Part 21 Report - 1996-703

ACCESSION #: 9609040049 LICENSEE EVENT REPORT (LER) FACILITY NAME: Virgil C. Summer Nuclear Station PAGE: 1 OF 5 DOCKET NUMBER: 05000395 TITLE: ITT Barton Model 763 Pressure Transmitter Strain Gage Failures EVENT DATE: 07/30/96 LER #: 96-07-00 REPORT DATE: 08/29/96 OTHER FACILITIES INVOLVED: DOCKET NO: 05000 OPERATING MODE: 1 POWER LEVEL: 75 THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR SECTION: OTHER LICENSEE CONTACT FOR THIS LER: NAME: George A. Lippard, III TELEPHONE: (803) 345-4810 COMPONENT FAILURE DESCRIPTION: CAUSE: B SYSTEM: AB COMPONENT: MANUFACTURER: B080 REPORTABLE NPRDS: Y SUPPLEMENTAL REPORT EXPECTED: YES EXPECTED SUBMISSION DATE: 10/18/96 ABSTRACT: This report is being made pursuant to 10 CFR Part 21. On June 5, 1996, engineering review of plant incident reports identified the third failure of M Barton Model 763 pressure transmitters at V. C. Summer Nuclear Station within a one week period. In each case. a strain gage lead was broken at its terminal pin. Model 763 transmitters are used at V. C. Summer Nuclear Station to provide protection signals based an pressurizer pressure; specifically. reactor trip on high pressurizer pressure or reactor trip and safety injection on low pressurizer pressure. The transmitters exhibiting the described defect were all from existing VCSNS stock and were received in the same shipment. Each transmitter was calibrated, and installed as IPT00457-RC where two filled after being in service for a short period of tim, and one failed prior to return to service. A Model 763 pressure transmitter, of a different purchase, was calibrated and installed as IPT00457-RC. V. C. Summer Nuclear Station ensured that the associated application was restored to operable status. Reliability of pressurizer pressure transmitters is verified by weekly monitoring and channel checks. ITT Barton has not established a root cause for what appears to be a repetitive failure of the Model 763 pressure transmitters. Barton is in the process of evaluating the defective V. C. Summer Mode 763 transmitters for failure analysis. END OF ABSTRACT TEXT PAGE 2 OF 5 PLANT IDENTIFICATION: Westinghouse - Pressurized Water Reactor EQUIPMENT IDENTIFICATION Pressure transmitters used in the protection scheme circuits for Pressurizer High Pressure Reactor Trip or Pressurizer Low Pressure Reactor Trip and Safety Injection. EIIS Code AB IDENTIFICATION OF EVENT: Potential failure of protection circuitry for Reactor Trip and Safety Injection. DISCOVERY DATE: July 30, 1996 - Virgil C. Summer Nuclear Station, upon review of failures which occurred through June 5, 1996, determined that the failure mechanism presented a substantial safety hazard and should be reported in accordance with 10CFR Part 21. REPORT DATE: August 29, 1996 This report was generated by Non-Conformance Notice 5481. COMMONS PRIOR TO THE EVENT MODE 1 75% Reactor Power TEXT PAGE 3 OF 5 DESCRIPTION OF EVENT On July 30, 1996, Virgil. C. Summer Nuclear Station determined that a substantial safety hazard, reportable pursuant to 10 CFR Part 21, existed relative to the potential failure of transmitters used for pressure projection in the Engineered Safeguards and Reactor Trip circuitry. The devices are ITT Barton Model 763 pressure transmitters. The Model 763 transmitters are used for providing High Pressurizer Pressure Reactor Trip, Low Pressurizer Pressure Reactor Trip and Low Pressurizer Pressure Safety Injection. On June 5, 1996, a Model 763 pressure transmitter was installed at the IPT00457-RC location and fail high prior to being placed in service, Non-Conformance Notice 5481 was generated for evaluation of the failure. Engineering review of plant incident reports identified this as the third failure of a transmitter installed at this location within i one week period. The two previous failures of Model 763 pressure transmitters at this location failed after being in service for a short period of time (2-5 days). Each of the transmitters installed at the IPT00457-RC location were obtained by the same purchase order and received at VCSNS in the same shipment. CAUSE OF EVENT: In each case, a strain gage lead was broken loose at its terminal pin. This condition appears to be an inherent defect in manufacturing/repair based on ITT Barton Failure Analysis Report PA 960701 and the number of similar failures occurring in a short period of time. ANALYSIS OF EVENT: The defect could cause a loss of safety function to the extent that there is a major reduction in the degree of protection provided to the public health and safety. The pressurizer pressure transmitters (IPT00455(6)(7)-RC) provide the following protection signals: 1. Reactor Trip on high pressurizer pressure. 