The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

Event Notification Report for November 13, 2001

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           11/09/2001 - 11/13/2001

                              ** EVENT NUMBERS **

37902  38486  38487  38488  38489  38490  38491  38492  38493  38494  38495  38496 
38497  
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37902       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CRYSTAL RIVER            REGION:  2  |NOTIFICATION DATE: 04/09/2001|
|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 11:08[EDT]|
|   RXTYPE: [3] B&W-L-LP                         |EVENT DATE:        04/09/2001|
+------------------------------------------------+EVENT TIME:        09:54[EDT]|
| NRC NOTIFIED BY:  RICHARD SWEENEY              |LAST UPDATE DATE:  11/11/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |CAUDLE JULIAN        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  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO THE NATIONAL MARINE AND FISHERIES SERVICE AS A      
|
| RESULT OF THE ENDANGERED SEA TURTLES NON-LETHAL TAKE LIMIT BEING
EXCEEDED    |
|                                                                              |
| "On April 09, 2001 at 0940 the 40th non-lethal sea turtle take in the        |
| biennial period occurred.                                                    |
|                                                                              |
| "In accordance with Crystal River Unit #3 Operating License, Appendix B,     |
| Environmental Protection Plan (Non-Radiological),  'Endangered or threatened |
| sea turtles shall be protected in accordance with the Incidental Take        |
| Statement issued by the National Marine and Fisheries Service (NMFS).'  The  |
| NMFS has established numerical limits on live takes, lethal takes causally   |
| related to plant operation, and lethal takes not related to plant            |
| operations.                                                                  |
|                                                                              |
| "The NMFS must be notified within five days whenever:                        |
|                                                                              |
| a.  The 40th non-lethal take occurs in the biennial period, or               |
| b.  The third causally related mortality occurs in the biennial period, or   |
| c.   The sixth non-causally related mortality occurs in the biennial         |
| period.                                                                      |
|                                                                              |
| "The current biennial period for monitoring sea turtle takes began January   |
| 1, 2001.                                                                     |
|                                                                              |
| "Thus, in accordance with Crystal Unit #3 Administrative Instruction 571,    |
| Sea Turtle Rescue and Handling Guidance, the NMFS must be notified within    |
| five days.                                                                   |
|                                                                              |
| "In accordance with Crystal River Unit #3 Compliance Procedure 151, External |
| Reporting Requirements, this 40th non-lethal sea turtle take is Reportable   |
| as a 4-Hour Report under 10 CFR 50.72(b)(2)(xi) as this event is related to  |
| the protection of the environment for which a notification to other          |
| government agencies has been or will be made."                               |
|                                                                              |
| The licensee will inform the NRC resident inspector.                         |
|                                                                              |
| * * * UPDATE 0944EDT ON 4/10/01 FROM R. SWEENEY TO S. SANDIN * * *           |
|                                                                              |
| "On April 10, 2001 at 0859 the 41st non-lethal sea turtle take in the        |
| biennial period occurred."                                                   |
|                                                                              |
| The licensee informed the NRC resident inspector.  Notified R2DO(Julian).    |
|                                                                              |
| ***** UPDATE RECEIVED AT 0911 ON 04/17/01 FROM CHRISTOPHER PELLERIN TO
LEIGH |
| TROCINE *****                                                                |
|                                                                              |
| The 42nd, non-lethal, sea turtle take in the biennial period occurred at     |
| 0810 on April 17, 2001.                                                      |
|                                                                              |
| The licensee notified the NRC resident inspector.  The NRC operations        |
| officer notified the R2DO (Ernstes).                                         |
|                                                                              |
| * * * UPDATE 1125 EDT ON 5/1/01 FROM DAVID SCHULKER TO FANGIE JONES * * *    |
|                                                                              |
| "On May 1, 2001 at 0805 a turtle was identified as the 43rd rescued, live    |
| sea turtle in this biennial period.  This sea turtle will be kept for a      |
| short observation period and then safely returned to the environment."       |
