Headquarters Daily report JUNE 21, 1994 *************************************************************************** REPORT NEGATIVE NO INPUT ATTACHED INPUT RECEIVED RECEIVED HEADQUARTERS X REGION I X REGION II X REGION III X REGION IV X *************************************************************************** € à ÃPRIORITY ATTENTION REQUIRED MORNING REPORT - REGION I JUNE 20, 1994Ä Ä € €Ã ÃÃÃLicensee/Facility:ÄÄÄ Ä Ã ÃÃÃNotification:ÄÄÄ Ä € €Baltimore Gas & Elec Co. MR Number: à Ã1-94-0067Ä Ä €Calvert Cliffs 1 Date: 06/20/94 €Lusby,Maryland €Dockets: 50-317 €PWR/CE € €Ã ÃÃÃSubject:ÄÄÄ Ä UNIT TRIP AND RESTART € €Ã ÃÃÃReportable Event Number:ÄÄÄ Ä 27403 € €Ã ÃÃÃDiscussion:ÄÄÄ Ä € €At 1:35 a.m. on June 16, 1994, during weekly turbine stop valve testing, €3 stop valves stroked closed, rather than the intended single valve. The €resulting steam flow transient caused steam generator levels to shrink, €initiating a reactor trip on S/G low levels. The reactor trip caused a €turbine trip instead of a turbine trip causing a reactor trip as was €erroneously reported in the 50.72 notification (Event # 27403). € €The reactor was taken critical on the morning of June 17th. The weekly €turbine stop valve test was repeated several times at low power (<15%) €which would preclude a reactor trip if the malfunction recurred. The €malfunction could not be reproduced. € €The plant resumed power operation on June 17, 1994. € €Ã ÃÃÃRegional Action:ÄÄÄ Ä € €Routine followup. € €Ã ÃÃÃContact:ÄÄÄ Ä Larry Nicholson (610)337-5128 € à ÃPRIORITY ATTENTION REQUIRED MORNING REPORT - REGION I JUNE 20, 1994Ä Ä € €Ã ÃÃÃLicensee/Facility:ÄÄÄ Ä Ã ÃÃÃNotification:ÄÄÄ Ä € €Gpu Nuclear Corp. MR Number: à Ã1-94-0068Ä Ä €Oyster Creek 1 Date: 06/20/94 €Forked River,New Jersey SRI PC €Dockets: 50-219 €BWR/GE-2 € €Ã ÃÃÃSubject:ÄÄÄ Ä LOGGERHEAD SEA TURTLE CAUGHT IN INTAKE € €Ã ÃÃÃReportable Event Number:ÄÄÄ Ä 27413 € €Ã ÃÃÃDiscussion:ÄÄÄ Ä € €On June 19, 1994, at 1:30 p.m. the control room received a report that a €Loggerhead Sea Turtle was caught in the intake current in the No. 4 €intake bay. The SRI was in the control room when the report was received €and immediately went to the intake structure. The licensee extracted the €sea turtle by lifting it high enough up the intake trash rack using hand €held rakes so an operator could physically grab the sea turtle. The sea €turtle was successfully removed at 1:45 p.m. The turtle appeared €uninjured and was quite active. Licensee personnel placed the turtle in a €large container and sprayed sea water on the turtle and the container to €keep the turtle cool. The turtle was also shaded by the licensee. €Notification was made to a licensee marine biologist who made €arrangements to transport the sea turtle to the New Jersey Stranded €Marine Mammal facility in Brigantine, New Jersey. The sea turtle was €removed from the Oyster Creek facility at approximately 3:00 p.m. on June €19, 1994. € €Ã ÃÃÃRegional Action:ÄÄÄ Ä € €No Additional Followup € €Ã ÃÃÃContact:ÄÄÄ Ä John Rogge (610)337-5146 € à ÃPRIORITY ATTENTION REQUIRED MORNING REPORT - REGION III JUNE 20, 1994Ä Ä € €Ã ÃÃÃLicensee/Facility:ÄÄÄ Ä Ã ÃÃÃNotification:ÄÄÄ Ä € €Consumers Power Co. MR Number: à Ã3-94-0115Ä Ä €Palisades 1 Date: 06/20/94 €Covert,Michigan RIII LAN €Dockets: 50-255 €PWR/CE € €Ã ÃÃÃSubject:ÄÄÄ Ä PLANT RESTART FOLLOWING EXTENDED FORCED OUTAGE € €Ã ÃÃÃReportable Event Number:ÄÄÄ Ä N/A € €Ã ÃÃÃDiscussion:ÄÄÄ Ä € €Plant operators took the reactor critical at 7:08 a.m. (EDT), on June 18, €1994, with the unit synchronized to the grid at 5:46 p.m. (EDT), that €same day. This concluded an extensive forced outage that began on €February 17, 1994. €The plant was initially shut down to repair a through wall leak found on €one of two ECCS containment sump outlet check valves. Although associated €repairs were completed by the end of March 1994, plant restart was €delayed until several important issues identified during an ensuing visit €by an NRC Diagnostic Evaluation Team (DET) were resolved. €The DET completed their onsite inspections of the licensee on April 22, €1994. Regional and Headquarters personnel followed the licensee's actions €to assure that all issues needing resolution prior to plant restart were €properly addressed. € €Ã ÃÃÃRegional Action:ÄÄÄ Ä € €Resident and regional inspectors were onsite around the clock observing €restart activities. € €Ã ÃÃÃContact:ÄÄÄ Ä M.E. PARKER (616)764-8971 € à ÃPRIORITY ATTENTION REQUIRED MORNING REPORT - REGION III JUNE 20, 1994Ä Ä € €Ã ÃÃÃLicensee/Facility:ÄÄÄ Ä Ã ÃÃÃNotification:ÄÄÄ Ä € €Commonwealth Edison Co. MR Number: à Ã3-94-0116Ä Ä €Dresden 1 2 Date: 06/20/94 €Morris,Illinois INFORMATION €Dockets: 50-010,50-237 €BWR/GE-1,BWR/GE-3 € €Ã ÃÃÃSubject:ÄÄÄ Ä ANNUAL INPO INSPECTION € €Ã ÃÃÃReportable Event Number:ÄÄÄ Ä N/A € €Ã ÃÃÃDiscussion:ÄÄÄ Ä € €An INPO team consisting of about 16 members will arrive on June 20, 1994, €for the periodic evaluation of the D. C. Cook plant. The evaluation will €continue through July 1, 1994. € €Ã ÃÃÃRegional Action:ÄÄÄ Ä € €Information Only € €Ã ÃÃÃContact:ÄÄÄ Ä WAYNE KROPP (708)829-9633 € à ÃPRIORITY ATTENTION REQUIRED MORNING REPORT - REGION III JUNE 20, 1994Ä Ä € €Ã ÃÃÃLicensee/Facility:ÄÄÄ Ä Ã ÃÃÃNotification:ÄÄÄ Ä € €Region Iii MR Number: à Ã3-94-0117Ä Ä €Region Iii Date: 06/20/94 €Lisle,Illinois € €Ã ÃÃÃSubject:ÄÄÄ Ä UKRAINIAN SCRNS STAFF VISIT TO REGION III € €Ã ÃÃÃReportable Event Number:ÄÄÄ Ä N/A € €Ã ÃÃÃDiscussion:ÄÄÄ Ä € €On June 20, 1994, four members of the Ukrainian State Committee for €Nuclear and Radiation Safety arrived at the Region III office. The €purpose of the visit is to receive training from the staff in materials €licensing. They will be in the Region through June 24. € €Ã ÃÃÃRegional Action:ÄÄÄ Ä € €N/A € €Ã ÃÃÃContact:ÄÄÄ Ä KEVIN NULL (708)829-9854 € JOHN MADERA (708)829-9834 € à ÃPRIORITY ATTENTION REQUIRED MORNING REPORT - REGION IV JUNE 20, 1994Ä Ä € €Ã ÃÃÃLicensee/Facility:ÄÄÄ Ä Ã ÃÃÃNotification:ÄÄÄ Ä € €Nebraska Public Power District MR Number: à Ã4-94-0055Ä Ä €Cooper 1 Date: 06/20/94 €Brownsville,Nebraska SRI €Dockets: 50-298 €BWR/GE-4 € €Ã ÃÃÃSubject:ÄÄÄ Ä UPDATE ON CURRENT OUTAGE € €Ã ÃÃÃReportable Event Number:ÄÄÄ Ä 27295 € €Ã ÃÃÃDiscussion:ÄÄÄ Ä € €This morning report provides an updated status of the ongoing issues €identified at the Cooper Nuclear Station. € €The licensee has completed load-shed testing for all loads connected to €the vital buses, the results are discussed below: € €- On the Division I vital bus, two 480-volt breakers (supply power to the €service air compressor and ventilation fans) failed to trip. The loads €represented approximately 260 amps of load at 480 volts. The breaker, €which was originally found to be tie-wrapped in a nontripping condition, €provided power to MCC N and represented a load of about 45 amps. €Therefore, the total load on the Division I vital bus that could not be €shed, as designed, was about 305 amps. The licensee stated that the €margin (the difference between design load and actual load) for Diesel €Generator I was approximately 250 amps. The licensee has stated that a €revision to the diesel generator calculation will be performed to remove €some conservatism and, as a result of these efforts, the calculation will €show that the actual load, even with the three breakers not tripping €open, will not exceed the design load of the diesel. The licensee has €not yet completed revision of the calculation. € €- On the Division II vital bus, two 480-volt failed to open within the €specified acceptance criteria. The total loads supplied by the two €breakers is about 95 amps. The margin for the Division II diesel €generator is about 220 amps. In addition to the two 480-volt breakers, €the 4160-volt supply breaker for the emergency failed to open. This €breaker is interlocked with the diesel output breaker and must open for €the diesel output breaker to close. Failure of