IR 05000329/1974005
| ML19329F155 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 03/13/1974 |
| From: | Rohrbacher R, Vetter W, Williams C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19329F154 | List: |
| References | |
| 50-329-74-05, 50-329-74-5, 50-330-74-05, 50-330-74-5, NUDOCS 8006200718 | |
| Download: ML19329F155 (5) | |
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[3 U. S. ATOMIC ENERGY C0!DIISSION l
DIRECTORATE OF REGULATORY OPERATIONS
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REGION I
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REPORT OF VENDOR INSPECTION
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50-330 RO VENDOR INSPECTION REPORT NO:
50-330/74-05, 50-329/74-05 DOCKET NO:
50-329
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VENDOR:
Babcock & Wilcox Company (B&W)
LICENSE NO: CPPR-82 I
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ADDRESS:
Mt Vernon, Indiana PRIORITY:
CATEGORY: A-2
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EQUIPMENT:
Pressure Vessel and Pipe LICENSEE:
Consumers Power Company CATION:
Jackson, Michigan (Midland, Units 1 and 2)
TYPE OF LICENSEE: - PWR.650 MW(e)
PWR-818 MW(e)
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TYPE OF INSPECTION:
Routine Announced DATE OF INSPECTION:
February 12-13, 1974 DATE OF PREVIOUS INSPECTION:
August 30-31, 1972
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REPORTING INSPECTOR:
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Ross L. Brown, Reactor Inspector PROJECT XMXXXEhma;A INSPECTOR 1 DATE:
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OTilER ACCOMPANYING PERSONNEL:
None
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NuL DATE:
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REVIEWED BY: _
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J! H. Tillou, Senior
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-[D SUMMARY OF' FINDINGS
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, U Enforcement Action None Licensee Action on Previously Identified Enforcement Items
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Not applicable-Design Changes
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None
, Unusual Occurrences None Other Significant Findings o
A.
Current Findings 1.
The referenced codes appear to be in compliance with the requirements of 10 CFR 50.55(a), Paragraph (j).
(Details, Paragraph 3).
2.
The unqualified weld material identified in these vessels has been removed and components re-welded.
(Details, Paragraph 4)
B.
Status "of Previously Reported Unresolved Items
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None Management Interview
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The inspector conducted a meeting with the following management i
representatives at the conclusion of the inspection:
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1.
Persons Present Consumers Power Company C.- Q. Hills, Quality Assurance Administrator
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Babcock & Wilcox Company (B&W)
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J. E. Hoke, Engineer
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R. T.. Hollander, Engineer J. L. Johnson, Quality Assurance Engineer J. F. Jaquess, Quality Assurance Engineer B.
The following items were discussed:
1.
The inspector discussed the AEC procedure-for the handling of
' inspection reports and documentation letters prior to their placement in the Public Document Room.
2.
The inspector stated that no violations were noted 'during the review of the documents relative to the removal of the identified
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unqualified weld metal in the reactor pressure vessel, steam
generators, and pressurizers.
(Details, Paragr >.ph 4)
3.
The inspector stated that the referenced codes for these components appear to be in compliance with the requirements of 10 CFR 50.55(a) Paragraph (j).
(Details, Paragraph 3)
4.
TheinspectorstatedthatnovioEationswereidentifiedduring
the audit of quality records relative to the fabrication of the primary piping components.
(Details, Paragraph 5)
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DETAILS
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1.
Persons Contacted
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Consumer Power Company C. Q. Hills, Quality Assurance Administrator Babcock & Wilcox J. L. Johnson, Quality Assurance Engineer J. F. Jaquess, Quality Assurance Engineer
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2.
General
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The vendor stat'ed that the anticipated shipping schedule for a.
the Unit 1 steam generators, pressurizers and primary piping is during the third quarter of 1974 and the reactor pressure vessel is scheduled to be shipped during the fourth quarter of 1974.
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b.