|                                                                              |
| The licensee will inform the NRC Resident Inspector and the National         |
| Wildlife and Fisheries Service.  Notified R2DO(Jay Henson).                  |
|                                                                              |
| * * * UPDATE ON 5/29/01 BY FERGUSON TO SANDIN * * *                          |
|                                                                              |
| On May 29, 2001 at 0943 two turtles were identified as the 44th and 45th     |
| rescued, live Sea turtles in this biennial period. These healthy sea turtles |
| will be kept for a short observation period and then safely returned to the  |
| environment.                                                                 |
|                                                                              |
| This is Reportable as a 4-Hour Report under 10 CFR 50.72 (b) (2) (xi) as     |
| this event is related to the protection of the environment for which a       |
| notification to other government agencies has been or will be made. This is  |
| an update to event 37902.                                                    |
|                                                                              |
| The NRC Resident Inspector was notified.  The REG2 RDO(Barr) was informed.   |
|                                                                              |
| * * * UPDATE 2014 EDT 6/4/2001 FROM RAWLS TAKEN BY STRANSKY * * *            |
|                                                                              |
| On June 4, 2001 at 1815, the 46th non-lethal sea turtle (Kemp's Ridley) take |
| in the biennial period occurred. The license has informed the NRC resident   |
| inspector.  Notified R2DO (Barr).                                            |
|                                                                              |
| * * * UPDATE 1315EDT ON 6/10/01 FROM CHARLES J. MORRIS TO S. SANDIN * * *    |
|                                                                              |
| On June 10, 2001 at 1100, the 47th non-lethal sea turtle take in the         |
| biennial period occurred. The license has informed the NRC resident          |
| inspector.  Notified R2DO (Bonser).                                          |
|                                                                              |
| * * * UPDATE 0952 ON 8/20/2001 FROM FERGUSON TAKEN BY STRANSKY * * *         |
|                                                                              |
| On August 20, 2001 at 0815, the 48th non-lethal sea turtle take in the       |
| biennial period occurred. The licensee as informed the NRC resident          |
| inspector. Notified R2DO (Payne).                                            |
|                                                                              |
| * * *  UPDATE 1216 ON 9/3/01 BY SCHULKER TO GOULD * * *                      |
|                                                                              |
| On September 3, 2001 at 0845 a turtle was identified as the 49th rescued,    |
| live sea turtle in this biennial period.  This turtle has an injury to the   |
| lower jaw and is being transported to the Clearwater Marine Science Station  |
| for treatment. It has not been determined at this time if the injury is      |
| casually related to Crystal River Operations.                                |
|                                                                              |
| This is Reportable as a 4-Hour Report under 10 CFR 50.72 (b) (2) (xi) as     |
| this event is related to the protection of the environment for which a       |
| notification to other government agencies has been or will be made. This is  |
| an update to event 37902.                                                    |
|                                                                              |
| The NRC Resident Inspector and  other government agencies will be notified.  |
|                                                                              |
| Notified Reg 2 RDO(Lesser)                                                   |
|                                                                              |
| *****  UPDATE FROM RICHARD SWEENEY TO LEIGH TROCINE AT 0910 ON 10/28/01      |
| *****                                                                        |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "On October 28, 2001, at 0030, a turtle was identified as the 50th rescued,  |
| live sea turtle in this biennial period.  This is Reportable as a 4-Hour     |
| Report under 10 CFR 50.72(b)(2)(xi) as this event is related to the          |
| protection of the environment for which a notification to other government   |
| agencies has been or will be made."                                          |
|                                                                              |
| The licensee plans to notify the national Marine and Fishery Services and    |
| the NRC resident inspector.  The NRC operations officer notified the Region  |
| 2 Incident Response Center (McCree).                                         |
|                                                                              |
| *****  UPDATE FROM CURTIS McKEOWN TO JOHN MacKINNON AT 1005 ON 10/30/01      |
| *****                                                                        |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "On October 30, 2001, at 0826, two turtles were identified as the 51st and   |
| 52nd rescued, live sea turtles in this biennial period.  Additionally, a     |
