Headquarters Daily Report JUNE 02, 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 JUNE 2, 1997 Licensee/Facility: Notification: Part 21 Database MR Number: H-97-0058 Ge Date: 06/02/97 Subject: PART 21 - Turbine pressure regulator downscale failure event not analyzed; affects minimum critical power ratio limit Discussion: VENDOR: GE PT21 FILE NO: 97-37-0 DATE OF DOCUMENT: 01/28/97 ACCESSION NUMBER: 9702030199 SOURCE DOCUMENT: LER 50-461/97-01 REVIEWER: PECB, V. Hodge NEW ISSUE. Clinton reports some potential to exceed minimum critial power ratio safety limit during previous cycles, given the subject event. The cause is attributed to an error by the nuclear fuel supplier in determining the limiting events to be analyzed for the fuel design. _ HEADQUARTERS MORNING REPORT PAGE 2 JUNE 2, 1997 Licensee/Facility: Notification: Part 21 Database MR Number: H-97-0059 Dragon Valves Date: 06/02/97 Subject: Part 21 - Improper QA certification of tubing welded on valve bodies Discussion: VENDOR: Dragon Valves PT21 FILE NO: 97-38-0 DATE OF DOCUMENT: 03/26/97 ACCESSION NUMBER: 9704010432 SOURCE DOCUMENT: REVIEWER: PECB, J. Carter NEW ISSUE. Watts Bar reports improper QA certification of steel tubing welded on valve bodies. Vendor does not consider this matter to be a substantial safety hazard. _ HEADQUARTERS MORNING REPORT PAGE 3 JUNE 2, 1997 Licensee/Facility: Notification: Part 21 Database MR Number: H-97-0060 Westinghouse Date: 06/02/97 Subject: Part 21 - Certain tests and inspections were not documented for refurbished type "DHP" and "DS" circuit breakers Discussion: VENDOR: Westinghouse PT21 FILE NO:97-39-0 DATE OF DOCUMENT: 05/14/97 ACCESSION NUMBER: SOURCE DOCUMENT: EN 32328 REVIEWER: PECB, D. Skeen NEW ISSUE. Westinghouse reports that certain tests and inspections were not performed or documented for refurbished and reinstalled type "DHP" series and "DS" series circuit breakers at Byron and Braidwood. These include timing test, contact resistance checks to correct values, reapplication of lubricant, opening force margin verification, and weld inspection. All affected breakers have been identified. _ HEADQUARTERS MORNING REPORT PAGE 4 JUNE 2, 1997 Licensee/Facility: Notification: Part 21 Database MR Number: H-97-0061 Siemens Date: 06/02/97 Subject: Part 21 - Inadequately supported critical heat flux correlation for ATRIUM (TM)-9 fuel design Discussion: VENDOR: Siemens PT21 FILE NO: 97-40-0 DATE OF DOCUMENT: 05/22/97 ACCESSION NUMBER: SOURCE DOCUMENT: EN 32379 REVIEWER: PECB, V. Hodge NEW ISSUE. The NRC determined that the critical heat flux data base for the ATRIUM (TM)-9 fuel design and other 9x9 fuel designs with internal water channels was not extensive enough to adequately estimate the uncertainties for the additive constants used in the critical heat flux correlations for these fuel designs. This may affect the minimum critical power ratio limit (NRC Inspection Report 9990081/97-01) at Quad Cities, Dresden, LaSalle, and WNP-2. _ HEADQUARTERS MORNING REPORT PAGE 5 JUNE 2, 1997 MR Number: H-97-0062 NRR DAILY REPORT ITEM GENERIC COMMUNICATIONS NRC Information Notice 97-31, "Failures of Reactor Coolant Pump Thermal Barriers and Check Valves in Foreign Plants," dated June 3, 1997. The NRC is issuing this information notice to alert addressees to reported problems discovered at foreign pressurized-water reactor plants. Technical contacts: Francis Grubelich, NRR 301-415-2784 Eric J. Benner, NRR 301-415-1171 _ REGION III MORNING REPORT PAGE 6 JUNE 2, 1997 Licensee/Facility: Notification: Commonwealth Edison Co. MR Number: 3-97-0074 Byron 1 Date: 05/31/97 Byron,Illinois LICENSE VIA ENS Dockets: 50-454 PWR/W-4-LP Subject: TECH. SPEC. REQUIRED SHUTDOWN Discussion: A REACTOR SHUTDOWN WAS CONDUCTED AS REQUIRED BY TECHNICAL SPECIFICATIONS 3.3.2 DUE TO A FAILURE OF THE 1A MAIN STEAM ISOLATION VALVE (MSIV) HYDRAULIC SINGLE TRAIN ACTUATOR CIRCUIT. THE FAILURE WAS IDENTIFIED WHILE CONDUCTING ROUTINE QUARTERLY SURVEILLANCE TESTING ON 5/29/97. THE FAILURE PLACED THE UNIT IN A 48 HOUR LCO WHICH EXPIRED AT 11:14 A.M. (CDT) ON 5/31. WHEN THE LICENSEE DISCOVERED THAT TIMELY REPAIRS COULD NOT BE MADE, THE SHUTDOWN WAS COMMENCED. THE MAIN GENERATOR WAS TAKEN OFF LINE AT 2:19 P.M. CDT ON 5/31/97. THE REACTOR WAS MANUALLY TRIPPED AT 2:58 P.M. CDT AND SUBSEQUENTLY PLACED IN MODE 4 (HOT SHUTDOWN.) THE LICENSEE CHANGED OUT THE SOLENOID OPERATED 4-WAY POSITIONER VALVE IN THE HYDRAULIC ACTUATOR CIRCUIT ON THE MSIV AND SATISFACTORILY COMPLETED THE SURVEILLANCE. THE OTHER THREE MSIVS WERE