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Event Notification Report for October 3, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/02/2000 - 10/03/2000

                              ** EVENT NUMBERS **

37396  37397  37398  37399  37400  37401  

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|Power Reactor                                    |Event Number:   37396       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 10/02/2000|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 07:42[EDT]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        10/02/2000|
+------------------------------------------------+EVENT TIME:        06:25[EDT]|
| NRC NOTIFIED BY:  MICHAUD                      |LAST UPDATE DATE:  10/02/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNU                   |JOHN KINNEMAN        R1      |
|10 CFR SECTION:                                 |ED GOODWIN           EO      |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |CHARLIE MILLER       IRO     |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |STEINDURF            FEMA    |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     M/R        Y       1        Startup          |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR WAS MANUALLY SCRAMMED FROM <1% DUE TO INDICATIONS OF THE             |
| ELECTROMATIC RELIEF VALVE(ERV) BEING OPEN.                                   |
|                                                                              |
| The manual scram was inserted due to indications of main steam ERV 111 being |
| stuck open.  All rods fully inserted, no ECCS initiations, no relief valves  |
| lifted and all systems functioned as expected.  They also had isolation of   |
| the main steam isolation valves due to the mode switch being in the shutdown |
| position, condenser vacuum less than LoLoLo and reactor pressure less than   |
| 600 psig.                                                                    |
|                                                                              |
| Following the reactor scram they declared an Unusual Event (@0712) due to    |
| unidentified drywell internal leakage greater than 10 gpm (they have not yet |
| determined the maximum leakage rate).  Initial indication of this problem is |
| the #11 main steam line ERV 111 is stuck open. The cause of the Drywell      |
| leakage is suspected to be a failure of one of the ERV line vacuum breakers  |
| to close resulting in leakage from Torus back to the Drywell.                |
|                                                                              |
| The unit also entered TS S/D LCO 3.2.5.a(1&2), Reactor Coolant System        |
| Leakage, which requires the plant to be in cold shutdown within 24 hours.    |
| They plan to depressurize and cool down the reactor using shutdown cooling   |
| to reach cold shutdown.                                                      |
|                                                                              |
| The NRC Resident Inspector, State and Local Agencies were notified.          |
|                                                                              |
| There will be a press release issued by the licensee.                        |
|                                                                              |
| * * * UPDATE 0912 10/2/00 FROM MICHAUD TAKEN BY STRANSKY * * *               |
|                                                                              |
| The Unusual Event was terminated at 0905 EDT. Total unidentified leakage is  |
| approximately 0.5 gpm. The unit is in cold shutdown, and is continuing to    |
| cool down. The NRC resident inspector has been informed of this update by    |
| the licensee. Notified R1DO (Linville), EO (Goodwin), IRO(Congel), and FEMA  |
| (Steindurf).                                                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37397       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VERMONT YANKEE           REGION:  1  |NOTIFICATION DATE: 10/02/2000|
|    UNIT:  [1] [] []                 STATE:  VT |NOTIFICATION TIME: 13:23[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        10/02/2000|
+------------------------------------------------+EVENT TIME:        13:10[EDT]|
| NRC NOTIFIED BY:  MITCHELL McCLUSKIE           |LAST UPDATE DATE:  10/02/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES LINVILLE       R1      |
|10 CFR SECTION:                                 |BRIAN SMITH          NMSS    |
|BAAA 20.1906(d)           SURFACE CONT/ EXT RAD |FRANK CONGEL         IRO     |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |THOMAS YATES         DOE     |
|                                                |RATHBUN (via NRC)    DOT     |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| RECEIPT OF A PACKAGE WITH EXTERIOR RADIATION LEVELS GREATER THAT THE LIMIT   |
|                                                                              |
| A package containing radioactive tools was received onsite, and the bottom   |
| side of one of the packages had a dose rate of 550 mR/hour on contact.  (The |
| limit is 200 mR/hour on contact.)  The package came from a Chem Nuclear      |
| facility on a flat bed truck, and the radioactive tools were going to be     |
| used for a spent fuel pool cleanup effort.                                   |
|                                                                              |
| The box in question is still located on the truck.  Radiation Protection     |
| Department personnel have posted the area  and roped it off as a Radiation   |
| Area in order to control access.  The licensee plans to unload the box and   |
| perform an investigation to find out what is in the box and why the event    |
| happened.  The licensee also plans to continue controlling access to the     |
