Event Notification Report for April 1, 2003
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/31/2003 - 04/01/2003
** EVENT NUMBERS **
39631 39645 39696 39706 39707 39708 39715 39716
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39631 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 03/02/2003|
| UNIT: [1] [2] [] STATE: FL |NOTIFICATION TIME: 16:00[EST]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 03/02/2003|
+------------------------------------------------+EVENT TIME: 14:30[EST]|
| NRC NOTIFIED BY: CHARLES PIKE |LAST UPDATE DATE: 03/31/2003|
| HQ OPS OFFICER: GERRY WAIG +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |WALTER RODGERS R2 |
|10 CFR SECTION: |DAVID AYRES R2 |
|APRE 50.72(b)(2)(xi) 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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO STATE AGENCY OF EXPIRED GREEN SEA TURTLE FOUND AT |
| BARRIER NET |
| |
| "NRC notification [is] being made due to state notification to [the] Florida |
| Wildlife Commission regarding a Green Sea Turtle found dead at barrier net |
| pursuant to 10 CFR 50.72(b)(2)(xi)." |
| |
| The turtle was found on the surface at the barrier net with no injuries or |
| abnormalities except for fresh cuts common for turtles coming through pipes. |
| The cause of death is unknown at this time. A necropsy is planned. |
| |
| The NRC Resident Inspector will be notified by the licensee. |
| |
| * * * UPDATE ON 3/15/03 @ 1033 EST FROM TEREZAKIS TO CROUCH * * * |
| |
| "On 3-15-03, a green sea turtle was retrieved from the plant's intake canal. |
| The turtle was determined to be in need of rehabilitation. The injuries to |
| the turtle are not causal to plant operation. Per the plant's turtle permit, |
| the Florida Fish and Wildlife Conservation Commission (FWCC) was notified at |
| 0920 EST. This non-emergency notification is being made pursuant to 10 CFR |
| 50.72(b)(2)(xi) due to the notification of FWCC." |
| |
| The NRC Resident Inspector will be notified by the licensee. |
| |
| * * * UPDATE ON 3/19/03 AT 1222 EST FROM E. SUMNER TO RIPLEY * * * |
| |
| "On 03/19/03 @ 1105 hrs., one loggerhead turtle was retrieved from the |
| plant's intake canal. The turtle was determined to be in need of |
| rehabilitation. The injury to the turtle is not causal to plant operation. |
| Per the plant's turtle permit, the Florida Fish and Wildlife Conservation |
| Commission (FWCC) was notified at 1115 EST." |
| |
| The NRC Resident Inspector was notified. |
| |
| * * * UPDATED ON 3/31/03 AT 1159 EST FROM W.L. PARK TO A. COSTA * * * |
| |
| "On 3-31-03 [1105 EST], a loggerhead sea turtle was retrieved from the |
| plant's intake canal. The turtle was determined to be in need of |
| rehabilitation. The injuries to the turtle are not causal to plant |
| operation. Per the plant's turtle permit, the Florida Fish and Wildlife |
| Conservation Commission (FWCC) was notified at 1105 EST. This non-emergency |
| notification is being made pursuant to 10 CFR 50.72(b)(2)(xi) due to the |
| notification of FWCC." |
| |
| The NRC Resident Inspector will be notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39645 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 03/07/2003|
| UNIT: [] [2] [] STATE: CT |NOTIFICATION TIME: 21:32[EST]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 03/07/2003|
+------------------------------------------------+EVENT TIME: 20:49[EST]|
| NRC NOTIFIED BY: ROBERT WHITE |LAST UPDATE DATE: 03/31/2003|
| HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNUSUAL EVENT |MOHAMED SHANBAKY R1 |
|10 CFR SECTION: |JOSEPH HOLONICH IRO |
|AAEC 50.72(a) (1) (i) EMERGENCY DECLARED |CHRISTOPHER GRIMES NRR |
|ASHU 50.72(b)(2)(i) PLANT S/D REQD BY TS |FEMA WATCH OFFICER FEMA |
|AINA 50.72(b)(3)(v)(A) POT UNABLE TO SAFE SD | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Hot Standby |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNUSUAL EVENT DECLARED DUE TO INABILITY TO REACH HOT SHUTDOWN WITHIN TECH |
| SPEC ACTION STATEMENT TIME LIMIT |
| |
| The licensee declared an unusual event at 2049 EST due to the inability to |
| reach Mode 4 within the Technical Specification action statement time limit |
| of 2049 EST for charging pumps inoperable. The charging pumps were declared |
| inoperable as a result of system complications associated with the reactor |
| trip and charging system leakage occurring at 1439 EST 3/7/03 (see Event # |