ALSO TESTED SATISFACTORILY. IN ORDER TO CONDUCT A STARTUP AN EMERGENCY TECH. SPEC. CHANGE WAS REQUESTED BY THE LICENSEE AND GRANTED BY NRR. THE EMERGENCY TECH. SPEC. CHANGE WAS NEEDED DUE TO AN EXISTING NOTICE OF ENFORCEMENT DISCRETION (NOED) RELATED TO VENTING THE CHARGING SYSTEM. THE NOED HAD BEEN GRANTED APPROXIMATELY 1 WEEK EARLIER TO PROVIDE SUFFICIENT TIME FOR AN EXIGENT TECH. SPEC. CHANGE TO BE ISSUED. THE LICENSEE PLANS TO RESTART THE UNIT FOLLOWING REPAIR OF A SAMPLE VALVE IN THE CONTAINMENT AIRBORNE AND GASEOUS MONITORING SYSTEM. Regional Action: THE RESIDENT INSPECTORS MONITORED THE SHUT DOWN AND WILL FOLLOW THE LICENSEE'S ACTIVITIES IN PREPARATION FOR STARTUP. Contact: R. D. LANKSBURY (630)829-9631 _ REGION III MORNING REPORT PAGE 7 JUNE 2, 1997 Licensee/Facility: Notification: Ohio Dept. Of Health, Bureau Of Pub. MR Number: 3-97-0075 Health Lab. Date: 05/29/97 Columbus, Ohio (Ohio Dept. Of Healt TELECON FROM OHIO DEPT. OF HEALTH Columbus,Ohio Dockets: 03008742 License No: 34-02305-03 Subject: LABORATORY AND PACKAGE CONTAMINATION Discussion: On May 29, 1997, the Ohio Department of Health Laboratory (ODHL) reported to Region III that one of two small, capped vials containing desiccant material, received from the Ohio Department of Agriculture (ODA) earlier that day, was externally contaminated with H-3. Approximately 3000 dpm of removable contamination was identified on one of the vials. The vials were found in the drawer of a laboratory at ODA's Consumer Analytical Laboratory in Reynoldsburg, Ohio, while the lab was being cleaned out by maintenance personnel on May 28, 1997. The vials were labeled with radiation caution symbols as containing 250 millicuries of H-3, dated 1978. The vials were hand delivered to ODHL by an ODA laboratory supervisor, so they could be analyzed to determine if they contained radioactive material. Although the vials were empty except for desiccant material, one was externally contaminated. ODA was previously licensed by the NRC for Ni-63 and H-3 foil sources for use in gas chromatograph units. The ODA last possessed H-3 foils in 1984, at which time three were returned to the gas chromatograph device manufacturer. It appears that the vials were part of a H-3 foil exchange kit, which were to house used foils for their return to the gas chromatograph device manufacturer. The cause of the contamination is unknown; however, leakage of one or more previously used H-3 foils is suspected. At NRC request, on May 30, 1997, the Radiation Protection Branch of the Ohio Department of Health conducted contamination smear surveys of the drawer where the vials were found, other ODA laboratory areas and the hands of two employees that handled the contaminated vials. All smear results were negative except one smear taken from the bottom of the drawer showed 20 dpm of H-3 contamination. No contamination was identified on the ODA employees. Regional Action: NMSS and the Office of State Programs were notified. No additional actions are planned at this time. The Ohio Department of Health Laboratory will retain possession of the contaminated vial for subsequent disposal along with other radioactive laboratory wastes. Contact: WAYNE SLAWINSKI (630)829-9820 JOHN MADERA (630)829-9834 _ REGION IV MORNING REPORT PAGE 8 JUNE 2, 1997 Licensee/Facility: Notification: Pacific Gas & Electric Co. MR Number: 4-97-0048 Diablo Canyon 1 Date: 06/02/97 Avila Beach,California Telephone call from RIs Dockets: 50-275 PWR/W-4-LP Subject: PLANT STARTUP FOLLOWING REFUELING OUTAGE Discussion: On June 1, 1997, at 5:58 p.m. (PDT), Diablo Canyon Unit 1 commenced critical operations following the eighth refueling outage. At 1:42 a.m. (PDT) on June 2, the main generator output breakers were shut which officially ended the outage. The refueling outage began on April 19, 1997. Major activities during the outage included steam generator eddy current inspections, replacement of a charging pump and an auxiliary saltwater pump, replacement of one of the vital batteries, replacement of a unit startup transformer, and implementation of a design change which bypassed approximately 800 feet of auxiliary saltwater piping. The auxiliary saltwater piping bypass was implemented as a result of external corrosion on the existing piping. Unit 1 is currently operating at 15 percent power. Regional Action: The resident inspectors observed portions of low power physics testing and will observe portions of power ascension testing. Contact: B. Olson (510)975-0295 M. Tschiltz (805)595-2354 _