The anticipated shipping schedule for the Unit 2 primary piping,
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reactor pressure vessel and pressurizers is scheduled for the third quarter of 1975 and the two steam generators scheduled to ship during the fourth quarter of 1975.
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3.
The Referenced Codes Appear to be in Compliance with the Requirements
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of 10 CFR 50.55 (a) Paragraph- (j ).
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The vendor, documents identifies the applicable code for these components as follows:
Pressure vessels ASME Section III', 1968 Edition, including a.
Addenda Through Summer of 1968 - ASME Section IX, 1971 Edition and including Addenda Through Winter 1971 and weld metal ASME Section III, 1971 Edition and including Addenda Through Summer 1972.
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Piping - Nuclear Power Piping, USAS-B31.7, February 1968 and Errata, dated June 1958 ASME Code,Section IX, 1971 Edition and including Adi'nda Through Winter 1971, weld metal ASME Code,Section II, 1971 Edition and including Addenda through Su==er 1972.
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These applicable codes are in compliance with the codes and
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standards ' requirements since the licensee published the public
-/~'t hearing date on October 20, 1970.
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4.
The unqualified weld metal identified in these vessels has been removed and components re-welded.
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The vendor identified non-conforming weld metal in the Unit 1 reactor pressure vessel, steam' generator, pressurizers, and the
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Unit 2 reactor pressure vessel.
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The shop travelers indicated that the c~rrective action was o
accomplished as follows:
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a.
Unit 1 and 2 reactor pressure vessels, completely removed the weld metal from the seal ledge to vessel flange by machining,
acid etched the weld area to assure complete removal of weld
deposit, re-welded with acceptable weld material and qualified procedure.
b.
Unit 1 steam generator - MK. 3 shell section, four base metal
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repairs.
Boat samples were removed from each repair area, samples tested and weld metal found to be acceptable. Repairs were successfully made with acceptable material and by qualified a procedure.
Unit 1 pressurizer (1) MK2 shell section weld preparations on c.
/~'h each end of section.
Unqualified weld material was removed
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area was acid etched,' and successfully repaired, (2) MK. 4 shell section two long seam welds built up and base metal repaired.
Non-conforming material removed and areas repaired with acceptable materials and by use of qualified procedures, (3) upper head weld prep repairs.
Unqualified weld material
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removed and replaced with qualified material.
The inspector did not identify any violation to the code or specifications during this review.
5.
Record Review Unit 1 Primary Piping - The inspector audited shop travelers and qtality records selected on a random basis and reviewed in detail to ensure corMormance with the applicable codes for the fabri-cation, heat treatment, and testing of a 28 inch and 36 inch elbow.
No deficiencies were noted.
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UNITED STATES
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' ATOMIC ENERGY COMMISSION
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y DIRECTORATC OF REGULATORY CPERATIONS h,
.l f-RCGlON llt 799 ROOSEVELT ROAD g'
GLEN ELLYN. ILLENOIS 6o137 (312) 858-2660 mag l
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A.
RO. Inspection Report No.: 050-330/74-05 and 050-329/74-05 Transmittal Date
- April 9, 1974
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Distribution:
Distribution:
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-RO Chief, FS&EB RO Chief, FS&EB RO:HQ (5)
RO:HQ (4)
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DR Central Files L:D/D for Fuels & Materials
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Regulatory Standards (3)
DR Central Files
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Licensing (13)-
RO Files
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RO Files
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B.
RO Inquiry Report No.
t j ;
Transmittal Date
Distribution:
Distribution:
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RO Chief, FS&EB RO Chief, FS&EB RO:HQ (5)
RO:HQ 4-DR Central Files DR Central Files Regulatory Standards (3)
RO Files
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Licensing (13)
RO Files L
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Incident Notification From:
i (Licensee & Docke,t No. (or License No.)
Transmittal Date
-Distribution:
Distribution:
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RO Chief, FS&EB RO Chief, FS&EB
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RO:HQ (4)
R0:HQ (4)
Licensing (4)
L:D/D for Fuels & Materials DR Central Files DR Central Files
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RO Files R0 Files
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