Event Notification Report for March 4, 2003
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/03/2003 - 03/04/2003 ** EVENT NUMBERS ** 39632 39633 39634 +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39632 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 03/03/2003| | UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 14:44[EST]| | RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/03/2003| +------------------------------------------------+EVENT TIME: [EST]| | NRC NOTIFIED BY: JOSEPH E. THOMPSON |LAST UPDATE DATE: 03/03/2003| | HQ OPS OFFICER: ERIC THOMAS +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |MOHAMED SHANBAKY R1 | |10 CFR SECTION: | | |ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |2 A/R Y 25.5 Power Operation |0 Hot Shutdown | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RPS ACTUATION WHILE CRITICAL | | | | "Unit 2 Reactor SCRAM occurred during scheduled down power associated with | | 2R07 activities. The Reactor SCRAM occurred as a result of an RPS actuation | | following a manual turbine trip due to elevated vibration levels. All | | systems actuated as designed. This report is being made pursuant to 50. | | 72(b)(2)(iv)(B) due to the actuation of the Reactor Protection System (RPS). | | Scheduled 2R07 activities continue." | | | | All rods inserted normally. All systems functioned as designed. There was | | nothing unusual or not understood. Decay heat removal method will be to the | | main condenser followed by establishing shutdown cooling with the RHR | | system. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39633 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 03/03/2003| | UNIT: [1] [2] [] STATE: PA |NOTIFICATION TIME: 20:38[EST]| | RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/03/2003| +------------------------------------------------+EVENT TIME: [EST]| | NRC NOTIFIED BY: DONALD ROLAND |LAST UPDATE DATE: 03/03/2003| | HQ OPS OFFICER: GERRY WAIG +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |MOHAMED SHANBAKY R1 | |10 CFR SECTION: | | |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 85 Power Operation |85 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION OF 2 CONTRACT EMPLOYEES REPORTING TO THE SITE WITH | | RADIOACTIVE CONTAMINATION | | | | "Two contract General Electric employees reported to the plant from a | | foreign nuclear power plant with levels of radioactive contamination which | | alarmed the plant's portal monitors while exiting the protected area. The | | radionuclides identified were Co-60 and Mn-54. These 2 personnel had not | | entered the RCA at Susquehanna. Additional follow-up radiological surveys | | are in progress. | | | | "The Resident NRC Inspector and Pennsylvania Department of Environmental | | Protection have been notified. | | | | "A press release is planned once the additional surveys are complete." | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 39634 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: GENERAL ELECTRIC |NOTIFICATION DATE: 03/03/2003| |LICENSEE: GENERAL ELECTRIC |NOTIFICATION TIME: 20:51[EST]| | CITY: San Jose REGION: 4 |EVENT DATE: 03/03/2003| | COUNTY: STATE: CA |EVENT TIME: [PST]| |LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 03/03/2003| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |MOHAMED SHANBAKY R1 | | |WALTER RODGERS R2 | +------------------------------------------------+MONTE PHILLIPS R3 | | NRC NOTIFIED BY: JASON S. POST |DALE POWERS R4 | | HQ OPS OFFICER: ERIC THOMAS |MICHAEL JOHNSON NRR | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PART 21 NOTIFICATION - FUEL CHANNEL BOW | | | | GE Nuclear reports a new phenomenon that causes fuel channel bow. "Shadow | | Corrosion" is the hydrogen-induced growth of the channel wall closest to the | | control blade when the fuel channel is in a highly controlled location | | during its initial fuel cycle. The hydrogen-induced growth leads to channel | | bowing toward the control blade late in life. This condition is believed to | | be most significant for BWR/6 plants. | | | | There are two effects of the new phenomenon: | | 1. It is not accounted for by thermal limit calculations | | 2. The bias towards the control blade can lead to control rod-fuel channel | | interference. | | | | To mitigate the impact on thermal limits, an interim penalty of .02 has been | | applied to the Operating Limit Minimum Critical Power Ratio for all BWR/6's. | | In the long-term, updated channel bow data will be used in the approved fuel | | licensing models and this data will be incorporated into future reload | | licensing analyses. Recommended actions for non-BWR/6 plants are expected | | by June 6, 2003. | | | | Concerns related to the control rod-fuel channel interference include: 1) | | friction that could cause fuel bundle lift, 2) transfer of forces to reactor | | internals causing higher stresses, and 3) slower scram speeds. There have | | been no interim actions designated to mitigate these effects, but | | recommendation for a surveillance to help detect control rod-fuel channel | | interference is expected by April 28, 2003. | | | | Affected plants at present are all BWR/6's. Potentially affected plants are | | all BWR's, with the exception of Columbia Generating Station. | +------------------------------------------------------------------------------+
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Page Last Reviewed/Updated Thursday, March 25, 2021