Event Notification Report for November 8, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
11/05/1999 - 11/08/1999
** EVENT NUMBERS **
36287 36364 36400 36401 36402 36403 36404 36405 36406 36407 36408 36409
36410 36411
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 36287 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 10/13/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 16:00[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 10/13/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 00:10[CDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 11/05/1999|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |JOHN MADERA R3 |
| DOCKET: 0707001 |SCOTT MOORE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: WALKER | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NCFR NON CFR REPORT REQMNT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| At 0010 on 10/13/99, the PSS office was notified that a primary condensate |
| alarm was received on the C-360 position 4 autoclave Water Inventory Control |
| System (WICS). The WICS system is required to be operable while heating in |
| mode 5 according to TSR 21.4.3. The autoclave was checked according to the |
| alarm response procedure and subsequently removed from service and declared |
| inoperable by the Plant Shift Superintendent. |
| Troubleshooting was initiated and is continuing in order to determine the |
| reason for the alarm. |
| |
| The NRC senior resident has been notified of this event. |
| |
| * * * UPDATE 2220EST ON 11/5/99 FROM E.G. WALKER TO S. SANDIN * * * |
| |
| "On 11/2/99, the same type of actuation occurred on the C-360 autoclave No. |
| 1 while out of service and open. While investigating this invalid actuation, |
| it was discovered that the gain adjustment on one of the WICS channels had |
| drifted out of tolerance. Discussions with the component manufacturer |
| concluded that the WICS alarm cards are susceptible to drift due to age and |
| fluctuations in temperature. These cards are exposed to ambient |
| temperatures, but the cards are rated for the range of temperatures at the |
| autoclaves. Given this and other indications that the WICS actuation |
| signals were invalid, i.e., not the result of water backing up in the drain, |
| it has been concluded that the subject actuation on 10/13/99 was caused by |
| [an] invalid signal (instrument drift) and thus does not meet the criteria |
| for reporting and should be retracted." |
| |
| The NRC resident has been notified of this retraction. Notified |
| R3DO(Creed). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 36364 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 10/28/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 16:16[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 10/27/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 17:05[CDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 11/05/1999|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |MIKE JORDAN R3 |
| DOCKET: 0707001 |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: W.F. CAGE | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NLTR LICENSEE 24 HR REPORT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| Safety System Actuation |
| |
| At 1705 CDT on 10/27/99, the Plant Shift Superintendent's (PSS) office was |
| notified that a primary condensate alarm was received on the C-360 position |
| 2 autoclave Water Inventory Control (WIC) System. The WIC system is |
| required to be operable while heating in mode 5 according to TSR 2.1.4.3. |
| The autoclave was checked according to the alarm response procedure, removed |
| from service and declared inoperable by the PSS. Troubleshooting was |
| initiated and is continuing in order to determine the reason for the alarm. |
| |
| The safety system actuation is reportable to the NRC as required by Safety |
| Analysis Report, section 6.9, table 1 criteria J.2, Safety System actuation |
| due to a valid signal as a 24-hour event notification. |
| |
| The NRC resident inspector has been notified. |
| |
| * * * UPDATE 2220EST ON 11/5/99 FROM E.G. WALKER TO S. SANDIN * * * |
| |
| "On 11/2/99, the same type of actuation occurred on the C-360 autoclave No. |
| 1 while out of service and open. While investigating this invalid actuation, |
| it was discovered that the gain adjustment on one of the WICS channels had |
| drifted out of tolerance. Discussions with the component manufacturer |
| concluded that the WICS alarm cards are susceptible to drift due to age and |
| fluctuations in temperature. These cards are exposed to ambient |
| temperatures, but the cards are rated for the range of temperatures at the |
| autoclaves. Given this and other indications that the WICS actuation |
| signals were invalid, i.e., not the result of water backing up in the drain, |
| it has been concluded that the subject actuation on 10/27/99 was caused by |