the breaker to open will €prevent the diesel generator from automatically loading onto the vital €bus. € €Licensee management has agreed that the previous testing performed on the €control room envelope did not take into account the pressure in the €buildings that connect to the control room envelope. As a result, €previous surveillance testing may not have been adequate to provide €assurance of the operability of the control room pressure boundary. €Licensee management has agreed to reperform the envelope testing in a €manner to ensure that the testing is done with all ventilation systems €operating at the design basis values. The testing has not yet been €scheduled by the licensee. In addition, the licensee, in conjunction €with NRR and Region IV, is attempting to establish the design basis value €for the control room envelope pressure. These discussions are currently €ongoing. € €In response to an escalated Notice of Violation, the licensee committed €to walk down all containment penetrations to verify that each penetration €was properly installed and that testing was appropriately performed. As €a result of the walkdowns, the licensee has identified 99 of €approximately 290 penetrations that contain deficiencies in either the €installation or testing. The licensee is currently in the process of €resolving the deficiencies. In addition, the licensee committed to €verify that the equipment or components attached to the penetrations are €properly tested to design basis postaccident pressure (58 psig). During €this review, the licensee identified 15 pressure switches that had not €been tested, during the performance of the integrated or local leak rate €tests, to 58 psig. The licensee is in the process of establishing a test €schedule for these pressure switches. € €A Confirmatory Action Letter, Revision 1, was issued, on June 16, 1994, €to require the licensee to meet with the NRC prior to startup from the €current outage. The purpose of the meeting is to discuss the above €issues and to provide assurance that the Cooper Nuclear Station is safe €to continue operation. € €Ã ÃÃÃRegional Action:ÄÄÄ Ä € €Routine followup. € €Ã ÃÃÃContact:ÄÄÄ Ä P. H. Harrell (817)860-8250 € à ÃPRIORITY ATTENTION REQUIRED MORNING REPORT - REGION IV JUNE 21, 1994Ä Ä € €Ã ÃÃÃLicensee/Facility:ÄÄÄ Ä Ã ÃÃÃNotification:ÄÄÄ Ä € €Washington Public Power Supply System MR Number: à Ã4-94-0056Ä Ä €Washington Nuclear 2 Date: 06/21/94 €Richland,Washington SRI €Dockets: 50-397 €BWR/GE-5 € €Ã ÃÃÃSubject:ÄÄÄ Ä EMPLOYEE PRANK € €Ã ÃÃÃReportable Event Number:ÄÄÄ Ä N/A € €Ã ÃÃÃDiscussion:ÄÄÄ Ä € €On June 20, 1994, the licensee advised the Senior Resident Inspector of €an apparent prank which occurred late in the afternoon on June 17 at €WNP-2. Two licensee maintenance craftsman employees (one permanent, one €temporary) decided to "scare" health physics people at the access control €point for the radiologically controlled area (RCA). The two individuals €were not inside the RCA but were heading towards the access control point €from the General Services Building. € €The two individuals donned ski masks and were riding an electric cart in €the protected area toward the RCA control point when they ran past a €security guard. The guard yelled at them to stop, but they reportedly €did not hear him and kept going. After turning a corner, they were seen €and stopped by another security guard, who made them remove their ski €masks and explain their actions. The individuals were counseled and €allowed to finish their shift at the station. Licensee management then €became involved in the issue and awarded disciplinary action to the two €individuals. € €A reporter for the Tri-Cities Herald also heard of this issue and called €the licensee to inquire. The local newspaper printed an article on this €event in the June 21, 1994, newspaper. € €Ã ÃÃÃRegional Action:ÄÄÄ Ä € €Followup by resident inspectors. € €Ã ÃÃÃContact:ÄÄÄ Ä D. Kirsch (510)975-0290 €