Event Notification Report for October 26, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
10/25/1999 - 10/26/1999
** EVENT NUMBERS **
36215 36329 36341 36342 36343 36344 36345 36346 36347
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36215 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 09/23/1999|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 03:13[EDT]|
| RXTYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 09/22/1999|
+------------------------------------------------+EVENT TIME: 23:55[CDT]|
| NRC NOTIFIED BY: McLAUGHLIN |LAST UPDATE DATE: 10/25/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ROGER LANKSBURY R3 |
|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 90 Power Operation |90 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DIVISION 3 EMERGENCY DIESEL GENERATOR TRIPPED ON OVER SPEED DURING MONTHLY |
| SURVEILLANCE TESTING. |
| |
| While performing monthly surveillance start of the High Pressure Core Spray |
| system Emergency Diesel Generator, the Diesel automatically tripped off on |
| an overspeed signal. The diesel does not appear to have been damaged but |
| remains shutdown and unavailable for on-going investigation of the failure. |
| The High Pressure Core Spray system is inoperable but available from normal |
| power source only. The failure mechanism is being investigated and |
| corrective actions will be performed. The Reactor Core Isolation Cooling |
| pump and all other Emergency Core Cooling Systems are also fully operable. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
| |
| |
| * * * RETRACTION AT 1756ET ON 10/25/99 BY R HASTY TAKEN BY MACKINNON* * * |
| |
| Preliminary troubleshooting on the 1B Emergency Diesel Generator determined |
| that the cause of the overspeed trip was that the governor synchronizer |
| speed setting was at its mechanical high-speed stop. It was not known when |
| the governor synchronizer speed setting had reached that position, so an ENS |
| call was made per 10 CFR 50.72. |
| |
| A through investigation has been performed. The investigation has |
| determined that the most probable cause of the event was a mechanical |
| failure of the local governor control switch. This switch is only in the |
| governor control circuit when the governor control is in local manual, which |
| indicates that the failure occurred during the initial start sequence, after |
| the diesel generator was out of service for the surveillance test. In |
| addition, the local governor control switch is bypassed when in remote |
| manual, switch is required for standby conditions and operability of the |
| diesel generator. |
| |
| Since the failure occurred after the diesel generator was out of service, |
| and was identified and repaired in 31 hours, well within the 14 day |
| Technical Specification allowed outage time, it has been determined that |
| this event is not reportable to the NRC, and this event notification is |
| being retracted. R3DO (Mike Jordan) notified. |
| |
| The NRC Resident was notified of this retraction by the licensee. |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36329 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 10/22/1999|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 06:24[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 10/22/1999|
+------------------------------------------------+EVENT TIME: 03:15[EDT]|
| NRC NOTIFIED BY: JESTER |LAST UPDATE DATE: 10/25/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |KERRY LANDIS R2 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
|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
+------------------------------------------------------------------------------+
| HPCI IS INOPERABLE |
| |
| WHILE PERFORMING HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM OPERABILITY |
| TEST (OPT-09-2) FOR POST MAINTENANCE TESTING, THE TURBINE STEAM SUPPLY VALVE |
| #1-E41-F001 FAILED IN MID-POSITION. THIS OCCURRED WHEN THE VALVE WAS BEING |
| CLOSED TO PLACE THE SYSTEM IN ITS STANDBY LINEUP FOLLOWING COMPLETION OF THE |
| OPERABILITY TEST. IN ADDITION, THE STEAM SUPPLY DRAIN POT INBOARD AND |
| OUTBOARD DRAIN VALVES #1-E41-F028 AND #1-E41-F029 DID NOT OPERATE AS |
| EXPECTED. THESE VALVES OPEN AND CLOSE IN UNISON AUTOMATICALLY AS DETERMINED |
| BY THE POSITION OF THE TURBINE STEAM SUPPLY VALVE #1-E41-F001. CURRENTLY, |
| THE INBOARD DRAIN VALVE #1-E41-F028 IS CLOSED AND THE OUTBOARD DRAIN VALVE |