| [an] invalid signal (instrument drift) and thus does not meet the criteria |
| for reporting and should be retracted." |
| |
| The NRC resident inspector has been notified of this retraction. Notified |
| R3DO(Creed). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36400 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 11/05/1999|
| UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 04:07[EST]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 11/04/1999|
+------------------------------------------------+EVENT TIME: 20:30[CST]|
| NRC NOTIFIED BY: RICK ROBBINS |LAST UPDATE DATE: 11/05/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES CREED R3 |
|10 CFR SECTION: | |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 0.25 INCH LONG CRACK WAS FOUND ON "1A" STEAM GENERATOR HEAD DRAIN VALVE. |
| |
| During a liquid penetrant examination of a weld on the top side of valve |
| 1R-526A, the '1A' Steam Generator head drain, a 0.25" long crack was found. |
| This appears to be a crack in the weld metal only, through wall of the |
| Reactor Coolant System pressure boundary. |
| |
| During initial screening of this condition at 2030 hours on 11/04/99 it was |
| not considered seriously degraded as no leak was detected while at power |
| (boric acid crystals were found in the vicinity of the valve). Upon further |
| review at 0200 hours on 11/05/99 this 4 hour non-emergency report was made. |
| |
| The NRC Resident Inspector will be notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36401 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 11/05/1999|
| UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 05:21[EST]|
| RXTYPE: [1] W-2-LP |EVENT DATE: 11/05/1999|
+------------------------------------------------+EVENT TIME: 02:32[CST]|
| NRC NOTIFIED BY: TIM SMITH |LAST UPDATE DATE: 11/05/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES CREED R3 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 97 Power Operation |97 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| STEAM GENERATOR BLOWDOWN ISOLATION VALVES CLOSED |
| |
| At 0232 on 11/05/99 steam generator liquid radiation monitor R-19 failed. |
| This failure caused the following valves to close: BT-2A/MV-32077, steam |
| generator blowdown isolation valve A1; BT-2B/MV-32079, steam generator |
| blowdown isolation valve B1; BT-3A/MV-32078, steam generator blowdown |
| isolation valve A2; and BT-3B/MV-32080, steam generator blowdown isolation |
| valve B2. These valves have a containment isolation function for a main |
| steam line rupture within containment. Their post - Loss of Coolant |
| Accident function is to provide steam generator isolation. |
| |
| The monitor failure will not allow the re-establishment of steam generator |
| blowdown flow. Plant chemistry and instrument and control personnel have |
| been contacted to determine corrective actions and to repair the radiation |
| monitor. Radiation monitor R-15, Air Ejector Exhaust, is indicating normal |
| readings and is being monitored by operations. Local indication of |
| radiation monitor R-19 are the normal count rate. The actual problem appears |
| to be that the Control Room indication for R-19 has failed. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36402 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 11/05/1999|
| UNIT: [1] [] [] STATE: IA |NOTIFICATION TIME: 11:14[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 11/05/1999|
+------------------------------------------------+EVENT TIME: 10:00[CST]|
| NRC NOTIFIED BY: BOB MURRELL |LAST UPDATE DATE: 11/05/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES CREED R3 |
|10 CFR SECTION: | |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 60% THROUGH WALL CRACK DISCOVERED DURING AN ULTRASONIC EXAMINATION |
| |
| While performing ultrasonic examination of recirculation riser weld RRB-F002 |
| (nozzle to safe-end weld) indications that are indicative of intragranular |
| stress-corrosion cracking (IGSCC) were identified. Specifically, a 60% |
| through wall crack was found on the "B" recirculation riser nozzle to |
| safe-end weld. This weld was replaced in 1978. The licensee will take review |
| the codes and expand the scope of work as appropriate. |
| |
| The NRC resident inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36403 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 11/05/1999|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 11:51[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 11/05/1999|
+------------------------------------------------+EVENT TIME: 10:51[EST]|
| NRC NOTIFIED BY: ZAREMBA |LAST UPDATE DATE: 11/05/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MOHAMED SHANBAKY R1 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 85 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TURBINE TRIP/REACTOR SCRAM ON "1B" MOISTURE SEPARATOR REHEATER HIGH WATER |
| LEVEL. |
| |