| turtle rescued on October 30, 2001, has been identified as the 53rd live sea |
| turtle rescued in this biennial period."                                     |
|                                                                              |
| "This is Reportable as a 4-Hour Report under 10 CFR 50.72(b)(2)(xi) as this  |
| event is related to the protection of the environment for which a            |
| notification to other government agencies has been or will be made."         |
|                                                                              |
| The licensee notified the NRC resident inspector and plans to notify the     |
| national Marine and Fishery Services.  The NRC operations officer notified   |
| the Region 2 Incident Response Center (Loren Plisco).                        |
|                                                                              |
| **** UPDATE FROM CURTIS McKEOWN John MacKinnon AT 1052 ON 11/01/01 *****     |
|                                                                              |
| "On November 01, 2001 at 0916 a turtle was identified as the 54 the rescued, |
| live sea turtle in this biennial period.  This is reportable as a 4-hour     |
| report under 10 CFR 50.72(b)(2)(xi) as this event is related to the          |
| protection of the environment for which  a notification to other government  |
| agencies has been or will be made.  This is an update to event 37902."       |
| R2IRC notified.                                                              |
|                                                                              |
| The licensee notified the NRC Resident Inspector of this event.              |
|                                                                              |
| *****  UPDATE FROM BRYAN FERGUSON TO LEIGH TROCINE AT 0938 ON 11/03/01       |
| *****                                                                        |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "On November 3, 2001, at 0840, a green sea turtle was identified as the 55th |
| rescued, live sea turtle in this biennial period.  This is Reportable as a   |
| 4-Hour Report under 10 CFR 50.72(b)(2)(xi) as this event is related to the   |
| protection of the environment for which a notification to other government   |
| agencies has been or will be made.  [...]"                                   |
|                                                                              |
| The licensee plans to notify the national Marine and Fishery Services and    |
| the NRC resident inspector.  The NRC operations officer notified the Region  |
| 2 Incident Response Center (Ken Barr).                                       |
|                                                                              |
| *****  UPDATE FROM RICKY RAWLS TO LEIGH TROCINE AT 1126 ON 11/04/01  *****   |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "On November 3, 2001, at 1035, two sea turtles were identified as Kemp's     |
| Ridley sea turtles.  This is Crystal River Unit 3['s] (CR-3) 56th and 57th   |
| rescue of live sea turtles in this biennial period.  This is Reportable as a |
| 4-Hour Report under 10 CFR 50.72(b)(2)(xi) as this event is related to the   |
| protection of the environment for which a notification to other government   |
| agencies has been or will be made.  [...]"                                   |
|                                                                              |
| The licensee plans to notify the national Marine and Fishery Services and    |
| the NRC resident inspector.  The NRC operations officer notified the Region  |
| 2 Incident Response Center (Jim Hufham).                                     |
|                                                                              |
| * * * UPDATE 1046 EST ON 11/6/01 FROM RICK SWEENEY TO FANGIE JONES * * *     |
|                                                                              |
| "On November 06, 2001 at 0905, a sea turtle was identified as Kemp's Ridley  |
| sea turtle. This is Crystal River Unit 3 (CR-3) 58th rescue of a live sea    |
| turtle in this biennial period. This is reportable as a 4-Hour Report under  |
| 10 CFR 50.72 (b) (2) (xi) as this event is related to the protection of the  |
| environment for which a notification to other government agencies has been   |
| or will be made. This is an update to event 37902."                          |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The R2DO (Caudle Julian)  |
| was notified.                                                                |
|                                                                              |
| * * * UPDATE 1149 11/11/01 FROM SCHULKER TAKEN BY STRANSKY * * *             |
|                                                                              |
| "On November 11, 2001 at 1045, a rescued sea turtle was Identified as a      |
| Kemp's Ridley. This is the 59th rescue of a live sea turtle at Crystal River |
| Unit 3 (CR-3) in this biennial period. This is Reportable as a 4-Hour Report |
| under 10 CFR 50.72 (b) (2) (xi) as this event is related to the protection   |
| of the environment for which a notification to other government agencies has |
| been or will be made. This is an update to event 37902."                     |
|                                                                              |
| The licensee informed the NRC resident inspector. Notified R2 IRC.           |
+------------------------------------------------------------------------------+
.
