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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 35000 |
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+------------------------------------------------------------------------------+
| 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
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| 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. |
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 35849 |
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| 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
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| 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. |
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+------------------------------------------------------------------------------+
|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. |
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|Power Reactor |Event Number: 35853 |
+------------------------------------------------------------------------------+
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| 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. |
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+------------------------------------------------------------------------------+
|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
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| 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
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| 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. |
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