| 39644). |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| * * * UPDATE 0420EST ON 3/8/03 FROM ROBERT MALONEY TO S.SANDIN * * * |
| The licensee terminated the Unusual Event at 0146EST after Unit 2 entered |
| mode 4. The licensee informed state/local agencies and the NRC resident |
| inspector. Notified R1DO(Shanbaky), EO(Grimes) and FEMA(Stinedurf). |
| |
| * * * UPDATE 0944EST ON 3/31/03 FROM STEPHEN BAKER TO S. SANDIN * * * |
| |
| The following information was submitted as an update: |
| |
| "On March 7, 2003, Millstone Unit No. 2 made a 1-hour report of an Unusual |
| Event declared due to an inability to reach hot shutdown within Tech Spec |
| action statement time limit (Event no. 39645). This notification was made |
| because the required Mode was not reached within the required Tech Spec |
| action time. Three charging pumps were declared inoperable resulting in an |
| entry into TS 3.0.3. The appropriate Mode could not be reached within the |
| time prescribed by the TS due to the inability of the charging system to |
| supply adequate makeup to the RCS through the normal flow path. An alternate |
| alignment was established via HPSI, The limited rate of makeup via this |
| alternate path prevented the plant from reaching Mode 4 within the allowed |
| outage time. |
| |
| "The criteria for deviation from plant Tech Specs was inappropriately |
| checked off as it was interpreted to mean a violation of plant Tech Specs. |
| Criterion 10CFR50.72(b)(1) 'deviation from the plant's Tech Specs pursuant |
| to � 50.54(x)' did not apply. |
| |
| "Additionally, criterion 10CFR50.72(b)(3)(v)(A), loss of safety function, |
| did apply and this event should have been reported under this criterion |
| since three charging pumps were declared inoperable." |
| |
| The licensee will inform the NRC resident inspector. Notified R1DO |
| (Bellamy). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 39696 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/25/2003|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 01:15[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/24/2003|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 00:30[CST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/31/2003|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |MICHAEL PARKER R3 |
| DOCKET: 0707001 |LARRY CAMPER NMSS |
+------------------------------------------------+JOHN JOLICOEUR IRO |
| NRC NOTIFIED BY: TOM WHITE | |
| HQ OPS OFFICER: ERIC THOMAS | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| BULLETIN 91-01 24 HOUR REPORT FOR CRITICALITY CONTROL |
| |
| At 0030 on 3-24-03, the Plant Shift Superintendent (PSS) was notified that |
| nine (9) pallets of process equipment containing less than a safe uranium |
| mass and spaced 2 feet edge to edge were discovered in C-335. NCSA GEN-010 |
| requires that the total uranium mass of an equipment group be independently |
| verified and documented to be less than or equal to a safe mass based on the |
| highest assay according to CP2-PO-FO1031. No documentation exists to support |
| that the total uranium mass was verified or independently verified according |
| to CP2-PO-FO1031 in violation of NCSA GEN-010. |
| |
| The NRC Senior Resident Inspector has been notified of this event. |
| |
| PGDP Assessment and Tracking Report No. ATR 03-0876; PGDP Event Report No. |
| PAD-2003-006, NRC Event Worksheet [EN 39696]. |
| |
| Responsible Division: Operations |
| |
| SAFETY SIGNIFICANCE OF EVENTS: |
| |
| Although the total mass of the grouped items was not independently verified |
| to be less than a safe mass, no single pallet contains greater than 35 |
| pounds of uranium. The highest enrichment of any item was 2.0 wt. % 235U. |
| The safe mass for uranium at 2.0 wt. % 235U is approximately 250 pounds. |
| |
| POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(S) OF HOW |
| CRITICALITY COULD OCCUR |
| |
| In order for a criticality to be possible, greater than a safe mass of |
| uranium must be accumulated and then become moderated. |
| |
| CONTROLLED PARAMETERS MASS. MODERATION, GEOMETRY, CONCENTRATION, ETC |
| |
| Double contingency is maintained by implementation of two controls |
| (verification and independent verification) of mass. |
| |
| ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS |
| LIMIT AND % WORST CASE CRITICAL MASS); |
| |
