IR 05000346/1987010
| ML20214F787 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/15/1987 |
| From: | Danielson D, Yin I NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20214F784 | List: |
| References | |
| 50-346-87-10, NUDOCS 8705260290 | |
| Download: ML20214F787 (4) | |
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U.S. NUCLEAR REGULATORY COMNISSION
REGION III
Report No'. 50-346/87010(DRS)
Docket No. 50-346!
License'No. NPF-3
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- Licensee:
Toledo Edison Company Edison Plaza 300 Madison Avenue Toledo, OH 43652 Facility Name:
Davis-Besse Nuclear Power Station, Unit 1
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Inspection At:
Davis-Besse~ Site, Oak Harbor,- Ohio Inspection Conducted:
May 6-7, 1987
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I. T. Yin / *'
I/#7 Inspector:
Date dp4V U Approved By:
D..H. Danielson, Chief 5//f/#7 Materials and Processes Section'
Date Inspection Summary Inspection on May-6 7, 1987 (Report No. 50-346/87010(DRS))
Areas Inspected:
Routine, announced inspection of licensee action on previous inspection findings (92701, 92702, 41400).
Results: -Of-the areas inspected, no violations or deviations were identified.
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8705260290 870515 PDR ADOCK 05000346
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DETAILS 1.
-Persons Contacted Toledo Edison Company (TED)
- J. C. Sturdavant, Licensing Staff
- G. Honma, Compliance Supervisor, Licensing
- D. Haiman, Engineering General Manager
- J. Chlapowski,. Director of Engineering
- A.'G. Weedman, Engineering Assurance Manager
- L. O. Ramsett,' QA Director-
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- P. H. Straube, Senior Engineer, Civil / Structural
- J. E. Moyers, Quality Verification Manager J. C. Buck, QA Auditor L. P. Zarkesh, Engineering Support Coordinator T. S. Swim, Civil / Structural Manager T. J. Zunk, Nuclear Technician B. Carrick,ir, Assistant Nuclear EngineerDirector of Design Engineering
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D. E. Kazim
- Denotes those attending the management meeting at the site on May 7, 1987.
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Licensee Action on Previous Inspection Findings a.
(0 pen) Unresolved Item (346/86004-02):
Abandoned unfilled anchor bolt holes and voids were identified during the TED repair of restraints pulled away from the wall.
The NRC followup inspection is documented in Region III Inspection Report No. 50-346/86019.
During this inspection, the NRC inspector reviewed.the TED draft procedure, "The Piping Support Inspection Program for Ungrouped Holes and Concrete Voids Behind Baseplates," and had no adverse comments.
The TED staff indicated that the procedure will be ready for issuance in June 1987, and that the inspection of pipe restraint with relatively heavy loaded bolts will soon be conducted in the auxiliary and containment buildings.
The study showed the minimum bolt inspection sample size will be 59.
If zero defects are identified, a confidence level of 95.15% will be provided that all installations are acceptable.
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(Closed) Unresolved Item (346/86019-01):
TED was to review the Grinnell original hanger calculations to assure compliance with desigry procedures.
The NRC inspector reviewed the Bechtel Associates Professional Corporation (Ohio) Procedure No. CGP-08,
" Procedure for the Consolidation of Large Bore Pipe Support Calculations for the Davis-Besse Nuclear Power Station, Unit 1,"
Revision 1, February 18, 1987, and had no adverse comments.
The program does not require Bechtel to perform mathematical checks,
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but to verify that the Grinnell calculations are adequate and complete..As of.May 1, 1987, 3750 calculations.had been. sorted
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Land entered into the computer database.
Of these, 250 had been;
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(0 pen)~ Unresolved. Item (346/86019-02)! TED was to provide additional -
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~ larificationTano procedural' revisions on the Facility Change Request)
c (FCR) system..The NRC inspector 1 reviewed the TED~ Intra-Company
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- Memorandum,.En ine eing" Support Coordinator to Licensing Principle,-
" Response to L TS 3287, March 17, 1987, and concluded that the'
a issues had not-been addressed adeq/ modifications should be under-the uately. 'The NRC inspector stated-
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that significant-plant evaluations
.' direct control-of the nuclear mission procedure.
The TED QA staff
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indicated that they will perform an audit of'onsite' design verifica-~
tion and control in June 1987.
