Headquarters Daily Report JULY 03, 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 - HEADQUARTERS JULY 3, 1996 MR Number: H-96-0052 NRR DAILY REPORT ITEM GENERIC COMMUNICATIONS NRC Information Notice 96-39, "Estimates of Decay Heat Using ANS 5.1 Decay Heat Standard May Vary Significantly," dated July 5, 1996. The NRC is issuing this information notice to alert addressees to the sensitivity of analytical results to input parameters used with American Nuclear Society standard 5.1 on decay heat. Technical contacts: W. L. Jensen, NRR (301) 415-2856 J. L. Birmingham, NRR (301) 415-2829 _ REGION II MORNING REPORT PAGE 2 JULY 3, 1996 Licensee/Facility: Notification: Duke Power Co. MR Number: 2-96-0060 Mc Guire 1 2 Date: 07/03/96 Cornelius,North Carolina Dockets: 50-369,50-370 PWR/W-4-LP,PWR/W-4-LP Subject: FAILURE OF REACTOR TRIP BREAKERS DURING INSPECTION/TESTING (FOLLOWUP TO EARLIER FAILURE) Discussion: On July 1, 1996, with Unit 1 at 100% power, while performing special inspection of the reactor trip and bypass breakers, the licensee identified that the secondary contact block on the back of the main B train reactor trip breaker (RTB) was broke in half and one of the secondary finger contacts had fallen into the breaker cubicle during removal of the breaker. The RTBs and bypass RTBs are Westinghouse model DS-416 with the secondary contact block manufactured by Cutler-Hammer The B train bypass RTB was in service at the time, providing unit trip protection during the B train main RTB inspection. In this configuration, Technical Specifications limit unit operation on the bypass breaker to two hours due to the reduction in the redundancy for protective trip functions (shunt and under voltage trip power supplies). Subsequently, the licensee removed the fallen finger contact and inspected the breaker cubical for damage. The licensee did not identify any damage to the cubical or electrical contacts and successfully replaced the affected breaker with the A train bypass RTB. Required testing of the replacement breaker was completed and the main B train RTB was placed in service. The licensee considered the main B train RTB operability to be unaffected by these deficiencies. The special inspection was being performed due to a previous Unit 2 reactor trip breaker problem identified on June 12, 1996, when a Unit 2 bypass RTB failed to open during testing. Inspection of the Unit 2 bypass breaker revealed a small piece of the secondary contact block broken and lodged in one of the finger contacts, preventing movement. Unit 2 was shutdown in MODE 5 at the time of discovery. Following questions from the resident inspector staff on reportability of the failure, the licensee reported the bypass RTB failure to the NRC on June 26, 1996 (EA-30680). The Unit 1 B train RTB was the last breaker being inspected for this problem. No similar problems (chips or cracks on the secondary contact blocks) were identified on the Unit 1 or 2 RTBs and bypass RTBs prior to identification of the current Unit 1 cracked secondary block problem. Regional Action: The resident inspectors were on site during the identification of the Unit 1 contact failure and observed the immediate corrective actions taken by the licensee. Currently, no root cause has been positively identified for either of the RTB secondary contact problems. The resident inspectors will continue to monitor these failures and the licensee's root cause evaluations for generic applicability. The Region is considering an Information Notice to address this issue. Contact: S. RUDISAIL (404)331-5563 _ REGION III MORNING REPORT PAGE 3 JULY 3, 1996 Licensee/Facility: Notification: Toledo Edison Co. MR Number: 3-96-0072 Davis Besse 1 Date: 07/01/96 Oak Harbor,Ohio RI VIA PC Dockets: 50-346 PWR/B&W-R-LP Subject: SENIOR MANAGEMENT CHANGES Discussion: On July 1, 1996, Centerior Service Corporation announced several senior management changes that affect both Davis-Besse (D-B) and Perry Nuclear Units. John Stetz, currently the D-B Site Vice President, has been named Senior Vice President-Nuclear and will be responsible for both nuclear units. Donald Shelton, the current Senior VP, will retire after completing a turnover with Mr. Stetz. John Wood, currently the D-B Plant Manager, will become the D-B Site VP. James Lash, currently the D-B Director of Engineering and Services, will become the D-B Plant Manager. Robert Donnellon, currently the D-B Manager of Engineering, will be promoted to D-B Director of Engineering and Services. The Perry Site VP position remains vacant. Mr. Shelton, in addition to his normal duties, has been the acting Perry Site VP as well. It is anticipated that he will continue in that role until his retirement in September. All changes were to be effective immediately. Regional Action: For information only Contact: R. D. LANKSBURY (708)829-9631 _ REGION III MORNING REPORT PAGE 4 JULY 3, 1996 Licensee/Facility: Notification: Cleveland Electric Illuminating Co. MR Number: 3-96-0073 Perry 1 Date: 07/01/96 Perry,Ohio RI VIA PC Dockets: 50-440 BWR/GE-6 Subject: SENIOR MANAGEMENT CHANGES Discussion: On July 1, 1996, Centerior Service Corporation announced several senior management changes that affect both Davis-Besse (D-B) and Perry Nuclear Units. John Stetz, currently the D-B Site Vice President, has been named Senior Vice President-Nuclear and will be responsible for both nuclear units. Donald Shelton, the current Senior VP, will retire after completing a turnover with Mr. Stetz. John Wood, currently the D-B Plant Manager, will become the D-B Site VP. James Lash, currently the D-B Director of Engineering and Services, will become the D-B Plant Manager. Robert Donnellon, currently the D-B Manager of Engineering, will be promoted to D-B Director of Engineering and Services. The Perry Site VP position remains vacant. Mr. Shelton, in addition to his normal duties, has been the acting Perry Site VP as well. It is anticipated that he will continue in that role until his retirement in September. All changes were to be effective immediately. Regional Action: For information only Contact: R. D. LANKSBURY (708)829-9631 _ REGION IV MORNING REPORT PAGE 5 JULY 3, 1996 Licensee/Facility: Notification: Southern California Edison & San MR Number: 4-96-0073 Diego Gas & Electric Co. Date: 07/02/96 San Onofre 2 3 Phone Call From Resident Inspectors San Clemente,California Dockets: 50-361,50-362 PWR/CE,PWR/CE Washington Public Power Supply System Washington Nuclear 2 Richland,Washington Dockets: 50-397 BWR/GE-5 Subject: POWER INTERRUPTION IN WESTERN UNITED STATES Discussion: At approximately 1:25 p.m. (PDT) on July 2, 1996, an electric power interruption occurred on the Pacific Intertie, near the California - Oregon boarder. As a result of the interruption, power outages were experienced throughout the Western United States. More than one and one-half million customers were affected from Colorado to California. The nuclear power plants in the Western United States were not affected by the power interruption, although electric frequencies dropped as low as 59.1 Hz for short periods of time. The units at San Onofre, Palo Verde, and Diablo Canyon continued to operate at full power. Washington Nuclear 2 was performing feedwater testing at the time of the power interruption and continued to operate at approximately 60 percent power. The cause of the power interruption is under investigation. Regional Action: No special action required. NRC resident inspectors continue to observe activities at the facilities. Contact: Dennis Kirsch (510)975-0290 Mark Hammond (510)975-0260 _