| No single pallet has greater than 35 pounds of uranium and the highest assay |
| of any Item is 2.0 wt. % 235U. The safe mass for this assay is 250 pounds. |
| |
| NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION |
| OF THE FAILURES OR DEFICIENCIES |
| |
| The first leg of double contingency is based on mass. NCSA GEN-010 requires |
| that the total uranium mass of grouped items be verified less than the UH |
| [Uncomplicated Handling] mass limit and documented. No documentation exists |
| that substantiates that this verification was performed; therefore, this |
| control was violated. However, since none of the groups contain greater than |
| a safe mass this parameter was not exceeded. |
| |
| The second leg of double contingency is based on mass. NCSA GEN-010 requires |
| that the total uranium mass of grouped items be independently verified less |
| than the UH mass limit and documented in accordance with CP2-PO-FO1031. No |
| documentation exists that substantiates that this independent verification |
| was performed; therefore, this control was violated. |
| |
| Even though the mass parameter was maintained, double contingency is based |
| on two controls on mass. Since neither control was maintained, double |
| contingency was not maintained. |
| |
| CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLEMENTED: |
| |
| 1. Properly group and document each pallet according to CP2-CO-CN2030. |
| 2. Upon completion of corrective action 1 for each of the 9 pallets, the |
| exclusion zone and postings may be removed. |
| |
| *** UPDATE ON 3/31/03 AT 2137 EST FROM T. WHITE TO A. COSTA *** |
| |
| "As a result of further investigation, four additional palettes of process |
| equipment containing less than a safe mass were discovered in C-335 at Col |
| W-26 to W-27 (the original event was in C-335 Col D-2 to D-3). These |
| additional pallets exist in the same state as the original nine. No |
| documentation exists to support that the total uranium mass was verified or |
| independently verified according to CP2-PO-FO1031 in violation of NCSA |
| GEN-010. |
| |
| "The NRC Resident Inspector has been notified of this update. |
| |
| "PGDP Assessment and Tracking Report No. ATR 03-0943." |
| |
| Notified R3DO (Clayton), NMSS EO (Frant) and DIRO (Jolicoeur). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39706 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: ILLINOIS DEPT OF NUCLEAR SAFETY |NOTIFICATION DATE: 03/27/2003|
|LICENSEE: SOURCE TECH MEDICAL |NOTIFICATION TIME: 16:22[EST]|
| CITY: SCHAUMBERG REGION: 3 |EVENT DATE: 03/26/2003|
| COUNTY: STATE: IL |EVENT TIME: 15:00[CST]|
|LICENSE#: IL-02062-01 AGREEMENT: Y |LAST UPDATE DATE: 03/27/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MICHAEL PARKER R3 |
| |RUDOLPH BERNHARD R2 |
+------------------------------------------------+E. WILLIAM BRACH NMSS |
| NRC NOTIFIED BY: JOE KLINGER (E-MAIL) | |
| HQ OPS OFFICER: HOWIE CROUCH | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - LOST OR STOLEN IODINE SOURCES |
| |
| The following information was received via e-mail from the Illinois |
| Department of Nuclear Safety: |
| |
| "[DELETED], RSO of SourceTech Medical [(DELETED)] in Carol Stream, IL called |
| at 1500 hours on March 26, 2003, to report that he had received a shipment |
| of returned I-125 seeds. The dose rate on the surface of the package was 9 |
| [millirem/hr] instead of the expected dose rate of less than 0.5 |
| [millirem/hr]. Upon opening the box, 2 loose sources were found on top of |
| the packing material. 7 sources were noted in the shipping papers. An |
| additional source was found in a partially loaded Mick applicator but there |
| were no sources in the second Mick applicator. A total of only 3 sources |
| were found after looking through the other two lead containers in the |
| package. |
| |
| "Based on assay of the three seeds, the 4 missing seeds are 425 [microcurie] |
| I-125 each for a total of 1.7 [millicurie]. The contents of the package |
| (Fed Ex tracking no., [DELETED]) were obviously not prepared in accordance |
| with instructions provided by Source Tech in that the lids to the containers |
| were not secured nor were the vials used in the lead containers as the |
| instructions call for. The carrier, Federal Express had been contacted by |
| [DELETED] and the delivery truck surveyed. No sources were located during |