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38486       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 11/09/2001|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 01:08[EST]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        11/08/2001|
+------------------------------------------------+EVENT TIME:        20:57[EST]|
| NRC NOTIFIED BY:  RONALD GREEN                 |LAST UPDATE DATE:  11/12/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |R1 IRC TEAM MANAGER  R1      |
|10 CFR SECTION:                                 |                             |
|AESF 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/R        N       0        Startup          |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP DURING UNIT STARTUP                                   |
|                                                                              |
| "During a reactor start up, BVPS Unit One Reactor tripped prior to reaching  |
| criticality.  The apparent cause of the trip is a blown control power fuse   |
| on Intermediate Range Nuclear Instrument channel N36.  The blown fuse caused |
| actuation of the Intermediate Range high level trip.  All control rods fully |
| inserted.  All equipment properly functioned.  Unit One is presently in mode |
| three at normal temperature and pressure.  Decay heat removal is through the |
| steam bypass valves to the main condenser as it was throughout the event.  A |
| main feed pump is supplying feedwater through the bypass feedwater           |
| regulating valves."                                                          |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
|                                                                              |
| * * * UPDATE 1237 EST ON 11/12/01 FROM MIKE KOGELSCHATZ TO S. SANDIN * * *   |
|                                                                              |
| The licensee is retracting this report based on the following:               |
|                                                                              |
| "Beaver Valley Power Station is retracting its previous 10 CFR               |
| 50.72(b)(3)(iv) notification from 11/9/2001, EN #38486. The automatic        |
| Reactor Protection System (RPS) actuation that occurred on 11/8/2001 was     |
| initiated by a blown fuse in the N36 intermediate range nuclear flux         |
| instrument causing a high intermediate range reactor trip signal to be       |
| generated. The blown fuse was not in response to actual plant conditions and |
| is not a parameter satisfying the requirements for initiation of the safety  |
| function of the system. Hence this RPS actuation was not a valid actuation   |
| since there was no actual high flux condition within the reactor. Therefore, |
| this event is not reportable pursuant to 10 CFR 50.72(b)(3)(iv)(A) since the |
| automatic trip was not generated by a valid actuation.                       |
|                                                                              |
| "This event is reportable pursuant to 10 CFR 50.73(a)(2)(iv)(A) since this   |
| event involved an automatic actuation of the Reactor Protection System which |
| was not part of a pre-planned sequence, did not occur with the RPS properly  |
| removed from service, and did not occur after the safety function of         |
| dropping the control rods had already been completed.                        |
|                                                                              |
| "However, pursuant to 10 CFR 50.73(a)(1), this event is being reported via   |
| this telephone notification instead of submitting a written LER since the    |
| automatic reactor trip occurred with the reactor subcritical, and was not    |
| generated by a valid actuation. On 11/8/2001, all control rods inserted due  |
| to the blown fuse initiating a reactor trip on a one out of two high         |
| intermediate range high power. All required safety systems operated as       |
| designed and the plant was stabilized in Mode 3."                            |
|                                                                              |
| The licensee will inform the NRC Resident Inspector.  Notified R1 IRC.       |
|                                                                              |
| HOO Note:  See EN #38496.                                                    |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   38487       |
+------------------------------------------------------------------------------+
                         
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  NC DIV OF RADIATION PROTECTION       |NOTIFICATION DATE: 11/09/2001|
|LICENSEE:  GUILFORD MILLS                       |NOTIFICATION TIME: 08:27[EST]|
|    CITY:  GREENSBORO               REGION:  2  |EVENT DATE:        11/08/2001|
|  COUNTY:                            STATE:  NC |EVENT TIME:        14:00[EST]|
|LICENSE#:  041-1139-0G           AGREEMENT:  Y  |LAST UPDATE DATE:  11/09/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |R2 IRC TEAM MANAGER  R2      |
|                                                |BRIAN SMITH          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  SPEIGHT                      |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| STATE OF NC REPORTED THAT ONE OF THEIR LICENSEES MISPLACED/LOST A BETA   
