Headquarters Daily report JULY 25, 1994 *************************************************************************** REPORT NEGATIVE NO INPUT ATTACHED INPUT RECEIVED RECEIVED HEADQUARTERS X REGION I X REGION II X REGION III X REGION IV X *************************************************************************** PRIORITY ATTENTION REQUIRED MORNING REPORT - HEADQUARTERS JULY 25, 1994 MR Number: H-94-0065 NRR DAILY REPORT ITEM GENERIC COMMUNICATIONS BRANCH/EVENTS ASSESSMENT BRANCH DIVISION OF OPERATING REACTOR SUPPORT OFFICE OF NUCLEAR REACTOR REGULATION Subject: N/A NRC Generic Letter 94-03,"Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors," will be issued July 25, 1994. The NRC issued this generic letter to request addressees: (1) inspect the core shrouds in their BWR plants no later than the next scheduled refueling outage, and perform an appropriate evaluation and/or repair based on the results of the inspection; and (2) perform a safety analysis supporting continued operation of the facility until inspections are conducted. Technical contacts: E. M. Hackett, NRR (301) 504-2751 A. E. Cubbage, NRR (301) 504-2875 Lead Project Manager: D. S. Brinkman, NRR (301) 504-1409 PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION II JULY 25, 1994 Licensee/Facility: Notification: Tennessee Valley Authority MR Number: 2-94-0065 Sequoyah 2 Date: 07/25/94 Soddy-Daisy,Tennessee Dockets: 50-328 PWR/W-4-LP Subject: BENT CONTROL ROD DRIVE SHAFT Reportable Event Number: N/A Discussion: On July 22, 1994, the licensee was performing activities to replace the reactor head following core offload. The upper core support structure (upper internals) were in place in the vessel, all fuel assemblies removed, and the vessel water level was approximately one foot below the reactor flange. The purpose of this evolution was to be able to drain the refueling cavity and repair a leaking cavity floor inspection port. The reactor head was being lowered onto the vessel when personnel monitoring the activity observed one of the control rod drive (CRD) shafts being significantly bent. Lowering of the reactor head was secured at approximately 6 feet above the vessel flange and limited inspections were made of the CRD shafts and reactor head guide components. The inspections revealed that one CRD shaft was misaligned and appeared to have been bent into an "s" shape. In addition, the alignment funnel for this shaft, which is normally attached to the bottom of the head adapter guide tube extending through the reactor head, was dislodged and rested around the CRD shaft at the point where the shaft protrudes from the control rod guide tube extension. After initial reviews were completed, the reactor head was raised and placed on its stand. Immediate activities included placing the CRD missile shield for dose reduction during the development of an action plan to repair the damaged components. During the last 60 hours, the licensee lowered vessel level to mid-loop to install the steam generator nozzle dams and conduct valve maintenance. After nozzle dams were installed, the missile shields were removed and vessel level was raised. The licensee's plans as of July 25, 1994, are to remove the upper internals package and place in its stand then place the reactor head on the vessel. Water level will then be lowered to repair the leaking inspection port. The licensee commenced an incident investigation for this event. Regional Action: The resident inspectors reviewed the licensee's immediate actions and are continuing followup of the licensee's investigation of root cause and corrective actions. Contact: Mark S. Lesser (404)331-0342 PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION III JULY 25, 1994 Licensee/Facility: Notification: Mercy Medical Center MR Number: 3-94-0132 Mercy Medical Center Date: 07/22/94 Springfield,Ohio VIA TELEPHONE Dockets: 03007510 License No: 34-00852-03 Subject: TELETHERAPY SOURCE DID NOT FULLY RETRACT TO SHIELDED POSITION Reportable Event Number: N/A Discussion: On July 22, 1994, the licensee's Radiation Safety Officer (RSO) informed Region III that a source (approximately 6000 curies, cobalt-60) in a Picker C-9 teletherapy unit failed to fully retract into the shielded position. The event occurred on July 21, 1994, during the performance of monthly spot- checks required by 10 CFR 35.634 to determine