2. Reactor Trip on low pressurizer pressure. 3. Safety Injection on low pressurizer pressure. TEXT PAGE 4 OF 5 ANALYSIS OF EVENT: (continued) The VCSNS FSAR takes credit for the low pressurizer pressure protection signals to mitigate the consequences of a Large Break LOCA. A transmitter installed at IPT 00455 (6)(7)-RC which fails high would not provide the low pressure protection signal. The protection circuitry is based on 2 out of 3 input logic, so the failure of one transmitter would not, in and of itself, prevent the proper protection function. However, this failure condition coincident with an additional transmitter failure would affect the automatic activation of safety injection should a large break LOCA occur. This could result in potential offsite exposure exceeding 10 CFR 100.11 limits. V. C. Summer Engineering, personnel have discussed this situation with ITT Barton. The failed transmitters were shipped and received together. The preliminary consensus is, that a manufacturing process error potentially contributed to the defect and this condition is an isolated occurrence limited to the lot of transmitters from which those shipped to VCSNS was supplied. V. C. Summer Engineering personnel also performed a review of M Barton 760 model series transmitter failures using the NPRDS data base. NPRDS indicated that most failures were either age related or unknown. There were no strain gage figures identified; thus this review was inconclusive as to industry experience with the problems noted for V. C. Summer. Other licensees with ITT Barton Model 763 pressure transmitters should review the history for their particular applications and determine if broken/loose strain gages have attributed to any failures which may lave occurred at their plants. IMMEDIATE CORRECTIVE ACTIONS: A Model 763 pressure transmitter, independent of existing VCSNS warehouse stock, was procured and installed at the IPT00457-RC location. V. C. Summer Station ensured that the associated applications were restored to operable status upon identification, replacement and testing of the respective Model 763 pressure transmitters. As the Model 763 currently totalled is from an unrelated stock and is performing satisfactorily, continued operation does not present an adverse impact on safety. TEXT PAGE 5 OF 5 ADDITIONAL CORRECTIVE ACTIONS: Long term corrective actions are under evaluation and will be coordinated with the vendor. SCE&G expects to obtain the vendor's analysis results and be able to submit a final report by October 18, 1996. PRIOR OCCURRENCES: None ATTACHMENT TO 9609040049 PAGE 1 OF 2 SOUTH CAROLINA ELECTRIC & GAS COMPANY Virgil C. Summer Nuclear Station P. O. Box 88 Jenkinsville, SC 29065 FAX # (803) 345-4356 Nuclear Licensing & Operating Experience To: Company: Telecopy No.: From: Telephone No.: Number of Sheets Including Transmittal Sheet: Special Instructions: Confirmation: Distribution: ATTACHMENT TO 9609040049 PAGE 2 OF 2 SCE&G/NL/SG SCE&G A SCANA COMPANY South Carolina Electric & Gas Company Gary J. Taylor P.O. Box 88 Vice President Jenkinsville, SC 29065 Nuclear Operations (803) 345-4344 August 29, 1996 RC-96-0222 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 Gentlemen: Subject: VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 LICENSEE EVENT REPORT (LER 960007) Attached is Licensee Event Report No. 96-007 for the Virgil C. Summer Nuclear Station. This report is submitted pursuant to the requirements of 10CFR Part 21. Should you have questions, please call Mr. Jim Turkett at (803) 345-4047. Very truly yours, JWT/GJT/nkk Attachment c. J. L. Skolds K. R. Jackson W. F. Conway D. L. Abstance R. R. Mahan (w/o attachment) NPRDS Coordinator R. J. White NRC Resident Inspector S. D. Ebneter J. B. Knotts Jr. A. R. Johnson INPO Records Center S. R. Hunt Marsh & McLennan S. F. Fipps NSRC A. R. Koon RTS (LER 960007) G. E. Williams Files (818.07, 818-18) T. L. Matlosz DMS (RC-96-0222) *** END OF DOCUMENT ***

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