Headquarters Daily Report DECEMBER 10, 1996 *************************************************************************** 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 DEC. 09, 1996 Licensee/Facility: Notification: Public Service Electric & Gas Co. MR Number: 1-96-0105 Salem 1 Date: 12/06/96 Hancocks Bridge,New Jersey DRS BRANCH CHIEF Dockets: 50-272 PWR/W-4-LP Subject: SHIPMENT OF STEAM GENERATOR FROM SALEM Discussion: On December 6, 1996, the first of four old steam generators was shipped from the Salem Nuclear Generating Station in Hancock's Bridge, New Jersey for disposal at the Barnwell Low Level Radioactive Waste Disposal Facility. This will be the first steam generator shipment under the new DOT shipping category of Surface Contaminated Object (SCO). The shipment will travel down the intracoastal waterway to the Savannah river for five days, followed by three days travel up the Savannah River to a dock at the Savannah River Site. Two days are projected for barge off-load preparations, and three days for land transport before arriving at the Barnwell facility on December 19, 1996, as currently projected. Regional Action: An NRC Radiation Specialist has inspected the steam generator shipment at the point of departure and found it to be in conformance with the applicable DOT regulations and specific DOT exemption requirements that were issued for this shipment. Contact: John White (610)337-5114 James Noggle (610)337-5063 _ REGION I MORNING REPORT PAGE 2 DECEMBER 9, 1996 Licensee/Facility: Notification: New York Power Authority MR Number: 1-96-0106 Fitz Patrick 1 Date: 12/09/96 Lycoming,New York SRI PC Dockets: 50-333 BWR/GE-4 Subject: PLANT STARTUP AFTER REFUELING OUTAGE Discussion: On December 8 at 12:30 a.m. the reactor was taken critical following a refueling outage which began on October 26, 1996. Following power ascension activities, the plant is expected to resume production of electricity on December 12. During the outage, activities completed included replacement of control rod drive mechanisms, replacement of degraded service water piping, main steam isolation valve repair, and overhaul of the high pressure turbine. In addition, the licensee completed modifications for power uprate to increase the plant's electrical production by about 4%. Regional Action: Resident inspectors are following startup and power ascension related activities. Contact: Gordon Hunegs (914)739-9360 Curtis Cowgill (610)337-5233 _ REGION III MORNING REPORT PAGE 3 DECEMBER 9, 1996 Licensee/Facility: Notification: Consumers Power Co. MR Number: 3-96-0127 Big Rock Point 1 Date: 12/07/96 Charlevoix,Michigan RIII LAN Dockets: 50-155 BWR/GE-1 Subject: LOSS OF GENERATOR EXCITATION CAUSES REACTOR TRIP Discussion: On December 7, 1996 at 12:10 p.m. (EST), the Big Rock Point reactor tripped automatically due to high power created when a resistor in the automatic main generator voltage regulation circuit opened. The resistor fault caused the lower generator exciter voltage protection relay to actuate, tripping the main generator output breaker, and the main turbine. The transient which ensued consisted of a rapid, momentary power increase to 140 percent reactor power due to the pressure increase from closure of the turbine stop valves. The licensee and the FSAR indicate that this response was within the analyzed response envelope. The licensee has not detected any fuel damage from the reactor trip and transient. All other post trip response was as expected, expect for one source range monitor which did not automatically run into the core. The source range was manually run-in after the trip. The senior resident inspector responded to the site on December 7 and 8 to confirm plant conditions and monitor the licensee's corrective actions. The licensee decided to cool down to cold shutdown to repack the emergency condenser No. 1 inlet valve, which had been backseated to stop leakage prior to the trip. The plant entered cold shutdown at 7:12 a.m. on December 8. Regional Action: The resident staff is following up on the licensee's corrective actions. Contact: L. MILLER (630)829-9629 R. LEEMON (616)547-4086 _ HEADQUARTERS MORNING REPORT PAGE 4 DECEMBER 10, 1996 MR Number: H-96-0089 NRR DAILY REPORT ITEM GENERIC COMMUNICATIONS Generic Letter 96-07, "INTERIM GUIDANCE ON TRANSPORTATION OF STEAM GENERATORS," was issued on December 5, 1996. This letter was issued to all holders of operating licenses and possession-only licenses for pressurized water reactors to notify them that the U.S. Department of Transportation (DOT) and NRC have agreed on the transportation requirements for discarded steam generators. The letter provides guidance on acceptable methods for shipping used steam generators. Contacts: Richard Boyle, DOT Earl P. Easton, NMSS (202) 366-4545 (301) 415-8520 e-mail: