Headquarters Daily report MARCH 01, 1995 *************************************************************************** REPORT NEGATIVE NO INPUT ATTACHED INPUT RECEIVED RECEIVED HEADQUARTERS X REGION I X REGION II X REGION III X REGION IV X *************************************************************************** PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION III MARCH 1, 1995 Licensee/Facility: Notification: Consumers Power Co. MR Number: 3-95-0023 Big Rock Point 1 Date: 03/01/95 Charlevoix,Michigan Dockets: 50-155 BWR/GE-1 Subject: TWO WIDE RANGE MONITOR CHANNELS CALIBRTED LOW DURING POWER ESCALATION Reportable Event Number: 28437 Discussion: DURING POWER ESCALATION FROM A WEEKEND OUTAGE, THE CONTROL ROOM OPERATORS NOTED A DIVERGENCE BETWEEN THE THREE CHANNELS OF WIDE RANGE NUCLEAR INSTRUMENTATION MONITORS (WRMs). AT BIG ROCK POINT, THE WRMs ARE EXCORE AND LOCATED AT APPROXIMATELY 120 DEGREE RADIALS AROUND THE OUTSIDE PERIMETER OF THE VESSEL. AT 3:15 P.M. ON FEBRUARY 22, 1995, THE DIVERGENCE WAS AS FOLLOWS: WRM1-78 PERCENT, WRM2-68 PERCENT, AND WRM3-82 PERCENT. THIS DIVERGENCE WAS EXPECTED BY THE NUCLEAR ENGINEERING STAFF, WITH WRM1 AND WRM3 EXPECTED TO READ ABOVE ACTUAL POWER AT THIS ROD PATTERN; HOWEVER, THE OPERATORS WERE NOT AWARE OF THE MAGNITUDE OF DIVERGENCE TO BE EXPECTED, AND DECIDED TO PERFORM A HEAT BALANCE AND RECALIBRATE THE WRMS. THE HEAT BALANCE RESULTED IN ALL MONITORS BEING SET TO 63 PERCENT POWER. DURING SHIFT TURNOVER, THE ONCOMING CREW WAS INFORMED OF THE RECALIBRATION, BUT NOT INFORMED OF ITS POTENTIAL EFFECT TO CAUSE THE READINGS TO AGAIN DIVERGE AT HIGHER POWER LEVELS. THE ONCOMING CREWS CONTINUED WITH THE STARTUP AND AT 7:00 A.M. THE FOLLOWING DAY, NOTED A SIGNIFICANT DIVERGENCE AGAIN, WITH WRM1 AT 85 PERCENT POWER, WRM2 AT 97 PERCENT POWER, AND WRM3 AT 83 PERCENT POWER. THE CREW PERFORMED ANOTHER HEAT BALANCE, WHICH INDICATED THE PLANT WAS AT 97 PERCENT POWER. THE OPERATORS CONTACTED I&C AND THE WRMs WERE SET TO 97 PERCENT POWER. AT 1:00 P.M. ON FEBRUARY 24, 1995, REACTOR ENGINEERING DETERMINED THAT AS A RESULT OF RECALIBRATING WRMs 1 AND 3 ON THE 22ND, THEY WOULD NOT HAVE TRIPPED UNLESS POWER HAD EXCEEDED 132 PERCENT AND 137 PERCENT, RESPECTIVELY. THE HIGH POWER TRIP SETPOINT IS REQUIRED TO BE AT 120 plus/minus 5 PERCENT. SINCE THE TRIP LOGIC IS 2 OUT OF 3, NO TRIP COULD HAVE OCCURRED UNTIL 132 PERCENT. ALTHOUGH A REACTOR TRIP ON HIGH PRESSURE WOULD STILL HAVE OCCURRED, THE TRIP FOR HIGH RATE OF CHANGE OF FLUX IS AUTOMATICALLY BYPASSED ABOVE 87 PERCENT POWER. THE LICENSEE CONCLUDED THAT THE CONDITION WAS OUTSIDE THE DESIGN BASIS AT 6:00 P.M. ON FEBRUARY 24, 1995, AND NOTIFIED THE NRC SHORTLY THEREAFTER. THE LICENSEE HAS INITIATED A ROOT CAUSE INVESTIGATION, INCLUDING UTILIZATION OF HUMAN PERFORMANCE EVALUATION SYSTEM (HPES) TECHNIQUES, AND AN EVALUATION TO DETERMINE WHETHER ANY CONCLUSIONS FROM THE FINAL SAFETY HAZARDS REPORT REGARDING ANALYZED ACCIDENTS COULD HAVE BEEN AFFECTED AS A RESULT OF THE HIGHER THAN EXPECTED TRIP POINT. Regional Action: THE RESIDENTS WILL EVALUATE THE LICENSEE'S FOLLOWUP ACTIONS AND WILL REVIEW THE EVENT FOR POSSIBLE ENFORCEMENT ACTION. Contact: M.P. PHILLIPS (708)829-9637 PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION III MARCH 1, 1995 Licensee/Facility: Notification: Illinois Power Co. MR Number: 3-95-0024 Clinton 1 Date: 03/01/95 Clinton,Illinois LAN Dockets: 50-461 BWR/GE-6 Subject: NOUE DUE TO A FIRE IN THE "A" REACTOR FEEDWATER PUMP ROOM EVENT NUMBER 28459 Reportable Event Number: N/A Discussion: This is a clarification to event notification 28459. At 11:30 a.m. on February 28, 1995, the "B" reactor feedpump tripped due to unknown causes. The reactor recirculation flow control valves ramped closed to minimum as designed. Reactor power stabilized at approximately 58 percent. On March 1, 1995, due to load requirements, the licensee increased power to 75 percent on the remaining turbine driven reactor feedpump. At 3:35 a.m., following the load increase, a plant operator discovered the fire. The licensee reduced power to 62 percent and stated that they do not plan on increasing power until the "B" feed pump is returned to service. Regional Action: The resident inspectors will continue to monitor the licensee's actions. Contact: B. CLAYTON (708)829-9602