ML20133D398
| ML20133D398 | |
| Person / Time | |
|---|---|
| Issue date: | 07/29/1985 |
| From: | Moist R, Potapovs U NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | |
| Shared Package | |
| ML20133D352 | List: |
| References | |
| REF-QA-99900902 NUDOCS 8508070326 | |
| Download: ML20133D398 (10) | |
Text
{{#Wiki_filter:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ORGANIZATION: Wyle Laboratories Scientific Services and Systems Group Huntsville, Alabama REPORT INSPECTION INSPECTION NO : 99900902/85-01 DATE(S): 6/10-14/85 ON-SITE HOURS: 59 CORRESPONDENCE ADDRESS: Wyle Laboratories Scientific Services and Systems Group l ATTN: Mr. W. W. Holbrook, General Manager Eastern Test and Engineering Operations 7800 Governors Drive t Huntsville, Alabama 35807 ORGANIZATIONAL CONTACT: Mr. E. W. Smith, Director, Contracts and Purchasing TELEPHONE NUMBER: (205)837-4411 PRINCIPAL PRODUCT: Research, engineering, and test operations NUCLEAR INDUSTRY ACTIVITY: Wyle Laboratories; Huntsville, Alabama, provides a variety of nuclear services to the industry which includes environmental and seismic qualification testing of safety-related equipment, refurbishment and recertification of valves, valve and component flow testing, mechanical and hydraulic snubber testing, decontamination, and repair. ASSIGNED INSPECTOR: +t/MAM O, 7)hhIf .:26JULM/6 A. N. Mcfist, Equippfent Qualification Inspection Date Section(EQIS) OTHER INSPECTOR (S): E. H. Richards, Sandia National Laboratories APPROVED BY: M h 7-29 -tf U. Potapovs, Sectioh Criief, EQIS Date INSPECTION BASES AND SCOPE: A. BASES: 10 CFR Part 21 and 10 CFR Part 50, Appendix B. B. SCOPE: This inspection consisted of: (1) a technical evaluation of equipment qualification (EQ) test activities for safety-related equipment; (2) Witnessing of inprocess EQ testing; and (3) verifica-tion of implementation of the quality assurance (QA) program. PLA'NT SITE APPLICABILITY: La Salle County 1 & 2 (50-373, 50-374); Dresden 1, 2, 3 (50-10, 50-237, 50-249); Quad Cities 1 & 2 (50-254, 50-265); Nine Mile Point 2 (50-410). 8508070326 850805 PDR GA999 EMVWYLE 99900902 PDR
ORGANIZATION: Wyle Laboratories, Scientific Services and Systems Group Huntsville, Alabama l REPORT INSPECTION NO.- 99900902/85-01 RESULTS: PAGE 2 of 4 A. Violations None. B. Nonconformances None. C. Unresolved Items None. D. Other Findings or Comments 1. Technical Evaluation The NRC inspector and Sandia consultant performed an in-depth technical evaluation and review of four test programs for quali-fication of safety related electrical equipment. The following table summarizes the test programs examined, including equipment type and types of documents examined. Test Program Equipment Type Documents Examined Plant 17605-1 SRV Solenoid Pilot Test Report (TR), La Salle Valve Qualification Plan (QP), County Purchase Order (P0), Data Sheets (DS) and Letter 17604-1 Level Switches TR, QP, P0, DS and La Salle Letter County 45916-03 Instrumentation TR,QP,P0, Letter,
- Dresden, and Power Cables Specification and dss Quad Cities 17590-1 Area Radiation TR, QP, Specification, La Salle Monitor Sensor and and Letter County Converter The NRC inspector and Sandia consultant reviewed the qualification prescribed in each QP and reviewed test results, including the basis for accelerated thermal aging and radiation, and verified calculations.
ORGANIZATION: Wyle Laboratories, Scientific Services and Systems Group Huntsville, Alabama REPORT INSPECTION NO.- 99900902/85-01 RESULTS: PAGE 3 of 4 Each of the four QPs and related engineering documents were examined to verify the following: a. Adequate test instrumentation and their accuracies were described and used to meet the requirements of IEEE-STD-323/1974. b. Equipment interfaces were addressed. c. Test acceptance criteria were established as described in the test specification or in the design engineering documents, such as calculations and engineering letters to meet the requirements of IEEE-STD-323/1974. d. Same equipment was used for all phases of testing and represented a standard production item. e. Environmental conditions were established aad described (e.g., pressure and temperature profiles, and thermal aging factors were consistent with those outlined in the test specification or test plan). f. Test results were adequately reduced and evaluated against established acceptance criteria described in customer test specifications or purchase orders. g. All prerequisites for the given tests as outlined in the test specification had been met. h. Test equipment included a description of all materials, parts, and subcomponents. i. Notices of Anomalies were properly documented. j. Appropriate margins were applied. The EQ documentation package for the level switch Model 751 manu-factured bf Magnetrol identified a test anomaly during post thermal functional testing where actuation of the switch mechanisms of both specimens would not cause sufficient travel of the micro-switch plungers to change the state of the contacts. Testing of two spare microswitch assemblies also had the same results. Because of this anomaly, a maintenance interval was incorporated into the test program. Malfunctions of the level switch during the accident test were also observed. Notices of anomalies were documented by Wyle Labs. The effect of these anomalies
O ORGANIZATION: Wyle Laboratories, Scientific Services and Systems Group Huntsville, Alabama REPORT INSPECTION NO.- 99900902/85-01 RESULTS: PAGE 4 of 4 on the qualification of the level switches are to be determined by Commonwealth Edison Company (CECO) and/or Sargent & Lundy (S&L). 2. Observation of Testing Activities The NRC inspector and Sandia consultant observed thermal aging testing of a Target Rock Solenoid Valve 6 X 10 Model 7567F being performed for General Electric Company (GE). The NRC inspector and Sandia consultant determined after review of test data, in-process environmental chamber surveillance records, test equipment calibration labels and chart recorder records that testing was performed in accordance with QP 47736-00 Rev. C dated 5/25/85. It was determined by Wyle Laboratories that the leakage rate exceeded the acceptance criterion for the valve operator during the post thermal functional test. The leaks were located at two plugs on the operator. Disposition of a Notice of Anomaly by the GE repreJentative directed Wyle to repair one plug using nuclear grade sealant which caused the leak rate to be brought back within the acceptance criterion. 3. Followup on 10 CFR Part 21 Report Crosby Valve and Guage Company filed a 10 CFR Part 21 report with NRC Headquarters concerning a latch roller bearing failure of a Crosby main steam line isolation valve similar to that used at Nine Mile Point 2. This failure occurred during seismic testing at Wyle Laboratories which was being conducted for Gulf and Western. The NRC inspector reviewed and evaluated one TR and verified that two notices of anomalies were documented for the above failure. The NRC inspector determined that the information contained in the notices of anomalies supported the information contained in the Part 21 report. Gulf and Western / Stone and Webster requested that the specimen be returned to Gulf and Western facility in the "as l failed" condition for their further evaluation. l l l t
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