADDITIONAL COMPONENTS TO EVALUATE PRIOR TO |
| COMPLETING LEAK RATE TESTING.                                                |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37438       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  MARYLAND DEPT OF THE ENVIRONMENT     |NOTIFICATION DATE: 10/18/2000|
|LICENSEE:  UNIVERSITY OF MARYLAND               |NOTIFICATION TIME: 16:15[EDT]|
|    CITY:                           REGION:  1  |EVENT DATE:        10/17/2000|
|  COUNTY:                            STATE:  MD |EVENT TIME:        19:00[EDT]|
|LICENSE#:  MD-0701401            AGREEMENT:  Y  |LAST UPDATE DATE:  10/18/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |WILLIAM COOK         R1      |
|                                                |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  RAY MANLEY                   |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT INVOLVING A MEDICAL MISADMINISTRATION (UNDERDOSE)     |
|                                                                              |
| AT 1650EDT ON 10/17/00, A 31 YEAR OLD MALE PATIENT UNDERGOING TREATMENT FOR  |
| LIVER CANCER RECEIVED 23.4% OF THE PRESCRIBED 150 GRAY DOSE USING YTTRIUM-90 |
| GLASS SPHERES PRODUCED BY NORDION.  THE LICENSEE HAS PERFORMED 10 SUCCESSFUL |
| THERAPIES OF THIS TYPE IN THE PAST.  THE MANUFACTURER IS EVALUATING THE      |
| ENTIRE DELIVERY SYSTEM IN ORDER TO DETERMINE ROOT CAUSE.  THE LICENSEE'S     |
| PRELIMINARY EVALUATION INDICATES A DIFFICULTY IN THE DELIVERY RESULTING FROM |
| AN AIR LEAK IN THE RUBBER CAP OF THE SOURCE VIAL AT THE SITE OF THE NEEDLE   |
| INSERTION.  THE LICENSEE SUSPECTS THAT THE INLET NEEDLE AND THE OUTLET       |
| NEEDLE MAY HAVE BEEN INSERTED TOO CLOSE WHICH CAUSED THE RUBBER CAP TO LOSE  |
| ITS SELF-SEAL CAPABILITY.  AT 1900EDT ON 10/18, THE LICENSEE DETERMINED THAT |
| THE UNDERDOSE MET THE REPORTING REQUIREMENTS AS A MEDICAL MISADMINISTRATION. |
|                                                                              |
|                                                                              |
| THE STATE OF MARYLAND INTENDS TO CONDUCT AN INVESTIGATION OF THIS INCIDENT.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37439       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: RIVER BEND               REGION:  4  |NOTIFICATION DATE: 10/18/2000|
|    UNIT:  [1] [] []                 STATE:  LA |NOTIFICATION TIME: 18:45[EDT]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        10/18/2000|
+------------------------------------------------+EVENT TIME:        14:37[CDT]|
| NRC NOTIFIED BY:  TOM LYNCH                    |LAST UPDATE DATE:  10/18/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN PELLET          R4      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       99       Power Operation  |99       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT EXPERIENCED A MOMENTARY GRID DISTURBANCE RENDERING SEVERAL              |
| SAFETY-RELATED RADIATION MONITORS INOPERABLE                                 |
|                                                                              |
| "At 1437CDT on 10/18/00, River Bend Station experienced an electrical        |
| perturbation in the Baton Rouge area.  Line 758 [138 kV]  was lost which     |
| feeds a local refinery and this loss resulted in a momentary grid            |
| undervoltage condition.  This undervoltage condition lasted less than one    |
| (1) second.  As a result of this undervoltage condition, power to selected   |
| radiation monitor sample pumps was lost.  Specifically, the Control Room     |
| Fresh air intake radiation monitors on both Division I and Division II lost  |
| sample pump power and this resulted in these monitors being inoperable for   |
| approximately three (3) minutes.  The monitors were subsequently restarted.  |
| As a result of this condition, the radiation monitors would have been unable |
| to initiate the Control Room Fresh Air Filter trains upon receipt of a high  |
| radiation signal.  This signal is required to be operable when handling      |
| irradiated fuel; modes 1, 2, 3 and/or performing operations with the         |
| potential to drain the reactor vessel.  No fuel handling or reactor vessel   |
| drain activities were in progress.  This condition also existed for the Fuel |
| Building ventilation radiation monitors.  This condition is conservatively   |
| being reported as a loss of safety function for the Control Room Fresh Air   |
| System.  Further evaluation if this condition is in progress."               |
|                                                                              |
| The licensee informed the NRC resident inspector.                            |
+------------------------------------------------------------------------------+