Headquarters Daily Report JULY 30, 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 JULY 30, 1997 MR Number: H-97-0093 NRR DAILY REPORT ITEM GENERIC COMMUNICATIONS NRC Information Notice 97-59, "Fire Endurance Test Results of Versawrap Fire Barriers," dated August 1, 1997. The NRC is issuing this information notice to alert addressees to the preliminary results of a recent fire endurance test of a new fire barrier system. Technical contacts: K.S. West, NRR 301-415-1220 T.J. Carter, NRR 301-415-1153 NRC Information Notice 97-60, "Incorrect Unreviewed Safety Question Determination Related to Emergency Core Cooling System Swapover from the Injection Mode to the Recirculation Mode," dated August 1, 1997. The NRC is issuing this information notice to alert addressees to an instance in which a licensee has incorrectly determined that changes to its emergency core cooling system swapover procedures that resulted in interruption of flow and a consequent core heatup in the long-term cooling phase of a potential loss-of-coolant accident did not involve an unreviewed safety question. Technical contacts: Mohammed A. Shuaibi, NRR Thomas Koshy, NRR 301-415-2859 301-415-1176 Frank R. Orr, NRR Doug Dempsey, RI 301-415-1815 (610) 337-5347 _ HEADQUARTERS MORNING REPORT PAGE 2 JULY 30, 1997 MR Number: H-97-0094 NRR DAILY REPORT ITEM GENERIC COMMUNICATIONS Information Notice 97-58,"MECHANICAL INTEGRITY OF IN-SITU LEACH INJECTION WELLS AND PIPING," will be issued on July 31, 1997. This notice is being issued to all holders of, and applicants for licenses for in-situ leach facilities to alert them to leaks related to faulty coupling and configuration of piping. Contact: J. Robert Tinsley, NMSS 301-415-6251 E-mail: jrt1@nrc.gov _ REGION III MORNING REPORT PAGE 3 JULY 30, 1997 Licensee/Facility: Notification: Commonwealth Edison Co. MR Number: 3-97-0086 Dresden 2 Date: 07/28/97 Morris,Illinois TELCON FROM RESIDENT INSPECTOR Dockets: 50-237 BWR/GE-3 Subject: MANUAL REACTOR SCRAM Discussion: On July 28, 1997, at approximately 1:45 a.m., the reactor operator initiated a reactor scram at the direction of the Unit Supervisor. The Unit 2 reactor, which operates in single element reactor vessel level control, was experiencing level transients as a result of attempting to transfer reactor feed to the 2C reactor feed pump from the 2B pump. The 2A reactor feed pump was also in service at the time. Reactor power had been reduced to approximately 85 percent power for the pump swap-over that was being performed in order to trouble shoot the 2B reactor feed pump recirculation valve which cycled unexpectedly open and closed on July 27, 1997, causing reactor level transients. The July 28 level transient was initiated when operators started the 2C reactor feed pump. With three reactor feedpumps in service, the reactor vessel level increased from 30 inches to 35 inches in approximately 20 seconds. The operator took manual control of the feedwater regulating valves and closed the valves. The reactor vessel level began to drop and reached 25 inches. The operator quickly opened the feedwater regulating valves, but the 2C reactor feed pump tripped on low suction pressure. With level dropping and one pump tripped, the Unit Supervisor directed a manual scram of the reactor. The time that elapsed from taking manual control of the feedwater regulating valves until the reactor was scrammed was approximately 24 seconds. Regional Action: Resident inspector responded to the site. A scram investigation team was dispatched to the site on July 29, 1997. Contact: W. KROPP (630)829-9633 _ REGION IV MORNING REPORT PAGE 4 JULY 30, 1997 Licensee/Facility: Notification: Nebraska Public Power District MR Number: 4-97-0060 Cooper 1 Date: 07/30/97 Brownville,Nebraska From the SRI Dockets: 50-298 BWR/GE-4 Subject: PLANT SHUTDOWN Reportable Event Number: 32695 Discussion: At 2:10 a.m. (CDT) on July 29, 1997, a torus-to-drywell vacuum breaker (Nonreturn Valve NRV-28), failed its monthly surveillance test and was declared inoperable. The valve had opened, but failed to reclose. The licensee was not able to close the valve and declared the primary containment inoperable at 8:35 a.m., after determining that the leakage between the drywell and suppression chamber was greater than allowed. At 10 a.m., the licensee initiated a plant shutdown as required by plant Technical Specifications. The unit achieved hot shutdown at 2:12 p.m. on July 29, when the licensee scrammed the reactor from about 20 percent power as part of the normal shutdown procedure. The unit achieved cold shutdown at about 2 a.m. on July 30. The unit is expected to be off line about 2 days while repairs are completed. Regional Action: The NRC resident inspectors observed the unit shutdown and are reviewing licensee outage activities. Contact: Mary H. Miller (402)825-3371 Elmo E. Collins (817)860-8291 _ REGION IV MORNING REPORT PAGE 5 JULY 30, 1997 Licensee/Facility: Notification: Entergy Operations, Inc. MR Number: 4-97-0061 Waterford 3 Date: 07/30/97 Killona,Louisiana Phone Call from Senior Resident Dockets: 50-382 PWR/CE Subject: RESTART FROM REFUELING OUTAGE Discussion: On July 29, 1997, the Waterford 3 facility was connected to the grid to end a 109 day refueling outage. The outage was extended as a result of the unanticipated replacement of a startup transformer. The transformer failed because of an internal fault and the licensee was required to obtain a replacement transformer since one was not available on site. During the outage, the licensee inspected steam generator tubes, refueled the reactor vessel, and installed plant modifications to correct and/or enhance component and equipment performance. Regional Action: For information only. Contact: P. H. Harrell (817)860-8250 L. A. Keller (504)783-6253 _