the coincidence of the radiation field utilizing the light beam localizing device. The RSO stated that when the unit was turned on, indicator lights on the console, Prime Alert, and treatment room door appeared to function as required. After completion of the exposure (0.13 minutes) the Prime Alert red light was off, indicating the radiation level in the therapy room had decreased. The treatment door light, however, showed both red and green lights and the console lights indicated a beam-on condition. The RSO entered the room using a calibrated Victoreen 290 survey meter. Radiation levels of 1-2 mR/hr were indicated. As he continued into the room to retrieve the x-ray film, he observed maximum readings of between 5-6 mR/hr near the teletherapy unit. The RSO estimated the time spent retrieving the x-ray film to be about 3 to 5 seconds. Upon exiting the room, the RSO reset the unit timer and attempted to duplicate the event. The unit turned on and the source returned to the shielded position. According to the RSO, upon subsequent trials, the unit did not duplicate the malfunction. The unit was immediately taken out of service. Atom Therapy Services, an authorized service company, was contacted and will evaluate and perform any required maintenance on the unit on July 25, 1994. The RSO sent his film badge in for immediate processing. He also verified the functioning of the Prime Alert. Region III will be informed of the dosimetry results and the results of the maintenance and evaluation of the teletherapy unit. In addition, the licensee will provide a report of the incident within 30 days. Regional Action: Region III will evaluate all information received from the licensee and, based on the results, determine the appropriate action to take. NMSS was notified. Contact: B.J. HOLT (708)829-9836 SAM J. MULAY (708)829-9859 PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION III JULY 25, 1994 Licensee/Facility: Notification: Commonwealth Edison Co. MR Number: 3-94-0133 Quad Cities 1 Date: 07/23/94 Cordova,Illinois SRI VIA LOCAL AREA NETWORK Dockets: 50-254 BWR/GE-3 Subject: FOREIGN MATERIAL IN RESIDUAL HEAT REMOVAL (RHR) SYSTEM Reportable Event Number: N/A Discussion: On July 14, 1994, during a post maintenance test run of the "A" loop of the RHR system, test data indicated that valve 1001-36A, RHR Torus Cooling/Test Return Valve, was plugged. The 36A valve was opened for inspection; remains of a yellow plastic bag were found shredded and caught within the anti-cavitation trim which was installed during the recent outage. The material appeared to have travelled the entire way through the anti- cavitation trim. The majority of the material was found lodged on the suction side of the valve trim. Subsequent to the July 14 event, the licensee observed reduced flow from the "C" RHR pump and initiated further investigation. On July 23, 1994, licensee maintenance personnel removed a drain plug on the volute of the "C" RHR pump and used a boroscope to inspect the pump internals. A 4 inch diameter wire brush wheel and a part of a putty knife were found wrapped around a vane of the pump. The licensee opened the RHR system during the outage to work on the RHR 7D valve and removed a butterfly valve on the common suction line (valve RHR 6B). A subsequent attempt to remove the foreign materials was unsuccessful. The licensee is evaluating disassembly of the "C" RHR pump to retrieve the material. Regional Action: Resident and regional inspectors will continue to evaluate the effects of foreign material on safety system performance and licensee corrective actions. Contact: P.L. HILAND (708)829-9603 PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION IV JULY 25, 1994 Licensee/Facility: Notification: Omaha Public Power District MR Number: 4-94-0067 Ft Calhoun 1 Date: 07/22/94 Fort Calhoun,Nebraska Senior Resident Inspector Dockets: 50-285 PWR/CE Subject: NEW LICENSING MANAGER Reportable Event Number: N/A Discussion: On July 22, 1994, the Omaha Public Power District announced that Mr. Delvin Trausch will replace Mr. Ron Short as Manager-Nuclear Licensing and Industry Affairs, effective August 22. Mr. Trausch is the Acting Manager-Training and previously was the Supervisor-Operations. Mr. Short is currently in the operator licensing class. Regional Action: For information only. Contact: W. D. Johnson (817)860-8148