| Turbine trip resulted in Reactor scram. Turbine trip was a result of a high |
| level alarm in the "1B" Moisture Separator Reheater. Just prior to the |
| turbine trip there appears to have been a level transient in the "4B" |
| feedwater heater. All control rods fully inserted into the core. Reactor |
| Feedwater Pumps tripped on High Reactor Vessel Water Level. A Reactor |
| Feedwater Pump was restarted when Reactor Vessel Water level decreased and |
| is currently maintaining Reactor Vessel Water Level. The Main Condenser is |
| being used as the heat sink. No Emergency Core Cooling Systems started as a |
| result of the turbine trip/Reactor scram. The offsite electrical grid is |
| stable, and the Emergency Diesel Generators are fully operable if needed. |
| |
| The Licensee is investigating what caused the level transient in the "4B" |
| feedwater heater. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36404 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 11/05/1999|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 13:28[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 11/05/1999|
+------------------------------------------------+EVENT TIME: 10:50[EST]|
| NRC NOTIFIED BY: MICHAEL WILLIAMS |LAST UPDATE DATE: 11/05/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PIERCE SKINNER R2 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R Y 100 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| Unit 1 was manually scrammed following the unplanned trip of the "1B" |
| Reactor Feed Pump during monthly surveillance testing. |
| |
| "On November 5,1999 at 1050 [hours] a manual Reactor Scram was inserted on |
| Unit 1 after Reactor Feed Pump '1B' tripped during feed pump testing and |
| Reactor Water Level was not maintained by the '1A' Reactor Feed Pump. |
| Primary Containment Groups 2, 6 and 8 Isolations were received following the |
| manual reactor scram from low Reactor Water Level. There is normally a level |
| transient following a reactor scram, which is anticipated by the operating |
| crew. Reactor Water Level lowered to 112 inches. The High Pressure Coolant |
| Injection system was manually started, but was not used for injection. All |
| required Isolations occurred as a result of the Reactor Water Level Low |
| Level One initiation signal. Group 2 isolation valves include Drywell |
| Equipment and Floor Drain, Traversing Incore Probe, Residual Heat Removal |
| (RHR) Discharge Isolation to Radwaste and RHR Process Sampling Valves. |
| Group 6 isolation valves include Containment Atmosphere Control System and |
| Post Accident Valves. Group 8 isolation valves include RHR System Shutdown |
| Cooling Isolation Valves, these valves were closed prior to the isolation |
| sign. |
| |
| "[The initial safety significance is] minimal, all systems functioned as |
| designed. The licensee took conservative action to insert a manual Reactor |
| Scram. |
| |
| "The cause of the '1B' Reactor Feed Pump trip will be determined and |
| corrected." |
| |
| All rods fully inserted. Decay heat is being removed via the Main |
| Condenser. The automatic reactor scram level setpoint is 162 inches with |
| HPCI injection occurring at 108 inches. |
| |
| The licensee informed the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 36405 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: ILLINOIS DEPT OF NUCLEAR SAFETY |NOTIFICATION DATE: 11/05/1999|
|LICENSEE: |NOTIFICATION TIME: 17:06[EST]|
| CITY: REGION: 3 |EVENT DATE: 11/01/1999|
| COUNTY: STATE: IL |EVENT TIME: 16:00[CST]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 11/05/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JAMES CREED R3 |
| |WAYNE HODGES NMSS |
+------------------------------------------------+FRANK CONGEL IRO |
| NRC NOTIFIED BY: BRUCE SANZA | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT INVOLVING INDIVIDUAL RECEIVING > 5X ANNUAL LIMIT ON |
| INTAKE (ALI) OF TRITIUM (INHALATION) |
| |
| AT 1645 HOURS ON 11/2/99, THE ILLINOIS DEPARTMENT OF NUCLEAR SAFETY WAS |
| INFORMED THAT AN INDIVIDUAL HAD SMASHED A TUBE ON 11/1/99 CONTAINING 2 |
| CURIES TRITIUM FROM A SELF-POWERED EXIT SIGN INSIDE HIS RESIDENTIAL GARAGE. |
| THIS QUANTITY EXCEEDS 5X THE (ALI) OF 10CFR20 APPENDIX B (1 ALI INHALATION |
| IS 80 mCi). THE REMAINING THREE TUBES WERE SAFELY REMOVED FROM THE |
| INDIVIDUAL'S GARAGE. THE INDIVIDUAL INITIALLY CONTACTED A POISON HOTLINE |
| AND WAS REFERRED. INSPECTORS FROM THE STATE AGENCY HAVE SURVEYED THE GARAGE |
| AND ARE FOLLOWING UP. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36406 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 11/05/1999|
| UNIT: [1] [] [] STATE: NH |NOTIFICATION TIME: 19:24[EST]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 11/05/1999|
+------------------------------------------------+EVENT TIME: 16:40[EST]|
| NRC NOTIFIED BY: RICHARD MESSINA |LAST UPDATE DATE: 11/05/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MOHAMED SHANBAKY R1 |
