Headquarters Daily Report MARCH 31, 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 31, 1997 Licensee/Facility: Notification: Part 21 Database MR Number: H-97-0031 Borg-Warner (Bw/Ip) Date: 03/31/97 Subject: Part 21 - In electrohydraulic actuator model number 88500, fluid temperature may exceed manufacturer recommendations Discussion: VENDOR: Borg-Warner (BW/IP) PT21 FILE NO: 97250 DATE OF DOCUMENT: 03/21/97 ACCESSION NUMBER: SOURCE DOCUMENT: EN 31994 REVIEWER: PECB, E. Benner NEW ISSUE. Enertech reports that this model actuator may not operate on demand. It is suspected that hydraulic fluid temperature inside the plunger of the solenoid valve exceeded manufacturer recommendations for continuous operation and affected performance of the actuator at McGuire Nuclear Station. _ HEADQUARTERS MORNING REPORT PAGE 2 MARCH 31, 1997 Licensee/Facility: Notification: Part 21 Database MR Number: H-97-0032 Victoreen Date: 03/31/97 Subject: Part 21 - Potential defect in Model 530 radiation detection instruments because of resistor network cracking Discussion: VENDOR: Victoreen PT21 FILE NO: 97260 DATE OF DOCUMENT: 03/25/97 ACCESSION NUMBER: SOURCE DOCUMENT: EN 32017 REVIEWER: PECB, V. Hodge NEW ISSUE. The vendor notifies that in a Model 530 radiation detection instrument, a resistive network can crack, causing the instrument to become nonfunctional. Measurements made with defective instruments would have errors, particularly if a defective instrument is used as a calibration standard. _ HEADQUARTERS MORNING REPORT PAGE 3 MARCH 31, 1997 Licensee/Facility: Notification: Part 21 Database MR Number: H-97-0033 Peebles Electric Date: 03/31/97 Subject: Part 21 - Failure of operational amplifier U8 chip in EDG automatic voltage regulator Discussion: VENDOR: Peebles Electric PT21 FILE NO: 97170 DATE OF DOCUMENT: 02/06/97 ACCESSION NUMBER: 9702120176 SOURCE DOCUMENT: REVIEWER: PECB, D. Skeen NEW ISSUE. On November 13, 1996, at Fermi, an emergency diesel generator failed a surveillance test. The electrical system voltage dropped about 50 percent on automatic actuation of a residual heat removal pump. Root cause investigation determined that operational amplifier U8 on automatic voltage regulator board revision B had failed. Replacement of board revision B produced the same failure. Replacement with earlier board revision A removed the fault. Independent testing of board revision B is continuing. _ HEADQUARTERS MORNING REPORT PAGE 4 MARCH 31, 1997 Licensee/Facility: Notification: Part 21 Database MR Number: H-97-0034 General Atomics Date: 03/31/97 Subject: Part 21 - Operations manual for radiation monitor RM-23A may not adequately define requirements for certain surveillance tests Discussion: VENDOR: General Atomics PT21 FILE NO: 97270 DATE OF DOCUMENT: 03/27/97 ACCESSION NUMBER: SOURCE DOCUMENT: EN 32033 REVIEWER: PECB, C. Petrone NEW ISSUE. Sorrento Electronics determined that the operations and maintenance manual for radiation monitor RM-23A may not define requirements for performing certain surveillance tests of certain safety-related applications. They recommend additional diagnostic tests as part of normal maintenance activities to identify hardware failures that are otherwise undetectable during normal operations. The vendor is notifying customers, including several domestic nuclear power plants. _ HEADQUARTERS MORNING REPORT PAGE 5 MARCH 31, 1997 Licensee/Facility: Notification: Part 21 Database MR Number: H-97-0035 Cooper Energy Date: 03/31/97 Subject: Part 21 - Emergency diesel generator cylinder cracked liner and underspecified piston crown thickness in area of failure Discussion: VENDOR: Cooper Energy PT21 FILE NO: 97280 DATE OF DOCUMENT: 03/27/97 ACCESSION NUMBER: SOURCE DOCUMENT: EN 32037 REVIEWER: PECB, C. Petrone NEW ISSUE. On January 27, 1997, at Zion, the licensee identified a significant drop in crankcase lube oil level in an emergency diesel generator. Subsequent investigation revealed that a cylinder liner was cracked and that water had entered the combustion chamber, which caused the piston to fail. On review of the failed piston, the licensee learned that the piston crown thickness in the area of failure was less than the drawing specification. This liner design is used on early KSV engines at Zion and Cooper. Several other nuclear power plants use later KSV engines. _ REGION I MORNING REPORT PAGE 6 MARCH 31, 1997 Licensee/Facility: Notification: Baltimore Gas & Elec Co. MR Number: 1-97-0025 Calvert Cliffs 2 Date: 03/31/97 Lusby,Maryland RI PC Dockets: 50-318 PWR/CE Subject: PROBLEM WITH REFUELING EQUIPMENT RESULTS IN INABILITY TO SHUT FUEL TRANSFER ISOLATION VALVE Discussion: During defueling operations on March 28, 1997, the refueling transfer carriage power supply breaker tripped on overload. Investigation by BGE identified that a limit switch actuating magnet mounted on the transfer carriage had become dislodged and had contacted the spent fuel pool upender, stopping the carriage and tripping the power supply. At the time, a six year old fuel assembly was in place in the carriage. BGE suspended all core alterations and prepared a detailed troubleshooting and repair plan. As part of the plan, the carriage was manually moved back into the refueling cavity where the fuel assembly was removed and placed in a safe storage