United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated With Events > Event Notification Reports > 1999

Event Notification Report for June 24, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/23/1999 - 06/24/1999

                              ** EVENT NUMBERS **

35000  35849  35852  35853  35854  35855  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35000       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DAVIS BESSE              REGION:  3  |NOTIFICATION DATE: 11/05/1998|
|    UNIT:  [1] [] []                 STATE:  OH |NOTIFICATION TIME: 11:57[EST]|
|   RXTYPE: [1] B&W-R-LP                         |EVENT DATE:        11/05/1998|
+------------------------------------------------+EVENT TIME:        11:07[EST]|
| NRC NOTIFIED BY:  JOHN BALDWIN                 |LAST UPDATE DATE:  06/23/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |RONALD GARDNER       R3      |
|10 CFR SECTION:                                 |                             |
|AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCOVERY OF DESIGN OVERSTRESS CONDITION IN PRESSURIZER NOZZLES              |
|                                                                              |
| THE LICENSEE HAS DETERMINED  (VIA ENGINEERING CALCULATION C-ME-064.085.01)   |
| THAT A DESIGN OVERSTRESS CONDITION EXISTED IN THE PRESSURIZER SAFETY VALVE   |
| NOZZLES DURING THE PERIOD FROM 7/22/87 (INSTALLATION OF PLANT MODIFICATION   |
| 87-1001, WHICH INCREASED RUPTURE DISC BURST PRESSURE) UNTIL 10/17/98 (PLANT  |
| MODIFICATION TM 98-0036, WHICH REMOVED THE RUPTURE DISCS).  BASED UPON THE   |
| OVERSTRESS CONDITION, THESE PRESSURIZER NOZZLES WERE NOT FUNCTIONAL DURING   |
| THAT TIME. HOWEVER, WITH THE RUPTURE DISCS REMOVED, THE LICENSEE HAS         |
| DETERMINED THAT STRESS LEVELS REMAIN WITHIN USAR DEFINED ALLOWABLE VALUES    |
| FOR ALL LOAD COMBINATIONS.                                                   |
|                                                                              |
| THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED.                                |
|                                                                              |
| *** UPDATE ON 6/23/99 @ 1326 BY MYERS TO GOULD ***       RETRACTION          |
|                                                                              |
| UPON FURTHER ANALYSIS OF THIS EVENT, IT HAS BEEN DETERMINED THAT NO          |
| REPORTABLE CONDITION EXISTS.  USING THE ACTUAL STEAM RELIEF CAPACITY OF THE  |
| PRESSURIZER SAFETY VALVES VERSUS THE RATED STEAM RELIEF CAPACITY, BOTH       |
| RUPTURE DISKS ON THE OUTLET PIPING TEE OF EACH SAFETY VALVE WOULD HAVE BURST |
| FOR ALL EXPECTED SAFETY VALVE LIFTS.  WITH BOTH RUPTURE DISKS BURST, THE     |
| POTENTIAL TO INDUCE EXCESSIVE ECCENTRIC LOADS ON THE VALVES OR PIPING IS     |
| ELIMINATED.  THEREFORE THEY ARE RETRACTING THIS EVENT.                       |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.   THE REG 3 RDO (JORDAN) WAS NOTIFIED.  |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35849       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FARLEY                   REGION:  2  |NOTIFICATION DATE: 06/21/1999|
|    UNIT:  [] [2] []                 STATE:  AL |NOTIFICATION TIME: 18:53[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        06/21/1999|
+------------------------------------------------+EVENT TIME:        16:57[CDT]|
| NRC NOTIFIED BY:  BOWEN                        |LAST UPDATE DATE:  06/23/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CAUDLE JULIAN        R2      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| THE PLANT ENTERED TS REQUIRED SHUT DOWN DUE TO LOSS OF TWO STEAM FLOW        |
| CHANNELS ON THE "A" STEAM GENERATOR.                                         |
|                                                                              |
| PRIOR TO THIS EVENT THERE WAS A BROKEN SENSING LINE ON THE  "B" STEAM        |
| GENERATOR STEAM FLOW CHANNEL WHICH REQUIRED PUTTING THE CHANNEL 3 STEAM      |
| FLOWS ON ALL THREE STEAM GENERATORS IN TEST.   TODAY @ 1657 CHANNEL 4 ON THE |
| "A" STEAM GENERATOR FAILED.  THERE ARE TWO STEAM FLOW CHANNELS PER STEAM     |
| GENERATOR AND TECHNICAL SPECIFICATIONS REQUIRE ONE OF THE TWO FLOW CHANNELS  |
| TO BE AVAILABLE.  SINCE  CHANNELS 3 AND 4 ON THE "A" STEAM GENERATOR ARE NOT |
| AVAILABLE, THE PLANT ENTERED TS LCO 3.0.3 WHICH GIVES THEM 7 HRS. TO BE IN   |
| HOT STANDBY, 6 HOURS TO HOT SHUTDOWN AND THE FOLLOWING 24 HOURS TO COLD      |
| SHUTDOWN.  THE FEED PUMP SPEED CONTROL AND THE "A" STEAM GENERATOR FLOW      |
| CONTROL VALVE WERE PLACED IN MANUAL AND LEVELS WERE STABILIZED.  THEY CAN    |
| EXIT THE LCO ACTION STATEMENT IF THEY  TAKE CHANNEL 3 OUT OF TEST ON "A"     |
