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Event Notification Report for July 23, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           07/20/2001 - 07/23/2001

                              ** EVENT NUMBERS **

38037  38156  38157  38158  38159  38160  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   38037       |
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| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 05/30/2001|
|    UNIT:  [] [2] []                 STATE:  NY |NOTIFICATION TIME: 17:20[EDT]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        05/30/2001|
+------------------------------------------------+EVENT TIME:        13:08[EDT]|
| NRC NOTIFIED BY:  PETRELLI                     |LAST UPDATE DATE:  07/20/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ERIC REBER           R1      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM WAS DECLARED INOPERABLE.        |
|                                                                              |
| The RCIC system was inoperable and available for planned maintenance and     |
| surveillance testing.   During the planned surveillance testing, the         |
| mechanical overspeed mechanism for the RCIC turbine was discovered to be     |
| tripped with no overspeed trip testing having been performed.   The          |
| overspeed trip mechanism may be degraded thereby constituting a condition    |
| that could have prevented the system from performing its function.  RCIC is  |
| currently in standby and inoperable but available.  Troubleshooting is in    |
| progress to determine the cause of the trip.  This report may be retracted   |
| if the cause of the trip is determined to not affect the operability of the  |
| system.                                                                      |
|                                                                              |
| The NRC resident inspector was notified.                                     |
|                                                                              |
| ***** RETRACTION FROM THOMAS SCWALECK TO LEIGH TROCINE AT 1537 ON 07/20/01   |
| *****                                                                        |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "On 5/30/01, during Reactor Core Isolation Cooling (RCIC) surveillance       |
| testing, the overspeed trip mechanism was discovered tripped with no         |
| overspeed testing having been performed.  The overspeed trip mechanism was   |
| discovered tripped after a section of the surveillance testing that closed   |
| the trip/throttle valve and then cycled the trip solenoid several times.     |
| Nine Mile Point determined that, because of degraded engagement between the  |
| trip tappet nut and the head lever, the overspeed mechanism was susceptible  |
| to tripping during the cycling of the trip solenoid with the throttle valve  |
| tripped.  Additionally, Nine Mile Point concluded that with the throttle     |
| valve latched open and RCIC aligned for operation, the overspeed trip        |
| mechanism would not have been susceptible to tripping.  Therefore, the       |
| conditions that resulted in the tripping of the RCIC overspeed trip          |
| mechanism during the surveillance would not have prevented RCIC from         |
| performing its function.  Based on the above, we are retracting the          |
| 50.72(b)(3)(v)(D) notification made on 5/30/01."                             |
|                                                                              |
| The licensee notified the NRC resident inspector.  The NRC operations        |
| officer notified the R1DO (Cook).                                            |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38156       |
+------------------------------------------------------------------------------+
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| FACILITY: SUMMER                   REGION:  2  |NOTIFICATION DATE: 07/20/2001|
|    UNIT:  [1] [] []                 STATE:  SC |NOTIFICATION TIME: 17:06[EDT]|
|   RXTYPE: [1] W-3-LP                           |EVENT DATE:        07/20/2001|
+------------------------------------------------+EVENT TIME:        16:15[EDT]|
| NRC NOTIFIED BY:  CHARLES McKINNEY             |LAST UPDATE DATE:  07/20/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JAY HENSON           R2      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION REGARDING A SODIUM NITRITE CHEMICAL RELEASE             |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "Notification is being made for exceeding the reportable quantity for        |
| release of sodium nitrite from a closed cycle cooling system to the outfalls |
| discharging effluents from the V.C. Summer Nuclear Station to the            |
| environment (Lake Monticello).  A drain valve was left open during           |
| maintenance on an instrument air compressor at approximately 1600 hours on   |
| 7/19/01.  The drain line discharged effluent from a closed cycle coolant     |
| system containing sodium nitrite to the plant sumps for approximately 16.5   |
| hours.  Following isolation of the line, a review of flow rates and          |
| discharge paths found (completed at 1615 hours on 7/20/01) that              |
| approximately 16,000 gallons of effluent had been discharged from the plant  |
| to the environment."                                                         |
|                                                                              |
| "It has been determined that approximately 135 pounds of sodium nitrite was  |
| discharged from the plant during this period.  The reportable quantity for   |
| release is 100 pounds in a 24-hour period."                                  |
|                                                                              |
| "The hazard from sodium nitrite is from the pH level of 10.5.  A daily check |
| of pH at the plant outfall that received this discharge found the pH to be   |
| 9.0; therefore, there is no hazard to the environment from this release      |
| since this is the normal pH at this sample point.  Plant personnel will      |
| continue to check the pH level of this discharge point each day."            |
|                                                                              |
| The licensee reported that they have not observed any environmental impacts  |
| and that there was no release of radioactive materials.                      |
|                                                                              |
| The licensee notified the Environmental Protection Agency via the National   |
| Response Center at 1650 hours, and the National Response Center is           |
| documenting this event under report #573719.  Because the site is located in |
| an Agreement State, the licensee also notified the South Carolina Department |
| of Health and Environmental Control at 1700 hours.  In addition, the         |
| licensee notified the Local Planning Committee and the NRC resident          |
