ML20040D722

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QA Program Insp Rept 99900760/81-01 on 811026-30. Noncompliance Noted:Failure to Adopt Procedures to Implement 10CFR21,to Remove Reject Tags,To Indicate Certification of Welding Machines & to Certify Competence of Examiner
ML20040D722
Person / Time
Issue date: 01/14/1982
From: Barnes I, Parker L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20040D715 List:
References
REF-QA-99900760 NUDOCS 8202020187
Download: ML20040D722 (10)


Text

{{#Wiki_filter:- ORGANIZATION: STEWART AND STEVENSON SERVICES, INC., ENGINE DIVISION HOUSTON, TEXAS REPORT NO.: 99900760/81-01 INSPECTION DATE(S): 10/26-30/81 INSPECTION ON-SITE HOURS: 53 CORRESPONDENCE ADDRESS: Stewart and Stevenson Services, Inc. Engine Division ATTN: Mr. C. L. Ward Executive Vice President and General Manager Post Office Box 1637 Houston, Texas 77001 ORGANIZATION CONTACT: Mr. Rich Stevens TELEPHONE: (713) 671-6100 PRINCIPAL PRODUCT: Diesel Generator Sets NUCLEAR INDUSTRY ACTIVITY: Present: 4 units total in-work 2 diesel generator sets 3875kW, 4.16kV 2 diesel auxiliary feedwater pump drives b I - I @ - O 7. ASSIGNED INSPECTOR: L. 8. Parker, Reactive Inspection Section (RIS) Date OTHER INSPECTOR (S): I. Barnes, RIS

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~ APPROVED BY: I. Barnes, Chief, RIS Date INSPECTION BASES AND SCOPE: A. BASES: 10 CFR Part 50, Appendix 8 and 10 CFR Part 21. B. SCOPE: This inspection was made in response to: (1) a request by Region III of the Nuclear Regulatory Commission to evaluate 10 CFR Part 21 compliance, resulting from the identification that the Commonwealth Edison Company, La Salle County Station, was not receiving maintenance publications for its diesel generators; and (2) the receipt of a Bechtel Power Corporation 10 CFR Part 21 report pertaining to a diesel generator camshaft bracket failure at the Southern California Edison, San Onofre Units 2 and 3. DESI 'IAIE3 ORIGIl!AL certe' icd E7 8202020187 820118 PDR GA999 EMVSSS 99900760 PDR ) )

ORGANIZATION: STEWART AND STEVENSON SERVICES, INC., ENGINE DIVISION HOUSTON, TEXAS REPORT NO.: 99900760/81-01 INSPECTION RESULTS: PAGE 2 of 4 A. VIOLATIONS: 1. Contrary to paragraph 21.6 in 10 CFR Part 21, a copy of Section 206 of the Energy Reorganization Act of 1974 was not posted. 2. Contrary to paragraph 21.21 in 10 CFR Part 21, procedures had not been adopted to implement 10 CFR Part 21. B. NONCONFORMANCES: 1. Contrary to Criterion V of Appendix B to 10 CFR Part 50 and paragraphs 3.5, 3.5.1, and 3.5.2 of Product Specification 008 (basic) issued December 20, 1976, red reject tags 0248, 0967 and 2695 had not been removed from an electrical control panel (Work Order N75744) in the test berth. The corresponding NCR's 920, 922, and 793 had been corrected and closed on May 5, 1981. 2. Contrary to Criterion V of Appendix B to 10 CFR Part 50 and Definition 1 of Engineering Specification ED007 (basic) issued December 15, 1976, Installation Drawing 62240-1, Revision H, " Commonwealth Edison Auxiliary Feedwater Pump Drive 16V 149T1" does not show an air intake support and a support for the service water booster pump. Also not shown are gussets which were added to eliminate the anomaly found during seismic testing of a similar unit (Work Order 74505). 3. Contrary to Criterion V of Appendix B to 10 CFR Part 50 and paragraphs 3.3, 3.4, and 4.0 of Production Specification 005 (basic) issued December 27, 1976, no documentary evidence was available to indicate that welding machines had been certified. 4. Contrary to Criterion XIV of Appendix 8 to 10 CFR Part 50, the established measures did not provide for identification of inspection and test status, as e.idenced by the inspection signoffs on Inspection l Point Program No 108 for Work Order No. N79905/6 (Marble Hill Auxiliary l Feedwater Pump Drive, Fan Assembly Support) indicating assembly machining and postweld heat treatment operation being performed prior to the assembly being fabricated. 5. Contrary to Criterion IX of Appendix B to 10 CFR Part 50 and Quality l Control Specification QCS 001, Revision B, measures were not established to assure that heat treating was controlled in accordance with specification requirements as evidenced by: (a) placement of a heat treatment vendor, Houston Heat Treating Company, on the Qualified Vendor List without evidence of capability to comply with heat treatment specification requirements; and (b) use of the vendor for postweld heat treatment of Marble Hill auxiliary feedwater pump diesel engine drive subassemblies without verification of temperature uniformity of the furnace that was used for the heat treatment cycles.

