Headquarters Daily Report DECEMBER 09, 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 DEC. 09, 1997 MR Number: H-97-0150 NRR DAILY REPORT ITEM GENERIC COMMUNICATIONS NRC Information Notice 95-49, Supplement 1, "Seismic Adequacy of Thermo-Lag Panels," dated December 10, 1997. The NRC is issuing this information notice to inform addressees about the results of mechanical properties testing of Thermo-Lag 330-1 fire barrier material performed by the National Institute of Standards and Technology. Technical contact: Hans Ashar, NRR 301-415-2851 _ REGION I MORNING REPORT PAGE 2 DECEMBER 9, 1997 Licensee/Facility: Notification: Peco Energy Company. MR Number: 1-97-0065 Limerick 1 2 Date: 12/09/97 Philadelphia,Pennsylvania SRI PC Dockets: 50-352,50-353 BWR/GE-4,BWR/GE-4 Subject: PRIMARY CONTAINMENT ISOLATION VALVE CONFIGURATION ERROR AND INADEQUATE TESTING Discussion: On December 5, 1997, the licensee identified a mis-wired closing circuit for the Unit 1 reactor core isolation cooling (RCIC) inboard steam isolation valve. A contact that bypasses the closed limit switch and thermal overload protection had been incorrectly terminated. The circuit, as wired, would permit the closed limit switch instead of the torque switch to stop valve motion during an automatic isolation. Consequently, the valve may not close fully into the seat, creating the potential for leakage past this primary containment isolation valve (PCIV). The licensee declared the RCIC inboard steam isolation valve inoperable and isolated the penetration to comply with technical specifications. The licensee identified that the computerized wire termination data base was consistent with the mis-wired RCIC circuit. The licensee evaluated the data base and determined that a number of PCIVs had the same or similar type closing circuits. Further review found three additional data base descriptions that appeared to be discrepant. In field inspections of these three discrepancies revealed only one additional valve, the Unit 1 RCIC exhaust line vacuum breaker, with the same mis-wiring. The licensee also identified that the PCIVs were not adequately tested. Specifically, the control circuit in question contains two parallel paths; one for manual operation with thermal overload protection and the other for automatic isolation with the thermal overload protection bypassed. Both these paths are energized during automatic valve isolation. The licensee identified that a failure of the bypass contact could be masked by the proper operation of the valve via the thermally protected portion of the circuit. Therefore, the test did not verify that a containment isolation signal would fully close the valve with the thermal overload protection bypassed, as required by technical specifications. The licensee implemented the appropriate technical specification requirements and subsequently tested the bypass contact for all affected valves. All but one PCIV functioned correctly when properly tested and the licensee is addressing this unrelated malfunction. The valve mis-wiring problem was identified by an engineer during a breaker cubicle inspection to evaluate the use of some non-quality parts. The licensee also determined that the problem was introduced during a modification added during construction to add a closed limit switch contact to address another issue with torque switch re-closure following valve isolation. REGION I MORNING REPORT PAGE 3 DECEMBER 9, 1997 MR Number: 1-97-0065 (cont.) Regional Action: The resident inspectors are following PECO Energy's continuing assessments and corrective actions. Contact: Clifford Anderson (610)337-5227 Arthur Burritt (610)327-1344 _ REGION I MORNING REPORT PAGE 3 DECEMBER 9, 1997 Licensee/Facility: Notification: Pennsylvania Power & Light Co. MR Number: 1-97-0066 Susquehanna 1 2 Date: 12/09/97 Allentown,Pennsylvania RI Telephone Dockets: 50-387,50-388 BWR/GE-4,BWR/GE-4 Subject: SENIOR MANAGEMENT CHANGES AT THE SUSQUEHANNA STEAM ELECTRIC STATION (SSES) Discussion: On December 8, 1997, PP&L announced organizational changes in the Nuclear Department's senior management structure under the Senior Vice President-Generation and Chief Nuclear Officer, Bob Byram. A new position of vice president-Site Operations was established to enhance the management team's ability to focus on making essential improvements in the day to day operations of Susquehanna. This position will be based at the site and as an interim measure, George Jones, Vice President-Operations, will immediately assume this responsibility. George Kuczynski, General Manager-SSES, will retain responsibility for day to day plant operations. Reporting to him will be the manager Outages, the manager-Nuclear Operations, the manager Nuclear Maintenance, the manager-Special Projects and the supervisors of Health Physics and Effluents Management. Reporting to the vice president- Site Operations will be the Supervisor-Nuclear Licensing, Manager-Nuclear Training, Manager-Nuclear Plant Services, Manager-Continuous Improvement, and the Manager-HR&D. Future changes planned for the organization will establish three officers, the vice president-Site Operations, the vice president-Engineering & Support, and the vice president-Power Production & Engineering. After a vice president- Site Operations is selected, George Jones will return to the corporate office position of vice president-Engineering & Support. Regional Action: This Is For Informational Purposes Only. Contact: Clifford Anderson (610)337-5227 _