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
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|Power Reactor |Event Number: 39632 |
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| 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 |
| | |
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EVENT TEXT
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| 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. |
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|Power Reactor |Event Number: 39633 |
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| 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
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| 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." |
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|General Information or Other |Event Number: 39634 |
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| 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 | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 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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