| STEAM GENERATOR AND RETURN IT TO SERVICE.                                    |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE INFORMED.                                     |
|                                                                              |
| *** UPDATE ON 6/21/99 @ 2017 BY BOWEN TO GOULD ***                           |
|                                                                              |
| THEY TOOK THE CHANNEL 3 STEAM FLOW OUT OF TEST AND RETURNED IT TO SERVICE AT |
| 1807 AND EXITED THE LCO ACTION STATEMENT.                                    |
|                                                                              |
| THE RESIDENT WILL BE NOTIFIED.  REG2 RDO (JULIAN)                            |
|                                                                              |
|                                                                              |
| *** UPDATE ON 6/23/99 @ 1834 BY HUNTER TO GOULD ***   RETRACTION             |
|                                                                              |
| SUBSEQUENT EVALUATION HAS DETERMINED THE FAILED COMPONENT HAD NO AFFECT ON   |
| THE PROTECTION FUNCTIONS PROVIDED BY THE STEAM FLOW CHANNELS.  THE FAILURE   |
| AFFECTED THE MAIN CONTROL BOARD INDICATION AND FEEDWATER CONTROL ONLY.       |
| THEREFORE, THIS EVENT IS BEING RETRACTED.                                    |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED.  THE REG 2 RDO (BELISLE) WAS        |
| NOTIFIED.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35852       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK                 REGION:  1  |NOTIFICATION DATE: 06/23/1999|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 06:18[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        06/23/1999|
+------------------------------------------------+EVENT TIME:        04:07[EDT]|
| NRC NOTIFIED BY:  TOM DOUGHERTY                |LAST UPDATE DATE:  06/23/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GLENN MEYER          R1      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(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 FAILED DURING A START TEST                                              |
|                                                                              |
| The High Pressure Coolant Injection (HPCI) system failed to start during     |
| surveillance testing.  At the time of the  failure, HPCI was inoperable for  |
| planned maintenance on the governor controller for the turbine control       |
| valve.  The nature of the failure was the turbine control valve did not open |
| in response to an initiation signal.  The cause of this failure is under     |
| investigation, it is unknown at this time if the failure was due to the      |
| maintenance or existed prior to the maintenance.                             |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35853       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: TURKEY POINT             REGION:  2  |NOTIFICATION DATE: 06/23/1999|
|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 12:25[EDT]|
|   RXTYPE: [3] W-3-LP,[4] W-3-LP                |EVENT DATE:        06/23/1999|
+------------------------------------------------+EVENT TIME:        11:38[EDT]|
| NRC NOTIFIED BY:  FLYNN                        |LAST UPDATE DATE:  06/23/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |AL BELISLE           R2      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     M/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE REACTOR WAS MANUALLY TRIPPED AFTER FOUR RODS FELL INTO THE CORE.         |
|                                                                              |
| SHUTDOWN BANK "B" GROUP 1 CONTROL RODS (4 RODS) FELL INTO THE CORE WITH THE  |
| CAUSE BEING UNKNOWN.  THE REACTOR WAS MANUALLY TRIPPED AND ALL RODS FULLY    |
| INSERTED AND NO INJECTION OCCURRED.  THEY DID HAVE TWO SECONDARY SIDE RELIEF |
| VALVES TO LIFT AND RESEAT ON THE FEEDWATER HEATERS.  THE CAUSE OF THIS       |
| INCIDENT IS BEING INVESTIGATED BY I&C TECHNICIANS.  THEN UNIT IS BEING       |
| MAINTAINED IN MODE 3 AND NO ABNORMAL CONDITIONS WERE NOTED.                  |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35854       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 06/23/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 19:37[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        06/23/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        16:00[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  06/23/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |MIKE JORDAN          R3      |
|  DOCKET:  0707002                              |ROBERT PIERSON       NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  CRABTREE                     |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 4 HOUR 91-01 BULLETIN RESPONSE                                               |
