U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
04/25/2003 - 04/28/2003
** EVENT NUMBERS **
39780 39790 39796 39797 39799 39800
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|General Information or Other |Event Number: 39780 |
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| REP ORG: MARYLAND DEPT OF THE ENVIRONMENT |NOTIFICATION DATE: 04/22/2003|
|LICENSEE: ENGINEERING CONSULTANT SERVICES |NOTIFICATION TIME: 11:05[EDT]|
| CITY: FREDERICK REGION: 1 |EVENT DATE: 04/22/2003|
| COUNTY: FREDERICK STATE: MD |EVENT TIME: [EDT]|
|LICENSE#: MD2103701 AGREEMENT: Y |LAST UPDATE DATE: 04/22/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |HAROLD GRAY R1 |
| |TOM ESSIG NMSS |
+------------------------------------------------+MATT HAHN IAT |
| NRC NOTIFIED BY: ALAN JACOBSON | |
| HQ OPS OFFICER: MIKE RIPLEY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGE |
| |
| The licensee reported that upon arriving at their work site in Bethesda, MD |
| early in the morning of 04/22/03 they discovered that their construction |
| trailer was broken into and a moisture density gauge stolen. The gauge is a |
| CPN Model # MC1DR, S/N MD00305503 containing 10 millicuries Cs-137 and 50 |
| millicuries Am-241:Be. The licensee notified the Montgomery County Police |
| (Case # B03089862). |
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|Power Reactor |Event Number: 39790 |
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| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 04/24/2003|
| UNIT: [1] [2] [] STATE: MI |NOTIFICATION TIME: 04:40[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/24/2003|
+------------------------------------------------+EVENT TIME: 03:48[EDT]|
| NRC NOTIFIED BY: STUART SCHUETTPELZ |LAST UPDATE DATE: 04/25/2003|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: ALERT |MONTE PHILLIPS R3 |
|10 CFR SECTION: |JAMES LYONS NRR |
|AAEC 50.72(a) (1) (i) EMERGENCY DECLARED |MICHELE EVANS IRO |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA|CHUCK CAIN R4 |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT|CHARLIE BAGWELL FEMA |
| |JOHN FLACH NRC |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R Y 100 Power Operation |0 Hot Standby |
|2 M/R Y 100 Power Operation |0 Hot Standby |
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EVENT TEXT
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| ALERT DECLARED |
| |
| At 0348 EDT on 4/24/03, the plant experienced an influx of fish on the |
| intake screens for the circwater and essential service water (ESW) systems. |
| This resulted in a loss of vacuum to Units 1 and 2 main turbines, which led |
| operators to manually trip both reactors. Following the trip, operators |
| noted that ESW flow to all 4 emergency diesel generators (EDGs) was severely |
| degraded. This resulted in the licensee declaring all 4 EDG's inoperable. |
| An alert was declared at 0348 EDT, and the NRC entered Monitoring Mode at |
| 0506 EDT. |
| |
| * * * UPDATE AT 0600 ON 4/24/03 FROM LICENSEE TO H. CROUCH * * * |
| |
| All EDG's have adequate flow to be used in an emergency, but remain |
| inoperable. |
| |
| The licensee is assessing damage to intake screens and strainers in the ESW |
| system, and manually backwashing ESW screens. |
| |
| * * * UPDATE AT 0718 ON 4/24/03 FROM DEAN BRUCK TO E. THOMAS * * * |
| |
| The licensee made a 4-hour ENS notification under 10 CFR 50.72(b)(2)(iv)(B) |
| to inform the NRC of the manual reactor trips inserted on Units 1 and 2 at |
| 0328 and 0329 on 4/24/03 for the reasons listed above. Post-trip response |
| of the plant was normal. Main Steam Isolation Valves were manually closed |
| on both units due to lowering Reactor Coolant System temperature and |
| lowering vacuum. Both units remain in Mode 3. |
| |
| * * * UPDATE AT 1020 ON 4/24/03 FROM TODD CASPER TO E. THOMAS * * * |
| |
| The licensee made an 8-hour ENS notification under 10 CFR 50.72(b)(3)(iv)(A) |
| to inform the NRC of the Auxiliary Feedwater System (AFW) actuations in |
| Units 1 and 2 following the reactor trips. The heat removal path for both |
| units is via AFW to the steam generator pressure operated relief valves. |
| |
| * * * UPDATE AT 0532 ON 4/25/03 FROM R3 IRC TO E. THOMAS * * * |
| |
| The licensee terminated the Alert at 0521 EDT. The Alert was terminated |
| based on having one train of ESW and one EDG declared OPERABLE for each |
| Unit. The NRC exited the Monitoring Mode of normal operations at 0532 EDT. |
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|Power Reactor |Event Number: 39796 |
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| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 04/25/2003|
| UNIT: [1] [2] [] STATE: MI |NOTIFICATION TIME: 09:58[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/24/2003|
+------------------------------------------------+EVENT TIME: 14:17[EDT]|
| NRC NOTIFIED BY: LEE BUSH |LAST UPDATE DATE: 04/25/2003|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MONTE PHILLIPS R3 |
|10 CFR SECTION: | |
|HFIT 26.73 FITNESS FOR DUTY | |
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| | |
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+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Hot Shutdown |0 Hot Shutdown |
|2 N N 0 Hot Shutdown |0 Hot Shutdown |
| | |
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EVENT TEXT
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| FITNESS FOR DUTY |
| |
| A contract employee was determined to be under the influence of marijuana |
| during a monitor result drug test. The employee's access to the plant has |
| been permanently terminated. Contact the HOO for additional details. |
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|Power Reactor |Event Number: 39797 |
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| FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 04/25/2003|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 10:24[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 03/29/2003|
+------------------------------------------------+EVENT TIME: 01:14[CDT]|
| NRC NOTIFIED BY: COY L. BLAIR |LAST UPDATE DATE: 04/25/2003|
| HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CHUCK CAIN R4 |
|10 CFR SECTION: | |
|AINV 50.73(a)(1) INVALID SPECIF SYSTEM A| |
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+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
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EVENT TEXT
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| 60-DAY OPTIONAL REPORT FOR INVALID SPECIFIED SYSTEM ACTUATION |
| |
| The following information was obtained from the licensee via facsimile: |
| |
| "THIS IS BEING REPORTED PER 10 CFR 50.73(a)(2)(iv)(A). |
| |
| "The following systems inadvertently actuated: |
| |
| "Core Spray A |
| "Core Spray B |
| "#2 Diesel Generator started and came to speed |
| |
| "Core Spray A and B were complete actuations. |
| |
| "#2 Diesel Generator was a partial actuation since it did not load. There |
| was no loss of offsite power or requirement to load. |
| |
| "Affected equipment started and functioned successfully." |
| |
| The cause of the actuation was human error when the operator performing a |
| Reactor Protection System surveillance test mechanically actuated the wrong |
| relay. The reactor was in refueling and flooded-up at the time of the core |
| spray actuation. There was a minor change in skimmer surge tank level |
| before Operations personnel were able to manually isolate core spray. |
| |
| The licensee still has a Significant Condition Report (SCR) open that should |
| address ways to minimize re-occurrence. |
| |
| The licensee will be notifying the NRC Resident Inspector. |
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|Power Reactor |Event Number: 39799 |
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| FACILITY: ROBINSON REGION: 2 |NOTIFICATION DATE: 04/26/2003|
| UNIT: [2] [] [] STATE: SC |NOTIFICATION TIME: 18:23[EDT]|
| RXTYPE: [2] W-3-LP |EVENT DATE: 04/26/2003|
+------------------------------------------------+EVENT TIME: 17:46[EDT]|
| NRC NOTIFIED BY: EAYRES |LAST UPDATE DATE: 04/26/2003|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNUSUAL EVENT |MIKE ERNSTES R2 |
|10 CFR SECTION: |JAMES LYONS NRR |
|AAEC 50.72(a) (1) (i) EMERGENCY DECLARED |MICHELE EVANS IRO |
| |DAN SULLIVAN FEMA |
| |ALTERNATE SITE |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N Y 100 Power Operation |100 Power Operation |
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EVENT TEXT
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| NOUE DECLARED DUE TO FIRE IN THE OWNER PROTECTED AREA LASTING MORE THAN 10 |
| MINS. |
| |
| The licensee declared a NOUE at 1803 due to a fire in the owner protected |
| area on the motor of the "B" circulating water pump at the intake that |
| lasted for more than 10 minutes. There are a total of three pumps and two |
| are now operable. The smoking fire (no flames) was extinguished at 1823 |
| with no assistance from offsite. There were no injuries or damage to the |
| plant. The licensee will not issue a press release. |
| |
| The licensee notified the State of South Carolina, Darling , Lee, and |
| Chesterfield counties. |
| |
| The NRC Resident Inspector was notified. |
| |
| *****UPDATE ON 4/26/03 AT 19:30 FROM EAYRES TO LAURA***** |
| |
| The NOUE was terminated at 19:23. The electrical fire is out and there was |
| no impact on continued plant operation. |
| |
| Notified R2DO (ERNSTES), DIRO (EVANS), NRR (LYONS), NRC ALTERNATE SITE, FEMA |
| (EACHES) |
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|Fuel Cycle Facility |Event Number: 39800 |
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| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/27/2003|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 18:05[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/26/2003|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 22:06[CDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/27/2003|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |MONTE PHILLIPS R3 |
| DOCKET: 0707001 |DANIEL GILLEN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: SKAGGS | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|OSAF 76.120(c)(2) SAFETY EQUIPMENT FAILUR| |
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EVENT TEXT
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| PLANT HAD A SAFETY EQUIPMENT FAILURE |
| |
| At 2208 CST, on 4-26-03 the Plant Shift Superintendent (PSS) was notified |
| that a UF6 Release Detection System smoke detector for the No. 3 Normetex |
| Pump in C-315 had fired. Operators responded and found no indications of a |
| UF6 release. The No. 3 Normetex Pump was in TSR 2.3.1 Mode 4, "Not In Use" |
| at the time the smoke detector alarmed. Operators then attempted to reset |
| the smoke detector and a system trouble alarm was received. The trouble |
| alarm would not reset and attempts to test fire the smoke detectors for the |
| Normetex Pumps was unsuccessful. At the time of this incident, the C-315 |
| No.1 and No. 2 Normetex Pumps were in an operational mode in which the UF6 |
| Release Detection System was required to be operable, TSR 2.3.4.3 Mode 2, |
| "Withdrawal". The PSS declared the system inoperable and TSR LCO 2.3.4.3 |
| actions were implemented to establish a smoke watch and place the Normetex |
| pumps in Mode 3, "Standby". The failed smoke detector was replaced, post |
| maintenance testing completed and the system was declared operable at 0053 |
| CST on 4-27-03. |
| |
| The event is reportable as a 24 hour event, as required by 10 CFR |
| 76.120(c)(2)(l); "An event in which equipment is disabled or fails to |
| function as designed when the equipment is required by a TSR to prevent |
| releases, prevent exposures to radiation and radioactive materials exceeding |
| specified limits, mitigate the consequences of an accident, or restore this |
| facility to a pre-established safe condition after an accident." The |
| equipment was required by TSR to be available and operable and no redundant |
| equipment was available to perform the required safety function. |
| |
| The NRC Resident Inspector has been notified of this event. |
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