IR 05000346/1977020
| ML19329B575 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 07/18/1977 |
| From: | Hayes D, Williams C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19329B458 | List: |
| References | |
| 50-346-77-20, NUDOCS 8002050711 | |
| Download: ML19329B575 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPFCTION AND ENFORCEMENT
REGION III
Report No. 50-346/77-20 Docket No. 50-346 Licence No. CPPR-80 Licensee: Toledo Edison Company
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l Edison Plaza 300 Madison Avenue Toledo, OH 43652
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Facility Name:
Davis-Besse Nuclear Power Station, Unit 1
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Inspection AT: Davis-Besse Site, Oak Harbor, OH
Inspection Conducted:
May 11-13 and 18-20, 1977 f h2y$ bCA w
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r, Inspector:
C. C. Williams
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date signed
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w 7/M/M Approved by:
D. W.
aye, C Projects Section
/datesigned Inspection Summary Inspection on May 11-13 and 18-20, 1977, (Report No. 50-346/77-20)
Areas Inspected:
(1) System interaction EIR's for halls and corridcrs; (2) large and small pipe, hangers, and anchors; (3) HVAC system rework activities; (4) steam generator level switch modification; (5) rework small Class I and Class 2 valves; (6) plant final documentation control; and (7) status of penetration scaling activity. The inspection involved 43 inspector-heurs by one NRC Inspector.
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Results: No items of noncompliance, deviation, nor unresolved matters
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were identified.
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DETAILS Persons Contacted Principal Licensee Employees
- L.
E. Roe, Vice President
- J. D. Lenardson, Quality Assurance !!anager
- K.
E. Blanchon, Cons truction Supervisor
- G. E. Eichenauer, Quality Assurance Engineer
- D. A. Poage, Quality Assurance Engineer
- E. M. Wilcox, Quality Assurance Supervisor
- D. Mominee, Quality Assurance Engineer Other Personnel
' C L. Huston, Field Construction Manager (Bechtel)
- R. Rosenthal, Project Manager (Eechtcl)
- W. C. Lowery, Quality Assurance Engineer (Bechtel)
D. Hughes, Quality Control Inspector (Bechtel)
The inspector also contacted and interviewed other licensee, Eechtel, ('~'N and contractor employees, including members of the quality, technical,
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and engineering staffs.
- denotes those attending the exit interview ('May'20, 1977).
Licensee Action on Previous Inspection Findings None identified.
Functional or Program Areas Inspected 1.
System Interaction - EIR's 5000 and 8000 (50-346/ 77-19)
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This matter (EIR's for halls and corridors) is closed. As previously reported, this reinspection and rework activity was incomplete.
The
' incomplete issues were divided into two separate areas of consideration relative to their need to be completed for various modes of plant operation. Those issues identified for mode 5 plant operation were completed and resolved during the previous inspection (50-346/77-19).
During this inspection, those.EIR's identifying issues within the halls and corridors were inspected.
Forty-seven of these subject EIR's required completion prior to mode 4, plant operation (hot
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shutdown), and had made a condition of the licenac (Items C.7.(a)
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and C.7.(b), Attachment 2).
The inspector verified that this work has been satisfactorily completed. This was accomplished througn observation of the as-built components, comparison to the design documents, and examination of the angineering evaluations. Approxi-mately 50 items (seismic supports for electrical conduit, etc.)
identified on four EIR's were examined. No discrepancies were noted.
Examples of the documents and EIR's review are as follows':
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a.
EIR No. 5536 I
Drawing No. HSC-106-5-H, Revision 3 Drawing No. HSC-55-2-H, Revision 4 Drawing No. HSC-106-1-3, Revision 3 Jeawing No. HSC-104-9-H, Revision 0
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Drawing No. HSC-55-1-H, Revision 0 Drawing No. HSC-108-2-H, Revision 0 b.
EIR No. 5446/Closuta Letter No. 5635 Drawing No. CS-4189-422A-37, Conduits No. 46747C and No. 57130A.
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The final documentation package assembled by Bechtel was also
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examined. No discrepancies were noted.
2.
Large and Small Pine Hangers and Anchors (50-346/77-19)
The matter is closed. As previously reported, satisfactory resolution of this issue and verification by the NRC was made a condition of the plant operation license (Items C.3 and C.4, Attachment 2).
