Headquarters Daily report MARCH 23, 1995 *************************************************************************** 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 MARCH 23, 1995 Licensee/Facility: Notification: Part 21 Database MR Number: H-95-0079 Limitorque Corp. Date: 03/22/95 Subject: Reportable Event Number: N/A Discussion: VENDOR: LIMITORQUE CORP. PT21 FILE NO: 95057 DATE OF DOCUMENT: 03/07/95 ACCESSION NUMBER: SOURCE DOCUMENT: Part 21 REVIEWER: OECB: J. TAPPERT LIMITORQUE CORP REPORTS RECEIPT OF MOTORS FROM SUPPLIER WITH BUNA-N GREASE SEALS RATHER THAN VITON. SEAL FAILURE DUE TO LOWER TEMP CAPABLTY. MOTOR USED IN SMB/SB/SBD 000 THRU 5 & SMB 000 THRU5/HBC 0 THRU 7 ACTUTR COMB. CORREC ACTION/AFFCTD LICENSEES IDEN. PRIORITY ATTENTION REQUIRED MORNING REPORT - HEADQUARTERS MARCH 23, 1995 MR Number: H-95-0080 NRR DAILY REPORT ITEM GENERIC COMMUNICATIONS BRANCH/EVENTS ASSESSMENT BRANCH DIVISION OF OPERATING REACTOR SUPPORT OFFICE OF NUCLEAR REACTOR REGULATION Subject: N/A NRC Information Notice 95-20, "Failures in Rosemount Pressure Transmitters due to Hydrogen Permeation into the Sensor Cell," issued March 22, 1995. The NRC issued this information notice to alert addressees to a potential failure mode in Rosemount Nuclear Instruments, Incorporated, Model 1152, 1153 and 1154 pressure transmitters due to hydrogen gas permeation through the isolating diaphragm exposed to process fluid. Technical contacts: S.V. Athavale, NRR Mark S. Miller, RII (301) 415-2974 (407) 464-7822 Stephen Alexander, NRR Jerry L. Mauck, NRR (301) 415-2995 (301) 415-3248 PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION II MARCH 23, 1995 Licensee/Facility: Notification: Southern Nuclear Operating Co. MR Number: 2-95-0035 Farley 1 2 Date: 03/23/95 Ashford,Alabama ONSITE REGIONAL INSPECTOR Dockets: 50-348,50-364 PWR/W-3-LP,PWR/W-3-LP Subject: CONTAMINATED CONTRACT WORKER ENTERS FARLEY Reportable Event Number: N/A Discussion: The licensee identified a contaminated contract worker during his inprocessing on March 21, 1995, at the Farley Nuclear Plant near Dothan, Alabama. The worker was detected to have low level contamination of approximately 1000 dpm of Cobalt 60 on the inside of his shoes and has now been fully deconned. The worker was employed to do RHR work during the ongoing Farley outage and had apparently been contaminated during work he had earlier performed at a nuclear plant in Spain. The licensee informed the NRC resident inspectors and the State of Alabama Department of Radiological Health on March 22, 1995. The State of Alabama dispatched two HP personnel to conduct surveys of the individual's motel room in Dothan, Alabama which was found to be clean. The licensee provided two HPs to accompany and assist the State of Alabama personnel during the surveys of the motel. Regional Action: An NRC Senior Radiation Specialist, who was onsite conducting a routine inspection will continue to provide followup as required. The NRC Region II office informed the State of Alabama and the NRC's Offices of International Programs and State Programs. Contact: W. RANKIN (404)331-5618 PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION IV MARCH 23, 1995 Licensee/Facility: Notification: Southern California Edison & San MR Number: 4-95-0037 Diego Gas & Electric Co. Date: 03/23/95 San Onofre 2 PHONE CALL FROM RESIDENT INSPECTORS San Clemente,California Dockets: 50-361 PWR/CE Subject: LOSS OF INVENTORY IN UNIT 2 REACTOR VESSEL Reportable Event Number: N/A Discussion: On March 21, 1995, with Unit 2 in Mode 5 during a refueling outage, a leak developed in a letdown filter located in the chemical and volume control system. Approximately 1000 gallons of inventory drained from the reactor vessel before the leak was isolated. While Unit 2 was in Mode 5 with preparations being made for Mode 4 entry, operators filled, vented, and placed into service a new chemical and volume control system letdown filter. Approximately five minutes later and before any alarms were received in the control room, operators noted a decrease in reactor vessel water level (from 1.22 to 1.43 feet below the reactor vessel flange). Operators inspected and observed no leakage from the letdown filter's vent and drain valves and took action to investigate other ongoing activities which may have resulted in the loss of inventory. After 20 minutes, operators identified a leak from the letdown filter housing, and isolated the filter. Water level stabilized at 2.28 feet below the reactor vessel flange. The top of the reactor coolant system hot leg piping is approximately 4.8 feet below the reactor vessel flange. During the period that the leak occurred, no abnormal shutdown cooling indications were observed. The water leaking from the filter drained to the radioactive waste system in the Unit 2 auxiliary building. The licensee's preliminary investigation revealed that the cause for the leak was an improper seal by an o-ring on the cover of the letdown filter. Regional Action: The resident inspectors will continue to assess and monitor the licensee's investigation and corrective actions. Contact: B. Olson (510)975-0295 J. Sloan (714)492-2641