Headquarters Daily report JANUARY 03, 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 JANUARY 3, 1995 Licensee/Facility: Notification: Michigan Electric Co. MR Number: 3-95-0001 Cook 2 Date: 01/03/95 Bridgman,Michigan TELECON FROM RESIDENT'S OFFICE Dockets: 50-316 PWR/W-4-LP Subject: THROUGH BODY LEAK ON FEEDWATER ISOLATION VALVE Reportable Event Number: N/A Discussion: On morning of December 29, 1994, with Unit 2 in Mode 1, the licensee discovered a small through body leak on gate valve FMO-203, a feedwater isolation valve for Steam Generator #3. Maintenance personnel peened the valve and stopped the leak. The leak was located on the bottom of the valve body on the steam generator side of the valve's disk. Ultrasonic examination (UT) of the valve at about 31 locations around the leak indicated no general erosion or degradation of the valve body. The valve body wall thickness was determined to be approximately 2.5 inches. The leaking valve is not a containment isolation valve as specified in the Technical Specifications and FSAR. There is a check valve downstream of FMO-203 outside of containment that is disassembled and inspected per the licensee's Inservice Testing Program (IST) every fourth refueling outage. The last time this check valve was inspected per the IST program was in 1990. The licensee has valve FMO-203 under surveillance and is evaluating options to repair the valve. The licensee is keeping NRC Region III and NRR informed of the status of the valve and any maintenance decisions regarding repair of the valve. Regional Action: The resident inspectors will inform Region III and NRR of any FMO-203 status changes. Contact: WAYNE KROPP (708)829-9633 PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION IV JANUARY 3, 1995 Licensee/Facility: Notification: Entergy Operations, Inc. MR Number: 4-95-0001 Arkansas Nuclear 1 Date: 01/03/95 Russelville,Arkansas Resident Inspector Dockets: 50-313 PWR/B&W-L-LP Subject: LOSS OF RCP AND 3 LOOP OPERATION Reportable Event Number: N/A Discussion: At 9:16 p.m. on January 1, 1995, a "Reactor Coolant Pump (RCP) Vibration Hi" annunciator alarmed. Operators found that the RCP B alarm and danger lights locked in. Further, the "Motor Upper" and "Motor Lower" vibration annunciators cycled into alarm and danger. The operators checked the bearing temperatures and found the thrust bearing upper and the radial bearing temperatures indicated off scale high, greater than 200 degrees F. Operators reduced power at 9:22 p.m., reached 60 percent power by 9:30 p.m., and secured RCP B at 9:35 p.m. System Engineering reviewed printouts from the RCP vibration monitoring and the loose parts monitoring system. While the data was not conclusive, the engineers concluded that a bearing was destroyed. All systems responded as expected for this event with one minor exception. The RCP temperature recorder failed to cause an annunciator to alarm at 180 degrees F as expected. The temperature indications from the recorder tracked properly. The licensee is investigating why the annunciator did not alarm. Operators raised the plant power to 72.5 percent power and reduced the nuclear instrumentation trip setpoint to 77.5 percent power. The licensee intends to operate with three pumps until February 14, 1995, when their next refueling outage starts. Regional Action: Resident Inspectors will continue to monitor licensee activities. Contact: Greg Pick (817)860-8270