| area until the investigation is complete.                                    |
|                                                                              |
| The licensee reported this event as a 1-hour report in accordance with 10    |
| CFR 20.1906(d)(2).                                                           |
|                                                                              |
| Radiation Protection Department personnel notified Chem Nuclear.  The        |
| licensee plans to notified the NRC resident inspector and the Vermont        |
| Department of Public Service.                                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37398       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK              REGION:  1  |NOTIFICATION DATE: 10/02/2000|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 14:02[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        10/02/2000|
+------------------------------------------------+EVENT TIME:        12:20[EDT]|
| NRC NOTIFIED BY:  GEORGE TASICK                |LAST UPDATE DATE:  10/02/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES LINVILLE       R1      |
|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                                   
+------------------------------------------------------------------------------+
| DISCOVERY THAT A HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM STEAM         |
| ADMISSION VALVE MAY NOT CLOSE AGAINST DESIGN BASIS DIFFERENTIAL PRESSURE     |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "Engineering review has determined that the steam admission valve (inboard   |
| primary containment isolation valve) for the HPCI system may not close       |
| against design basis differential pressure (dP).  Engineering review has     |
| determined that the valve position limit switch may not indicate true stem   |
| and disc position and, therefore, under design basis dP conditions, may stop |
| closure before hard seat contact.  Evaluation of operability is continuing.  |
| A review of 1995 test data is underway which may determine that this valve   |
| is in fact operable.  In the event this review determines that this valve is |
| operable, this notification will be retracted."                              |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   37399       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  SCHNABEL ENGINEERING ASSOCIATES      |NOTIFICATION DATE: 10/02/2000|
|LICENSEE:  SCHNABEL ENGINEERING ASSOCIATES      |NOTIFICATION TIME: 17:11[EDT]|
|    CITY:  RICHMOND                 REGION:  2  |EVENT DATE:        10/02/2000|
|  COUNTY:  CITY OF RICHMOND          STATE:  VA |EVENT TIME:        10:00[EDT]|
|LICENSE#:  45-19703-01           AGREEMENT:  N  |LAST UPDATE DATE:  10/02/2000|
|  DOCKET:  03019126                             |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CHARLES R. OGLE      R2      |
|                                                |JOHN HICKEY          NMSS    |
+------------------------------------------------+FRANK CONGEL         IRO     |
| NRC NOTIFIED BY:  BOB HILL                     |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SCHNABEL ENGINEERING ASSOCIATES REPORT OF A VEHICLE CONTAINING A LOCKED      |
| TROXLER NUCLEAR DENSITY GAUGE THAT WAS STOLEN FROM AN EMPLOYEE'S RESIDENCE   |
| IN RICHMOND, VIRGINIA                                                        |
|                                                                              |
| Schnabel Engineering Associates reported that an employee worked over the    |
| weekend and locked a Troxler nuclear density gauge in the back of his 1988   |
| Chevy Blazer located in the parking lot at his residence (an apartment       |
| building or townhouse complex in Richmond, Virginia).  At approximately 0700 |
| on 10/02/00, the employee discovered that his Chevy Blazer had been stolen   |
| from the parking lot at his residence.  Bob Hill (the licensee's Radiation   |
| Safety Officer for the Richmond, Hampden, Charlottesville, Leesburg Office)  |
| was notified at approximately 1000 on 10/02/00, and several attempts were    |
| made to located the vehicle.  The licensee notified the Police of the stolen |
| vehicle and that a locked nuclear density gauge was in the back of the       |
| stolen vehicle.  So far, there has been no record of the truck being found.  |
| The licensee also checked with local towing companies, and there is also no  |
| record of the vehicle being towed.                                           |
|                                                                              |
| The missing nuclear density gauge (model #3430, serial #29171) had a sealed  |
| source containing 40 mCi of Americium-241/beryllium and 8 mCi of cesium-137. |
| The gauge also had two locks on it (one on the trigger and one on the box),  |
| and the box was locked inside the back of the enclosed vehicle.  The vehicle |
| was also locked.                                                             |
|                                                                              |
| The licensee notified the NRC Region 2 office (Wade Loo) via telephone at    |
| approximately 1130 on 10/02/00.  The licensee also reported to the NRC       |
| Operations Center that the NRC Region 2 office planned to notify the         |
| Virginia Bureau of Radiological Health and planned to issue a Preliminary    |
| Notification.  The licensee also plans to submit a 30-day written report.    |
|                                                                              |
| (Call the NRC operations officer for licensee contact telephone numbers, a   |
| licensee address, the employee's name, and the employee's address.)          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37400       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 10/02/2000|