| the survey. According to tracking information, the package had gone from |
| St. Augustine through Jacksonville FL, Atlanta GA, Memphis TN, Chicago, IL |
| and the Schaumburg IL sorting facility prior to delivery in Carol Stream. |
| An inspector was dispatched to the Schaumburg facility at 15:45 to attempt a |
| search of the Schaumburg facility. |
| |
| "The sources were shipped from Slagley Hospital (Florida [DELETED]) in St. |
| Augustine Florida on Monday 3/24/2003. [DELETED] tried contacting the site |
| RSO, [DELETED], this afternoon but was unsuccessful. The department |
| contacted Mr. [DELETED] of the Florida program in their Orlando office and |
| relayed the information available at the time (see above). He indicated |
| that he would attempt a call as well but suspected the hospital staff would |
| be gone given the time of day (16:30) in Fla. On 3/27/03, [DELETED] |
| notified the department that he contacted the Florida licensee and the St. |
| Augustine hospital claimed that they counted twice the seven seeds not used |
| in a patient, placed them in a 'screwed sealed cartridge' then put them in a |
| shipping box for FedEx. The department also informed [DELETED], Ph.D., |
| health physics consultant for FedEx, that there are apparently 4 iodine-125 |
| seeds in FedEx facilities or vehicles somewhere as indicated by the routing |
| in the message below. Jim Lynch of the NRC was also advised of the |
| situation. On 03/26/03, a departmental inspector arrived at the Federal |
| Express Depot located at 1270 Wilkening Road in Schaumburg; [DELETED] and |
| explained the purpose of the visit. The inspector was provided access to |
| the package/truck staging area. Based on the FedEx tracking number, the |
| author was told that the bay used by the vehicle was the same one used in a |
| previous, recent incident involving I-125 seeds. Surveys were performed by |
| the inspector using an Eberline Model PRM-6 ratemeter, serial number 1470, |
| last calibrated on May 16, 2002, with an Eberline Model LEG-1 probe. |
| Background readings were [approximately] 250 - 350 CPM. Areas surveyed |
| included the conveyor belt system, particularly junctions between belts, |
| walkways, and the concrete pad where vehicles park for loading/unloading. |
| Particular attention was paid to the area where the truck was unloaded and |
| the seeds had been found in the previous incident. No seeds were located by |
| the inspector. The department is reviewing the packaging used by |
| SourceTech and the instructions to see if there they can be improved to |
| prevent recurrences. The event was reported to the NRC Operations Center at |
| 1622 hours EST on 3/27/03 and assigned Event No. 39706. A copy of this |
| report was electronically forwarded to the Ops Center as well as the states |
| of FL, GA, TN and NRC Region III." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39707 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: NEW YORK STATE DEPT. OF HEALTH |NOTIFICATION DATE: 03/27/2003|
|LICENSEE: NOT AVAILABLE |NOTIFICATION TIME: 17:40[EST]|
| CITY: REGION: 1 |EVENT DATE: 03/27/2003|
| COUNTY: STATE: NY |EVENT TIME: [EST]|
|LICENSE#: NOT AVAILABLE AGREEMENT: Y |LAST UPDATE DATE: 03/27/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |PAMELA HENDERSON R1 |
| |E. WILLIAM BRACH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ROBERT DANSEREAU (FAX) | |
| HQ OPS OFFICER: HOWIE CROUCH | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - MEDICAL MISADMINISTRATION |
| |
| The following information was received from the New York State Department of |
| Health, Bureau of Environmental Radiation Protection: |
| |
| "This notice is in regard to a medical misadministration involving a Novoste |
| Beta-Cath IVB 3.5F system, Model A1767 with AEAT Model SIC W.2 source train. |
| The event occurred on March 25, 2003. |
| |
| "Two attempts to advance the source train into the delivery catheter were |
| unsuccessful. A third (and final) attempt resulted in the source train |
| becoming stuck in the patient's femoral artery, somewhere in the lower groin |
| area. The sources could not be returned to the base unit. The treatment team |
| then removed the catheter, with the source extended, and placed these items |
| into the emergency bailout box. |
| |
| "The licensee estimated that the patient received an exposure of 250 Rads to |
| an area of the femoral artery in the lower groin area. The oncologist and |