During this inspection, the inspector examined the final documentation relative to this issue. Further, the inspector verified that the as-built configuration of the sub-ject hangers and anchors met the design requirements.
This was accomplished by a walk-down inspection involving observations i
No significant deficiencies were noted.
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N-Examples of items involved in this ef fort are as follows:
Hanger No. 6-C-EBB-4-H-14 Hanger No. 3A-EBD-19-H-86
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Hange r No. 6C-EBD-14-H-95 Hanger No. 6C-EBD-4-H-H
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Hange r No. 3A-EBB-2-H-6 i
Hanger No. 30-CCC-8-H-9 Hanger No. CCB-27-4-H i
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Hanger No. EBB-5-5-H l
Hanger No. HCB-33-2-H
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3.
Heating Ventilation and Air Conditioning System (50-346/77-19)
i This matter is closed. As previously reported, satisfactory
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resolution of this matter was made a condition of the plant operating license (Item C.2, Attachment 2).
The only aspect of this rework t
remaining to be completed and verified and was the completion
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and turnover of final documentation.
i During this inspection, the inspector reviewed the final record l
packages for this work. No discrepancies were disclosed. The
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drawings and associated engineering instruction were verified to be in accordance with the requirements.
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4.
Steam Generator Level Svitch Modification This matter is closed.. Satisfactory resolution of this mattar was made a condition of the plant operating license (Item E.1, Attach-ment 2). This matter involved a required modification to replace the four level' switches in each steam generator inside containment with four. level transmitters. This modification has been satisfactorily
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completed. The inspector verified this through examination of.
the modification records and observation of components.
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The following documents are examples of those reviewed during the i
inspection:
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a.
System Revision Notice (SRM) No. 197J b.
Construction Uork Permit -(CWP)' No. 63-ISC-60 start-up System
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No. 63A (steam generator)
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.CWP No. 63-ISC-81
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Design Document No. 3-167 Sheet 2 of Revision 6 j
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CWP No. 63-E-82 f.
Design Document No. E164A g.
CWP No. 63-ISC-76 h.
SRM No. 197E i.
Revised SRN No. 197E.
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5.
Rework Small Class 1 and Class 2 Valves (50-346/77-19)
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This item is resolved. As previously reported, this matter and its satisfactory completion and verification by NRC inspection was made a condition of the plant operating license (Icem D.1, Attachment 2).
During this inspection, the inspector examined and reviewed the final data package and release of the four remaining valves (CS-21, CS-22, D'A-38, and CV-Il7).
No discrepancies were noted.
6.
Plant Final Documentation During this inspection the inspector examined the implementation of TECo procedures for the control of permanent plant records.
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the site contractors, Bechtel and TECo QA/QC review of these records N
This effort involves Bechtel's acquisition of plant records from and the establishment of interim storage.
The inspector reviewed the final documentation package for the
" Ins trument and AC Power System" start-up system No.17.
No discrepancies were noted.
This overall work ef fort is approximately 55% complete.
This matter will be reviewed during subsequent NRC inspections.
7.
Penetration and llockout Sealant-BISCO (50-346/77-19)
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This work remains incomplete. Penetrations and blockouts in certain safety related areas of the plant have been completed, and verified by the NRC inspector to be in conformance with the requirements.
These areas include:
(a) control room, (b) cable spreading room, (c).switchgear room, (d) emergency diesel rooms, etc.
The licensee is now concentrating the scalant work activity in those areas
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involving the " negative pressure boundary".
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Completion of penetration scalant activity within the "nngative i
pressure boundary" areas is a prercquisite for the emergency j-
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ventilation sys tem tes t.
The licensee made a commitment to NRR
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to complete TP 110.01, " Emergency Ventilation System Test" prior
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to entering operational mode C.
This commitment is contained in
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TECo/NRR letter dated February 22, 1977.
The licensee's representatives indicated that a routine over time t
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This :r,tter will be reviewed during subsequent NRC inspections.
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I Exit Interview t
The inspector met with site staff representatives (denoted under Persons
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Contacted) at the conclusion of the inspection on May 20, 1977, the l
l inspector summarized his inspection findings. The licensee acknowledged the
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the findings reported herein.
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