{ ORGANEN. STEWART AND STEVENSON SERVICES, INC., ENGINE DIVISION HOUSTON, TEXAS REPORT NO.: 99900760/81-01 INSPECTION RESULTS: PAGE 3 of 4 6. Contrary to Criterion V of Appendix B to 10 CFR Part 50 and Quality Control Specification QCS 017, Revision F, review of the Qualified Vendor List showed no basis for inclusion of 411 Category B vendors from a total of 555 such vendors. 7. Contrary to Criterion V of Appendix B to 10 CFR Part 50 and paragraph T-661 in Section V of the ASME Code, Article 6, Liquid Penetrant ExaminationProceduresQCS003,Revisiong,hadnotbeenqualifiedat the minimum examination temperature of 50 F permitted by the procedure. 8. Contrary to Criterion V of Appendix B to 10 CFR Part 50 and Quality Control Specification QCS 003, Revision G, Clinton, Unit 1 emergency diesel generator set cooling system piping welds had been signed off on May 23, 1980, as being acceptable in the applicable inspection point program but had not been recorded on a Quality Control Liquid Penetrant Inspection Report as of the date of this inspection. 9. Contrary to Criterion IX of Appendix B to 10 CFR Part 50 n.d paragraph ND-5521(a) in Section III of the ASME Code, a Level III examiner was appointed on December 4, 1978, by Stewart and Stevenson and not certified by the required examination for technical competence. C. UNRESOLVED ITEMS: None D. STATUS OF PREVIOUS INSPECTION FINDINGS: None E. OTHER FINDINGS OR COMMENTS: 1. Regional Requests a. A 10 CFR Part 21 report by Bechtel Power Corporation reported that Stewart and Stevenson (S&S) had been advised that a diesel generator camshaft bracket failure was a substantial safety hazard defect. S&S requested Electro-Motive Division General Motors Corporation (EMD) to evaluate the failure. EMD made a failure l analysis and concluded that "this is an isolated failure in that it is due to human error rather than a design or mechanical problem." S&S made no other evaluation of the failure. See violation A.2. b. Region III requested inspection of S&S to determine how S&S was handling the reporting of 10 CFR Part 21 matters, as a result of identification that diesel generator maintenance publications were not being forwarded to Commonwealth Edison La Salle County Station.

.\\ ORGANIZATION:- STEWART AND STEVENSON SERVICES, INC., ENGINE DIVISION HOUSTON, TEXAS REPORT NO.: 99900760/81-01 INSPECTION RESULTS: PAGE 4 of 4 S&S had received a request from Commonwealth Edison in regard to this matter and had forwarded the request to EMD for action. Violation A.2 was identified as a result of the failure to adopt procedures for implementation of 10 CFR Part 21. 2. Follow-Up Item San Onofre Nuclear Generating Station, Units 2 and 3 were experiencing problems with high crankcase oil pressure in their diesel generator units. S&S was evaluating the deficiency. 3. Implementation of 10 CFR Part 21 10 CFR Part 21 was posted. See violations A.1 and A.2. 4. Manufacturing Process Control Travelers, inspection point program checklists, quality assurance work order files, personnel certifications, and other documentation were examined. Two units were in test berths, but no testing was being performed. See nonconformances B.1 through B.9. In regard to nonconformance B.4, the Inspection Point Program for the fan assembly support (IPP #108) identified that postweld heat treat and machining operations had been performed on the assembly, respectively, on March 21, 1980, and April 8, 1980. IPP #108 showed also, however, that the fan assembly was not fabricated until March 26, 1981. In response to questions concerning the date inconsistencies, the NRC inspector was informed that the assembly had been rebuilt as a result of the discovery of dimensional errors. It was not established how it was possible for the same IPP record to be used for inspection operations during the second assembly fabrication, or why inspection operations had not been signed off for the initial fabrication.

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