IR 05000445/1982030
| ML20028E752 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 01/10/1983 |
| From: | Brickley R, Hale C, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20028E746 | List: |
| References | |
| 50-445-82-30, NUDOCS 8301280174 | |
| Download: ML20028E752 (4) | |
Text
{{#Wiki_filter:. - -. _. -. -- -- .. . - . . APPENDIX B.
U. S. NUCLEAR REGULATORY COP 90SSION
REGION IV
Report: 50-445/82-30 Docket: 50-445 Category:- _ A2 Licensee: Texas Utilities Generating Company (TUGCO) 2001 Bryan Tower Dallas, Texas 75201 Facility Name: Comanche Peak, Unit 1 Inspection At: Comanche Peak Stean Electric Station, Glen Rose, Texas Inspection Conducted: December 13-16, 1982 Inspector: T M, N //5/73 R. H. Brickley, Reac r Engineer Datfe ' Reactor Systems Secti , Vendor Program Branch ll Approved: N 7Q s C. J.W1 b, Chief Date Reactor Systems Section, Vendor Program Branch 21. Wh ihJn T. F. Westerman, Chief Date/ Reactor Project Section A Inspection Summary Inspection Conducted December 13-16, 1982 (Report 50-445/82-30) Areas Inspected: Special announced inspection of piping hanger / support design.
The inspection involved 26 inspector-hours by one NRC inspector.
Results: Within the area inspected, one violation was identified: failure, by checkers, to identify and correct mathematical errors in calculations as required by procedures (paragraph 3), CK 0$h0h&g i PDR
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! ' ! Details 1.
Persons Contacted
- R. G. Tolson, Site QA Supervisor, TUGC0
- M. R. McBay, Engineering Manager, Texas Utilities Service,-Inc. (TUSI)
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- H. A. Harrison, Technical Services Supervisor, TUSI
- J. C. Finneran, Project Pipe Support Engineer, TUSI D. M. Rencher, Black & Veatch, Supervisor, Technical Services Design Review Engineering (TSDRE)
T. Kerlin, Technical Coordinator, TSDRE
- R. P. Baker, OEM Staff, Brown & Root (B&R)
, R. Hemrajani, Technical Services, Nuclear Power Services, Inc. (NPSI).
- Denotes those attending the exit interview.
2.
Status of Previous Inspection Findings (Closed) Unresolved Item (82-05) - The inspector's examination of the analysis performed as a result of changes to hanger / support SI-1-093-011-S42R disclosed that an error had been made in.the calculation of Mc (moment at point c), Vc (vertical stress at point c), and Va (vertical stress at i point a).
TSDRE personnel performed another analycis which confirmed that . the changes made to SI-1-093-011-S42R were acceptable. During NRC Inspec-l tion Report 82-05, time did not permit a detailed examination of the new ~ ' analysis or examination of design review file (DRF) to determine whether-
this was an isolated case or generic in nature.
The NRC inspector reviewed the certified calculation package for hanger /. support SI-1-093-011-S42R and found it to be acceptable.
The review of additional certified calculation packages ~(see paragraph 3 below) disclosed an additional package with similar mathematical errors; therefore, this item is elevated to a violation (see Notice of Violation).
, 3.
Design Inspection - Pipe Supports Onsite engineering activities, with respect to large bore pipe nangers/ supports, consist of translating the vendor design drawing (ITT Grinnell/ Nuclear Power Services) into a B&R construction drading, review and approval of subsequent changes (documented via component modification cards), and producing "as-built" drawings. After a hanger / support has ! been installed and accepted by QC, the technical services mechanical drafting department compiles a hanger / support document package for review by TSDRE. This package typically consists of the latest revision of the vendor drawing, change documents affecting the design, and other related l information; i.e., sketches, load changes, etc. TSDRE reviews the changes j and conducts any necessary reanalysis.
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As a result of the unresolved item identified in NRC Inspection Report 50-445/82-05, paragraph 2 (also see paragraph 2 above) the NRC inspector selected and reviewed 15 certified calculation packages to determine if similar mathematical errors existed in other calculations.
The following certified calculation packages were reviewed: AF-1-001-018-Y43R SI-1-050-006-S22R AF-1-001-022-Y33K SI-1-044-016-522K CC-1-007-034-A63K AF-1-035-012-S33K ' CC-1-007-044-A73R AF-1-035-033-Y33R CS-1-055-010-S42S CC-1-035-008-E33R' CS-1-063-021-S22R CC-1-035-013-E235 FW-1-103-006-S62R CS-1-063-030-532R FW-1-101-008-C525 The review of the certified calculation package for hanger / support i FW-1-101-008-C525 disclosed similar mathematical errors.
TSDRE personnel performed another analysis which confirmed that the hanger / support-and associated base plate and bolts can withstand the anticipated forces.
It should be noted that in both of the cases (SI-1-093-011-S42R and FW-1-101-008-C52S) wherein mathematical errors were identified by the NRC , inspector, the errors were in the conservative direction.
The failure by the checker of calculations to identify and correct mathematical errors existing in those calculations is considered a viola-l tion of 10 CFR Part 50, Appendix B, Criterion V in that the requirements ~ of TUSI Instruction CP-EI-4.5.4, ITT Grinnell Procedure QCES-2.3.6, or ' NPSI Procedure WP 3.1.5 were not implemented.
4.
Exit Interview The NRC inspector met with licensee representatives (denoted in paragraph 1) and R. G. Taylor (NRC Senior Resident Inspector) at the conclusion of the inspection on December 16, 1982. The NRC inspector summarized the purpose, scope, and findings of the inspection.
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