| #1-E41-F029 IS OPEN. |
| |
| THE AUTOMATIC DEPRESSURIZATION SYSTEM, LOW PRESSURE COOLANT INJECTION |
| SYSTEM, CORE SPRAY SYSTEM AND REACTOR CORE ISOLATION COOLANT SYSTEM ARE |
| OPERABLE. THE LICENSEE IS INVESTIGATING THE CAUSE OF THE PROBLEM AND |
| SUSPECTS IT MIGHT BE DUE TO A LOGIC/LIMIT SWITCH CIRCUITRY PROBLEM. |
| |
| THE SAFETY SIGNIFICANCE OF THIS EVENT IS MINIMAL. |
| |
| THE RESIDENT INSPECTOR WAS NOTIFIED. |
| |
| * * * RETRACTION AT 1614ET ON 10/25/99 BY STEVE TABOR TAKEN BY MACKINNON * * |
| * |
| |
| BASED ON FURTHER EVALUATION, IT HAS BEEN DETERMINED THAT THE HPCI |
| MALFUNCTION WAS CAUSED BY THE PLANNED MAINTENANCE ACTIVITIES AND WAS NOT A |
| PRE-EXISTING CONDITION. SPECIFICALLY, THE MALFUNCTION WAS DUE TO A |
| CONDITION WHICH WAS INTRODUCED BY THE REPLACEMENT OF THE HPCI TURBINE TRIP |
| SOLENOID VALVE, E41-C002-SV1 (ie, DELAYED OPERATION OF THE E41-C003-SV1). |
| THIS CONDITION WAS CORRECTED AND POST-MAINTENANCE TESTING COMPLETED |
| SATISFACTORILY. SINCE THIS CONDITION WAS INTRODUCED DURING THE MAINTENANCE |
| ACTIVITIES WITH THE HPCI SYSTEM PROPERLY REMOVED FROM SERVICE AND IDENTIFIED |
| AS PART OF POST-MAINTENANCE TESTING ACTIVITIES, IT DOES NOT REPRESENT AN |
| EVENT OR CONDITION THAT ALONE COULD HAVE PREVENTED THE FULFILLMENT OF THE |
| SAFETY FUNCTION OF HPCI. AS SUCH, THIS EVENT IS REPORTABLE IN ACCORDANCE |
| WITH 10 CFR 50.72(b)(2)(iii)(D). R2DO (K. LANDIS) NOTIFIED. |
| |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36341 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 10/25/1999|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 09:39[EDT]|
| RXTYPE: [1] GE-2 |EVENT DATE: 10/23/1999|
+------------------------------------------------+EVENT TIME: 02:00[EDT]|
| NRC NOTIFIED BY: MALCOLM BROWNE |LAST UPDATE DATE: 10/25/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |WILLIAM COOK R1 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO THE NATIONAL MARINE FISHERIES SERVICE AND THE NEW |
| JERSEY DEPARTMENT OF ENVIRONMENTAL PROTECTION (NJ DEP). |
| |
| AN IMMATURE GREEN SEA TURTLE WAS FOUND DEAD AT APPROXIMATELY 0200EDT ON |
| 10/23/99 IN UNIT'S DILUTION WATER STRUCTURE. THE LICENSEE WILL NOTIFY THE |
| NJ DEP AND MARINE FISHERIES SERVICE AND WILL INFORM THE NRC RESIDENT |
| INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 36342 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 10/25/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 11:17[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 10/24/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 22:50[CDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 10/25/1999|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |ROGER LANKSBURY |
| DOCKET: 0707001 |JOSIE PICCONE |
+------------------------------------------------+ |
| NRC NOTIFIED BY: W. F. CAGE | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | |
|OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | |
|OCBC 76.120(c)(2)(iii) REDUNDANT EQUIP INOP | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INADEQUATE HIGH PRESSURE FIRE WATER SYSTEM INSTALLATION IN THE C-337 |
| BUILDING |
| |
| "On 10/24/99, at 2250 CDT, the Plant Shift Superintendent was notified that |
| High Pressure Fire Water system D5 in the C-337 building, does not meet |
| NFPA Code 13. During a walkdown of the system, two non-conformances were |
| noted. The spacing between two of the branch lines exceeds the NFPA 13 |
| maximum spacing criteria of 15 feet. It was also noted that the spacing of |
| the sprinkler heads on these two branch lines is between 5 to 6 feet. NFPA |
| 13 requires the heads to be spaced a minimum of 6 feet apart unless baffles |
| have been installed. These heads do not have baffles installed on them. |
| This system was inoperable at the time of discovery, and LCO required fire |
| patrols were being performed. |
| |
| "It has been determined that this event is reportable under |
| 10CFR76.120(c)(2) as an event in which equipment is disabled or fails to |
| function as designed. |
| |
| "The NRC Resident Inspector has been notified of this event." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36343 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 10/25/1999|
| UNIT: [1] [2] [] STATE: WI |NOTIFICATION TIME: 15:30[EDT]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 10/25/1999|
+------------------------------------------------+EVENT TIME: 14:15[CDT]|
