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Event Notification Report for October 11, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/10/2000 - 10/11/2000

                              ** EVENT NUMBERS **

37410  37420  37421  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   37410       |
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| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 10/04/2000|
|    UNIT:  [1] [2] []                STATE:  WI |NOTIFICATION TIME: 19:50[EDT]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        10/04/2000|
+------------------------------------------------+EVENT TIME:        18:20[CDT]|
| NRC NOTIFIED BY:  MIKE MEYER                   |LAST UPDATE DATE:  10/10/2000|
|  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  |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| POTENTIAL OUTSIDE DESIGN BASIS ISSUE DUE TO LACK OF DOCUMENTATION TO SHOW    |
| THAT ATMOSPHERIC STEAM DUMP VALVE CAPACITY WILL SUPPORT THE COOLDOWN         |
| ASSUMPTIONS FOR A STEAM GENERATOR TUBE RUPTURE EVENT WHEN OFFSITE POWER IS   |
| NOT AVAILABLE                                                                |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "During a main steam and steam dump system validation, no documentation      |
| could be found to show that the atmospheric steam dump (ADV) valve capacity  |
| will support the 44-minute cooldown assumptions for a steam generator tube   |
| rupture (SGTR) event as described in the FSAR when offsite power is not      |
| available.  FSAR Chapter 14 and plant procedures include assumptions and     |
| procedure steps that require use of the [ADVs] to cool down the reactor      |
| coolant system (RCS) within 44 minutes of a SGTR event to allow the RCS      |
| pressure to equalize with the faulted steam generator pressure to terminate  |
| primary to secondary break flow.  The SGTR radiological dose assessment is   |
| based upon this 44-minute time frame for ending flow to the ruptured steam   |
| generator."                                                                  |
|                                                                              |
| "The current licensing basis calculation for the SGTR event calculates steam |
| releases from the intact and the faulted steam generators for the purpose of |
| determining offsite dose releases.  However, this calculation does not       |
| appear to support a demonstration of the capability of the ADV on the intact |
| steam generator to reduce the primary system temperature (with sufficient    |
| subcooling margin) to allow depressurizing the RCS to equilibrium pressure   |
| with the faulted steam generator.  No calculation or other documentation has |
| been located that provides an evaluation of the amount of heat in the form   |
| of steam to be removed by the intact steam generator's ADV to provide the    |
| cooldown within the 44-minute time assumed in the accident analysis.  An     |
| operability determination is being performed per [Generic Letter] 91-18."    |
|                                                                              |
| The licensee stated that there was nothing unusual or not understood and     |
| that all systems functioned as required.  The licensee also stated that the  |
| units were not in any limiting conditions for operation as a result of this  |
| issue.                                                                       |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| * * * RETRACTION on 10/10/00 at 0934 ET by John Sell taken by MacKinnon * *  |
| *                                                                            |
|                                                                              |
| The licensee's engineering staff has completed an Operability Determination  |
| (OD) in accordance with GL 91-18, which investigated the applicability of    |
| the existing SGTR analysis for Point Beach Nuclear Plant (PBNP). This        |
| evaluation concluded that the actual installed capacity of the ADV supports  |
| the 44 minute cooldown assumption and that there exists ample assurance that |
| under design and licensing conditions, the PBNP physical plant can actually  |
| support a significantly shorter duration mitigation.  The limiting factor    |
| for the SGTR mitigation remains the operator response and the procedures     |
| driving that response.  The approved OD concluded that the ADV system is     |
| operable and fully meets performance requirements. R3DO (John Madera)        |
| notified.                                                                    |
|                                                                              |
| The NRC Resident Inspector was notified of this event retraction by the      |
| licensee.                                                                    |
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+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   37420       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  MIDAMERICA PETERBUILT                |NOTIFICATION DATE: 10/10/2000|
|LICENSEE:  MIDAMERICA PETERBUILT                |NOTIFICATION TIME: 15:17[EDT]|
|    CITY:  O'FALLON                 REGION:  3  |EVENT DATE:        09/25/2000|
|  COUNTY:  ST. CHARLES               STATE:  MO |EVENT TIME:             [CDT]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  10/10/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MONTE PHILLIPS       R3      |
|                                                |                             |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  LONNIE EKEREN                |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOST STAT ATTACK GUN WITH POLONIUM-210 SOURCE                                |
|                                                                              |
| The company lost an anti-static device used in painting vehicles.  The       |
| device is a Stat Attack Gun, containing a nominal 10 mCi Po-210 sealed       |
| source.  The device is a model # PBM1002H, serial #9807KB.  The device is    |
| believed lost in the trash after an extensive search of the facility.        |
|                                                                              |
| The company notified NRC Region 3 (Monte Phillips).                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37421       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MCGUIRE                  REGION:  2  |NOTIFICATION DATE: 10/10/2000|
|    UNIT:  [] [2] []                 STATE:  NC |NOTIFICATION TIME: 20:05[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        10/10/2000|
+------------------------------------------------+EVENT TIME:        19:07[EDT]|
| NRC NOTIFIED BY:  WESLEY HILL                  |LAST UPDATE DATE:  10/10/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KEN BARR             R2      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Hot Standby      |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE TURBINE DRIVEN AUXILIARY FEEDWATER PUMP STARTED UNEXPECTEDLY             |
|                                                                              |
| "During turbine driven auxiliary feedwater pump testing the pump started     |
| when it should not have.  A check of the procedure found that it was not     |
| correctly removed from service for the test."                                |
|                                                                              |
| It is believed that a jumper placement was done wrong and is being           |
| investigated.                                                                |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.                   |
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