Headquarters Daily Report AUGUST 30, 1995 *************************************************************************** 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 - REGION I AUGUST 30, 1995 Licensee/Facility: Notification: Public Service Electric & Gas Co. MR Number: 1-95-0111 Salem 1 2 Date: 08/30/95 Hancocks Bridge,New Jersey SRI PC Dockets: 50-272,50-311 PWR/W-4-LP,PWR/W-4-LP Subject: PERSONNEL CHANGES AT ARTIFICIAL ISLAND (SALEM UNITS 1 AND 2 - DNS 50-272; 50-311 AND HOPE CREEK - DN 50-354) Discussion: Recently PSE&G made several changes in senior Salem and Nuclear Business Unit (NBU) management. Effective September 5, Gary Overbeck, formerly of Ogden Environmental and Energy Services Company, starts as the Director of Design Engineering. Mr. Overbeck will assume responsibility for all design engineering functions and will report directly to Bert Simpson, the NBU Senior Vice President of Engineering. David Garchow, formerly of Palo Verde Nuclear Generating Station, became the Director of System Engineering on August 21. He has responsibility for Hope Creek and Salem system engineering functions and will also report to Bert Simpson. Effective August 24, Nick Conicella, formerly of the Nuclear Regulatory Commission, became the Manager of Salem Projects reporting to Clay Warren, the Salem General Manager. Jay Laughlin, formerly of Commanche Peak, became the Manager of Salem Maintenance, effective August 28. Jay will report to Clay Warren, with the Mechanical Maintenance Manager and the Electrical and Controls Maintenance Manager reporting to him in turn. Christopher Bakken, formerly of Beaver Valley Nuclear Generating Station, became the Manager of Salem Operations, effective August 28. Jerry McMahon, formerly of Commanche Peak, will be the Manager of Nuclear Training, effective September 5. He will report to Clay Warren. Regional Action: NONE - information only. Contact: Charles Marschall (207)882-7519 _ REGION III MORNING REPORT PAGE 2 AUGUST 30, 1995 Licensee/Facility: Notification: Michigan Electric Co. MR Number: 3-95-0149 Cook 2 Date: 08/29/95 Bridgman,Michigan RI PC Dockets: 50-316 PWR/W-4-LP Subject: UNIT 2 REACTOR TRIP. Discussion: On August 29, 1995, at 9:24 a.m., the Unit 2 reactor tripped from a negative rate trip signal after both control rod motor-generator sets' output breakers opened. The licensee is still investigating the cause of the trip. The auxiliary feedwater (AFW) pumps auto-started, as designed, in response to the trip. However, the two normally-open discharge valves associated with the "West" motor-driven AFW pump did not initially respond to a flow retention signal or manual operator action following the trip. The operators were able to operate the valves after temporarily removing the pump from service and declared the pump inoperable. The licensee is currently investigating the problem with the valves, but a preliminary cause for one valve failure was related to the torque switch. The licensee also experienced two letdown isolations during the post-trip recovery. Both isolations were attributed to excessive cooldown of the primary system by the AFW system. The first isolation occurred due to the failure of the AFW pump discharge valves to respond initially following the trip. The second isolation occurred when the operators were filling the two steam generators that were fed by the discharge valves to the high end of the normal operating band to allow the AFW pump to be temporarily removed from service. Regional Action: The resident inspectors responded to the control room upon notification of the event and will monitor the licensee's root cause investigation of the problems with the MG sets and the AFW discharge valves. Contact: WAYNE KROPP (708)829-9633 _ REGION IV MORNING REPORT PAGE 3 AUGUST 30, 1995 Licensee/Facility: Notification: Houston Lighting & Power Co. MR Number: 4-95-0103 South Texas 1 Date: 08/30/95 Wadsworth,Texas SRI on 8/29 Dockets: 50-498 PWR/W-4-LP Subject: REACTOR TRIP DUE TO HUMAN ERROR Reportable Event Number: 29255 Discussion: At 11:27 a.m. on August 29, 1995, South Texas Project Unit 1 tripped from 100 percent power on low reactor coolant system flow due to the trip of Reactor Coolant Pump 1C. Reactor Coolant Pump 1C tripped when the 13.8KV bus feeding it was deenergized because maintenance personnel inadvertently tripped the main feeder breaker to the 13.8KV bus. The trip occurred when the field supervisor attempted to reset a jammed trip indicating flag on the overcurrent relay for the feeder breaker without isolating the relay from the trip circuit as required by procedure. All control rods inserted fully upon the trip. The auxiliary feedwater system actuated on lo-lo steam generator level as expected following a trip from high power level. Decay heat removal is being accomplished via the steam dumps to the main condenser. The auxiliary feedwater system has been secured and main feedwater restored. The licensee has established an event review team to investigate the event. At 12:09 p.m. the same day, a small fire was reported in the packing gland area of Valve MS-MOV-0084, the isolation valve in the main steam supply to the moisture separator reheater. This valve had closed on a high temperature signal following the turbine trip. The fire was caused by lubricant leakage from the motor actuator onto the hot valve and was extinguished immediately by the licensee's fire brigade. Currently, the licensee is completing repairs on Valve MS-MOV-0084 and will commence startup around noon today. Regional Action: Resident staff followup of repairs and startup. Contact: L. A. Yandell (817)860-8182 _ REGION IV MORNING REPORT PAGE 4 AUGUST 30, 1995 Licensee/Facility: Notification: Southern California Edison & San MR Number: 4-95-0104 Diego Gas & Electric Co. Date: 08/28/95 San Onofre 3 Phone Call from Resident Inspectors San Clemente,California Dockets: 50-362 PWR/CE Subject: DEFORMED CONTROL ELEMENT ASSEMBLY Discussion: On August 28, 1995, during refueling outage work to reassemble the San Onofre Unit 3 reactor, the licensee was unable to insert a four-finger control element assembly into its associated fuel cells. The assembly, one of four used in the reactor, is located in the periphery of the core and spans two fuel cells. The four-fingered assemblies are lowered into their associated fuel cells after the core is reloaded and the upper guide structure is installed. The licensee subsequently lifted the upper guide structure, inspected the control element assembly, and observed that one of the assembly fingers was deformed. The deformed assembly, which had not been previously used, will be replaced. The licensee also inspected the associated fuel cells and observed that one cell had some guide tube deformation. The licensee intends to swap that fuel cell with one from another core location. The licensee's preliminary cause determination is that the control element assembly contacted the fuel cell during installation of the upper guide structure. The licensee's practice was to have the four-fingered control element assemblies pinned to the upper guide structure in a position not fully retracted into their shrouds. The San Onofre 3 reactor core consists of 217 fuel cells, 79 five-finger full length control element assemblies, 8 five-finger part length control element assemblies, and 4 four-finger control element assemblies. San Onofre Unit 3 continues in a refueling outage. San Onofre Unit 2 is operating at full power. Regional Action: The NRC resident inspectors will follow the licensee's actions to replace the control element assembly, evaluate the acceptability of using the damaged fuel cell in another core location, and determine the cause of the event. Contact: R. Huey (510)975-0342 J. Sloan (714)492-2641 _