Headquarters Daily Report MAY 27, 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 - REGION III MAY 27, 1997 Licensee/Facility: Notification: Iowa Electric Light & Power Co. MR Number: 3-97-0072 Duane Arnold 1 Date: 05/27/97 Palo,Iowa SRI PC Dockets: 50-331 BWR/GE-4 Subject: MAINTENANCE OUTAGE TO REPAIR MSIV INDICATION Discussion: On May 23, 1997, at 10:24 a.m. (CDT), the licensee commenced a reactor shutdown to repair a dual indication condition on the "C" inboard MSIV. Other maintenance items planned for the short duration outage included replacing the "B" IRM and replacing the drywell airlock test connection valves. Operators tripped the main turbine at 11:42 p.m. (CDT) on May 23, 1997, and inserted a manual scram at 00:51 a.m. (CDT midnight) on May 24. In addition to the planned repairs, the licensee completed work on two emergent items: a dual indication condition on a torus to drywell vacuum breaker and a leaking decontamination flange on the "A" recirculation discharge loop. The licensee commenced a reactor startup at 5:00 p.m. (CDT) on May 26, 1997. The reactor was made critical at 8:34 p.m. (CDT) on May 26, 1997. Startup activities are currently in progress. Regional Action: The resident inspectors monitored the plant shutdown, repair and outage activities, and the plant startup. Contact: M. JORDAN (630)829-9637 _ REGION IV MORNING REPORT PAGE 2 MAY 27, 1997 Licensee/Facility: Notification: Arizona Public Service Co. MR Number: 4-97-0045 Palo Verde 1 Date: 05/27/97 Wintersburg,Arizona Telephone Call from SRI Dockets: 50-528 PWR/CE80 Subject: UNIT 1 REACTOR TRIP (REFER TO EVENT 32393) Discussion: At approximately 12:34 a.m. (MST) on May 27, 1997, the Unit 1 reactor tripped on low DNBR resulting from the loss of two of the four reactor coolant pumps. Approximately 30 minutes prior to the trip, the voltage indication on nonsafety-related 13.8 KV bus NAN-SO1 began to decrease, although the actual bus voltage remained steady at the required value. At about 10.1 KV indicated voltage, the two reactor coolant pumps powered by the bus tripped as a result of the indicated undervoltage, resulting in a reactor trip on low DNBR. All systems responded as required. No safety equipment was called upon to operate. The unit is stable in Mode 3. The licensee believes that the potential transformer supplying the bus voltage indication malfunctioned because the bus never lost voltage. The licensee is working to establish the root cause. The Senior Resident Inspector responded to the site to verify the licensee's actions. Regional Action: The resident inspection staff will verify the root cause and assess readiness for restart. Contact: D. Kirsch (510)975-0290 K. Johnston (602)386-3638 _