| NRC NOTIFIED BY: JOHN SELL |LAST UPDATE DATE: 10/25/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ROGER LANKSBURY |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| SEVERAL SAFE SHUTDOWN PANELS WERE FOUND THAT NEEDED ADDITIONAL LIGHTING |
| |
| During the Appendix R re-baselining project, several safe shutdown |
| components were found that need additional emergency lighting on them and |
| additional pathway lighting. This additional lighting is required by 10CFR |
| 50 Appendix R, Section III. This condition is also applicable to Unit 1. |
| Unit 1 is presently in a refueling outage. |
| |
| Extra Emergency lighting is needed in the following areas: Auxiliary |
| Feedwater Cubicles; D-16, 17, 18, & 19 Panels in Control Room,; Panels in |
| the Computer Room; Non Vital 4.16kV buses 1A01, 1A02, 2A01, & 2A02; Vital AC |
| 120V Buses D107, D109, D302, & D303; 480V Non Vital Buses 2B01, 2B02; 480V |
| Non Vital Buses 1B01, & 1B02; Unit 1 Sump Room West Entry, etc. |
| |
| The Licensee is not in any Tech Spec action statements as a result of the |
| above information. |
| |
| The NRC Resident Inspector will be notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 36344 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: STATE OF TENNESSEE |NOTIFICATION DATE: 10/25/1999|
|LICENSEE: GTS DURATEK WEST |NOTIFICATION TIME: 14:30[EDT]|
| CITY: MEMPHIS REGION: 2 |EVENT DATE: 10/25/1999|
| COUNTY: STATE: TN |EVENT TIME: 12:00[EDT]|
|LICENSE#: TN-99-145 AGREEMENT: Y |LAST UPDATE DATE: 10/25/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |KERRY LANDIS R2 |
| |CHARLEY HAUGHNEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: EDDIE NANNY, FAXED | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| BOTTOM OF BOX RADIATION READINGS ARE 350mR/hr. SHIPPING PAPERS SHOW A |
| MAXIMUM READING OF 105mR/hr. |
| |
| A shipment from G.E. Laguna Verde power plant in Mexico was received at GTS |
| Duratek West, (formerly Frank W. Hake) , Memphis, TN. The receiving survey |
| at GTS revealed a small hot spot on the bottom of an upper stacked box |
| (between boxes ) of equipment being shipped from G.E. The elevated area was |
| 10" across with a maximum measured level of 350 mR/hr. The point of origin |
| surveys showed a maximum of 105 mR/hr on the bottom of the box. GTS |
| requested and was given permission to receive and offload shipment to |
| minimize perimeter and allow evaluation of the cause of the elevated |
| reading. Event number assigned to this event by the State of TN is |
| TN-99-145. License number is R-79171. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36345 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 10/25/1999|
| UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 17:36[EDT]|
| RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE: 10/25/1999|
+------------------------------------------------+EVENT TIME: 16:50[EDT]|
| NRC NOTIFIED BY: J. MCGUFFIN |LAST UPDATE DATE: 10/25/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |KERRY LANDIS R2 |
|10 CFR SECTION: | |
|DDDD 73.71 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 100 Power Operation |100 Power Operation |
|3 N Y 100 Power Operation |100 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TEMPORARY ACCESS GRANTED INAPPROPRIATELY. IMMEDIATE COMPENSATORY MEASURES |
| TAKEN UPON DISCOVERY. VENDOR EMPLOYEE WAS TERMINATED. AN INVESTIGATION |
| INTO THE INCIDENT IS CONTINUING. |
| |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. |
| |
| SEE HOO LOG BOOK FOR FURTHER DETAILS. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 36346 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: RAC SERVICES, INC. |NOTIFICATION DATE: 10/25/1999|
|LICENSEE: RAC SERVICES, INC. |NOTIFICATION TIME: 18:27[EDT]|
| CITY: WASHINGTON REGION: 4 |EVENT DATE: 10/22/1999|
| COUNTY: STATE: OK |EVENT TIME: 12:30[CDT]|
|LICENSE#: UNK AGREEMENT: N |LAST UPDATE DATE: 10/25/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |DAVID LOVELESS R4 |
| |LINDA HOWELL R4 |
+------------------------------------------------+CHARLEY HAUGHNEY NMSS |
| NRC NOTIFIED BY: JUDY GAYANICH |JOSEPH GIITTER IRO |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| IN-LINE DENSIOMETER CONTAINING 200mCi of CESIUM-137 STOLEN THE MORNING OF |
| OCTOBER 22, 1999. POLICE AND SHERIFFS DEPARTMENTS NOTIFIED, REWARD POSTED BY |
| LICENSEE. |
| |
| The following event was reported by RAC Services, Inc., located in |