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(Closed).UnresolvedItem(346/86019-03):
SomeQAAuditorFinding Reports:(AFRs) were'not dispositioned and closed in a timely
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manner. -The TED QA AFRs were-issued in March 1986.. At the time of
the NRC inspection in October 1986, nine out of 12 of these AFRs'
were still open. These nine AFRs have since been resolved and closed on'the following dates:
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AFR No. 2, January 5,1987.
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AFR No. 3,
' January 5, 1987.
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AFR No. 4, March 8,.1987.-
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AFR No. 5, March 11, 1987.
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AFR No.:6,
' March 24, 1987.-
.AFR No. 7, February 24, 1987.
'e-AFR No.'8, March 12, 1987.
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AFR No. 9, December 8, 1986.
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se AFR No. 12,.
-October 19, 1986.
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The NRC inspector reviewed the pertinent records of the closeout for the.AFRs,_and some of the technical bases for the disposition, and
' had no adverse comments.
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(Closed) Open. Item (346/86019-04):.Some of the safety related FCR i
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' design reviews did not use proper Design Verification Checklists 1(DVCs).
Subsequently,.12 DVCs were determined to require rework or correction.
The reevaluations did not call for'any hardware
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(0 pen) Violation (346/86019-05):
Bechtel failed to follow design procedure, and did not have a procedure for' combining design loads.
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x The:NRC inspector reviewed the TED response to the violation Serial
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No. 1-701,-January 16, 1987, and considered the licensee action acceptable. -The NRC inspector reviewed the Bechtel Power Corporation,
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Davis-Besse'(Project Unique) Stress Group Newsletter, " Design Guide for Davis-Besse Pipe Support / Anchor Design-Load Calculations,"
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Revision 0, October 29, 1986 and Revision 1, March 25, 1987, and had F
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no adverse comments.
The NRC inspector also reviewed the'Bechtel
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. Interoffice: Memorandum,'" Corrective Action - Violation: NRC
Inspection Report.No. 50-346/86019,"iJanuary 15, 1987, and:
considered it acceptable.
TED performed a QA~ audit, Audit Report No.~AR-87-BECHT-01, at Bechtel on February 9-13,fl987.. Contrary.
- to the TED response letter, Serial No. 1-701, the February 1987
- audit did not specifically address the' effectiveness of Bechtel implementation of the. hanger load combination procedure, and-Bechtel!s strict adherence to procedural requirements. The TED QA Director committed to conduct a special audit in'the'near future'.
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to cover the above areas and to further evaluate Bechtel' design-
-document traceability and.the bases'for some of the' design 1 justifications.
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(Closed)Violatione(346/86019-07):
The TED staff failed to issue'a~
Potential Condition Adverse to Quality Report (PCAQR) for some pipe restraint. design nonconformances.
The NRC inspector reviewed'PCAQR No.'86-0551, issued on October 29,' 1986, closed on November 19,~
.1986, and had no adverse comments.
The TED Director of Design
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Engineering and the Nuclear Licensing Manager have. instructed the-engineering.and licensin personnel to identify, evaluate, and track'
nonconformances on a PCA R.
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(0 pen)OpenItem-(346/86019-08):
TED review of.approximately 230
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Bechtel calculations to reconcile as-built dimensional deviations, a'nd' verification of the M0V'models forithe remaining 13 Teledyne alping analyses'.
The'NRC--inspector was informed that from r bruary 1987 to the present,.TED sent 14 Bechtel and two Teledyne e
calculations to Bechtel-for as-built reconciliation.
Bechtel has evaluated ten calculations and found them to be-acceptable without any. hardware modification.
The NRC inspector noted that actions were progressing relatively slow.
The:TED staff indicated that all 243 Bechtel and Teledyne calculations will be' reconciled to the
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as-built condition prior to the completion of next plant refueling outage.
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Personnel: Interview
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Throughout the NRC inspection,-the TED staff demonstrated technical
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competence and a clear understanding of the issues. There was also-evidence'of a cooperative spirit and understanding between the TED'
management and technical staff.
Exit-Interview
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The NRC inspector met with licensee representative (denoted in
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The inspector
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-summarized the scope and findings of the inspection.
The inspector also discussed the likely informational content of the inspection report with regard to documents reviewed by the inspector during the inspection.
The-licensee representatives did not identify any such documents as
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