| cardiologist decided not to proceed with IVB treatment of this patient. |
| Hospital staff concluded that the misdirected radiation exposure would not |
| have a significant health effect on the patient. |
| |
| "This event meets the reporting requirements in 10 NYCRR 16. The facility |
| will investigate the circumstances, procedures, training, history of use, |
| etc., and will submit a written report within 7 days. The device, including |
| catheter and hydraulic attachment (syringe) will be sent to the vendor for |
| evaluation." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39708 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: ALABAMA RADIATION CONTROL |NOTIFICATION DATE: 03/27/2003|
|LICENSEE: THOMPSON ENGINEERING AND TESTING, INC|NOTIFICATION TIME: 15:18[EST]|
| CITY: REGION: 2 |EVENT DATE: 03/27/2003|
| COUNTY: STATE: AL |EVENT TIME: [CST]|
|LICENSE#: 694 AGREEMENT: Y |LAST UPDATE DATE: 03/27/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |RUDOLPH BERNHARD R2 |
| |E. WILLIAM BRACH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: DAVID WALTER (FAX) | |
| HQ OPS OFFICER: HOWIE CROUCH | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - LOST TROXLER MOISTURE/DENSITY GAUGE |
| |
| The following information was received from Alabama Office of Radiation |
| Control via facsimile: |
| |
| "The Agency has been notified by Thompson Engineering and Testing, Inc. that |
| a Troxler Model 3440 Gauge (serial #32128) containing a maximum of 9 |
| millicuries of cesium 137 and 44 millicuries of americium 241/beryllium is |
| missing. They have conducted a search of many of their Alabama offices, and |
| have been unable to locate it. Since their records do not show this device |
| being used in some time, it had been in storage, and was not detected as |
| lost until the six month leak test was due. They are continuing to search |
| for the gauge, and will notify this office of their findings." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39715 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 03/31/2003|
| UNIT: [] [2] [] STATE: VA |NOTIFICATION TIME: 15:40[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 03/31/2003|
+------------------------------------------------+EVENT TIME: 12:59[EST]|
| NRC NOTIFIED BY: ROBERT RINK |LAST UPDATE DATE: 03/31/2003|
| HQ OPS OFFICER: ARLON COSTA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |RUDOLPH BERNHARD R2 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 100 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP DUE TO A MAIN FEEDWATER REGULATING VALVE FAILING |
| CLOSED |
| |
| "While Unit 2 was operation at 100% power steady state, 'C' MFRV [Main |
| Feedwater Regulating Valve] failed closed due to a failed driver card at |
| 1259 [EST]. The reactor automatically tripped 13 [thirteen] seconds later |
| due to steam flow greater than feed flow coincident with a low SG [Steam |
| Generator] level in the 'C' SG as expected. This is a 4 [four] hour |
| notification. |
| |
| "All 3 [three] AFW [Auxiliary Feedwater] pumps auto started due to a low-low |
| SG level in 'C' SG as expected. This is an 8 [eight] hour notification. |
| |
| "The unit is stable in Mode 3. Expect to re-start after repairs are made to |
| 'C' MFRV circuitry." |
| |
| All rods inserted normally. All safety and electrical systems operated as |
| designed during and after the reactor trip. There was nothing unusual or |
| not understood. |
| |
| The NRC Resident Inspector has been notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39716 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 03/31/2003|
| UNIT: [1] [2] [] STATE: AL |NOTIFICATION TIME: 18:03[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 03/31/2003|
+------------------------------------------------+EVENT TIME: 16:25[CST]|
| NRC NOTIFIED BY: RICK LULLING |LAST UPDATE DATE: 03/31/2003|
| HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |RUDOLPH BERNHARD R2 |
|10 CFR SECTION: |CATHY HANEY IAT |
|DDDD 73.71(b)(1) SAFEGUARDS REPORTS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOST/MISSING SAFEGUARDS INFORMATION |
| |
| Compensatory measures not required at this time. |
| |
| The licensee will be informing the NRC Resident Inspector. |
| |
| Contact the Headquarters Operations Officer for additional details. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021