Headquarters Daily Report MARCH 17, 1997 *************************************************************************** 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 MARCH 17, 1997 MR Number: H-97-0022 NRR DAILY REPORT ITEM GENERIC COMMUNICATIONS NRC Information Notice 97-10, "Liner Plate Corrosion in Concrete Containments," dated March 13, 1997. The NRC is issuing this information notice to alert addressees to occurrences of corrosion in the liner plates of reinforced and pre-stressed concrete containments, and to detrimental effects such corrosion could have on containment reliability and availability under design-basis and beyond-design-basis events. Technical contacts: Hans Ashar, NRR (301) 415-2851 R. A. Benedict, NRR (301) 415-1157 NRC Information Notice 97-09, "Inadequate Main Steam Safety Valve (MSSV) Setpoints and Performance Issues Associated with Long MSSV Inlet Piping," dated March 12, 1997. The NRC is issuing this information notice to alert licensees to the recent staff findings related to improper main steam safety valve (MSSV) setpoints and MSSV performance issues associated with long inlet piping. Technical contacts: Christopher P. Jackson, NRR (301) 415-2947 Charles G. Hammer, NRR (301) 415-2791 Eric J. Benner, NRR (301) 415-1171 NRC Information Notice 97-08, "Potential Failures of General Electric Magne-Blast Circuit Breaker Subcomponents," dated March 12, 1997. The NRC is issuing this information notice to alert addressees to potential failures of six subcomponents in General Electric type AM or AMH 4.16-kV circuit breakers that can render the breakers inoperable. Technical contacts: Kamalaka Naidu, NRR (301) 415-2980 Stephen Alexander, NRR (301) 415-2995 HEADQUARTERS MORNING REPORT PAGE 2 MARCH 17, 1997 MR Number: H-97-0022 (cont.) David Skeen, NRR (301) 415-1174 _ REGION I MORNING REPORT PAGE 2 MARCH 17, 1997 Licensee/Facility: Notification: Gpu Nuclear Corp. MR Number: 1-97-0022 Three Mile Island 1 Date: 03/17/97 Middletown,Pennsylvania Dockets: 50-289 PWR/B&W-L-LP Subject: THREE MILE ISLAND MANAGEMENT CHANGES Discussion: GPU Nuclear Corporation announced that Mr. James W. Langenbach has assumed the duties of Site Director and Vice President, Three Mile Island Nuclear Station, effective March 17, 1997. Mr. Langenbach was formerly the Director, Materials and Services, at the GPU Nuclear corporate office in Parsippany, NJ. Previously, he held the positions of Outage Director at Oyster Creek, Engineering Projects Director at TMI Unit 1, and Manager of Special Projects in Parsippany. Regional Action: The resident inspectors have been briefed on this management change. The licensee plans to issue a press release later this week. Contact: Michele Evans (717)948-1165 Peter W. Eselgroth (610)337-5234 _ REGION III MORNING REPORT PAGE 3 MARCH 17, 1997 Licensee/Facility: Notification: Commonwealth Edison Co. MR Number: 3-97-0043 Byron 2 Date: 03/17/97 Byron,Illinois RI VIA TELECON Dockets: 50-455 PWR/W-4-LP Subject: PLANNED SHUTDOWN AND SPECIAL MAINTENANCE OUTAGE Discussion: AT APPROXIMATELY 11:45 P.M. (CST) ON MARCH 14, 1997, THE LICENSEE COMMENCED A 4 TO 5-DAY MAINTENANCE OUTAGE BY CONDUCTING A NORMAL SHUTDOWN TO JUST AFTER THE MAIN TURBINE-GENERATOR WAS TAKEN OFF THE GRID. THE REACTOR WAS THEN MANUALLY SCRAMMED TO VERIFY THAT ALL OF THE CONTROL RODS SETTLED TO THE BOTTOM POSITION. THE PRIMARY PURPOSE OF THE OUTAGE WAS TO REPAIR A STEAM/WATER LEAK ON A SLUDGE LANCING PORT ON THE SECONDARY SIDE OF THE 2A STEAM GENERATOR, REPAIR A SMALL LEAK ON CV202 (MANUAL BYPASS FOR THE REACTOR COOLANT