Headquarters Daily report MAY 30, 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 - HEADQUARTERS MAY 30, 1995 MR Number: H-95-0103 NRR DAILY REPORT ITEM GENERIC COMMUNICATIONS BRANCH/EVENTS ASSESSMENT BRANCH DIVISION OF OPERATING REACTOR SUPPORT OFFICE OF NUCLEAR REACTOR REGULATION Subject: N/A NRC Information Notice 95-26, "Defect in Safety-Related Pump Parts due to Inadequate Heat Treatment," to be issued May 31, 1995. The NRC is issuing this information notice to alert addressees to a potential for pump failure as a result of inadequate heat treatment of pump parts. Technical contacts: James A. Davis, NRR (301) 415-2713 Peter C. Wen, NRR (301) 415-2832 NRC Information Notice 95-27, "NRC Review of Nuclear Energy Institute, "Thermo-Lag 330-1 Combustibility Evaluation Methodology Plant Screening Guide," to be issued May 31, 1995. The NRC is issuing this information notice to inform addressees of the results of NRC staff review of the Nuclear Energy Institute (NEI) "Thermo-Lag 330-1 Combustibility Evaluation Methodology Plant Screening Guide." Technical contact: Pat Madden, NRR (301) 415-2854 PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION I MAY 30, 1995 Licensee/Facility: Notification: Consolidated Edison Co. Of N.Y. MR Number: 1-95-0072 Indian Point 2 Date: 05/30/95 Buchanan,New York SRI PC Dockets: 50-247 PWR/W-4-LP Subject: TURBINE DAMAGE Reportable Event Number: N/A Discussion: On May 23 at 5:20 a.m., operators manually tripped the main turbine from 1650 rpm after observing sparks at the #1 oil seal. Operators were in the process of increasing turbine speed to 1800 rpm for initial roll-up when at 1400 rpm, return oil temperature increased to 175 degrees F and an alarm was received in the control room. The high pressure (HP) turbine and bearings were disassembled to assess damage. The damage observed was to the #1 bearing, governor extended shaft, #2 blade ring strip seals, nozzle block strip seals, and oil pump seal ring. The #2 bearing showed signs of overload but was acceptable. The HP turbine blades were slightly discolored but a hardness test showed that there was no damage. The damage was caused by the turbine rotor misalignment when the #1 governor end high pressure turbine bearing failed. The cause of the #1 bearing failure was installation of the upper half of the bearing in the reverse direction. This resulted in the oil port being covered which resulted in no oil flow to the bearing. It was noted that the bearing was not manufactured to drawings in that the dowel alignment pins were not offset. The problem was not identified sooner because, while on the turning gear, bearing lift oil masked the problem. Regional Action: The resident inspectors are monitoring activities. Contact: Lawrence Doerflein (610)337-5378 Gordon Hunegs (914)739-9360 PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION I MAY 30, 1995 Licensee/Facility: Notification: New York Power Authority MR Number: 1-95-0073 Indian Point 3 Date: 05/30/95 Buchanan,New York SRI PC Dockets: 50-286 PWR/W-4-LP Subject: PLANT COOLDOWN AND DEPRESSIZATION FOR MAINTENANCE Reportable Event Number: N/A Discussion: On May 27, 1995, Indian Point 3 commenced a cooldown and depressurization from the normal reactor coolant system (RCS) operating pressure and temperature conditions. On May 29, 1995, the unit was placed in the cold shutdown condition on normal residual heat removal cooling. The unit was returned to the cold shutdown condition to support the replacement of both the inner and outer reactor vessel (RV) flange O-ring seals. To accomplish this work, the unit will be depressurized, RCS level lowered, and the vessel head removed. RV flange seal leakage was noted during the recent plant operation at normal operating pressure and temperature. Initially, RV inner seal leakage was noted soon after plant heatup. It was determined by the licensee that this had been an existing condition from the previous operating cycle. Subsequently, on May 20, 1995, indications of RV flange outer seal leakage were observed in the control room. The licensee was able to quantify this leakage at approximately one one hundredth of a gallon per minute. It should be noted that during the current performance improvement outage, the RV head was not removed since this had not been a refueling outage. In addition to replacing both RV flange o-ring seals, the licensee also plans to perform repairs for certain equipment problems noted during recent plant evolutions. In particular, maintenance will be performed on both pressurizer spray valves to correct body-to-bonnet leakage and both power operated relief valves to address seat leakage. The licensee estimates that all work will be completed and the unit to be returned to normal operating pressure and temperature in approximately three weeks. Regional Action: Routine resident followup. Contact: Curtis Cowgill (610)337-5233 PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION IV MAY 30, 1995 Licensee/Facility: Notification: Omaha Public Power District MR Number: 4-95-0076 Ft Calhoun 1 Date: 05/30/95 Fort Calhoun,Nebraska Phone Call from Senior Res. Insp. Dockets: 50-285 PWR/CE Subject: REACTOR STARTUP FOLLOWING REACTOR COOLANT PUMP OIL COOLER REPAIRS Reportable Event Number: N/A Discussion: On May 29, 1995, at 9:07 a.m. (CDT), the Fort Calhoun Station main electrical generator was synchronized to the grid after an unplanned outage of five days. This outage occurred after the reactor was manually tripped due to component cooling water leaking into a reactor coolant pump lube oil cooler as described in PNO-IV-95-022. The licensee discovered a through wall leak in one tube of the cooler for Reactor Coolant Pump RC-3D. This particular tube had been recently eddy current tested after a similar tube leak required a manual reactor trip on May 11 and subsequent repairs. Eddy current testing of this tube did not show any indications that required plugging at that time. During the outage, which began on May 24, the licensee replaced the lube oil cooler heat exchangers on all four reactor coolant pumps. The licensee is having an independent third party review the previous eddy current testing results and has arranged for laboratory services to perform testing of the tube to determine the cause of failure. Regional Action: For information only. Contact: W. Walker (817)860-8148 Ray Mullikin (402)426-9611