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Event Notification Report for May 16, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           05/15/2001 - 05/16/2001

                              ** EVENT NUMBERS **

37815  37816  37968  37989  37990  37991  37992  37993  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37815       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 03/08/2001|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 13:04[EST]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        03/05/2001|
+------------------------------------------------+EVENT TIME:        16:08[CST]|
| NRC NOTIFIED BY:  PAT DECKER                   |LAST UPDATE DATE:  05/15/2001|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN MADERA          R3      |
|10 CFR SECTION:                                 |                             |
|*UNA 50.72(b)(3)(ii)(B)  UNANALYZED CONDITION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOW PRESSURE CORE SPRAY STRUCTURAL ANALYSIS DID NOT CONSIDER ALL POSSIBLE    |
| FLOW CONDITIONS                                                              |
|                                                                              |
| "On March 5, 2001, it was discovered that the structural analysis of         |
| in-vessel Core Spray piping did not consider all applicable flow conditions. |
| A notification should have been made at that time because the effect of the  |
| unanalyzed condition on degradation of plant safety was not considered with  |
| respect to all plant operating conditions (i.e., the plant was shut down at  |
| the time of discovery).  Preliminary analysis results indicated that         |
| previous analyses are bounding."                                             |
|                                                                              |
| This issue will be resolved before the next plant startup.                   |
|                                                                              |
| The licensee will notify the NRC resident inspector.                         |
|                                                                              |
| **** RETRACTION RECEIVED AT 1641 EDT ON 05/15/01 FROM PATRICK DECKER TO      |
| LEIGH TROCINE ****                                                           |
|                                                                              |
| The licensee is retracting this event notification.  The following text is a |
| portion of a facsimile received from the licensee:                           |
|                                                                              |
| "[...]  On [03/08/01], we reported that structural analysis of the in-core   |
| spray piping did not consider all the applicable flow conditions.  Upon      |
| re-evaluation, this is not reportable since:  1) this condition only         |
| affected one train of core spray piping, and 2) the flaw condition believed  |
| to have been overlooked was determined [analytically] to be bounded by       |
| [existing] analyses."                                                        |
|                                                                              |
| The licensee notified the NRC resident inspector.  The NRC operations        |
| officer notified the R3DO (Parker).                                          |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37816       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 03/09/2001|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 04:30[EST]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        03/09/2001|
+------------------------------------------------+EVENT TIME:        01:30[CST]|
| NRC NOTIFIED BY:  TIM ROGERS                   |LAST UPDATE DATE:  05/15/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN MADERA          R3      |
|10 CFR SECTION:                                 |                             |
|*SHU 50.72(b)(2)(i)      PLANT S/D REQD BY TS   |                             |
|*ESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A          N       0        Refueling        |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MODE CHANGE DUE TO LITERAL INTERPRETATION OF REQUIREMENTS                    |
|                                                                              |
| "To meet compliance with literal interpretation of Tech Spec 3.7.A.5 and     |
| 3.8.B.6, containment venting and purging using SBGT is required above 'Cold  |
| Shutdown.'  Plant is < 212, all rods in BUT mode switch was in 'Refuel.' To |
| comply with Tech Specs, a Tech Spec shutdown with mode switch was performed. |
| All rods were already in but it wasn't a preplanned shutdown evolution.      |
| Other similar 'Cold Shutdown' Tech Spec compliance issues are being looked   |
| at."                                                                         |
|                                                                              |
| An automatic scram signal was generated when the mode switch was taken to    |
| the 'Shutdown' position. Although all control rods were already inserted,    |
| the licensee considers this action to be reportable as a valid safety system |
| actuation. The NRC resident inspector will be informed of this event by the  |
| licensee.                                                                    |
|                                                                              |
| **** RETRACTION RECEIVED AT 1641 EDT ON 05/15/01 FROM PATRICK DECKER TO      |
| LEIGH TROCINE ****                                                           |
|                                                                              |
| The licensee is retracting this event notification.  The following text is a |
| portion of a facsimile received from the licensee:                           |
|                                                                              |
| "[...]  On [03/09/01], we reported the failure to literally comply with      |
| [Technical] Specification 3.7.A and 3.8.B.6.  This event is being retracted  |
| since 1) the requirement to use SBGT 'above' Cold Shutdown does not apply to |
| plant conditions where the plant is below the Cold Shutdown temperature of   |
| 212 degrees F with the mode switch in 'refuel,' and 2) moving the mode       |
| switch back to shutdown from 'refuel' was required to comply with a          |
| prerequisite of an approved plant procedure.  Therefore, this was part of a  |
| preplanned sequence."                                                        |
|                                                                              |
| The licensee notified the NRC resident inspector.  The NRC operations        |
