Event Notification Report for July 22, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
07/19/2002 - 07/22/2002
** EVENT NUMBERS **
39063 39064 39065 39071 39074 39075 39076 39077 39078 39079 39080 39081
.
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39063 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: NEW MEXICO RAD CONTROL PROGRAM |NOTIFICATION DATE:
07/16/2002|
|LICENSEE: SPECTRA TEK |NOTIFICATION TIME: 10:51[EDT]|
| CITY: ALBUQUERQUE REGION: 4 |EVENT DATE: 07/10/2002|
| COUNTY: STATE: NM |EVENT TIME: [MDT]|
|LICENSE#: TA172-21 AGREEMENT: Y |LAST UPDATE DATE: 07/17/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LINDA HOWELL R4 |
| |DOUG BROADDUS NMSS |
+------------------------------------------------+CHARLIE PAYNE R2 |
| NRC NOTIFIED BY: FLOYD | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PARTIAL SHIPMENT OF SCANDIUM - 46 LOST IN TRANSIT |
| |
| A FedEx shipment from the Spectra Tek in Albuquerque to Protechnics in |
| Lafayette, LA. of six packages of scandium - 46 at 40 millicuries each |
| arrived at its destination one package short on 7/10/02. They are tracing |
| the shipment and determined it was last scanned on 7/9/02 in Memphis, TN. |
| |
| **** Update at 1152 ET on 07/17/02 by Bill Floyd taken by MacKinnon **** |
| |
| The missing package containing the scandium-46 was found on the FedEx |
| loading dock in Lafayette , LA. The package will be delivered to |
| Protechnics. R4DO (Linda Howell) & NMSS EO (Fred Brown) notified. |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39064 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: TENNESSEE DIV OF RAD HEALTH |NOTIFICATION DATE: 07/16/2002|
|LICENSEE: DURATEK RADWASTE PROCESSING, INC. |NOTIFICATION TIME:
12:05[EDT]|
| CITY: OAK RIDGE REGION: 2 |EVENT DATE: 07/12/2002|
| COUNTY: STATE: TN |EVENT TIME: 08:30[EDT]|
|LICENSE#: R-73008 AGREEMENT: Y |LAST UPDATE DATE: 07/16/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CHARLIE PAYNE R2 |
| |JAMES LINVILLE R1 |
+------------------------------------------------+FRED BROWN NMSS |
| NRC NOTIFIED BY: BILLY FREEMAN | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT INVOLVING EQUIPMENT FAILURE OF SHIPPING
CONTAINER |
| |
| "Event Report ID No.: TN-02-094 |
| |
| "License No.: R-73008 |
| |
| "Licensee: Duratek Radwaste Processing, Inc. |
| |
| "Event date and time: July 12, 2002, 0830EDT |
| |
| "Event location: Oak Ridge, Tennessee |
| |
| "Event type: Equipment failure |
| |
| "Notifications: USNRC Region II |
| |
| "Event description: Duratek Radwaste Processing, Inc., a Tennessee |
| licensee, called the Knoxville Field Office Manager to report that a sealand |
| container of metals from Calvert Cliffs Nuclear Power Plant was received at |
| the Duratek facility on July 12, 2002. During performance of the receipt |
| survey/inspection, metal from the interior was observed protruding |
| approximately 1/2" from a penetration in the side of the container. No |
| detectable contamination was found on the accessible item or on the adjacent |
| sealed surfaces. The penetration in the container wall was covered to permit |
| undisturbed storage pending further investigation. |
| |
| "Media attention: None" |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39065 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: NC DIV OF RADIATION PROTECTION |NOTIFICATION DATE: 07/16/2002|
|LICENSEE: AMERISTEEL CORPORATION |NOTIFICATION TIME: 14:08[EDT]|
| CITY: CHARLOTTE REGION: 2 |EVENT DATE: 07/11/2002|
| COUNTY: STATE: NC |EVENT TIME: [EDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 07/16/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CHARLIE PAYNE R2 |
| |FRED BROWN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: GRANT T. MILLS | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT INVOLVING Cs-137 SOURCE FOUND IN SCRAP STEEL
|
| |
| "SUBJECT: North Carolina Incident No. 02-21 |
| |
| "On July 11, 2002 the North Carolina Radiation Protection Section was |
| notified by AmeriSteel Corp., Charlotte Steel Mill Division that they had |