PUMP SEAL WATER FLOW CONTROL VALVE), REPLACE MAIN FEEDWATER PUMP GLAND SEAL WATER PIPING (THIS PREVIOUSLY FAILED ON UNIT 1), AND OPEN AND INSPECT THE CONTAINMENT FLOOR DRAIN SUMP(RF008). THE LEAK RATES ON THE 2A STEAM GENERATOR AND CV202 WERE OF THE ORDER OF 0.5 GPM OR LESS AND NEITHER COULD BE TEMPORARILY REPAIRED WITH A SEALANT INJECTION TECHNIQUE. THEREFORE, THE LICENSEE CHOSE SHUTTING DOWN AND COOLING DOWN TO MODE 4 IN ORDER TO CONDUCT REPAIRS. Regional Action: A RESIDENT INSPECTOR OBSERVED PORTIONS OF THE SHUTDOWN AND THE RESIDENT INSPECTORS AND A REGIONAL PROJECT ENGINEER ARE MONITORING OUTAGE ACTIVITIES. Contact: R.D. LANKSBURY (630)829-9631 _ REGION III MORNING REPORT PAGE 4 MARCH 17, 1997 Licensee/Facility: Notification: Indiana MR Number: 3-97-0044 Cook 1 Date: 03/17/97 Bridgman,Michigan SRI PHONE CALL TO BRANCH CHIEF Dockets: 50-315 PWR/W-4-LP Subject: DISCOVERY OF SIGNIFICANT AMOUNTS OF DEBRIS ON THE CORE PLATE Discussion: During the core offload for Unit 1, the licensee elected to inspect the bottom nozzles of fuel assemblies using cameras. Camera inspections of fuel assemblies removed from the reactor vessel identified debris stuck to the bottom nozzle of three fuel assemblies. Following core offload the licensee performed a routine bottom core plate inspection and identified significant amounts of debris. The debris was identified by the licensee as failed spiral wound gasket material used in several residual heat removal and primary coolant system valves. The gasket material is steel and can cause damage to the fuel due to fretting. The debris has the potential to be located in several primary system locations, including the pressurizer, the reactor coolant system, the refueling water storage tank, the suction to the ECCS pumps. The licensee is preparing a plan to search for and remove the gasket material. The root cause for the gasket material failure and number of gasket failures is presently unknown. Regional Action: The residents will continue to follow the licensee's corrective actions. Contact: BRUCE BURGESS (630)829-9629 BRUCE BARTLETT (616)465-6775 _ REGION III MORNING REPORT PAGE 5 MARCH 17, 1997 Licensee/Facility: Notification: Michigan Electric Co. MR Number: 3-97-0045 Cook 2 Date: 03/17/97 Bridgman,Michigan SRI PHONE CALL TO BRANCH CHEIF Dockets: 50-316 PWR/W-4-LP Subject: DISCOVERY OF SIGNIFICANT AMOUNTS OF DEBRIS ON THE CORE PLATE Discussion: During the core offload for Unit 1, the licensee elected to inspect the bottom ozzles of fuel assemblies using cameras. Camera inspections of fuel assemblies removed rom the reactor vessel identified debris stuck to the bottom nozzle of three fuel ssemblies. Following core offload the licensee performed a routine bottom core plate nspection and identified significant amounts of debris. The debris was identified by the icensee as failed spiral wound gasket material used in several residual heat removal and rimary coolant system valves. The gasket material is steel and can cause damage to the fuel due to fretting. The debris as the potential to be located in several primary system locations, including the ressurizer, the reactor coolant system, the refueling water storage tank, the suction to the CCS pumps. The licensee is preparing a plan to search for and remove the gasket material. The root ause for the gasket material failure and number of gasket failures is presently unknown. Regional Action: The residents will continue to follow the licensee's corrective actions. Contact: BRUCE BURGESS (630)829-9629 BRUCE BARTLETT (616)465-6775 _