|    UNIT:  [1] [2] []                STATE:  WI |NOTIFICATION TIME: 19:00[EDT]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        10/02/2000|
+------------------------------------------------+EVENT TIME:        17:10[CDT]|
| NRC NOTIFIED BY:  RICK ROBBINS                 |LAST UPDATE DATE:  10/02/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN MADERA          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                                   
+------------------------------------------------------------------------------+
| DISCOVERY OF A DISCREPANCY BETWEEN A PROCEDURE, THE PLANT CONFIGURATION TO   |
| ESTABLISH PORTABLE SHIELDING, AND THE FINAL SAFETY ANALYSIS REPORT (FSAR)    |
| ANALYSIS FOR CONTROL ROOM DOSE                                               |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "During a engineering review for placing a table adjacent to an exterior     |
| Control Room wall, it was noticed that the calculation for placing portable  |
| shielding in front of the Control Room window and South access door assumes  |
| the shielding [is] in place from the on set of the event.  A discrepancy     |
| exists between the procedure and the plant configuration to establish the    |
| portable shielding to limit the whole body dose to Control Room operators    |
| and the FSAR analysis for Control Room dose (FSAR 14.3.5).  The analysis     |
| (FSAR 14.3.5-1 of 14, last paragraph, Calculation 97-0115) assumes that the  |
| portable shielding is in place at initiation of event; however, the          |
| procedure necessary to implement the portable shielding (EOP-1, step 18)     |
| provides instructions to set up the portable shielding some time after the   |
| initiating event."                                                           |
|                                                                              |
| "At this time, portable shielding is being installed until further           |
| engineering reviews of this calculation and its assumptions can be made."    |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   37401       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 10/02/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 22:52[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        10/02/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        15:41[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  10/02/2000|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |JOHN MADERA          R3      |
|  DOCKET:  0707002                              |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ERIC SPAETH                  |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NCFR                     NON CFR REPORT REQMNT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HISTORICAL INFORMATION REGARDING A FAILURE TO COMPLETE X-333 LOW ASSAY       |
| WITHDRAWAL (LAW) COMPRESSOR PYROTRONIC SMOKE DETECTION SYSTEM ENGINEERING    |
| MODIFICATIONS AS DESIGNED  (24-hour report)                                  |
|                                                                              |
| The following text is a portion of a facsimile received from Portsmouth      |
| personnel:                                                                   |
|                                                                              |
| "The engineering modifications to the X-333 LAW compressor Pyrotronic smoke  |
| detection system were not completed as designed.  The modifications were     |
| intended to cause the safety system to alarm with only one smoke head firing |
| instead of requiring two smoke heads to activate the alarm.  The             |
| investigation into this matter was completed 10/02/00 at 1541 [hours].  The  |
| investigation identified that on one occasion, a LAW station compressor was  |
| in an applicable operating mode where the Pyrotronic smoke detection safety  |
| system was required to be operable and one of the heads was in fact          |
| inoperable making the system inoperable.  Operations personnel did post an   |
| immediate smoke watch to maintain [Technical Safety Requirement (TSR)]       |
| compliance."                                                                 |
|                                                                              |
| "This finding is reportable to the NRC as a 24-hour event due to the fact    |
| the equipment was required by the TSR to be available and operable and       |
| should have been operating, and no redundant equipment was available to      |
| provide the required safety function."                                       |
|                                                                              |
| "Note:  The engineering modifications were completed 10/01/00, and           |
| applicable [post-maintenance tests were completed satisfactorily]."          |
|                                                                              |
| It was reported that the inoperable head that was identified to be           |
| inoperable on 10/01/99, but this issue was not identified until the          |
| investigation was completed today (10/02/00) at 1541 hours.  It was also     |
| reported that there was nothing unusual or misunderstood and that all        |
| systems functioned as required.                                              |
|                                                                              |
| NOTE:  The X-333 building LAW station was reported to be a UF6 withdrawal    |
| station.                                                                     |
|                                                                              |
| Portsmouth personnel have notified the NRC resident inspector and plan to    |
| notify the Department of Energy site representative.                         |
+------------------------------------------------------------------------------+