Headquarters Daily Report FEBRUARY 05, 1997 *************************************************************************** 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 - HEADQUARTERS FEB. 05, 1997 MR Number: H-97-0005 NRR DAILY REPORT ITEM GENERIC COMMUNICATIONS NRC Information Notice 97-02, "Cracks Found in Jet Pump Riser Assembly Elbows at Boiling Water Reactors," dated February 6, 1997. The NRC is issuing the information notice to alert addressees that cracking has been detected in a jet pump riser assembly at a location not previously known to have cracks. Technical contacts: C. E. Carpenter, Jr., NRR (301) 415-2169 Kerri A. Kavanagh, NRR (301) 415-3743 _ REGION I MORNING REPORT PAGE 2 FEBRUARY 5, 1997 Licensee/Facility: Notification: MR Number: 1-97-0012 Crozer Chester Medical Center Date: 02/03/97 Upland,Pennsylvania Dockets: 03003159 License No: 37-12240-01 Subject: Misadministration Discussion: On February 3, 1997, NRC Operations Center received from Crozer Chester Medical Center, Upland, PA, a notification of an apparent brachytherapy (cesium-137) misadministration that occurred on October 5, 1994, while treating a patient for endometrium cancer. The misadministration was identified during a routine inspection conducted January 27 & 28, 1997. During the inspection, in discussions with the attending radiation oncologist, the inspector learned that the apparent misadministration was caused by the patient unintentionally dislodging the cesium-137 source. The brachytherapy source and the applicator were dislodged and rested on the patient's thigh for approximately one and one-half hour. Initially, the licensee estimated the dose to the patient's thigh to be 270 centigray. However, the licensee is currently performing a more comprehensive evaluation of the dose to the unintended site and will submit a written report of the event to the NRC. The licensee stated that when the event occurred initially, the NRC was notified by telephone and they were informed that since the event was caused by patient intervention, it was a recordable but not reportable event. Regional Action: Based on the inspection findings, Region I, in coordination with NMSS, is reassessing this event. Contact: Teresa Hall Darden (610)337-5245 Mohamed Shanbaky (610)337-5209 _ REGION I MORNING REPORT PAGE 3 FEBRUARY 5, 1997 Licensee/Facility: Notification: New York Power Authority MR Number: 1-97-0013 Indian Point 3 Date: 02/05/97 Buchanan,New York SRI PC Dockets: 50-286 PWR/W-4-LP Subject: NYPA SENIOR MANAGEMENT CHANGE (ALSO INCLUDES CHANGES TO J. A. FITZPATRICK SENIOR MANAGEMENT - DN 05000333) Discussion: On February 4, 1997, the following management change was announced for the New York Power Authority (NYPA). Effective February 24, 1997, Mr. Jim Knubel will succeed Mr. William Cahill as NYPA senior vice president and Chief Nuclear Officer (CNO). Mr. William Cahill is retiring from the senior vice president and CNO position. Since June 1995, Mr. Jim Knubel was vice president and director of Three Mile Island (TMI) Nuclear Station. Prior to Mr. Knubel's selection as TMI site director, he served as plant operations director at the Oyster Creek Nuclear Station. Regional Action: This Is For Informational Purposes Only. Contact: Curtis Cowgill (610)337-5233 _ REGION III MORNING REPORT PAGE 4 FEBRUARY 5, 1997 Licensee/Facility: Notification: Consumers Power Co. MR Number: 3-97-0016 Big Rock Point 1 Date: 02/03/97 Charlevoix,Michigan PHONE CALL FROM RESIDENT INSPECTORS Dockets: 50-155 BWR/GE-1 Subject: REACTOR STARTUP Discussion: The reactor was started up on February 1 and the turbine was paralleled to the grid at 1:27 p.m. February 2, 1997, completing a 57-day forced outage. The outage started when the reactor scrammed on high power following a loss of the generator voltage regulator. Major work accomplished included low pressure turbine repair, a containment integrated leak rate test, and main steam stop repairs. Regional Action: Resident Inspector coverage Contact: BRUCE BURGESS (630)829-9629 _ REGION III MORNING REPORT PAGE 5 FEBRUARY 5, 1997 Licensee/Facility: Notification: Wisconsin Public Service Corp. MR Number: 3-97-0017 Kewaunee 1 Date: 02/05/97 Kewaunee,Wisconsin Dockets: 50-305 PWR/W-2-LP Subject: STEAM GENERATOR WELD REPAIR Discussion: Over the weekend, the licensee identified leaking tubes in both steam generators that had been repaired using a laser weld in the upper hybrid expansion joint (HEJ) sleeves above the location of the parent tube degradation. This repair method was an alternative to plugging. The weld replaces the HEJ as the structural boundary and essentially modifies the HEJ sleeve to the configuration of a conventional laser welded sleeve. The degradation of the parent tube within the HEJ (below the laser weld) would be immaterial to the structural and leakage integrity of the repaired joint. Kewaunee had completed laser weld repairs in both generators. A hydrostatic head was applied on the secondary side of the B generator, and 4 repaired sleeves were detected leaking ("dripping"). The A generator was then examined under a static head, and approximately 40 leakers (drippers) were detected. A 100 psi overpressure was then applied on the A steam generator, and approximately an additional 32 leakers were detected. Eddy current (ET) exams were repeated for the leakers, and no anomalies were detected. Repeat ultrasonic exams (UT) of the weld area will be completed when the equipment returns to the site (within the next two days). Previously obtained ultrasonic and eddy current data were reassessed. The UT Analysis results were the same as the original calls (that is, acceptable welds). Video examinations of the leaky tubes indicated that the leaks were over the top of the edge of the sleeve. Grab samples of the leakage confirmed that it was secondary fluid. The cause of the leakage is unknown at this time. Westinghouse representatives on site and at two corporate facilities are currently supporting the evaluation of the leaky tubes. Contact: BRUCE BURGESS (630)829-9629 _