position. The refueling transfer isolation valve can now be shut if necessary. A detailed inspection of refueling equipment and a series of dives were planned to initiate repairs to the refueling equipment. A review of the root cause and corrective actions by the plant operations safety review committee will be completed prior to resuming defueling activities. The resident inspectors are following the BGE activities as they progress. Regional Action: For information only. Contact: Scott Stewart (410)586-2626 Lawrence Doerflein (610)337-5378 _ REGION III MORNING REPORT PAGE 7 MARCH 31, 1997 Licensee/Facility: Notification: Abb Combustion Engineering MR Number: 3-97-0055 Hematite Nuclear Fuel Manufacturing Date: 03/26/97 Hematite,Missouri NRC INSPECTORS Dockets: 07000036 Subject: NRC INSPECTOR AND LICENSEE REPRESENTATIVE EXPOSED TO HF Discussion: During the conduct of a material control and accountability inspection in the cylinder yard at the ABB Combustion Engineering Nuclear Fuel Manufacturing facility, an NRC inspector and a licensee representative were exposed to a hydrofluoric acid (HF) gas release between 9:30 - 10:00 a.m. on March 26, 1997. The HF was apparently released due to a leak in the HF dry scrubber system next to the cylinder yard. The licensee representative complained of feeling nauseous and was sent home. He returned to work the next day. The NRC inspector experienced a burning sensation in the nose and throat at the time of the event. Medical attention was provided as a precautionary measure. Examination results identified a mild nasal irritation. The NRC Health and Safety Manager has been notified. The office of Nuclear Materials Safety and Safeguards (NMSS) is aware of this event and the State of Missouri has been notified. Regional Action: NMSS will conduct a follow up chemical safety inspection. Contact: TIM REIDINGER (630)829-9816 WALTER S. SCHWINK (630)415-7253 _ REGION III MORNING REPORT PAGE 8 MARCH 31, 1997 Licensee/Facility: Notification: Commonwealth Edison Co. MR Number: 3-97-0056 Braidwood 1 Date: 03/29/97 Braceville,Illinois SRI VIA TELECON AND FAX Dockets: 50-456 PWR/W-4-LP Subject: PLANNED SHUTDOWN AND REFUEL OUTAGE Discussion: AT APPROXIMATELY 12:08 A.M. (CST) ON MARCH 29, 1997, THE GENERATOR WAS TAKEN OFF LINE. THE REACTOR WAS SHUTDOWN AT 1:25 A.M. AND THE LICENSEE COMMENCED A 53-DAY REFUEL OUTAGE. IN ADDITION TO REFUELING DURING THE OUTAGE, THE MAJOR ACTIVITIES PLANNED INCLUDE: A TEN YEAR REACTOR VESSEL INSPECTION, LOCAL LEAK RATE TESTING, STEAM GENERATOR EDDY CURRENT TESTING, AND PREPARATION FOR THE FUTURE STEAM GENERATOR REPLACEMENT. OTHER ACTIVITIES INCLUDE PLANS TO CONDUCT 18-MONTH DIESEL GENERATOR INSPECTIONS, INSPECT AND CLEAN ELECTRICAL BUSSES, INSPECT THE MAIN TURBINE AND GENERATOR, AND NUMEROUS OTHER ACTIVITIES. Regional Action: THE RESIDENT INSPECTORS MONITORED THE SHUT DOWN AND, IN CONJUNCTION WITH REGIONAL SPECIALISTS, WILL MONITOR THE OUTAGE ACTIVITIES. Contact: R. D. LANKSBURY (630)829-9631 _ REGION IV MORNING REPORT PAGE 9 MARCH 31, 1997 Licensee/Facility: Notification: MR Number: 4-97-0031 Riverside County Fire Dept Date: 03/28/97 Lake Elsinore,California National Response Center Subject: RADIOACTIVE MATERIAL FOUND BY CITIZEN Reportable Event Number: 32041 Discussion: At 5:36 p.m. (EST) on March 27, 1997, the HQ Operations Officer was notified by the National Response Center of an incident in California wherein a private citizen found a tube containing strontium-90 alongside a road. The individual took it to a Lake Elsinore fire department where it was reported that the individual and his vehicle were contaminated. Region IV contacted the State of California on March 28, 1997, and received the following update. The state dispatched an inspector on the morning of March 28. The inspector reported that the tube is a generally licensed deviced labeled as containing 25 uci Sr-90. The manufacturer's name is obliterated on the label, but a serial number was visible. The state will attempt to trace the device by the serial number. The device was described as a 3-inch diameter pipe about 1-foot long with a shutter mechanism (the shutter was closed). A 4 mrem contact dose rate was measured and wipes of the device and the source showed no contamination. The state said the report of the individual and truck being contaminated were erroneous. The state transported the device to a state licensed hospital for storage pending an attempt to trace the owner. The hospital will dispose of the device, lacking any success in identifying the owner. Regional Action: No further action planned. Contact: F. Wenslawski (817)860-8249 _ REGION IV MORNING REPORT PAGE 10 MARCH 31, 1997 Licensee/Facility: Notification: Nebraska Public Power District MR Number: 4-97-0032 Cooper 1 Date: 03/29/97 Brownville,Nebraska Dockets: 50-298 BWR/GE-4 Subject: SHUTDOWN FOR SCHEDULED REFUELING OUTAGE Discussion: On March 29, 1997, Cooper Nuclear Station started its 17th refueling outage. Major activities scheduled for the 40-day outage include installation of larger torus suction strainers, cleaning of the torus, and refueling. Regional Action: The resident inspectors monitored the shutdown in the control room and will monitor licensee activities during the outage. Contact: Mary Miller (402)825-3371 Elmo Collins (817)860-8291 _