   |
| THICKNESS GAUGE                                                              |
|                                                                              |
| The Guilford Mills textile plant is in the process of being decommissioned   |
| and disposing of 4 gauges when it was discovered that one gauge could not be |
| located.  The gauge that is missing is a Mahlo America model                 |
| FMIR-7AK-6271-12-1400 beta thickness gauge.  It contained 100 millicuries of |
| Krypton-85 source serial # 1603BX and was last inventoried in 1997.   The    |
| licensee is continuing to look for the device.                               |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38488       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK               REGION:  1  |NOTIFICATION DATE: 11/09/2001|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 12:31[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        11/09/2001|
+------------------------------------------------+EVENT TIME:        11:00[EST]|
| NRC NOTIFIED BY:  ERV PARKER                   |LAST UPDATE DATE:  11/09/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |R1 IRC TEAM MANAGER  R1      |
|10 CFR SECTION:                                 |                             |
|AESF 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     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SAFETY SYSTEM ACTUATION DURING TESTING OF THE EHC SYSTEM                     |
|                                                                              |
| "At 1859 on October 30, 2001, during performance of Electro-Hydraulic        |
| Control (EHC) testing, a Nuclear Steam Supply Shutoff System isolation       |
| actuation occurred.  The plant was in operational condition 4, mode switch   |
| locked in refuel, all control rods inserted and reactor pressure vessel      |
| level and temperature were within the appropriate band, at the time of the   |
| event.                                                                       |
|                                                                              |
| "The cause of the actuation was due to the impact of test setup conditions   |
| established to perform EHC testing being performed concurrent with reactor   |
| vessel cold hydrostatic testing, which effectively un-bypassed a low vacuum  |
| trip input signal.                                                           |
|                                                                              |
| "The NRC Resident is fully aware of the event.                               |
|                                                                              |
| "This notification is being made in accordance with                          |
| 10CFR50.72(b)(3)(iv)(A).                                                     |
|                                                                              |
| "PSE&G Nuclear is continuing to evaluate this condition to determine other   |
| possible causes and corrective actions."                                     |
|                                                                              |
| This event was identified as reportable as part of the licensee's corrective |
| action program review.  The licensee will also inform the Lower Alloways     |
| Creek Township (LAC).                                                        |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38489       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 11/09/2001|
|    UNIT:  [] [2] []                 STATE:  NY |NOTIFICATION TIME: 17:05[EST]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        11/09/2001|
+------------------------------------------------+EVENT TIME:        11:13[EST]|
| NRC NOTIFIED BY:  BOISMENU                     |LAST UPDATE DATE:  11/09/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |R1 IRC TEAM MANAGER  R1      |
|10 CFR SECTION:                                 |                             |
|HFIT 26.73               FITNESS FOR DUTY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| FITNESS FOR DUTY REPORT                                                      |
|                                                                              |
| An employee acting in a supervisory position failed a random alcohol test.   |
| Access was immediately revoked and EAP assistance was sought by the          |
| individual.  A supervisor will review work performed by the individual for   |
| impact on quality and safety.                                                |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38490       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER                   REGION:  4  |NOTIFICATION DATE: 11/09/2001|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 21:28[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        11/09/2001|
+------------------------------------------------+EVENT TIME:        15:34[CST]|
| NRC NOTIFIED BY:  WILLIAM GREEN                |LAST UPDATE DATE:  11/09/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |LINDA SMITH          R4      |
|10 CFR SECTION:                                 |                             |
