IR 05000329/1975004
| ML19329F105 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 06/25/1975 |
| From: | Hayes D, Yin I NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19329F104 | List: |
| References | |
| 50-329-75-04, 50-329-75-4, 50-330-75-04, 50-330-75-4, NUDOCS 8006200625 | |
| Download: ML19329F105 (6) | |
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U. S. NUCLEAR REGULATORY COMMISSION
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0FFICE OF INSPECTION AND ENFORCEMENT
REGION III
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Report of Construction Inspection
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IE Inspection Report No. 050-329/75-04 IE Inspection Report No. 050-330/75-04 Licensee:
Consumers P'over Company 1945 W. Parnall Road Jackson, Michigan 49201
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Midland Plant License No. CPPR-81 i
Units 1 and 2 License No. CPPR-82 l
Midland, Michigan Category: A Type of Licensee:
PWR (B&W)'- Unit 1 - 650 MWe PWR (B&W) - Unit 2 - 818 MWe
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Type of Inspection:
Special, Announced
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Dates of Inspection:
' June 10, 1975 g/
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a Principal Inspector:
I. T. Yin
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Accompanying Inspectors:
None Other Accompanying Personnel: None
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Reviewed By:
D. I. Ha e
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Senior Reactor Inspector
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Construction Projects
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r SUMMARY OF FINDINGS b
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Inspection Summary Inspection on June 10, 1975:- Re' view of open items contained in AEC/NRC inspection reports since 1970.
The inspection was held in the IE:1II office.
Enforcement Items
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None.
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Licensee Action on Previously Identified Enforcement Items Not applicable.
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Other Significant Items
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A.
Systems and Components Not applicable.
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B.
Facility Items (Plan and Procedures)
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Not applicable.
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C.
Managerial Items
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A meeting was held with the licensee's representative in the Region III office on June 10, 1975.
The purpose of the meeting l
vas to review status of unresolved or open items identified in
'RO/IE inspection reports singe 1970.
D.
Noncompliance Identified and Corrected by Licensee j
l None.
E.
Deviations f
None.
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Status of Previously Reported Unresolved Items
A number of unresolved items have been identified by both the j
licensee and'the inspector. A follow up inspection at constru-
tion site is planned.
(Appendix)
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Management Interview i
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A..
The following persons attended the management interview at the conclusion of the inspection:
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Consumers Power Company (CP)
H. W. Slager, Project Quality Assurance Administrator I-
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~ USNRC,.IE:III I. T. Yin, Reactor Inspector - Projects D. W. Hayes, Senior Reactor Inspector - Projects
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B.
Matters discussed and cot:ments, on the part of management personnel,
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were as follows:
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The licensee representative acknowledged the inspector's commen-l dation on behalf of his effort of documenting 'nd evaluating a
NRC open inspection items.
The inspector stated that he will l
review the subject matter in depth and plan for followup
'l inspections as required at the site.
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f REPORT DETAILS
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Results of Inspection 1.
Documentation of NRC Inspection Open Items by the Licensee
' An effort was made by the licensee to systematically record and evaluate all noncompliance, deviation, unresolved and open items
/statedinRegionIII'sinspectionreport, Summary and Detail Sections, since 1970.
To date, no noncompliance items remain uncorrected, and most of the concerned matters have been resolved
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and recorded in IE:III reports. For those open items that have not been officially closed in IE:III reports, the licensee has grouped them into the following categories and has requested
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IE:III for concurrence:
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a.
NRC~ Open Items considered to be resolved by CP.
b.
NRC Open Items considered to be unresolved by CP.
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2.
IE:III's Position on Licensee Presentation The inspector appreciates CP's effort and their awareness of the b
construction problems.
Subsequent ieview of open items, considered to be resolved and unresolved by CP, has been made by the inspector.
Results of the evaluation indicate that sixteen (16) items remain to be resolved.
These items are identified in the Appendix.
Followup review is planned relative to these matters during future inspections..
-1 Other open items presented by CP but not listed in the Appendix
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were either never considered.to be open by NRC or were resolved based on documentation or other information provided by the licensee.
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Attachment:
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Appendix l
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APPENDIX
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Midland Units 1 and 2
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'Openitems
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IE:III IE:III IE:III CP's Iden-Report Report Summary
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Rspart No.
tification Page No.
Section t
70-6 F
Summary 4'
Concrete pour location QA and QC did not
II-9-b promptly identify and correct apparent deviations from the standards.
70-6 J
Management Questionable practice of only having one Interview signature appear on QA audit forms, i.e.,
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- 7 same person requested by, audited by,
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and reviewed by.
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70-6 K
Management Incorrect concrete for=ula number on Interview concrete transit ticket - steps will be
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II-8-6 on Class I pours.
Printout malfunction.
10 & 11 II-8-d
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70-6 L
II-A-2-Special concrete testing per PSAR.
71-1 A
Management Requires adequate steps to verify the Interview integrity of existing structure before
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resuming construction.
71-2 A
II-9-b Significantsurfacedeterd.orationof
II-10 material in storage requested Bechtel's report and recommendations.
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73-3 C
AEC Letter Perform evaluation to compliance of 6-21-73 electroslag welding.
Regulatory Cuide 1.: I
Management CP will follow up on audit.
Interview
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Results of (
Inspection s
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IE:III IE:III
IE:III CP's Iden-Report Report Summary Report No.
tification Page No.
Section 73-4 C
Management Adjustment of the applicable codes in
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Interview line to 50.55(a) urgently needs attentice '
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73-6 P
QAF-7 Requirements for receiving, inspection, storing, protecting, and using of materia not included in Midland FIM.
73-11 E
9 & 11 1-b-4 QA Administrator onsite one day every
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two weeks.
74-10 B
Results of Liner plate protective coating activities Inspection review to dettraine the degree of imple-
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dur,ing subsequent inspection.
74-10 D-1
Results of Third party (2) review CP audits of Inspection contractor's performance to' date
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, B-1 Inspection of NSSS equipment interiors.
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75-01 A
B-2 Damaged spraylat.
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75-01 B
B-4 Differences between specification and
11-3 PSAR in clump requirements.
75-03 A
B Lack of control of field sketches
B-3 resulting in auxiliary building rebar
II-3 problems.
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