| discovered a radioactive source in their scrap stream. The source has been |
| isolated and secured by AmeriSteel personnel. Exposure rates of 120 |
| microR/hr @ 3" have been reported by AmeriSteel personnel. Using an |
| Exploranium GR-130 AmeriSteel personnel have identified the source as |
| Cesium-137. The North Carolina Radiation Protection Section is continuing to |
| gather information and work with the facility to provide appropriate |
| action." |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39071 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 07/19/2002|
| UNIT: [1] [2] [] STATE: VA |NOTIFICATION TIME: 06:30[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 07/18/2002|
+------------------------------------------------+EVENT TIME: 22:55[EDT]|
| NRC NOTIFIED BY: R. DILLARD |LAST UPDATE DATE: 07/19/2002|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CHARLIE PAYNE R2 |
|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
+------------------------------------------------------------------------------+
| UNIT 2 CORE COOLING BAR ON THE SAFETY PARAMETER DISPLAY SYSTEM (SPDS)
WAS |
| NOTED TO BE INOPERABLE. |
| |
| |
| At 2255 hours on 07/18/02, the Unit 2 Core Cooling Bar on the SPDS was noted |
| to be inoperable. A reboot the system was attempted, but the SPDS |
| indication did not change. Further checks showed that multiple computer |
| points (46 total) had been turned off (off scan), which made the data |
| points invalid. These points would not have been immediately available if |
| needed. The points were all placed on scan, and the Unit 2 Core Cooling |
| SPDS Bar returned to its normal condition. The remaining SPDS functions |
| were functional during this time, only the Unit 2 Core Cooling SPDS Bar |
| was affected. |
| |
| |
| The NRC Resident Inspector will be notified of this event by the licensee. |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39074 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 07/19/2002|
| UNIT: [2] [] [] STATE: NY |NOTIFICATION TIME: 15:15[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 07/19/2002|
+------------------------------------------------+EVENT TIME: 14:13[EDT]|
| NRC NOTIFIED BY: DENNIS CORNAX |LAST UPDATE DATE: 07/19/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JAMES LINVILLE R1 |
|10 CFR SECTION: |CHRIS GRIMES NRR |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION |TIM MCGINTY IRO |
| |BETH HAYDEN PA |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION AT IP2 OF ONSITE FATALITY |
| |
| The licensee reported an onsite fatality occurred that prompted the need to |
| notify the New York State Public Service Commission and the local Fire |
| Department which responded to the site. Specifically, a contract worker was |
| electrocuted while trimming trees onsite, behind the emergency diesel |
| generator building, adjacent to a 138 KV feeder. |
| |
| The event resulted in the protective relaying tripping the feeder and a loss |
| of offsite power (LOOP) resulted. The plant remained online at 100% power. |
| The emergency diesel generators were started and powered two of the |
| safeguard buses. |
| |
| The NRC Resident Inspector was notified. |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 39075 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: ELI LILLY & COMPANY |NOTIFICATION DATE: 07/19/2002|
|LICENSEE: ELI LILLY & COMPANY |NOTIFICATION TIME: 15:40[EDT]|
| CITY: INDIANAPOLIS REGION: 3 |EVENT DATE: 06/20/2002|
| COUNTY: STATE: IN |EVENT TIME: [CST]|
|LICENSE#: 13-0133-02 AGREEMENT: N |LAST UPDATE DATE: 07/19/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MONTE PHILLIPS R3 |
| |DOUG BROADDUS NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: STAN HAMPTON | |
| HQ OPS OFFICER: RICH LAURA | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|BLO1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOST/MISSING NUCLEAR MATERIAL AT A RESEARCH FACILITY |
| |
| During an annual audit, Eli Lilly & Company became aware of lost nuclear |
| material involving 9.4 milli-curies of Carbon-14. The last accounting of |
