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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!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 |
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| 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
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| 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
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| 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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