|ADEG 50.72(b)(3)(ii)(A)  DEGRADED CONDITION     |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| CONTAINMENT PATHWAY DECLARED INOPERABLE FOLLOWING LLRT TESTING              
|
|                                                                              |
| "This condition is being reported in accordance with the requirements of     |
| 10CFR50.72(b)(3)(ii) as an event or condition that results in: (A) The       |
| condition of the nuclear power plant. including its principal safety         |
| barriers, being seriously degraded.                                          |
|                                                                              |
| "During local leak rate testing (LLRT) being performed on the 'B' reactor    |
| feed line to the reactor, both primary containment boundary check valves     |
| (RF-CV-13CV and RF-CV-14CV) failed LLRT.  Efforts to quantify the leak rate  |
| were unsuccessful. The maximum leakage indicated on the test equipment used  |
| is 424 Standard Cubic Feet Hour (SCFH).  The allowable leakage (La) for      |
| Primary Containment is 317.41 SCFH.  Subsequently this primary containment   |
| pathway was declared inoperable.  CNS is in MODE 5 for refueling with vessel |
| level >23 feet above the flange and the spent fuel pool gates removed.  No   |
| fuel movements or operations with the potential to drain the reactor vessel  |
| were in progress.  Primary containment is not required per CNS Technical     |
| Specifications in this mode of operation."                                   |
|                                                                              |
| The licensee informed the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38491       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OYSTER CREEK             REGION:  1  |NOTIFICATION DATE: 11/11/2001|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 10:44[EST]|
|   RXTYPE: [1] GE-2                             |EVENT DATE:        11/11/2001|
+------------------------------------------------+EVENT TIME:        09:36[EST]|
| NRC NOTIFIED BY:  FRANK CIGANIK                |LAST UPDATE DATE:  11/11/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |MOHAMED SHANBAKY     R1      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(2)(i)      PLANT S/D REQD BY TS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |88       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO LOSS OF SUBSTATION      
   |
|                                                                              |
| The licensee reported that at 0610 EST on 11/11/2001 that the 1B2 Unit       |
| Substation was lost on a ground fault on the 4160 side.  The actual cause of |
| the ground fault is unknown and is being investigated.  The licensee has     |
| entered multiple LCOs due to loss of other vital equipment and the most      |
| limiting is due to the inoperability of containment isolation valves, which  |
| is a requirement to be in Cold Shutdown in 24 hours.  The licensee expects   |
| the plant to shutdown completely within the 24 hour window.                  |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38492       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA              REGION:  1  |NOTIFICATION DATE: 11/11/2001|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 22:23[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        11/11/2001|
+------------------------------------------------+EVENT TIME:        17:45[EST]|
| NRC NOTIFIED BY:  GORDON ROBINSON              |LAST UPDATE DATE:  11/11/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |R1 IRC TEAM MANAGER  R1      |
|10 CFR SECTION:                                 |                             |
|AINA 50.72(b)(3)(v)(A)   POT UNABLE TO SAFE SD  |                             |
|AIND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| HPCI SYSTEM DECLARED INOPERABLE                                              |
|                                                                              |
| "At 1727 EST, Unit 1 received a 'high level' alarm for the HPCI Turbine      |
| Steam Supply line Drain Pot. Investigation revealed that power was lost to   |
| the solenoid on one of the steam line drain valves causing it to fail        |
| closed. In this configuration, condensate is no longer drained from the HPCI |
| Steam Supply line so there would be a potential for water to enter the       |
| turbine upon a HPCI initiation. Given this concern, the HPCI system was      |
| declared inoperable at 1745 EST when actions were taken to align the system  |
| in a configuration to prevent an automatic initiation (breaker was opened    |
| for the Aux Oil Pump and the Flow Controller was placed to Manual/Minimum).  |
| Because HPCI is a single train ECCS safety system, this event results in the |
| loss of an entire safety function which requires an 8 hour ENS notification  |
| in accordance with 10CFR50.72(b)(3)(v) and the guidance provided under       |
| NUREG-1022, rev. 2.                                                          |
|                                                                              |
| "There are no other ECCS systems presently out of service."                  |
|                                                                              |
| The NRC resident inspector has been informed of this notification by the     |
