Headquarters Daily Report MAY 07, 1996 *************************************************************************** REPORT NEGATIVE NO INPUT ATTACHED INPUT RECEIVED RECEIVED HEADQUARTERS û REGION I û REGION II û REGION III û REGION IV û PRIORITY ATTENTION REQUIRED MORNING REPORT - HEADQUARTERS MAY 7, 1996 MR Number: H-96-0038 NRR DAILY REPORT ITEM GENERIC COMMUNICATIONS NRC Bulletin 96-03, "Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling-Water Reactors," dated May 6, 1996. The NRC is issuing this bulletin to: (1) request addressees to implement appropriate procedural measures and plant modifications to minimize the potential for clogging of emergency core cooling system (ECCS) suppression pool suction strainers by debris generated during a loss-of-coolant accident, and (2) require that addressees report to the NRC whether and to what extent the requested actions will be taken and to notify the NRC when actions associated with this bulletin are complete. Technical contact: Robert Elliott, NRR (301) 415-1397 _ REGION III MORNING REPORT PAGE 2 MAY 7, 1996 Licensee/Facility: Notification: Commonwealth Edison Co. MR Number: 3-96-0052 La Salle 1 Date: 05/06/96 Marseilles,Illinois RI VIA TELCON Dockets: 50-373 BWR/GE-5 Subject: UNIT 1 STARTUP FROM REFUELING OUTAGE L1R07 Discussion: LaSalle Unit 1 was paralleled to the grid at 11:06 p.m. on May 6, 1996, ending its seventh refueling outage. The outage was scheduled for 70 days but lasted 103 days. A previous attempt to start up the unit on April 16 was unsuccessful when the turbine could not achieve rated speed. Due to electro- hydraulic control (EHC) calibration problems, speed was limited to 1750 rpm. The unit was shutdown and the problems addressed. The unit was again started up on April 22; however, a resin intrusion from the reactor water cleanup (RWCU) system occurred and startup was delayed by reactor water chemistry conditions. The unit is presently at approximately 15 percent power with startup testing ongoing. Major activities during this refueling outage included: core shroud inspections, suppression pool cleaning, replacement of the 1B reactor recirculation (RR) pump impeller and shaft, chemical cleaning of RR and RWCU, main generator inspections, and valve testing. Two significant improvements were made with regard to materiel condition. The first involved upgrading the turbine building ventilation system such that the building pressure will remain negative in accordance with the FSAR. The second improvement addressed a major operator work around on the leakage detection system. Setpoint changes were made to the main steam tunnel high temperature isolation signals. In addition, a key lock switch was installed rather than requiring the operators to install jumpers. Regional Action: The resident inspectors are providing coverage of the Unit 1 restart activities. Contact: BRENT CLAYTON (708)829-9602 MARY MCCORMICK-BARGR (708)829-9619 _ REGION IV MORNING REPORT PAGE 3 MAY 7, 1996 Licensee/Facility: Notification: Texas Utilities Electric Co. MR Number: 4-96-0044 Comanche Peak 2 Date: 05/07/96 Glen Rose,Texas Dockets: 50-446 PWR/W-4-LP Subject: STARTUP FOLLOWING REFUELING OUTAGE Discussion: Following its second refueling outage, Unit 2 went critical at 9:46 p.m. on May 5, 1996, and synchronized to the grid at 8:31 a.m. on May 7, 1996. The outage began on February 23, 1996, and ended after 74 days. The outage duration was extended beyond the planned schedule due to various equipment problems, including three stuck reactor vessel head studs and an unplanned replacement of a failed reactor coolant pump motor. In addition to normal refueling maintenance activities, the licensee performed a major inspection of the high pressure turbine and a 40-month reactor pressure vessel hot leg nozzle exam. During the outage, the licensee installed temporary diesels in order to minimize risk during shutdown. They also made several permanent modifications to improve reliability, including a digital speed control system for the main feedwater pumps, replacement of the solid state protection system circuit cards, an overhaul on the safety and nonsafety-related inverters, and a reactor protection system bypass modification. The licensee anticipates reaching 100 percent power on May 12, 1996. Regional Action: The residents will continue to follow the licensee actions. Contact: Vonna Ordaz-Purkey (817)897-1500 Ron A. Kopriva (817)860-8104 Linda J. Smith (817)860-8193 _