Headquarters Daily report JULY 22, 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 - REGION I JULY 22, 1994 Licensee/Facility: Notification: E.I. Dupont De Nemours And Company, MR Number: 1-94-0081 Inc. Date: 07/22/94 E.I. Dupont De Nemours And Co.,Inc. Wilmington,Delaware License No: 07-00455-27 Subject: MEDIA REPORT OF A FIRE AT A E.I. DUPONT FACILITY IN WILMINGTON, DELAWARE Reportable Event Number: N/A Discussion: At 9:20 a.m. on July 22, 1994, the E. I. DuPont Experimental Station was called by the NRC Region I office to inquire about a media report of a fire at a DuPont facility. The licensee informed Region I that the fire was located at the Chestnut Run Site, Wilmington, Delaware, and involved an overheated oven. The fire was quickly extinguished. The site is authorized by the NRC, License No. 07-00455-27, to possess only sealed sources. The fire did not involve any radioactive materials and was not in the vicinity of licensed material. Regional Action: The licensee has notified the State of Delaware of this incident. Contact: C. Thor Oberg (610)337-5202 Mohamed M. Shanbaky (610)337-5209 PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION III JULY 22, 1994 Licensee/Facility: Notification: Northern States Power Co. MR Number: 3-94-0131 Prairie Island 2 Date: 07/22/94 Welch,Minnesota PC RI Dockets: 50-306 PWR/W-2-LP Subject: UNIT 2 TRIP AND RESTART Reportable Event Number: N/A Discussion: At 10:19 a.m. on July 21, 1994, a main generator ground protection relay actuation resulted in a turbine trip/reactor trip from 100 percent power. A hydrostatic test was being conducted on a modification upgrade to the turbine-generator fire protection system. During the test, a sprinkler head located near the main generator lead bushings failed and the water spray caused a path to ground from the generator B-phase lead. Approximately 50 gallons of potable water were released from the sprinkler head. The fire protection modification had recently been installed during the Unit 1 refueling outage and the Unit 1 portion of the modification was hydrostatically tested during the outage. The next Unit 2 scheduled outage is in May 1995. Following the trip, feedwater leakage past the feedwater regulating valves caused an additional cooldown of the reactor coolant system (RCS) to about 10 degrees below no-load average RCS temperature. Letdown isolation occurred upon low pressurizer level. Feedwater isolation valves were closed and temperature returned to normal. The new portion of the fire protection system was isolated for both Unit 1 and Unit 2 pending a more detailed review of the sprinkler head failure. The licensee inspected Unit 2 generator components and observed no damage. The reactor was taken critical at 3:11 a.m. CDT and resumed power operation at 7:03 a.m. on July 22, 1994. Regional Action: Routine followup. Contact: W. KROPP (708)829-9633 PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION IV JULY 22, 1994 Licensee/Facility: Notification: Southern California Edison & San MR Number: 4-94-0063 Diego Gas & Electric Co. Date: 07/21/94 San Onofre 2 3 CALL FROM LICENSEE TO WCFO DIRECTOR San Clemente,California Dockets: 50-361,50-362 PWR/CE,PWR/CE Subject: RECENT PERSONNEL ERRORS BY MAINTENANCE WORKERS Reportable Event Number: N/A Discussion: On July 21, 1994, at approximately 4:15 p.m. PDT, the Nuclear Generation Vice President of SCE, Mr. R. Krieger, notified the NRC Region IV, that maintenance personnel had recently made three errors while working on safety-related equipment. Mr. Krieger stated that although he considered that none of the three errors appeared to have any immediate safety significance, the occurrence of these errors was a significant performance problem. He ordered a halt to all non-urgent maintenance work, and will talk personally with all maintenance personnel. He stated that he would work closely with the new Maintenance Manager, Mr. John Fee, to develop long-term corrective actions, and that he planned to request a Management Meeting with Region IV to discuss the performance of maintenance at San Onofre (SONGS). SONGS Unit 2 was operating at 98 percent and Unit 3 was operating at 97 percent when the maintenance errors occurred. Regional Action: The resident and project inspectors will followup on the individual maintenance errors. Contact: D. Acker (510)975-0315 D. Solorio (714)492-2641 PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION IV JULY 22, 1994 Licensee/Facility: Notification: Houston Lighting & Power Co. MR Number: 4-94-0064 South Texas 1 Date: 07/22/94 Wadsworth,Texas PHONE CALL WITH RESIDENT INSPECTOR Dockets: 50-498 PWR/W-4-LP Subject: TECHNICAL SPECIFICATION 4.7.4 VIOLATION Reportable Event Number: 