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BRUNSWICK-1 - RCS LEAKAGE ROSE FROM 0.63 GPM TO 2.69 GPM, PROMPTING SHUTDOWN
BRUNSWICK-1 NOTIFICATION DATE: 06/30/2003
TECH SPEC REQUIRED SHUTDOWN
On June 30, 2003, at 1710 EDT, Unit 1 reactor power was decreased, initiating a reactor shutdown required by Technical Specification (TS) Limiting Condition for Operation (LCO) 3.4.4 due to Reactor Coolant System (RCS) operational leakage exceeding a TS LCO limit. At 0615 hours, TS LCO 3.4.4 was entered due to an increase in unidentified leakage of greater than 2 gpm (gallons per minute) within the previous 24 hour period. Leakage increased from 0.63 gpm on June 29, 2003 at 2000 EDT, to 2.69 gpm on June 30, 2003 at 0615 EDT. Required Actions from LCO 3.4.4 are to reduce leakage to within TS limits within 8 hours or be in Mode 3 (Hot Shutdown) in 12 hours and Mode 4 (Cold Shutdown) in 36 hours. As of 1700 EDT, leakage could not be reduced to exit the TS LCO Condition.
The licensee notified the NRC Resident Inspector.
+------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39968 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 06/30/2003| | UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 17:30[EDT]| | RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/30/2003| +------------------------------------------------+EVENT TIME: 17:10[EDT]| | NRC NOTIFIED BY: D. W. BAIN |LAST UPDATE DATE: 06/30/2003| | HQ OPS OFFICER: ERIC THOMAS +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |CHARLES R. OGLE R2 | |10 CFR SECTION: | | |ASHU 50.72(b)(2)(i) PLANT S/D REQD BY TS | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 93 Power Operation |92 Power Operation | | | | +------------------------------------------------------------------------------+
Source: The above is excerpted from
NRC Operations Center,
Event Notification Report for July 1, 2003