|10 CFR SECTION: | |
|HFIT 26.73 FITNESS FOR DUTY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 24-HOUR FITNESS FOR DUTY REPORT INVOLVING CONTRACTOR SUPERVISOR EMPLOYEE |
| |
| CONTRACTOR SUPERVISOR EMPLOYEE CONFIRMED POSITIVE FOR COCAINE FOLLOWING |
| RANDOM DRUG TESTING. THE INDIVIDUAL'S ACCESS HAS BEEN DENIED. CONTACT THE |
| HEADQUARTERS OPERATIONS CENTER FOR ADDITIONAL DETAILS. |
| |
| THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36407 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 11/06/1999|
| UNIT: [1] [] [] STATE: LA |NOTIFICATION TIME: 09:12[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 11/05/1999|
+------------------------------------------------+EVENT TIME: 15:38[CST]|
| NRC NOTIFIED BY: RUSS GODWIN |LAST UPDATE DATE: 11/06/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CLAUDE JOHNSON R4 |
|10 CFR SECTION: | |
|NCFR NON CFR REPORT REQMNT | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 90 Power Operation |90 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 24-HOUR REPORT PURSUANT TO REGULATORY GUIDE 1.133 |
| |
| "At 1538 CST, on November 5, 1999, the River Bend Station (RBS) staff |
| concluded that a loose part had been detected in the primary system. |
| |
| "The RBS staff was alerted to this condition when channel six of the Loose |
| Parts Monitoring System (LPMS) began to alarm at approximately three to five |
| minute intervals. Channel six monitors the Feedwater 45� line. Over the |
| remainder of the day, the alarms gradually decreased to none and there is |
| currently no alarming condition. No other Loose Parts Monitoring channels |
| detected this condition. |
| |
| "The RBS staff and the LPMS vendor reviewed the data and concluded that the |
| loose part is of relatively low mass, probably less than two pounds. The RBS |
| staff will continue to evaluate this condition. |
| |
| "This report is submitted pursuant to Reg. Guide 1.133." |
| |
| The NRC resident inspector has been informed of this notification by the |
| licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36408 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 11/06/1999|
| UNIT: [1] [2] [] STATE: WI |NOTIFICATION TIME: 21:46[EST]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 11/06/1999|
+------------------------------------------------+EVENT TIME: 18:44[CST]|
| NRC NOTIFIED BY: PHILLIP SHORT |LAST UPDATE DATE: 11/06/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES CREED R3 |
|10 CFR SECTION: | |
|AMED 50.72(b)(2)(v) OFFSITE MEDICAL | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INJURED POTENTIALLY CONTAMINATED WORKER TRANSPORTED TO LOCAL HOSPITAL |
| |
| "A WORKER SLIPPED AND FELL IN THE LAUNDRY ROOM. AN AMBULANCE WAS CALLED DUE |
| TO A POSSIBLE HIP INJURY. A COMPLETE FRISK OF THE INDIVIDUAL WAS NOT ABLE |
| TO BE PERFORMED PRIOR TO TRANSPORTING OFFSITE TO A LOCAL HOSPITAL. THE |
| INJURED PERSON IS BEING CONSIDERED POTENTIALLY CONTAMINATED. A RADIATION |
| PROTECTION TECHNICIAN IS ACCOMPANYING THE INJURED PERSON TO THE HOSPITAL." |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36409 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 11/07/1999|
| UNIT: [1] [] [] STATE: MI |NOTIFICATION TIME: 11:56[EST]|
| RXTYPE: [1] CE |EVENT DATE: 11/07/1999|
+------------------------------------------------+EVENT TIME: 09:35[EST]|
| NRC NOTIFIED BY: HUGH NIXON |LAST UPDATE DATE: 11/07/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES CREED R3 |
|10 CFR SECTION: | |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| CONTAINMENT SUMP SCREEN INTEGRITY QUESTIONABLE DURING A DESIGN BASIS |
| ACCIDENT |
| |
| "CONTAINMENT SUMP SCREENS (ESS RECIRC) ARE IN A DIFFERENT CONFIGURATION THAN |
| PREVIOUSLY THOUGHT. THE SCREEN MATERIAL IS NOT WELDED TO THE SCREEN FRAME |
| FOR AT LEAST ONE THIRD OF IT'S LENGTH. INSTEAD, THE PERIPHERY OF THE SCREEN |
| IS CLAMPED AT NUMEROUS PLACES MAKING THE SCREEN INTEGRITY QUESTIONABLE IN |
| THE EVENT OF A DESIGN BASIS ACCIDENT FLOW RATES." |
| |
| THIS CONDITION, DISCOVERED DURING THE REFUELING INSPECTION OF THE |
| CONTAINMENT SUMP, MAY HAVE EXISTED SINCE INITIAL CONSTRUCTION. THE LICENSEE |
| IS PERFORMING FURTHER ANALYSIS TO DETERMINE APPROPRIATE CORRECTIVE ACTIONS |
| FOR IMPLEMENTATION PRIOR TO RESTART. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36410 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 11/07/1999|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 15:19[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 11/07/1999|
+------------------------------------------------+EVENT TIME: 13:48[CST]|
| NRC NOTIFIED BY: JIM McKAY |LAST UPDATE DATE: 11/07/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES CREED R3 |
|10 CFR SECTION: | |
|AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM DECLARED INOPERABLE DUE TO |
| FAILURE OF THE ASSOCIATED ROOM COOLER |
| |
| "DURING NORMAL OPERATIONS, HPCI HAS BEEN DECLARED INOPERABLE IN ACCORDANCE |