27554 Discussion: Following discussions with the resident inspectors concerning the use of danger tags as a substitute for locks on valves, the licensee agreed that they had failed to meet Technical Specification surveillance requirements for the essential cooling water system valve position verification. Technical Specification 4.7.4.a requires verification each 31 days that each valve which services safety related equipment and which is not locked, sealed, or otherwise secured in position, is in the correct position. The resident inspectors had found that the licensee had not been performing this verification for certain valves. The licensee had been using danger tags as an "administrative lock" on valves which presented difficulties in the installation of a mechanical lock. The valves in question have been verified to be in the correct position. Regional Action: The resident inspectors will continue to review this issue, including its applicability to Unit 2 and the licensee's corrective actions. Contact: William Johnson (817)860-8148 PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION IV JULY 22, 1994 Licensee/Facility: Notification: Houston Lighting & Power Co. MR Number: 4-94-0065 South Texas 1 2 Date: 07/22/94 Wadsworth,Texas PHONE CALL WITH RESIDENT INSPECTOR Dockets: 50-498,50-499 PWR/W-4-LP,PWR/W-4-LP Subject: INADEQUATE CHANNEL CHECK Reportable Event Number: 27523 Discussion: Following discussions with the resident inspectors concerning the adequacy of the channel checks being performed each month on the remote shutdown and accident monitoring instruments, the licensee agreed that their past practice had not met the requirements for a meaningful channel check on one channel of containment sump wide range water level in each unit. The normal indication for these instruments is provided by the qualified parameter display system (QDPS). Plant operators had been accepting an indication of "LO" during their monthly channel checks. Since this is the same indication which would be displayed for a de-energized transmitter, the inspectors questioned the validity of channel checks on instruments with this QDPS output. On July 11 the licensee declared the channels inoperable after failing to demonstrate their operability by checking their output on the emergency response facility data acquisition and display system (ERFDADS) computer and finding invalid data there also. The licensee subsequently revised the surveillance test procedure for these channel checks, adding guidance to take voltage readings on the terminals at the input to the QDPS if the QDPS and ERFDADS indicated bad data. On July 19 for Unit 2 and July 21 for Unit 1, the licensee successfully performed the revised procedure and exited the Technical Specification action statements. The resident inspectors, with the assistance of NRR, have determined that the revised procedure performs a valid channel check. Regional Action: The resident inspectors will review the licensee's corrective actions in response to the violation. Contact: William Johnson (817)860-8148 PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION IV JULY 22, 1994 Licensee/Facility: Notification: Entergy Operations, Inc. MR Number: 4-94-0066 Waterford 3 Date: 07/22/94 Killona,Louisiana SENIOR RESIDENT INSPECTOR Dockets: 50-382 PWR/CE Subject: DILUTION EVENT Reportable Event Number: N/A Discussion: On July 20, 1994, an inadvertent boron dilution occurred at Waterford 3 resulting in a reactor power increase to 100.38 percent for approximately 30 minutes. A reactor operator was in the process of making a routine addition of blended makeup water to the volume control tank (VCT). During this evolution, a low pressure alarm came in on one of the safety injection tanks (SITs). The operator responded to the SIT alarm after he had initiated flow of pure reactor makeup water to the VCT, but before he had commenced the associated boration. After approximately seven minutes, a second senior reactor operator trainee notified the reactor power increase. The operators initiated boration to the VCT and then directly to the reactor coolant system (RCS) to halt the power increase and return reactor power to 100 percent. Approximately 700 gallons of pure water were added to RCS. The excess boration caused Tc to decrease from 545 to 541 degrees Fahrenheit. The operators then returned Tc to its required band by running the turbine back in power. The unit is currently at 100 percent power. The licensee is currently evaluating the incident and has implemented an event review team, including interviews with all the operators. Regional Action: The resident inspectors will continue to followup. Contact: C. A. VanDenburgh (817)860-8161