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Event Notification Report for October 1, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           09/28/2001 - 10/01/2001

                              ** EVENT NUMBERS **

38183  38326  38328  38329  38330  38332  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   38183       |
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| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 08/02/2001|
|    UNIT:  [] [3] []                 STATE:  NY |NOTIFICATION TIME: 19:17[EDT]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        08/02/2001|
+------------------------------------------------+EVENT TIME:        15:00[EDT]|
| NRC NOTIFIED BY:  TIM RIEGER                   |LAST UPDATE DATE:  09/28/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |CLIFFORD ANDERSON    R1      |
|10 CFR SECTION:                                 |HERB BERKOW          NRR     |
|AUNA 50.72(b)(3)(ii)(B)  UNANALYZED CONDITION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| UNANALYZED CONDITION INVOLVING SEISMIC EVENT DISCOVERED DURING ENGINEERING   |
| REVIEW                                                                       |
|                                                                              |
| "On August 2, 2001, at approximately 1500 hours, Engineering notified        |
| operations that the Service Water (SW) System may not meet analyzed flow     |
| requirements after a seismic event as a result of a system re-alignment      |
| change implemented June 4, 2001. The SWS re-alignment change placed an 8     |
| inch non-seismic SW line on the essential SW header. The SWS was originally  |
| analyzed for a seismic event with the break of a 10 inch non-seismic SW      |
| line. The change evaluation concluded that this configuration was bounding   |
| for the alignment. The assessment of the alignment change did not adequately |
| consider the effects of the seismic event. After a review of the change,     |
| Engineering judged that the SWS would not meet system design flow            |
| requirement after a seismic event with two out of three pumps due to the     |
| failure of both non-seismic lines that were aligned as a result of the       |
| change. Operations initiated realignment of the 8 inch SW line back to the   |
| non-essential header which was completed at 1640 hours. Engineering is       |
| performing evaluations but judged that the SWS would have met flow           |
| requirements for plant shutdown with three SW pumps operable after a seismic |
| event with no random single failure (three pumps operable)."                 |
|                                                                              |
| The licensee will inform the NRC resident inspector.                         |
|                                                                              |
| **** RETRACTION ON 09/28/01 AT 1002 HOURS BY TIM RIEGER TAKEN BY MACKINNON   |
| ****                                                                         |
|                                                                              |
| Upon further assessment, the re-alignment condition is not considered        |
| reportable.  Additional engineering reviews showed that the alignment to the |
| non-seismic SW lines to the Essential header was not risk significant.       |
| Engineering judgement and analysis concluded that the plant design basis     |
| events, including the seismic event, would not cause a consequential loss of |
| the non-seismic lines aligned to the Essential header.  Therefore, the       |
| condition did not significantly degrade plant safety and although at the     |
| time was unanalyzed, the condition does not meet reporting requirements.  As |
| part of Indian Point 3's corrective action program, the cause and extent of  |
| condition of the event is being evaluated and identified corrective actions  |
| will be performed.   R3DO (John Kinneman) notified.                          |
|                                                                              |
| The NRC Resident Inspector was notified of this retraction by the licensee.  |
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|General Information or Other                     |Event Number:   38326       |
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| REP ORG:  NE DIV OF RADIOACTIVE MATERIALS      |NOTIFICATION DATE: 09/28/2001|
|LICENSEE:  THOMPSON DREESSEN DORNER INC.        |NOTIFICATION TIME: 11:43[EDT]|
|    CITY:  SPRINGFIELD              REGION:  4  |EVENT DATE:        09/27/2001|
|  COUNTY:                            STATE:  NE |EVENT TIME:        13:00[CDT]|
|LICENSE#:  01-7001               AGREEMENT:  Y  |LAST UPDATE DATE:  09/28/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GREG PICK            R4      |
|                                                |FRED BROWN           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JOHN FASSELL                 |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| DENSITY GAUGE SOURCE ROD BROKEN OFF                                          |
|                                                                              |
| A Humboldt Model # 5001gauge was run over by a 50-ton blader vehicle.  The   |
| density gauge source rod was broken off, and the gauge itself was flattened. |
| The blader vehicle ran over the density gauge in a landfill while the person |
| who was assigned to guard the gauge had his back turned.  The source was in  |
| its stored position when it was run over by the blader vehicle.  There was   |
| no contamination on the blader vehicle and no radioactive release from the   |
| gauge.  The Humboldt Model # 5001 has 8 mCi of cesium-137 and 40 mCi of      |
| americium-241/beryllium.  The owner of the gauge is Thompson Dreessen Dorner |