| officer notified the R3DO (Parker).                                          |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37968       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 05/06/2001|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 06:02[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        05/06/2001|
+------------------------------------------------+EVENT TIME:        03:10[CDT]|
| NRC NOTIFIED BY:  SCHMIDT                      |LAST UPDATE DATE:  05/15/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MELVYN LEACH         R3      |
|10 CFR SECTION:                                 |                             |
|*INA 50.72(b)(3)(v)(A)   POT UNABLE TO SAFE SD  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       90       Power Operation  |73       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MAIN TURBINE STOP VALVE FAILED TO CLOSE DURING TESTING                       |
|                                                                              |
| The #4 main turbine stop valve failed to close during the performance of     |
| turbine valve testing procedure.  Failure of the turbine valve to close      |
| affects the turbine stop valve closure scram function of both A&B reactor    |
| protection trip systems.  Reactor power is currently being reduced to less   |
| than 45% power which is required when the minimum conditions for the turbine |
| stop valve closure scram function are not satisfied.  The licensee believes  |
| the cause of the problem is probably due to a bad solenoid valve.            |
|                                                                              |
| The NRC Resident Inspector will be notified.                                 |
|                                                                              |
| **** RETRACTION RECEIVED AT 1641 EDT ON 05/15/01 FROM PATRICK DECKER TO      |
| LEIGH TROCINE ****                                                           |
|                                                                              |
| The licensee is retracting this event notification.  The following text is a |
| portion of a facsimile received from the licensee:                           |
|                                                                              |
| "[...]  On [05/06/01], we reported the failure to close of Main Turbine Stop |
| Valve #4 during routine testing. Subsequently, it was learned that the       |
| failure affected the test circuit only and had no effect on the normal       |
| operation of the stop valve. Therefore, this event is not reportable. The    |
| test circuit failure has been corrected, and the Main Turbine Stop Valve #4  |
| retested successfully."                                                      |
|                                                                              |
| The licensee notified the NRC resident inspector.  The NRC operations        |
| officer notified the R3DO (Parker).                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   37989       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  OTTWELL  MALBY                       |NOTIFICATION DATE: 05/15/2001|
|LICENSEE:  OTTWELL  MALBY                       |NOTIFICATION TIME: 10:42[EDT]|
|    CITY:  TRAVERSE CITY            REGION:  3  |EVENT DATE:        05/15/2001|
|  COUNTY:                            STATE:  MI |EVENT TIME:        10:30[EDT]|
|LICENSE#:  21-32235-01           AGREEMENT:  N  |LAST UPDATE DATE:  05/16/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GARY SHEAR           R3      |
|                                                |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  TOD CRAMER                   |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| STRUCTURE FIRE INVOLVING NUCLEAR GAUGE                                       |
|                                                                              |
| The licensee reported that a fire is currently occurring at their field      |
| office.  A Troxler Model 3411 moisture/density gauge is currently stored in  |
| the building.  The sources are locked in their safe positions, and the gauge |
| is located in a storage locker.  The licensee has notified local police and  |
| fire departments regarding the presence of this device.                      |
|                                                                              |
| ***** UPDATE RECEIVED AT 1515 ON 05/15/01 FROM TOD CRAMER TO LEIGH TROCINE   |
| *****                                                                        |
|                                                                              |
| The licensee is updating this event notification.  The gauge was not damaged |
| in the fire.  There was some water damage, and that area of the building was |
| reported to be underwater after the fire.  The HAZMAT team obtained a        |
| surface reading on the gauge, and the reading was 1 millirem per hour.  The  |
| gauge was intact, and there was no heat damage, melting, or physical damage. |
| The licensee plans to perform a wipe test and possibly repair the gauge.     |
|                                                                              |
| The licensee notified the Fire Department, HAZMAT, local/city police         |
| agencies, and NRC region 3 office (Jim Hastings).  The NRC operations        |
| officer notified the R3DO (Parker) and NMSS EO (Cool).                       |
|                                                                              |
| (Please call the NRC operations officer for a licensee contact telephone     |
| number.)                                                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37990       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  NC DIVISION OF RADIATION PROTECTION  |NOTIFICATION DATE: 05/15/2001|
|LICENSEE:  S&ME                                 |NOTIFICATION TIME: 14:56[EDT]|
|    CITY:  GREENSBORO               REGION:  2  |EVENT DATE:        05/12/2001|
|  COUNTY:                            STATE:  NC |EVENT TIME:             [EDT]|
|LICENSE#:  041-0922-1            AGREEMENT:  Y  |LAST UPDATE DATE:  05/15/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CHARLES R. OGLE      R2      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  SHARN JEFFRIES               |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT REGARDING A TROXLER MOISTURE DENSITY GAUGE            |
| LOST/STOLEN FROM S&ME IN WINSTON SALEM, NORTH CAROLINA                       |
|                                                                              |
| The following text is a portion of a facsimile received from the North       |
| Carolina Department of Environment and Natural Resources, Division of        |
| Radiation Protection:                                                        |
|                                                                              |
| "SUBJECT:  Incident 01-14"                                                   |
|                                                                              |