| licensee.                                                                    |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38493       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OCONEE                   REGION:  2  |NOTIFICATION DATE: 11/12/2001|
|    UNIT:  [] [] [3]                 STATE:  SC |NOTIFICATION TIME: 04:59[EST]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE:        11/12/2001|
+------------------------------------------------+EVENT TIME:        03:35[EST]|
| NRC NOTIFIED BY:  MICHAEL DUNTON               |LAST UPDATE DATE:  11/12/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |CHARLES OGLE         R2      |
|10 CFR SECTION:                                 |                             |
|ADEG 50.72(b)(3)(ii)(A)  DEGRADED CONDITION     |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| INDICATION OF PRESSURE BOUNDARY LEAKAGE DISCOVERED DURING VISUAL
INSPECTION  |
| OF HEAD                                                                      |
|                                                                              |
| The licensee was conducting visual inspection of the reactor vessel control  |
| rod drive mechanism (CRDM) nozzles in response to the NRC Bulletin 2001-01.  |
| They discovered indications of leakage evidenced by minor boric acid buildup |
| around 4 CRDM nozzles.  There is potential for 3 additional nozzles leaking  |
| that will require further inspections.  Additional inspections and repairs   |
| will be conducted in accordance with NRC Bulletin 2001-01.  The plant will   |
| remain at or below Cold Shutdown until repairs are completed.                |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| (Note:  See similar events #38416, 38365, 38169)                             |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38494       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 11/12/2001|
|    UNIT:  [1] [] []                 STATE:  FL |NOTIFICATION TIME: 11:20[EST]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        11/10/2001|
+------------------------------------------------+EVENT TIME:        03:14[EST]|
| NRC NOTIFIED BY:  STEVEN MERRILL               |LAST UPDATE DATE:  11/12/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JAY HENSON           R2      |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Hot Shutdown     |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DETERMINATION MADE THAT A PREVIOUSLY TERMINATED EVENT MET THE CRITERIA
FOR   |
| EMERGENCY PLAN ENTRY                                                         |
|                                                                              |
| "This report is being made due to the determination that a previously        |
| terminated event had met the criteria for emergency plan entry.              |
|                                                                              |
| "At approximately 03:14 on 11/10/01, St. Lucie Unit 1 was operating in Mode  |
| 4. The Shutdown Cooling System had been secured for approximately 15 minutes |
| when a realignment sequence was initiated to place the system back in        |
| service. During the performance of this evolution, thermal relief valve      |
| V3431 lifted and did not immediately reseat. The event was terminated when   |
| the 1B Low Pressure Safety Injection Pump was secured and the relief valve   |
| reseated.                                                                    |
|                                                                              |
| "Initial assessment of the leakage rate, while the relief valve was open,    |
| concluded that the flow rate was less than 10 gpm and therefore did not meet |
| the threshold for Emergency Plan entry. A Condition Report was initiated to  |
| perform a more in depth analysis of the event.                               |
|                                                                              |
| "Subsequent, detailed analysis of the event has determined that the flow     |
| rate from the relief valve did exceed the 10 gpm criteria for Emergency Plan |
| implementation."                                                             |
|                                                                              |
| The licensee notified the NRC Resident Inspector and intends to notify the   |
| State and Local Authorities.                                                 |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38495       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OYSTER CREEK             REGION:  1  |NOTIFICATION DATE: 11/12/2001|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 12:28[EST]|
|   RXTYPE: [1] GE-2                             |EVENT DATE:        11/12/2001|
+------------------------------------------------+EVENT TIME:        10:45[EST]|
| NRC NOTIFIED BY:  CIGANIK                      |LAST UPDATE DATE:  11/12/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |R1 IRC TEAM MANAGER  R1      |
|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          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LARGE FISHKILL REPORTED TO THE STATE OF NEW JERSEY                           |
|                                                                              |
| The New Jersey Department of Environmental Protection was notified of a      |
