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Report for May 13, 2002
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/10/2002 - 05/13/2002 ** EVENT NUMBERS ** 38912 38915 38916 +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38912 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 05/10/2002| | UNIT: [3] [] [] STATE: LA |NOTIFICATION TIME: 14:20[EDT]| | RXTYPE: [3] CE |EVENT DATE: 05/09/2002| +------------------------------------------------+EVENT TIME: 14:30[CDT]| | NRC NOTIFIED BY: RONALD WILLIAMS |LAST UPDATE DATE: 05/10/2002| | HQ OPS OFFICER: RICH LAURA +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |MARK SHAFFER R4 | |10 CFR SECTION: | | |NONR OTHER UNSPEC REQMNT | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |3 N Y 100 Power Operation |100 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSE CONDITION VIOLATION OF THERMAL POWER AT WATERFORD 3 | | | | "During initial installation of the LEFM Check-Plus ultrasonic feedwater | | flow measuring system installed as part of the Appendix K Power Uprate | | Project at Waterford 3, it was noted that the three available reactor core | | calorimetric thermal power indications calculated by the Core Operating | | Limits Supervisory System (COLSS) were not in agreement. This disagreement | | was noted on 4/20/02. These thermal power indications consist of: Main | | Steam venturi Secondary Calorimetric (MSBSCAL), Feedwater Flow venturi | | Secondary Calorimetric (FWBSCAL) and the Calorimetric indication generated | | by the newly installed LEEM Check-Plus ultrasonic flow measuring system | | (USBSCAL). The LEFM Check-Plus ultrasonic flow measuring system was | | certified for use on May 9, 2002. | | | | "Preliminary information indicates the mismatch in indication is likely the | | result of biases factored into the MSBSCAL indication as well as possible | | degradation of the secondary side of the plant over time since August 1997. | | These biases, based on the most accurate USBSCAL indication, are | | approximately 0.22% power beyond the accepted power measurement uncertainty | | of 1.68% power for the MSBSCAL. indication. Thus, Waterford 3 may have | | operated at average power levels in excess of the 100% licensed power limit | | since approximately August 1997. | | | | "Waterford 3 is currently in Mode 1 at 99.9% power using FWBSCAL, the most | | conservative indication of reactor power. This report is being made per | | Waterford 3 License Condition 2.F for potential violation of License | | Condition 2.C.1, "Maximum Power Level." The investigation for this condition | | is ongoing". | | | | The NRC resident inspector was notified. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38915 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 05/13/2002| | UNIT: [] [2] [] STATE: MI |NOTIFICATION TIME: 02:39[EDT]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/12/2002| +------------------------------------------------+EVENT TIME: 23:01[EDT]| | NRC NOTIFIED BY: BRADDOCK D. LEWIS |LAST UPDATE DATE: 05/13/2002| | HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |ANTON VEGEL R3 | |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 100 Power Operation |0 Hot Standby | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR TRIP DUE TO AN INSTRUMENTATION RACK POWER SUPPLY FAILURE | | WHICH CAUSED A STEAM GENERATOR FEEDWATER REGULATING VALVE TO FAIL CLOSED | | | | The following text is a portion of a facsimile received from the licensee: | | | | "DC Cook Unit 2 tripped from full power due to an instrumentation rack power | | supply failure on 05/12/02 [at] 2301. All control rods fully inserted. No | | Safety Injection was required. The Unit 2 Reactor is stable and | | subcritical. The Steam Generator Stop Valves were manually closed by the | | Operating Crew to stabilize RCS Temperature in accordance with Plant | | operating procedures. Reactor Coolant Temperature is being maintained | | manually on the Steam Generator Atmospheric relief valves at No-Load T(ave) | | in accordance with plant procedures." | | | | "This instrumentation rack power supply failure caused the #21 Steam | | Generator Feed Regulating Valve to fail CLOSED. The Unit 2 Reactor | | subsequently TRIPPED on Low Level in [the] #21 Steam Generator coincident | | with Low Feedwater Flow. Several control systems were affected by the | | control rack instrumentation failure: Pressurizer Pressure Control - | | transferred control to manual and restored Pressurizer pressure, Pressurizer | | Level Control - transferred control to manual and restored Pressurizer water | | level, Refueling Water Sequence - Manually transferred Charging Pump Suction | | to the RWST. Manual Operator response maintained and restored critical | | plant parameters in MANUAL to normal parameter values." | | | | "Unit 2 entered Technical Specification 3.0.3 for 34 minutes because the | | control system failures and plant system response temporarily caused the | | Boration Flow paths from both the Refueling Water Storage Tank and Boric | | Acid Storage Tanks to become INOPERABLE. Both Boration flow paths were | | subsequently returned to OPERABLE status by manual Operator action." | | | | "The Reactor trip is reportable in accordance with 10 CFR 50.72(b)(2)(iv)(B) | | as an actuation of the Reactor Protection System (RPS) when the Reactor was | | critical. The Reactor TRIP was the result of an instrumentation rack power | | supply failure and was not part of any preplanned test or evolution." | | | | The licensee stated that the unit is currently stable in Mode 3 (Hot | | Standby). The reactor coolant pumps are available for primary system | | transport control. Pressurizer level and pressure control are in manual. | | Normal charging and makeup are available, but the automatic function of the | | refueling water sequence is not available. The auxiliary feedwater pumps | | automatically started as expected and are currently being utilized to supply | | water to the steam generators. Secondary steam is being dumped to | | atmosphere. There is no evidence of steam generator tube leakage, and | | containment parameters are as expected. There were no safety injections and | | none were required, and none of the primary power-operated relief valves | | lifted. | | | | The licensee notified the NRC resident inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38916 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 05/13/2002| | UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 03:21[EDT]| | RXTYPE: [1] GE-6 |EVENT DATE: 05/13/2002| +------------------------------------------------+EVENT TIME: 00:16[CDT]| | NRC NOTIFIED BY: TOM CLAY |LAST UPDATE DATE: 05/13/2002| | HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |ANTON VEGEL R3 | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 A/R Y 86 Power Operation |0 Hot Shutdown | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR SCRAM ON HIGH WATER LEVEL DUE TO THE FAILURE OF THE | | STARTUP LEVEL CONTROLLER DURING EXTENDED POWER UPRATE TESTING ON FEEDWATER | | LEVEL CONTROL | | | | The following text is a portion of a facsimile received from the licensee: | | | | "With the reactor at 86% power, extended power uprate testing on feedwater | | level control was in progress. A six-inch level step change from 32" to 38" | | was inputted for testing. Feedwater was being controlled by the startup | | level controller. The startup level controller failed to respond, allowing | | reactor water level to go high and cause a reactor scram on level 8, 52". | | All other systems responded normally." | | | | The licensee stated that all control rods fully inserted due to the | | automatic reactor scram and that the highest reactor water level was 53". | | There were no safety injections or emergency core cooling system actuations, | | and none were required. | | | | The licensee stated that the unit is currently in Hot Shutdown. Normal | | feedwater is being supplied to the reactor vessel for level control, and | | pressure is being controlled via the main steam line drains which go to the | | condenser (the heat sink). The outboard main steam isolation valves were | | manually closed. Containment parameters are normal. | | | | The licensee notified the NRC resident inspector. | +------------------------------------------------------------------------------+