| Washington, OK. NRC Region 4 Linda Howell had the licensee call the event |
| into the Operations Center and she remained on line during the event |
| notification. |
| |
| The In-Line Densiometer was last serviced by Texas Nuclear (TN) Technologies |
| on October 14, 1999 at its office located in Round Rock, Tx (10-15 miles |
| north of Austin). The In-Line Densiometer is 3' in length, 2' wide and |
| weighs about 80 pounds. The In-Line Densiometer is gray in color and its |
| model number is 5192 and its serial number is B6670, contains 200mCi of |
| Cs-137. It is licensed under a general license number (owners did not |
| know/have the license number for the In-Line Densiometer). Rex, one of the |
| callers, said that this In-Line Densiometer did not have any radioactive |
| placards or labels on it (may have been rubbed off). Rex said that he did |
| not have to wear a Film Badge or TLD when carrying the In-Line Densiometer. |
| |
| |
| In the early morning hours (0300 AM) of 10/21/99 the licensee was heading |
| back on a county road (road runs between 2 county lines) about 8 miles North |
| of Calumet, OK when the trailer blew a tire. The trailer was full of scrap |
| iron painted red and the In-Line Densiometer was chained to the trailer. The |
| In-Line Densiometer was not in its case at this time. The licensee checked |
| on the trailer twice during October 21, 1999 (Thursday) and the last time |
| they saw the trailer was around 2030 hours on 10/21/99. When the licensee |
| arrived around 1230 hours on 10/22/99 (Friday) to replace the flat tire they |
| discovered that the trailer was missing and presumed stolen. |
| |
| The licensee notified police and one of the county Sheriffs Department that |
| the trailer and In-Line Densiometer had been stolen Friday afternoon |
| (10/22/99). On Monday, October 25, 1999, the licensee notified the other |
| county Sheriffs Department that their In-Line Densiometer had been stolen |
| along with the trailer. The licensee has offered a $5,000 reward for the |
| In-Line Densiometer. The In-Line Densiometer is shipped in a Type "A |
| "package. |
| |
| A telephone call was placed to Texas Nuclear Technologies and a message was |
| left on their answering machine to either call the NRC Headquarters |
| Operations Officer or call NRC Region 4 Office. |
| |
| Ask HOO for telephone numbers and address.. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36347 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 10/26/1999|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 03:06[EDT]|
| RXTYPE: [1] CE |EVENT DATE: 10/26/1999|
+------------------------------------------------+EVENT TIME: 01:32[CDT]|
| NRC NOTIFIED BY: LARRY LEES |LAST UPDATE DATE: 10/26/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: ALE |DAVID LOVELESS R4 |
|10 CFR SECTION: |BRUCE BOGER NRR |
|AAEC 50.72 (a) (1) (I) EMERGENCY DECLARED |JOSEPH GIITTER IRO |
| |CANUPP FEMA |
| |PERKINS DOE |
| |TURMAN EPA |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| UNIT 1 REPORTED ENTERING AND EXITING CONDITIONS REQUIRING AN ALERT |
| DECLARATION |
| |
| "AT 0132CDT, WHEN ATTEMPTING TO TRANSFER STATION LIGHTING, VITAL BUSES 1A3 |
| AND 1A4 WERE DEENERGIZED. [BOTH] DIESEL GENERATORS [DG-1 AND DG-2] WERE IN |
| 'OFF-AUTO' FOR MODE 5 CONDITIONS. WHEN THE DIESEL GENERATORS WERE TAKEN TO |
| 'AUTO,' THE DIESEL GENERATORS AUTOSTARTED AND ENERGIZED VITAL BUSES 1A3 AND |
| 1A4, AT 0134CDT. SHUTDOWN COOLING WAS LOST FOR APPROXIMATELY [TWO] 2 |
| MINUTES AND RESTORED WHEN THE DIESEL GENERATORS WERE PLACED ON THE BUS. |
| SHUTDOWN COOLING TEMPERATURE INDICATED [ZERO] 0 DEGREES FAHRENHEIT |
| TEMPERATURE RISE IN THE [TWO] 2 MINUTES THAT SHUTDOWN COOLING WAS LOST. |
| WHEN THE EMERGENCY PLAN WAS ENTERED, VITAL BUSES WERE ALREADY RE-ENERGIZED. |
| AN ALERT WAS REPORTED UNDER EAL 4.3 BUT NOT DECLARED. OFFSITE POWER WAS |
| ALWAYS AVAILABLE, AND AS OF THIS TIME IS ON VITAL BUS 1A3." |
| |
| OFFSITE POWER WAS RESTORED TO BUSES 1A3 AND 1A4 AT 0159CDT AND 0209CDT, |
| RESPECTIVELY. INITIAL RCS TEMPERATURE WAS 103 DEGREES FAHRENHEIT. SHUTDOWN |
| COOLING TRAIN "A" WAS PLACED IN-SERVICE TO REPLACE THE OPERATING TRAIN "B" |
| WHICH WAS DEENERGIZED. THE ELECTRICAL MAINTENANCE HAS LOOKED AT |
| TRANSFORMERS INSIDE AND OUTSIDE THE PLANT AND FOUND NO APPARENT FAILURE. |
| |
| THE LICENSEE NOTIFIED BOTH STATE AND LOCAL AGENCIES AND WILL INFORM THE NRC |
| RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021