Headquarters Daily report APRIL 26, 1994 *************************************************************************** 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 APRIL 26, 1994 MR Number: H-94-0041 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 94-32, "Revised Seismic Hazard Estimates," will be issued April 29, 1994. The NRC is issuing this information notice to alert addressees to NUREG-1488, "Revised Livermore Seismic Hazard Estimates for 69 Sites East of the Rocky Mountains," published in April 1994. Technical contacts: Gus Giese-Koch, NRR (301) 504-2736 Ron Hernan, NRR (301) 504-2010 PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION III APRIL 26, 1994 Licensee/Facility: Notification: Harrison Steel Castings Company MR Number: 3-94-0083 Harrison Steel Castings Company Date: 04/25/94 Attica,Indiana PHONE NOTIF. TO RIII DUTY OFFICER Dockets: 03004335 Subject: RADIOACTIVE SLAG Reportable Event Number: N/A Discussion: Region III received a call from the Radiation Safety Officer at Harrison Steel Castings Company in Attica, Indiana, on April 25, 1994. An incoming semi-trailer containing ferro silicon metal and slag from SKW Metal and Alloys located in Niagara Falls, NY, caused the radiation monitoring system to alarm at Harrison Steel Castings Company on the afternoon of April 22, 1994. Company personnel contacted the State of Indiana Radiological Health Section. State of Indiana inspectors using an Eberline SP-1 MicroR meter reported 80 to 90 microR/hr (20 to 22.5 nC/kg/hr) at contact with the slag material inside the trailer. State personnel retrieved a small piece of slag for analysis at their laboratory. The State of Indiana notified the New York State Radiation Control Program of the return of the trailer. New York State personnel were dispatched to SKW Metal and Alloys to inspect the trailer which arrived on the morning of April 25, 1994. Regional Action: Region III will obtain and review a copy of the State of Indiana report. The Office of State Programs, NMSS and Region I were notified. Contact: B. J. HOLT (708)829-9836 D. R. GIBBONS (708)829-9843 PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION III APRIL 26, 1994 Licensee/Facility: Notification: General Testing And Inspection Co. MR Number: 3-94-0084 General Testing And Inspection Co. Date: 04/25/94 Washingtonville,Ohio CALL FROM LICENSEE'S RSO Dockets: 03005776 License No: 34-09037-01 Subject: POSSIBLE OVEREXPOSURE Reportable Event Number: N/A Discussion: On April 25, 1994 Region III received a call from the Radiation Safety Officer (RSO) of General Testing and Inspection Co., an industrial radiography licensee. The RSO stated that the licensee's dosimetry supplier reported a 5,650 mRem dose to an employee's film badge for the month of February 1994. The RSO was informed by the dosimetry supplier that there was no visible pattern on the film indicating that it may have been exposed outside of its holder. The RSO interviewed personnel, reviewed daily use logs and pocket dosimeter reports. The employee could not recall any unusual working conditions or events. He stated that his pocket dosimeter did not go offscale. He worked closely with a second individual during February whose film badge reading was 100 mRem. Pocket dosimeter records did not reveal any exposures above 100 mR to the workers during that badge period. The licensee is continuing to evaluate this matter and will submit a written report to Region III within 30 days. The licensee has prohibited the employee from engaging in licensed activities until the evaluation is complete and a final dose is determined. Regional Action: Region III will review the licensee's written report and will determine, based on the results of the review, if a special inspection is warranted. NMSS was notified. The State of Ohio will be notified. Contact: B. J. HOLT (708)829-9836 D. R. GIBBONS (708)829-9843 PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION III APRIL 26, 1994 Licensee/Facility: Notification: Commonwealth Edison Co. MR Number: 3-94-0085 Lasalle 1 2 Date: 04/26/94 Marseilles,Illinois VIA RIO Dockets: 50-373,50-374 BWR/GE-5,BWR/GE-5 Subject: STATION ORGANIZATIONAL CHANGES Reportable Event Number: N/A Discussion: On April 21, 1994, the licensee announced several significant organizational changes at LaSalle County Station. The licensee has formed a Business Unit Plan (BUP) Team to ensure that actions are implemented as outlined in the BUP to improve performance at the station. The BUP Team consists of eight individuals with Jim Gieseker leading the team as the BUP Manager. In addition, the licensee announced the following personnel selections at LaSalle Station: Dennis Leggett, Operations Manager; Les Guthrie, Maintenance Superintendent; and Jim Abel, Site Engineering and Construction Manager. Several lower level management personnel changes were also announced. Regional Action: Information only. Contact: H. B. CLAYTON (708)829-9602 PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION III APRIL 26, 1994 Licensee/Facility: Notification: Illinois Power Co. MR Number: 3-94-0086 Clinton 1 Date: 04/26/94 Clinton,Illinois RI BY LAN Dockets: 50-461 BWR/GE-6 Subject: PLANT STARTUP AND EVENT FOLLOWUP Reportable Event Number: N/A Discussion: At 6:44 a.m. (CDT) on April 26, 1994, the generator was synchronized to the grid to end a 10 day maintenance outage. Major work accomplished included replacing a reactor recirculating pump seal and a main transformer bushing. Morning Report 3-94-0081 and Event Notification 27104 discussed an overpower event that occurred on April 15, 1994. The licensee determined that a solenoid valve on the reactor recirculation flow control valve hydraulic power unit (RR FCV HPU) stuck in the intermediate position. The hydraulic fluid used in the system is Fyrquel. The heat from the solenoid coil caused resin from the Fyrquel to accumulate on the valve actuating shaft. This valve was normally operated once per month, but at the vendor's recommendation, it was changed to once per week. The licensee expects this to preclude the buildup of the resin. Additionally, the licensee is going to replace these valves with a newer model. Regional Action: The resident inspectors will continue to follow the licensee's corrective actions. Contact: H. B. CLAYTON (708)829-9602 PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION IV APRIL 26, 1994 Licensee/Facility: Notification: Entergy Operations Inc. MR Number: 4-94-0039 Waterford 3 Date: 04/26/94 Killona,Louisiana Licensee telecon Dockets: 50-382 PWR/CE Subject: REACTOR TRIP FROM 70 PERCENT POWER (EVENT 27162) Reportable Event Number: N/A Discussion: At 8:11 a.m., on April 26, 1994, a reactor trip occurred from 70 percent power. The licensee was in the process of resuming power operations after completing the sixth refueling outage on April 22. Reactor physics testing at the 68 percent power level had been completed and, while increasing power at 3 percent per hour, the plant experienced a reactor trip. Just before the trip, the licensee had armed the automatic power cutback function as directed by its startup procedure. At that time, an unexpected cutback occurred when Rod Groups 5 and 6 (the normally preselected power cutback control rods) dropped into the core. Although the licensee currently is unable to identify any indication of a load rejection or secondary plant malfunction, the licensee believes a cutback signal was present when the function was armed. The reactor cutback is designed to realign reactor and secondary power upon the loss of a feed pump or other secondary plant malfunction that reduces secondary power. However, a reactor trip was generated by the reactor protection system core protection calculators during the cutback. At the time of this report, the licensee could not accurately determine which reactor trip signal was generated. In its 50.72 report, the licensee stated that auxiliary trips on Channels A and B due to low pressurizer pressure were the most likely cause of the trip. The licensee now believes that DNBR or TM/LP limits were the most likely cause, but that is still being reviewed. Preliminary reports from the licensee indicate that all systems performed as designed in response to the trip. The licensee has convened a review group to review and evaluate the event. Licensee procedures require the cause of the trip to be determined and corrective actions identified prior to resuming power operations. The licensee plans to complete its posttrip review and being in the position to restart the reactor at 12 midnight on April 27. Regional Action: The resident inspector staff will evaluate the licensee's actions taken in response to the trip. Contact: T. Reis (817)860-8185 T. Stetka (817)860-8247