Headquarters Daily Report JANUARY 17, 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 JANUARY 17, 1997 MR Number: H-97-0003 NRR DAILY REPORT ITEM GENERIC COMMUNICATIONS NRC Administrative Letter 97-01, "State Initiatives to Legalize Schedule 1 Drugs," dated January 17, 1997. The NRC is issuing this administrative letter to remind addressees that the requirements of Part 26 of Title 10 of the Code of Federal Regulations (10 CFR Part 26) remain in effect, even where State law attempts to legalize the use of Schedule 1 drugs. Technical contacts: Reactor Licensees: Loren Bush, NRR (301) 415-2944 Fuel Cycle Licensees: Brett Mill, NMSS (301) 415-8152 _ REGION IV MORNING REPORT PAGE 2 JANUARY 17, 1997 Licensee/Facility: Notification: Southern California Edison & San MR Number: 4-97-0002 Diego Gas & Electric Co. Date: 01/17/97 San Onofre 2 3 Resident Inspector San Clemente,California Dockets: 50-361,50-362 PWR/CE,PWR/CE Subject: STEAM GENERATOR (SG) EDDY-CURRENT TESTING (ECT) PRELIMINARY RESULTS Discussion: During the current Unit 2 refueling outage, the licensee is performing an ECT inspection program consisting of full-length bobbin inspection of all tubes and motorized-rotating pancake coil inspection (MRPC) of selected areas. In addition, the licensee is performing enhanced inspection of tubes in the upper bundle considered susceptible to freespan axial cracking based on experience at similar plants. Further testing and evaluation of test data is in progress; however, sufficient data has been analyzed to identify significant degradation beyond that predicted based on previous inspection results. In addition to finding cracks in potentially susceptible areas, the licensee identified freespan axial cracks in tubes outside the susceptible region. The licensee has also identified a number of dent indications at eggcrate support intersections. Based on available data, the licensee is considering pulling one or more tubes and performing a limited number of individual tube pressure tests for diagnostic purposes. Based on preliminary review of ECT results, the licensee believes that the cracks are shallow and slowly propagating. The licensee is reviewing the implications of the Unit 2 data on operation and inspection of Unit 3. Unit 3 is currently operating at approximately 100 percent power and is scheduled to begin a refueling outage in mid-April 1997. Both units have similar operating histories (including plant chemistry) and, with the exception of the recent enhanced upper bundle inspection on Unit 2, the ECT inspection program in the last outage was the same in both units. Regional Action: The resident inspectors will review the licensee's actions and provide information to Regional engineering personnel. Contact: J. A. Sloan (714)492-2641 D. E. Corporandy (510)975-0319 _ REGION IV MORNING REPORT PAGE 3 JANUARY 17, 1997 Licensee/Facility: Notification: Washington Public Power Supply System MR Number: 4-97-0003 Washington Nuclear 2 Date: 01/15/97 Richland,Washington SRI Call to Regional office Dockets: 50-397 BWR/GE-5 Subject: MANUAL REACTOR RECIRCULATION PUMP TRIP Discussion: On January 15, 1997, at approximately 2:02 p.m. (PST) with the reactor at 100 percent power, Adjustable Speed Drive (ASD) 1A1 malfunctioned, causing fluctuations in reactor recirculation pump speed and resultant changes in reactor flow and power. Reactor power fluctuated four times over a 50-second interval between a minimum of 65 and a maximum of 113 percent power. The ASD output appeared to rapidly decrease and then cycle from full output to zero output. The control room operators tripped Reactor Recirculation Pump A, which terminated the flow and power changes, and transitioned the reactor to single-loop operation. The licensee's initial assessment was that, with the exception of ASD 1A1, all reactor systems performed as designed and operators responded to the event well. The reactor remains in single-loop operation at approximately 67 percent power while the licensee investigates the cause of the ASD malfunction. The resident inspector was in the control room at the time of the event and observed both plant and operator response. Plant and operator response appeared appropriate. Regional Action: The resident inspector will continue to monitor the licensee's investigation of the cause of the event and appropriateness of the plant response. NRR and Regional staff reviewed the event with the licensee on January 16, 1997. The licensee will brief the NRC staff on the root cause of the ASD problem prior to restoration of two-loop operation. Contact: H. J. Wong (510)975-0296 R. C. Barr (509)377-2627 _