United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated With Events > Event Notification Reports > 2002

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,                                     |
+------------------------------------------------------------------------------+
.