| the material was in December, 1999. The material is used for basic |
| metabolic research purposes. The licensee suspects that the material may |
| have been disposed of as radwaste. The licensee investigation will |
| continue. |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39076 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 07/19/2002|
| UNIT: [1] [2] [3] STATE: AZ |NOTIFICATION TIME: 16:16[EDT]|
| RXTYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 07/19/2002|
+------------------------------------------------+EVENT TIME: [MST]|
| NRC NOTIFIED BY: DAN MARKS |LAST UPDATE DATE: 07/19/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |LINDA HOWELL R4 |
|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 99 Power Operation |99 Power Operation |
|2 N Y 98 Power Operation |98 Power Operation |
|3 N Y 99 Power Operation |99 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF COMMUNICATIONS CAPABILITY AT THE JOINT EMERGENCY NEWS CENTER
|
| |
| "The following event description is based on information currently |
| available. It through subsequent reviews of this event, additional |
| information is identified that is pertinent to this event or alters the |
| information being provided at this time, a follow-up notification will be |
| made via the ENS or under the reporting requirements of 1OCFR5O.73. |
| |
| "On July 19, 2002 at approximately 10:30 AM Mountain Standard Time Palo |
| Verde Emergency Planning personnel were notified that installed |
| communications to and from the Joint Emergency News Center (JENC) had been |
| totally disabled when an underground cable was cut. The affected cable and |
| the JENC are located in Phoenix, AZ. |
| |
| "This loss of communications capability does not affect the assessment or |
| response capability of Palo Verde, state or county personnel in the event of |
| an emergency The JENC and its communications capability are an integral part |
| of media notification and information dissemination as described in the Palo |
| Verde Emergency Plan. |
| |
| "As a compensatory measure, the state has access to cellular phones for use |
| in the JENC. The state will deploy those phones in the event of an actual |
| emergency. In addition, most media personnel normally carry their own |
| cellular phones The phone company has assigned their highest priority to |
| this repair. The latest estimate for repair is approximately one-half day. |
| |
| "The cable was cut yesterday at approximately 3:00 PM on Thursday, July 18, |
| 2002 but the state was not informed until approximately 09:00 AM today and |
| then the state notified Palo Verde at approximately 10:30 AM." |
| |
| The NRC Resident Inspector was notified. |
| |
| *****UPDATE ON 7/19/02 AT 19:22 FROM MARKS TO LAURA***** |
| |
| "The state has notified Palo Verde that JENC communications were restored at |
| 13:28 MST on July 19, 2002." |
| |
| Notified R4DO (L. Howell). |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39077 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 07/19/2002|
| UNIT: [1] [] [] STATE: MO |NOTIFICATION TIME: 17:33[EDT]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 07/19/2002|
+------------------------------------------------+EVENT TIME: 09:45[CDT]|
| NRC NOTIFIED BY: GARY OLMSTEAD |LAST UPDATE DATE: 07/19/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |LINDA HOWELL R4 |
|10 CFR SECTION: | |
|AUNA 50.72(b)(3)(ii)(B) UNANALYZED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| APPENDIX "R" BREAKER COORDINATION AND SEPARATION ISSUES AT CALLAWAY
|
| |
| "On July 2,2002, with Callaway Plant in Mode 1 at 100% power, an Operability |
| Determination was completed that revealed the potential for Safety Related |
| components and electrical load centers to experience a common cause failure |
| if a fire were to occur in a specific location. If the postulated fire were |
| to occur in 1974' Auxiliary Building Fire Area A-1, safety related load |
| centers NG01A and NG02A (opposite trains) could experience a fire induced |
| ground fault condition due to cable damage on downstream loads. This ground |