| WITH TECH SPEC SECTION 3.5.A.3.g. HPCI IS INOPERABLE DUE TO THE FAILURE OF |
| SUPPORT AUXILIARY EQUIPMENT, i.e., THE VENTILATION COOLING COIL HAS A MAJOR |
| LEAK REQUIRING ISOLATION OF THE VENTILATION UNIT. HPCI IS IN A 14-DAY |
| LCO." |
| |
| THE LICENSEE WILL INFORM STATE/LOCAL AGENCIES AS A COURTESY AND THE NRC |
| RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 36411 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 11/07/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 22:36[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 11/07/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 04:00[EST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 11/07/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |JAMES CREED R3 |
| DOCKET: 0707002 | |
+------------------------------------------------+ |
| NRC NOTIFIED BY: KURT SISLER | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 24-HOUR NRC BULLETIN 91-01 NOTIFICATION INVOLVING LOSS OF CRITICALITY |
| CONTROL (MODERATION) |
| |
| "On 11/7/99 at 0400 hours, it was discovered that the standard solution used |
| to calibrate X-344, Autoclave #2 conductivity system probes on 11/1/99 was |
| past its shelf life expiration date as stated on the certificate of NIST |
| traceability. This brings into question the operability (AQ-NCS boundary |
| item) of the conductivity system. Autoclave #2 was operated in Mode II |
| (Cylinder Heating) for approximately 30 minutes on 11/2/99. Conductivity |
| system as-found readings were performed on 11/2/99 with a standard solution |
| in date according to NIST requirements, The as-found results were within |
| tolerance indicating that the system would have performed its intended |
| safety function. |
| |
| "Nuclear Criticality Engineering has determined that the operation of the |
| autoclave, after calibration of the conductivity system with out-dated |
| conductivity standard solution, constitutes the loss of one (1) NCS control |
| (moderation). The other control (Mass) was maintained throughout the |
| duration of this event. The loss of one NCS control is reportable to the NRC |
| as a 24-hour event. |
| |
| "THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR |
| RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT. |
| |
| "SAFETY SIGNIFICANCE OF EVENTS: |
| |
| "The safety significance of this event is low. The conductivity probes are |
| required to be operable and are tested semi-annually to verify this. The |
| probes were tested on 11/1/99 however, the solution used to calibrate the |
| probes was out of date. If the probes completely failed a UF6 release in |
| quantities greater than the minimum critical mass would have to occur or a |
| slow release could allow a dilute UO(2)F(2) solution to reach unfavorable |
| geometry storm drains. There was no UF6 release during this event and the |
| autoclave was only operated for 30 minutes in this condition (As-found |
| testing with in-date standard on 11/2/99 revealed that the conductivity |
| system was within allowable tolerance). |
| |
| "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO[S] OF HOW |
| CRITICALITY COULD OCCUR): |
| |
| "The potential pathway to criticality is that a slow UF6 release occurs |
| (less than 2 pounds per minute) and the conductivity probes fail to detect |
| it. A release with greater than 2 pounds per minute would isolate the |
| autoclave due to high pressure. This slow release could allow a dilute |
| solution to reach unfavorable geometry storm drains. |
| |
| "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.): |
| |
| "The controlled parameters are mass and moderation. |
| |
| "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS |
| LIMIT AND % WORST CASE OF CRITICAL MASS): |
| |
| "The estimated amount of material is zero because there was no release, the |
| maximum enrichment is 5% U235 and the form of material is UF6. |
| |
| "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION |
| OF THE FAILURES OR DEFICIENCIES |
| |
| "The control that was lost was moderation. The conductivity probes were |
| calibrated with a solution that was out of date and therefore the probes |
| were inoperable. The autoclave was operated for 30 minutes in this |
| condition. |
| |
| "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED: |
| |
| "As found readings were completed with an in-date batch of conductivity |
| standard solution. All as-found readings were in acceptable limits. |
| Autoclave #2 is inoperable (since 11/4/99) for reasons other than this |
| event." |
| |
| The standard solution used to calibrate the conductivity system expired on |
| 10/12/99. Operations has the cause for this incident report under review; |
| however, the preliminary investigation attributes the failure to personnel |
| error. |
| |
| The NRC Resident Inspector was informed. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021