|                                                                              |
| PLANT SHIFT SUPERINTENDENTS OFFICE WAS NOTIFIED BY THE NUCLEAR CRITICALITY   |
| SAFETY(NCS) STAFF THAT A NUCLEAR CRITICALITY SAFETY APPROVAL(NCSA) WAS NOT   |
| BEING MAINTAINED IN THE X-744H STORAGE WAREHOUSE.  NCSA-PLANT048 COVERS      |
| CONTAMINATED METALS.  VALVES AND THE OTHER CASCADE EQUIPMENT WERE BEING      |
| STORED WITH THE UNDERSTANDING THAT EACH PIECE OF EQUIPMENT HAD LESS THAN 15  |
| GRAMS U-235, BECAUSE THE DESCRIPTION OF THE OPERATION WHICH  STATES  " IN    |
| THE CASE OF CONTAMINATED EQUIPMENT SENT TO PORTSMOUTH FROM PADUCAH, OR OAK   |
| RIDGE OR ANY OTHER FACILITY, NON- DESTRUCTIVE ANALYSIS INFORMATION VERIFYING |
| THAT THERE IS LESS THAN 15GM U-235 IS REQUIRED PRIOR TO ACCEPTANCE."  THUS   |
| THE VALVES WERE HANDLED UTILIZING 15 GRAMS U-235 PER PIECE FOR TRANSPORT AND |
| BATCHING CONSIDERATIONS.                                                     |
|                                                                              |
| ALL VALVES IN QUESTION HAD BEEN IN STORAGE FOR AN EXTENDED PERIOD OF         |
| TIME(YEARS), AND IT WAS ASSUMED THAT THE EQUIPMENT STORED IN X-744H MET THE  |
| ACCEPTANCE REQUIREMENTS.  THE VALVES WERE ANALYZED USING NON-DESTRUCTIVE     |
| ANALYSIS MEASUREMENTS TO VERIFY THEY MET THE ACCEPTANCE CRITERIA FOR         |
| DECONTAMINATION IN THE DRY ICE BLASTER(REF. NCSA-PLANT081).  MEASUREMENTS    |
| IDENTIFIED HIGHER U-235 ENRICHMENT AND MASS THAN WAS PREVIOUSLY IDENTIFIED   |
| WITH AVAILABLE HISTORICAL DATA.  BY THE TIME THE DATA HAD BEEN INTERPRETED,  |
| SEVERAL COMPONENTS HAD BEEN TRANSFERRED OUT OF THE BUILDING AND STAGED FOR   |
| TRANSPORT.  HOWEVER, IT SHOULD BE NOTED THAT THE VALVES HAD BEEN STAGED IN   |
| COMPLIANCE WITH NCSA-PLANT048, EVEN IN LIGHT OF THE HIGHER MASSES            |
| IDENTIFIED.  IN RESPONDING TO THAT CONCERN, ADDITIONAL QUESTIONS REGARDING   |
| THE APPLICABILITY OF THE 15 GRAM U-235 PER PIECE OF EQUIPMENT CAME UP.  IT   |
| WAS CONCLUDED THAT OPERATIONS IN X-744H WOULD BE HALTED PENDING FULL         |
| DETERMINATION OF COMPLIANCE WITH NCSA-PLANT048.                              |
|                                                                              |
| HOWEVER, BASED ON A REVIEW OF AVAILABLE HISTORICAL DATA PERFORMED BY THE     |
| BUILDING MANAGEMENT, IT HAS BEEN DETERMINED THAT FULL COMPLIANCE WITH        |
| NCSA-PLANT048 CANNOT BE ESTABLISHED FOR A LARGE PORTION OF THE LEGACY        |
| EQUIPMENT STORED IN X-744H.  IN ADDITION, NO PROCEDURE COULD BE IDENTIFIED   |
| WITH WHICH THE EQUIPMENT HAS BEEN HANDLED WHICH INCORPORATED THE             |
| REQUIREMENTS OF NCSA-PLANT048.                                               |
|                                                                              |
| THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR                       |
| RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT.   |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED ALONG WITH THE DOE REPRESENTATIVE.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35855       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 06/24/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 05:18[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        06/23/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        20:50[CDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  06/24/1999|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |MIKE JORDAN          R3      |
|  DOCKET:  0707001                              |ROBERT PIERSON       NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  MATT MAURER                  |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24 HOUR REPORT - SAFETY SYSTEM ACTUATION                                     |
|                                                                              |
| "At 2050 CDT on 6/23/99, C-333A Autoclave Position 1 North received a High   |
| Autoclave Steam Pressure Alarm while in TSR mode 5.  The Autoclave Steam     |
| Pressure Control System is required to be operable while in mode 5 per LCO   |
| 2.2,3.3.  An Increase in autoclave steam pressure was observed by the        |
| Autoclave Steam Pressure Control System and the system isolated the steam    |
| from the autoclave as designed.  The autoclave was placed in mode 2 and the  |
| cause of the safety system actuation is being investigated."                 |
|                                                                              |
| The NRC Resident Inspector has been notified of this event.                  |
+------------------------------------------------------------------------------+