| fault condition could cause the loss of either or both NG01A and NG02A. |
| NG01A and NG02A supply post fire safe shutdown equipment such as the "A" and |
| "B" Residual Heat Removal (RHR) pump room coolers. Discussions with Wolf |
| Creek on July 19, 2002 in conjunction with the ongoing evaluation concluded |
| this scenario could impact post fire safe shutdown equipment. |
| |
| "In addition, it has been identified that cables in Fire Area A-1 for the |
| "A" and "B" RHR pump room coolers, which are post fire safe shutdown |
| equipment, have less than 20 feet of horizontal separation and do not meet |
| the separation requirements of Appendix R lII.G.2, as committed to. |
| |
| "Based on the guidance provided in NUREG 1022, Revision 2, this situation |
| meets the criterion of 10 CFR 50.72(b)(3)(ii) for an 8-hour notification. |
| |
| "The following compensatory actions have been taken: |
| - An hourly fire watch was established for the affected area on 7/2/02 as |
| the evaluations were completed. |
| - Circuit Breakers associated with Essential Service Water Sump Heaters have |
| been isolated, pending completion of a design change to address electrical |
| coordination consistent with the FSAR. |
| - An Operations Night Order detailing actions to be taken to restore NG01A |
| and or NG02A if a fire were to occur that affected these load centers. |
| Actions include measures to isolate faulted circuits. |
| - Permanent revisions to Fire Area Pre-plans are under evaluation to |
| incorporate the guidance of the Operations Night Order. |
| |
| "The licensee is continuing its review to determine the extent of Cable |
| Separation/Breaker Coordination issues that may lead to similar |
| consequences." |
| |
| The NRC Senior Resident Inspector has been notified. |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39078 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 07/19/2002|
| UNIT: [1] [] [] STATE: KS |NOTIFICATION TIME: 18:09[EDT]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 07/19/2002|
+------------------------------------------------+EVENT TIME: 09:45[CDT]|
| NRC NOTIFIED BY: Steven Henry |LAST UPDATE DATE: 07/19/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |LINDA HOWELL R4 |
|10 CFR SECTION: | |
|AUNA 50.72(b)(3)(ii)(B) UNANALYZED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| APPENDIX R CABLE SEPARATION AND BREAKER COORDINATION ISSUES AT WOLF
CREEK |
| |
| "On July 19, 2002 at approximately 0945 CDT, based on discussions with |
| Callaway, conditions were discovered where a postulated fire could lead to |
| the loss of motor control centers that power post fire safe shutdown |
| equipment in both trains. Wolf Creek is in Mode 1, at 100% power. |
| |
| "A postulated fire in the Auxiliary Building 1974' Fire Area A-1 could cause |
| loss of motor control centers NG01A ("A" train) and NG02A ("B" train). NG01A |
| and NG02A supply post fire safe shutdown equipment such as "A" and "B" train |
| pump room coolers and miscellaneous valves. |
| |
| "10 CFR 50 Appendix R requires that one train of systems necessary to |
| achieve and maintain post fire safe shutdown will be available. Conditions |
| have been identified where there is mis-coordination of the ground fault |
| protection on feeder breakers. This could cause the entire MCC to be lost in |
| the case of a ground fault. Feeder breakers on both MCCs have been |
| identified as having ground fault protection mis-coordination. The cables |
| for the associated loads have less than 20 feet of horizontal separation |
| causing the above identified MCCs to be potentially lost due to a fire in |
| Fire Area A-1. This does not meet the requirements of 10 CFR 50 Appendix |
| R.lll.G. |
| |
| "In addition, it has been identified that post fire safe shutdown cables in |
| Fire Area A-I for the "A" and "B" RHR pump room coolers have less than 20 |
| feet of horizontal separation and do not meet the separation requirements of |
| 10 CFR 50 |
| Appendix R.lll.G. |
| |
| "Based on the guidance provided in NUREG 1022 Revision 2, this situation |