| Inc., which is located in Omaha.                                             |
|                                                                              |
| (Call the NRC operations officer for State contact information.)             |
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+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   38328       |
+------------------------------------------------------------------------------+
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| REP ORG:  US ARMY                              |NOTIFICATION DATE: 09/28/2001|
|LICENSEE:  US ARMY                              |NOTIFICATION TIME: 13:34[EDT]|
|    CITY:  ABERDEEN PROVING GROUNDS REGION:  1  |EVENT DATE:        09/28/2001|
|  COUNTY:                            STATE:  MD |EVENT TIME:        12:07[EDT]|
|LICENSE#:  19-30563-01           AGREEMENT:  Y  |LAST UPDATE DATE:  09/28/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JOHN KINNEMAN        R1      |
|                                                |MONTE PHILLIPS       R3      |
+------------------------------------------------+FRED BROWN           NMSS    |
| NRC NOTIFIED BY:  JOYCE KUYKENDAL              |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MISSING CHEMICAL AGENT DETECTOR CONTAINING 30 MICROCURIES OF AMERICIUM-241   |
|                                                                              |
| A chemical agent detector (CAD) containing 30 microcuries of americium-241   |
| was discovered to be missing during a physical inventory conducted during    |
| 08/01.  A search was performed at all units, and the US Army Aberdeen        |
| Proving Ground in Maryland was notified of the missing CAD at 1207 on        |
| 09/28/01.  It is believed that the CAD may have been last used by the        |
| Wisconsin Army National Guard located in Black River Falls during nuclear    |
| biological chemical (NBC) training.                                          |
|                                                                              |
| (Call the NRC operations officer for licensee contact information.)          |
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|Fuel Cycle Facility                              |Event Number:   38329       |
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| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 09/28/2001|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 17:11[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        09/28/2001|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        15:20[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  09/28/2001|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |MONTE PHILLIPS       R3      |
|  DOCKET:  0707002                              |PATRICIA HOLAHAN     NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ERIC SPAETH                  |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| OFFSITE NOTIFICATION REGARDING AN OPACITY VIOLATION (4-hour Report)          |
|                                                                              |
| The following text is a portion of a facsimile received from Portsmouth      |
| personnel:                                                                   |
|                                                                              |
| "At 1520 hours [on] 09/28/01, the Ohio Environmental Protection Agency       |
| (OEPA) was notified per Ohio Administrative Code (OAC) 3745-15-06(B) that an |
| opacity exceedance had occurred at the X-600 Steam Plant.  The opacity       |
| violation occurred on [the] #2 Boiler when our #2A Precipitator voltages     |
| began to fluctuate.  Operators adjusted load/air requirements on the #2      |
| Boiler in an effort to prevent further exceedances.  [The] cause of the      |
| voltage fluctuations has not been determined at this time."                  |
|                                                                              |
| "This is reportable as a 4-hour NRC Event due to notification to an outside  |
| agency (OEPA) being made per Nuclear Regulatory Reporting Procedure          |
| UE2-RA-RE1030, Appendix D, Criteria P (Miscellaneous)."                      |
|                                                                              |
| Portsmouth personnel notified the NRC resident inspector.                    |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38330       |
+------------------------------------------------------------------------------+
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| FACILITY: FERMI                    REGION:  3  |NOTIFICATION DATE: 09/28/2001|
|    UNIT:  [2] [] []                 STATE:  MI |NOTIFICATION TIME: 18:39[EDT]|
|   RXTYPE: [2] GE-4                             |EVENT DATE:        09/28/2001|
+------------------------------------------------+EVENT TIME:        16:25[EDT]|
| NRC NOTIFIED BY:  MIKE PHILIPPON               |LAST UPDATE DATE:  09/28/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |MONTE PHILLIPS       R3      |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
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| POTENTIAL MAXIMUM POWER LEVEL VIOLATION                                      |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "This report is being made in accordance with Fermi 2 License Condition 2.F, |
| as a potential violation of the Maximum Power Level of 3430 MWth as          |
| described in License Condition 2.C(1)."                                      |
|                                                                              |
| "GE report titled, 'Impact of Steam Carryover Fraction on Process Computer   |
| Heat Balance Calculations, September 2001,' documents a non-conservative     |
| assumption for moisture [carryover] used in the calculation of core thermal  |