| "Today, a North Carolina Portable Gauge Licensee (S&ME 041-0922-1            |
| Greensboro) reported a loss/theft of a Portable Moisture Density Gauge from  |
| Winston Salem, NC, between the evening on Friday, May 11, 2001, and          |
| Saturday, May 12, 2001.  Local and State law enforcement agencies were       |
| notified on Saturday, May 12, 2001.  This Agency was notified by NC          |
| Emergency Management of the incident at [1630] on Monday, May 14, 2001.  The |
| Licensee reported the incident to this Agency [on] May 15, 2001."            |
|                                                                              |
| "The device that was lost/stolen is:"                                        |
|                                                                              |
| "Troxler 3411B Moisture Density Gauge SN 14682                               |
| Cs-137                  #50-3361          8 mCi                              |
| Am-241:Be            #47-10037        40 mCi"                                |
|                                                                              |
| (Call the NRC operations officer for a State contact telephone number.)      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   37991       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  STORK TWIN CITY TESTING              |NOTIFICATION DATE: 05/15/2001|
|LICENSEE:  STORK TWIN CITY TESTING              |NOTIFICATION TIME: 15:31[EDT]|
|    CITY:  ST. PAUL                 REGION:  3  |EVENT DATE:        05/08/2001|
|  COUNTY:  RAMSEY                    STATE:  MN |EVENT TIME:        09:00[CDT]|
|LICENSE#:  22-01376-02           AGREEMENT:  N  |LAST UPDATE DATE:  05/15/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MICHAEL PARKER       R3      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  PATRICK LIEBL                |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| STUCK IRIDIUM-192 SOURCE AND FAILURE TO MAKE AN EVENT NOTIFICATION WITHIN 24 |
| HOURS                                                                        |
|                                                                              |
| On 05/05/01, an X-ray crew in Heron Lake, MN, was inspecting a flat bottom   |
| tank using an Amertest-660A device containing 80 curies of iridium-192.  At  |
| 0900 CDT, during performance of an exposure, the stand that the guide tube   |
| was connected to fell over and kinked the tube.  As a result, the crew could |
| not initially retract the source.  The crew subsequently followed procedures |
| and successfully retracted the source to its shielded position.  There were  |
| no overexposures as a result of this event.                                  |
|                                                                              |
| In preparation for submitting a 30-day letter, the licensee discovered       |
| (today) that this event should have been reported as a 24-hour event         |
| notification.                                                                |
|                                                                              |
| (Call the NRC operations officer for a licensee contact telephone number.)   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37992       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALVERT CLIFFS           REGION:  1  |NOTIFICATION DATE: 05/15/2001|
|    UNIT:  [1] [2] []                STATE:  MD |NOTIFICATION TIME: 16:44[EDT]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        05/15/2001|
+------------------------------------------------+EVENT TIME:        16:08[EDT]|
| NRC NOTIFIED BY:  BRUCE SHICK                  |LAST UPDATE DATE:  05/15/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN ROGGE           R1      |
|10 CFR SECTION:                                 |                             |
|*COM 50.72(b)(3)(xiii)   LOSS COMM/ASMT/RESPONSE|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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       68       Power Operation  |68       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MAJOR LOSS OF EMERGENCY PREPAREDNESS CAPABILITIES IN THE CALVERT COUNTY      |
| AREA                                                                         |
|                                                                              |
| At 1608 on 05/15/01, the control room was notified that 40 of the 49         |
| [emergency] sirens failed to respond [during] the weekly silent test at      |
| 1445.  The apparent cause is currently believed to be a potential            |
| transformer failure.   Troubleshooting and repairs are in progress.          |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37993       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BYRON                    REGION:  3  |NOTIFICATION DATE: 05/16/2001|
|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 05:38[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        05/15/2001|
+------------------------------------------------+EVENT TIME:        07:00[CDT]|
| NRC NOTIFIED BY:  BRYAN HERRING                |LAST UPDATE DATE:  05/16/2001|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MICHAEL PARKER       R3      |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       98       Power Operation  |98       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PLANT MAY HAVE  OPERATED ABOVE 100% POWER                                    |
|                                                                              |
| During power up-rate data verification, Byron Station identified that an     |
| improper feedwater density factor and thermal expansion coefficient had been |
| used to calculate feedwater flow constants (referred to as AMAG constants)   |
| on Units 1 and 2.  The improper constants resulted in a non-conservative     |
| determination of reactor power via the thermal power calorimetric            |
| calculation.  Thermal power was underestimated by 0.12 percent rated thermal |
| power.  The improper AMAG constants have been utilized since AMAG was        |
| implemented at Byron Station in May of 2000 (Unit 1 on 5/16/00 and Unit 2 on |
| 5/12/00).  It is believed since May of 2000 either unit may have exceeded    |
| 100 percent rated thermal power over an eight hour period based on the       |
| non-conservative AMAG constants.  There is no evidence that either unit ever |
| exceeded 102.0 percent rated thermal power.  A formal review of past power   |
| history for both units is in progress.  The AMAG constants have been         |
| corrected for Unit 2 and are in progress for Unit 1.  Unit 1 is being        |
| maintained at or below 99.88 percent rated thermal power until the AMAG      |
| constants have been corrected.                                               |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+