| meets the criterion of I0 CFR 50.72(b)(3)(ii)(B) for an 8-hour ENS |
| notification, as it relates to being in an unanalyzed condition. |
| |
| "The licensee has implemented a 1-hour fire watch and is developing |
| compensatory measures. |
| |
| "The licensee is continuing its review to determine if there are any other |
| cable separation/breaker mis-coordination issues that may lead to similar |
| consequences." |
| |
| The NRC Resident Inspector has been informed. |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39079 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 07/20/2002|
| UNIT: [3] [] [] STATE: FL |NOTIFICATION TIME: 22:15[EDT]|
| RXTYPE: [3] B&W-L-LP |EVENT DATE: 07/20/2002|
+------------------------------------------------+EVENT TIME: 16:45[EDT]|
| NRC NOTIFIED BY: DAN DEBOER |LAST UPDATE DATE: 07/20/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CHARLIE PAYNE R2 |
|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
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC EDG START DUE TO LOSS OF THE OFFSITE POWER TRANSFORMER
|
| |
| "On July 20, 2002 at 1645, the "A" Emergency Diesel Generator automatically |
| actuated and powered the "A" 4160V Engineered Safeguards bus. This event is |
| Reportable as an 8-Hour Notification per 10 CFR 50.72 (b) (3) (iv) (B) (8). |
| The actuation occurred due to the loss of the Off-Site Power Transformer. |
| The cause of the transformer loss has been identified to be a faulted cable |
| between the Off-Site Power Transformer and the "A" 4160 V Engineered |
| Safeguards bus." |
| |
| The licensee reported the unit was entered into a 72 hour LCO action |
| statement per TS 3..8.1.A. Corrective maintenance has been started to |
| replace the cable within the specified TS AOT. The licensee reconfigured |
| the electrical line-up and was able to secure the EDG. |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39080 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 07/21/2002|
| UNIT: [] [] [3] STATE: IL |NOTIFICATION TIME: 22:48[EDT]|
| RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 07/21/2002|
+------------------------------------------------+EVENT TIME: 20:33[CDT]|
| NRC NOTIFIED BY: STAN VICK |LAST UPDATE DATE: 07/21/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MONTE PHILLIPS R3 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 A/R Y 100 Power Operation |0 Hot Shutdown |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR SCRAM CAUSED BY TURBINE TRIP |
| |
| The licensee reported that an automatic reactor scram occurred due to a |
| turbine trip. The cause of the turbine trip is under investigation. Group |
| 2 and 3 isolations occurred as expected during post scram conditions. The |
| lowest reactor vessel water level was 0 inches. All systems functioned as |
| designed. |
| |
| The NRC Resident Inspector was notified. |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39081 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 07/22/2002|
| UNIT: [] [2] [] STATE: MI |NOTIFICATION TIME: 02:33[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/22/2002|
+------------------------------------------------+EVENT TIME: 00:45[EDT]|
| NRC NOTIFIED BY: JOHNSON |LAST UPDATE DATE: 07/22/2002|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MONTE PHILLIPS R3 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 100 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR AUTOMATICALLY TRIPPED FROM 100% POWER ON REACTOR
TRIP/TURBINE TRIP |
| |
| The reactor trip/turbine trip from 100% power was caused by a loss of main |
| turbine condenser vacuum that occurred while flushing the condenser |
| waterboxes. The cause is unknown and being investigated at this time. All |
| control rods fully inserted, no ECCS actuated and all emergency and |
| non-emergency systems functioned as designed. The main steam stop valves |
| were manually closed to arrest RCS cooldown. RCS temperature was |
| stabilized using the atmospheric relief valves. |
| |
| The NRC Resident Inspector was notified, |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021