Headquarters Daily report JANUARY 18, 1995 *************************************************************************** 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 JANUARY 18, 1995 MR Number: H-95-0007 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 95-03, "Loss of Reactor Coolant Inventory and Potential Loss of Emergency Mitigation Functions While in a Shutdown Condition," to be issued Januany 18, 1995. The NRC is issuing this information notice to alert addressees to a recent incident involving a loss of reactor coolant inventory while in a shutdown condition at a Westinghouse pressurized-water reactor. Technical contacts: J. Frederick Ringwald, RIV (316) 364-8653 Lambros Lois, NRR (301) 504-3233 NRC Information Notice 95-04, "Excessive Cooldown and Depressurization of the Reactor Coolant System Following a Loss of Offsite Power," to be issued January 19, 1995. The NRC is issuing this information notice to alert addressees to an excessive cooldown and depressurization of the reactor coolant system (RCS) and the main steam system following a loss of offsite power at the McGuire Nuclear Station Unit 2. Technical contacts: Eric J. Benner, NRR (301) 504-1171 Chu-Yu Liang, NRR (301) 504-2878 NRC Information Notice 95-05, "Undervoltage Protection Relay Settings out of Tolerance due to Test Equipment Harmonics," to be issued January 20, 1995. The NRC is issuing this information notice to alert addressees that undervoltage relay settings could be out of tolerance because of test equipment harmonics. Technical contacts: D. Nguyen, NRR D. Butler, RIII (301) 504-3202 (708) 829-9720 F. Ashe, NRR D. Skeen, NRR (301) 504-2785 (301) 504-1174 PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION I JANUARY 18, 1995 Licensee/Facility: Notification: Consolidated Edison Co. Of N.Y. MR Number: 1-95-0004 Indian Point 2 Date: 01/17/95 Buchanan,New York SRI PC Dockets: 50-247 PWR/W-4-LP Subject: REACTOR TRIP Reportable Event Number: N/A Discussion: At 00:39 a.m. on January 17, an automatic reactor trip occurred from 89% reactor power. All automatic actions occurred as expected. The first out annunciator was the turbine control oil auto stop. The trip is sensed by a decrease in autostop oil pressure which initiates a reactor trip when the reactor is operating above 10% power. The trip is provided via redundant solenoids which are energized to trip the turbine by dumping autostop oil. The solenoids are energized under the following conditions: generator trip, reactor trip, manual turbine trip, turbine overspeed, main steam isolation valve closure, high turbine vibration, high differential expansion, loss of main generator cooling water, safety injection or high steam generator water level, and AMSAC. The cause of the trip is not readily apparent and the licensee is investigating. The plant is in hot shutdown and stable. Regional Action: The senior resident inspector responded to the site to monitor activities. Contact: Gordon Hunegs (914)739-9360 PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION I JANUARY 18, 1995 Licensee/Facility: Notification: Maine Yankee Atomic Power Co. MR Number: 1-95-0005 Maine Yankee 1 Date: 01/17/95 Wiscasset,Maine SRI PC Dockets: 50-309 PWR/CE Subject: MANUAL REACTOR TRIP DUE TO MAIN GENERATOR PROBLEMS Reportable Event Number: 28241 Discussion: On January 14, 1995, at 8:39 a.m, control room operators manually tripped the plant from 100 percent power, after a "Generator Ground" alarm was received in the control room. All safety systems responded as expected. No safety injection was required and offsite power remained available during the transient. A trip response team, led by one of the assistants to the manager of operations, has been assembled and is investigating the situation. The plant will remain in hot shutdown to troubleshoot and repair the generator. The plant is expected to be down for at least the next three days. Regional Action: The resident inspector was informed by the facility at the time of the trip and responded to the site. Facility activities to identify the cause of the ground and repair the generator are being monitored. Contact: Jimi Yerokun (207)882-7519 William Lazarus (610)337-5231 PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION I JANUARY 18, 1995 Licensee/Facility: Notification: Public Service Electric & Gas Co. MR Number: 1-95-0006 Salem 2 Date: 01/18/95 Hancocks Bridge,New Jersey SRI PC Dockets: 50-311 PWR/W-4-LP Subject: REACTOR COOLANT PUMP (RCP) SEAL INSPECTION Reportable Event Number: N/A Discussion: On January 11, while in mode 4 with the No. 23 RCP running, the seal leak-off isolation valve failed closed. The pump continued to run for about six minutes before operators got a low seal differential pressure alarm and tripped the pump. Westinghouse recommended that PSE&G inspect the No. 1 seal. Salem management elected to disassemble and inspect the seal by putting the pump on the backseat formed by the lower surface of the radial bearing and the upper surface of the thermal barrier. At 10:00 p.m. on January 17, PSE&G, assisted by Westinghouse, successfully lowered the RCP onto the backseat with RCS level approximately four feet above the level considered reduced inventory. Workers initially observed about one gallon of RCS leakage as they lowered the RCP internals, then leakage dropped off to about 0.25 gpm. Plant staff expects to complete RCP work late on January 20, assuming the No. 1 seal has not suffered significant damage. The plant staff also expects to complete replacement of the pressurizer code safety valves early on January 20. Mode change is projected for January 24. The resident inspectors observed preparations for the RCP work throughout the weekend, and monitored the pump backseat activity on January 18. The resident inspectors will continue to observe RCP and pressurizer code safety valve work. Regional Action: Region I and PSE&G management will discuss reliability of the 500kv switchgear before the licensee begins to increase Salem Unit 1 power. Contact: Charles Marschall (207)882-7519 John White (610)337-5114