| inspector.                                                                   |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38157       |
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| FACILITY: LIMERICK                 REGION:  1  |NOTIFICATION DATE: 07/20/2001|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 21:57[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        07/20/2001|
+------------------------------------------------+EVENT TIME:        14:50[EDT]|
| NRC NOTIFIED BY:  PETE ORPHANOS                |LAST UPDATE DATE:  07/20/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |WILLIAM COOK         R1      |
|10 CFR SECTION:                                 |                             |
|AUNA 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          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCOVERY OF THE POTENTIAL FOR A LOSS OF REACTOR CORE ISOLATION COOLING      |
| (RCIC) REMOTE SHUTDOWN PANEL CAPABILITY DURING A POSTULATED MAIN CONTROL     |
| ROOM FIRE                                                                    |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "A review of the Limerick fire safe shutdown analysis identified that during |
| a fire in the control room, RCIC system operation from the remote shutdown   |
| panel (RSP) may not be available for safe shutdown of the unit.  A           |
| postulated fire that results in a short of the Division 1 DC distribution    |
| system to ground causes a voltage control device to fail integral to [an     |
| RSP] instrument power supply inverter.  This ground, potentially caused by a |
| fire that affects Division 1 DC in the control room, results in failure of   |
| the fused instrument power supply to the RCIC RSP inverter."                 |
|                                                                              |
| "The current fire safe shutdown analysis credits only one safe shutdown      |
| method as being analyzed as acceptable during a worst case main control room |
| fire.  This analysis requires RCIC to be operational from the RSP to support |
| acceptability of the method.  With this loss of RCIC RSP capability during a |
| [main control room] fire, this event is reportable under                     |
| 10CFR50.72(b)(3)(ii)."                                                       |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
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|Power Reactor                                    |Event Number:   38158       |
+------------------------------------------------------------------------------+
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| FACILITY: LASALLE                  REGION:  3  |NOTIFICATION DATE: 07/21/2001|
|    UNIT:  [1] [2] []                STATE:  IL |NOTIFICATION TIME: 18:26[EDT]|
|   RXTYPE: [1] GE-5,[2] GE-5                    |EVENT DATE:        07/21/2001|
+------------------------------------------------+EVENT TIME:        15:28[CDT]|
| NRC NOTIFIED BY:  MARK OKOPNY                  |LAST UPDATE DATE:  07/21/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |GARY SHEAR           R3      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION REGARDING A MINOR FISH KILL IN THE COOLING LAKE DUE TO  |
| INCREASING SUMMER TEMPERATURES                                               |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "... this notification is being made pursuant to 10CFR50.72(b)(2)(xi) and    |
| Exelon Reportability Manual Section SAF 1.9.  At 1528 CST on 07/21/01, it    |
| was discovered that a minor fish kill took place in LaSalle County Nuclear   |
| Station's cooling lake due to increased temperature.  As summer air          |
| temperatures increase, the cooling lake temperature increased to 97F,       |
| beyond the threshold at which point species susceptible to increased         |
| temperature begin to perish.  It was communicated to the Illinois Department |
| of Natural Resources that approximately 2,000 fish, mainly Gizzard Shad, had |
| perished."                                                                   |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38159       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRAIDWOOD                REGION:  3  |NOTIFICATION DATE: 07/22/2001|
|    UNIT:  [1] [2] []                STATE:  IL |NOTIFICATION TIME: 15:15[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        07/22/2001|
+------------------------------------------------+EVENT TIME:        13:30[CDT]|
| NRC NOTIFIED BY:  DAN COMISKY                  |LAST UPDATE DATE:  07/22/2001|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |GARY SHEAR           R3      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION REGARDING A MINOR FISH KILL                             |
|                                                                              |
| This notification was being made pursuant  to 10CFR50.72(b)(2)(xi),          |
| Braidwood Station Technical Specification Appendix B 4.1, and Exelon         |
| Reportability Manual Section SAF 1.9.  At 1330 CDT on 07/22/01, it was       |
| communicated to the Illinois Department of Natural Resources that            |
| approximately 700 fish had perished in a minor fish kill in Braidwood        |
| Nuclear Station cooling lake due to increased temperature. As summer air     |
| temperature increased, the cooling lake temperature increased to above 97    |
| degrees F, beyond the threshold at which point species susceptible increased |
| temperature begin to perish.                                                 |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38160       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OYSTER CREEK             REGION:  1  |NOTIFICATION DATE: 07/22/2001|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 19:08[EDT]|
|   RXTYPE: [1] GE-2                             |EVENT DATE:        07/22/2001|
+------------------------------------------------+EVENT TIME:        17:44[EDT]|
| NRC NOTIFIED BY:  MALCOLM BROWNE               |LAST UPDATE DATE:  07/22/2001|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |WILLIAM COOK         R1      |
|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       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| CALLED IN AS A 24 HOUR NOTIFICATION                                          |
|                                                                              |
| A dead sea turtle, species unknown, was discovered in dilution intake        |
| structure bay # 5.  The sea turtle has a gash in the back of the head which  |
| may have been caused by a boat propeller.  National Marine Fisheries was     |
| notified. The licensee will notify the New Jersey Department of              |
| Environmental Protection.                                                    |
|                                                                              |
| The licensee will contact the NRC resident inspector.                        |
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