rick.boyle@rspa.dot.gov e-mail: exe@nrc.gov ------------------------------------------------------------------------- Information Notice 96-63, "POTENTIAL SAFETY ISSUE REGARDING THE SHIPMENT OF FISSILE MATERIAL," was issued on December 5, 1996. This notice was issued to all licensees authorized to possess special nuclear materials in unsealed quantities greater than critical mass to alert them to a situation where a large quantity of exempt concentration fissile material could create a criticality hazard if transported with a special moderating material (i.e., beryllium). Contact: Earl P. Easton, NMSS (301) 415-8520 e-mail: exe@nrc.gov _ HEADQUARTERS MORNING REPORT PAGE 5 DECEMBER 10, 1996 MR Number: H-96-0090 NRR DAILY REPORT ITEM GENERIC COMMUNICATIONS NRC Information Notice 96-64, "Modifications to Containment Blowout Panels Without Appropriate Design Controls," dated December 10, 1996. The NRC is issuing this information notice to alert addressees to the potential for operating outside of the design basis as a result of modifying structures without appropriate design controls. Technical contacts: Donald R. Taylor, RII (540) 984-5421 Neal K. Hunemuller, NRR (301) 415-1152 NRC Information Notice 96-65, "Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown," dated December 11, 1996. The NRC is issuing this information notice to alert addressees to ongoing issues related to an undetected loss of reactor coolant inventory at Haddam Neck caused by an accumulation of nitrogen in the reactor coolant system. Technical contacts: Eric J. Benner, NRR (301) 415-1171 Warren C. Lyon, NRR (301) 415-2947 _ REGION I MORNING REPORT PAGE 6 DECEMBER 10, 1996 Licensee/Facility: Notification: Duquesne Light Co. MR Number: 1-96-0107 Beaver Valley 2 Date: 12/10/96 Shippingport,Pennsylvania Dockets: 50-412 PWR/W-3-LP Subject: Unit 2 Reactor Vessel Head Vent Leak Repair Discussion: On December 2, 1996, a 1-inch flow gage isolation valve (2RCS-624) in the reactor head vent system was leak sealed to stop an internal leak through the disc of the valve. The unit was in cold shutdown (mode 5) nearing completion of an extended refueling outage. During post maintenance testing of the reactor head vent isolation valves following the leak repair of 2RCS-624, one of the downstream valves (2RCS-HCV-250A) did not stroke fully closed. Subsequent inspection of the valve by the licensee revealed that it was obstructed by leak sealant material that prevented proper operation. Inspection of a parallel valve (2RCS-HCV-250B) also revealed sealant material in the upstream portion of the valve. Duquesne Light Company has completed removal of the affected piping and valves and is conducting an inspection to determine the full effect of the sealant injection into 2RCS- 624. The Plant Manager has issued a stop work order for leak sealant repairs and ordered a complete review of the leak sealant repair process, including all existing leak repairs. Preliminary review of the leak sealant repair of 2RCS-624 by the licensee revealed that incorrect sealant may have been used to conduct the repair. The sealant used was specified by the licensee's engineers for conditions of 610 degrees F and 2235 psia, but the conditions at the valve were ambient temperature and near atmospheric pressure. As a result, the sealant apparently did not harden after injection and migrated downstream to 2RCS-HCV-250A and 250B. Preliminary review also revealed that licensee control of the vendor during the leak repair was weak with respect to the drilling of the injection hole and control of the quantity of leak sealant injected. Initial indications are that the amount of leak sealant material injected was greater than planned and approved by the licensee and vendor. Regional Action: The resident inspectors have closely monitored the licensee's repairs to the reactor head vent system. They will continue to monitor repair and testing of the system and the licensee's root cause investigation and corrective actions. Contact: Peter Eselgroth (610)337-5234 David Kern (412)643-2000 _ REGION III MORNING REPORT PAGE 7 DECEMBER 10, 1996 Licensee/Facility: Notification: Wisconsin Electric Power Co. MR Number: 3-96-0128 Point Beach 1 2 Date: 12/10/96 Two Rivers,Wisconsin DISCUSSION WITH SRI INSPECTOR Dockets: 50-266,50-301 PWR/W-2-LP,PWR/W-2-LP Subject: POINT BEACH MANAGEMENT CHANGES Discussion: On December 9, 1996, Wisconsin Electric announced that Mr. Robert Link, Vice President, Nuclear Power, resigned effective immediately. Mr. Richard Grigg, President of Wisconsin Electric will assume the duties as Chief Nuclear Officer. Mr. Scott Patulski, General Manager of Nuclear Operations, was promoted to Site Vice President at the Point Beach Nuclear Plant. Regional Action: For Information Contact: J. MCCORMICK-BARGER (630)829-9872 _