| large fishkill(approximately several hundred fish) in their discharge canal. |
| Most of the fish were Jack fish, but there were also other species.  The     |
| cause is from the unplanned unit shutdown on 11/11/01.                       |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38496       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 11/12/2001|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 12:37[EST]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        11/08/2001|
+------------------------------------------------+EVENT TIME:        20:57[EST]|
| NRC NOTIFIED BY:  MIKE KOGELSCHATZ             |LAST UPDATE DATE:  11/12/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |R1 IRC TEAM MANAGER  R1      |
|10 CFR SECTION:                                 |                             |
|AINV 50.73(a)(1)         INVALID SPECIF SYSTEM A|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        N       0        Startup          |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INVALID RPS ACTUATION DURING STARTUP DUE TO A BLOWN FUSE                     |
|                                                                              |
| "Beaver Valley Power Station is retracting its previous 10 CFR               |
| 50.72(b)(3)(iv) notification from 11/9/2001, EN# 38486. The automatic        |
| Reactor Protection System (RPS) actuation that occurred on 11/8/2001 was     |
| initiated by a blown fuse in the N36 intermediate range nuclear flux         |
| instrument causing a high intermediate range reactor trip signal to be       |
| generated. The blown fuse was not in response to actual plant conditions and |
| is not a parameter satisfying the requirements for initiation of the safety  |
| function of the system. Hence this RPS actuation was not a valid actuation   |
| since there was no actual high flux condition within the reactor. Therefore, |
| this event is not reportable pursuant to 10 CFR 50.72(b)(3)(iv)(A) since the |
| automatic trip was not generated by a valid actuation.                       |
|                                                                              |
| "This event is reportable pursuant to 10 CFR 50.73(a)(2)(iv)(A) since this   |
| event involved an automatic actuation of the Reactor Protection System which |
| was not part of a pre-planned sequence, did not occur with the RPS properly  |
| removed from service, and did not occur after the safety function of         |
| dropping the control rods had already been completed.                        |
|                                                                              |
| "However, pursuant to 10 CFR 50.73(a)(1), this event is being reported via   |
| this telephone notification instead of submitting a written LER since the    |
| automatic reactor trip occurred with the reactor subcritical, and was not    |
| generated by a valid actuation. On 11/8/2001, all control rods inserted due  |
| to the blown fuse initiating a reactor trip on a one out of two high         |
| intermediate range high power. All required safety systems operated as       |
| designed and the plant was stabilized in Mode 3."                            |
|                                                                              |
|                                                                              |
| The licensee will inform the NRC Resident Inspector.                         |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38497       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE                  REGION:  3  |NOTIFICATION DATE: 11/13/2001|
|    UNIT:  [1] [2] []                STATE:  IL |NOTIFICATION TIME: 02:16[EST]|
|   RXTYPE: [1] GE-5,[2] GE-5                    |EVENT DATE:        11/12/2001|
+------------------------------------------------+EVENT TIME:        21:00[CST]|
| NRC NOTIFIED BY:  HAROLD VINYARD               |LAST UPDATE DATE:  11/13/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BRUCE JORGENSEN      R3      |
|10 CFR SECTION:                                 |                             |
|ACOM 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       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ERDS DISCOVERED INOPERABLE                                                   |
|                                                                              |
| "...This report is being made pursuant to 10 CFR 50.72(b)(3)(xiii) and       |
| Exelon Reportability Manual SAF 1.10.  At 2100 hours on 11/12/01, it was     |
| discovered that the Emergency Response Data System (ERDS) was not            |
| operational.  This system provides a data link between the LaSalle onsite    |
| computer system and the NRC Headquarters Operational Center when activated   |
| during emergency situations.  The ERDS system was restored to an operable    |
| status at 2320 hours on 11/12/01 after resolving a computer system software  |
| issue. The NRC resident inspector has been notified of this event."          |
|                                                                              |
| The discovery was made while conducting training of a new candidate.         |
+------------------------------------------------------------------------------+
.

Page Last Reviewed/Updated Wednesday, March 24, 2021