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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  

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|Power Reactor                                    |Event Number:   38912       |
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| 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  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| 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.                                     |
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|Power Reactor                                    |Event Number:   38915       |
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| 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      |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| 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.                            |
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|Power Reactor                                    |Event Number:   38916       |
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| 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.                            |
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