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
Page Last Reviewed/Updated Wednesday, March 24, 2021