| power.  The assumed carryover fraction of .1% was discovered to be closer to |
| 0.0% (non-conservative) in later model GE BWRs."                             |
|                                                                              |
| "An initial review at Fermi 2 was completed at 1625 on 09/28/01.  The        |
| initial review indicated that Fermi is susceptible to the non-conservative   |
| core thermal power calculation, with an estimated bias of 1.64 MWth.  This   |
| initial analysis was based on a carryover test performed in 1996 at Fermi    |
| 2."                                                                          |
|                                                                              |
| "Fermi 2 has an administrative 8-hour average power limit of 3428.8 MWth.    |
| Given the 1.64 MWth bias, it is possible that the license limit of 3430 MWth |
| has been exceeded in the past.  Fermi 2 took immediate action to reduce the  |
| administrative power limit to 3427 MWth.  Reactor power was reduced by 3     |
| MWth."                                                                       |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38332       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE               REGION:  4  |NOTIFICATION DATE: 09/30/2001|
|    UNIT:  [] [] [3]                 STATE:  AZ |NOTIFICATION TIME: 20:28[EDT]|
|   RXTYPE: [1] CE,[2] CE,[3] CE                 |EVENT DATE:        09/30/2001|
+------------------------------------------------+EVENT TIME:        14:00[MST]|
| NRC NOTIFIED BY:  STEVE BANKS                  |LAST UPDATE DATE:  09/30/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |GREG PICK            R4      |
|10 CFR SECTION:                                 |JOHN ZWOLINSKI       NRR     |
|ADEG 50.72(b)(3)(ii)(A)  DEGRADED CONDITION     |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|                                                   |                          |
|3     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| EVIDENCE OF REACTOR COOLANT SYSTEM PRESSURE BOUNDARY LEAKAGE DISCOVERED      |
| WHILE IN COLD SHUTDOWN.                                                      |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "The following event description is based on information currently           |
| available.  If through subsequent reviews of this event, additional          |
| information is identified that is pertinent to this event or alters the      |
| information being provided at this time, a follow-up notification will be    |
| made via the ENS or under the reporting requirements of 10CFR50.73."         |
|                                                                              |
| "On September 30, 2001, at approximately 1400 MST, Palo Verde Nuclear        |
| Generating Station (PVNGS) Unit 3 discovered evidence of reactor coolant     |
| system (RCS) pressure boundary leakage.  PVNGS Unit 3 was shutdown in Mode 5 |
| conducting cooldown and depressurization in its [ninth] refueling outage at  |
| the time of discovery.  Current RCS temperature is approximately 135 degrees |
| Fahrenheit and RCS pressure is approximately 20 psia."                       |
|                                                                              |
| "The leakage was discovered at two [Inconel] alloy 600 nozzle locations      |
| during inservice inspection (ISI); one in a RCS hot leg temperature detector |
| nozzle and another in a pressurizer heater sleeve.  The RCS hot leg leakage  |
| is located in the RTD nozzle for an inservice temperature [detector] (Loop   |
| #1, Equipment ID: 3JRCETW112HD).  The pressurizer heater sleeve leakage is   |
| located at pressurizer heater B17.  The leakage was identified in the form   |
| of small deposits of boron accumulation around the circumferences of the hot |
| leg nozzle and that of the pressurizer sleeve.  PVNGS has conducted          |
| inspections of these nozzles [and] sleeves during each refueling outage      |
| since the discovery that Inconel alloy 600 nozzles are susceptible to axial  |
| cracking.  No evidence of leakage was identified when inspected during the   |
| last refueling outage approximately 18 months ago."                          |
|                                                                              |
| "The timing of this ENS report was based on the determination at 14:00 MST   |
| on September 30, 2001, that the boron accumulation represented a serious of  |
| a principle safety barrier.  PVNGS Unit 3 Technical Specification Limiting   |
| Condition for Operation (LCO) 3.4.14 (RCS Operational Leakage) permits no    |
| reactor coolant system pressure boundary leakage.  It was therefore          |
| conservatively concluded that any evidence of pressure boundary leakage,     |
| regardless of magnitude, represents serious degradation of a principle       |
| safety barrier.  Technical Specification [LCO] 3.4.14 is applicable in Modes |
| 1, 2, 3, and 4.  Unit 3 was in Mode 5 in a planned refueling outage at the   |
| time of discovery; therefore, LCO 3.4.14 is currently not applicable.        |
| The-hot leg nozzle and pressurizer sleeve will be repaired prior to          |
| re-entering Mode 4.  It is anticipated that the repair will be utilizing the |
| Mechanical Nozzle Seal Assembly (MNSA).  No ESF actuations occurred and none |
| were required.  No structures systems or components were inoperable that     |
| contributed to this event particularly the fuel cladding and the containment |
| fission product barriers.  The event did not result in the release of        |
| radioactivity to the environment and did not adversely affect the safe       |
| operation of the plant or the health and safety of the public."              |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
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