ML19319C783
| ML19319C783 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Crystal River, Zion  |
| Issue date: | 04/20/1971 |
| From: | Oller R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Vetter W US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML19319C775 | List: |
| References | |
| NUDOCS 8003040743 | |
| Download: ML19319C783 (3) | |
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'.l ATOMIC ENERGY COMMISSION DIVISION OF COMPLIANCE RcGION lli 799 ROOSEVELT ROAD gang GLEN ELLYN. ILLINOIS 60137 em ess-zsso April 20, 1971 W. E. Vetter, Senior Reactor Inspector VENDOR INSPECTION REPORT - BACKBOCK & WILCOX COMPANY, MT. VERNON, INDIANA REACTOR PMSSURE VESSELS FOR CRYSTAL RIVER 3 (DOCKET NO. 50-203),
OCONEE 3 ' DOCKET No. 50-287), AND ZION 1 (DOCKET NO. 50-295)
Attached.s a report of an announced vendor inspection of the B&W plant at Mt. Vernon, Indiana, with regard to the reactor pressure vessels (LPV) for Crystal River 3 (CR-3), Oconee 3 (0-3), and Zion 1 (Z,1) nuclear facilities.
A review of docu=entation and work revealed that the 0-3 RPV is complete and schedule'd for hydrostatic test on April 5,1971.
No items of code nonconformance were observed.
A review of docu=entation anS work revealed that the 0-3 RPV is in q
an advanced stage of completion. Two possible ite=s of nonconformance (V) with the ASME Code Section III requirements #ere observed.
Itecs of nonconformance were the occurrence of errors and omissions in the reported specimen heat treatment data reported by the forging supplier, Klockner-Werke, A. G., for the reactor vessel and closure head flanges and lower torus ring.
In addition, the heat treatment data reported for forging specimens, supplied by Rotterdam Dockyard (RDM) for two shell ring forgings, was found unclear and confusing with respect to precise code conformance.
Moreover, indications were that the heat treatment data had not been reviewed by B&W, Mt. Vernon personnel for either Klockner-Werke or RDM.
The' above discrepancies appear to be in nonconformance with Paragraph IX-22F.a) of the ASME Code,,Section III.
The second, a Code violation of Paragraph IX-333(b), ASME Section 1
III, was the incorrect use of penetrameters during radiography of the weld joining the rec 1rculation inlet nozzle to the shell.
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W. E. Vetter April 20, 1971 A draf t (.DN has been prepared covering the above items, for review and consideration by Region II prior to issuance to Duke Power Company.
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A final review of the Zion I RPV shop hydrostatic test data and
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post-hydro NDT inspection with regard to the repair of the lower head circle weld, established that the RPV passed the second shop hydrostatic test in accordance with Article 7, ASME Section III.
The weld repair was confirmed to have been completed in accordanc2 with Paragraph N-528,Section III, ASME Code.
Limited information was available from B&W regarding RPV pressure boundary welds untrasonic tested at Mt.
no information was yet available on weldsVernon and practically in other.yV's, using a' cobalt 60 source. previously radiographed, It appears that this subject will have to be pursued further, on an individual basis, with B&W, Westinghous,e, and General Electric.
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Robert E. Oller 1
Metallurgical Engineer 1
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Babcock & Wilcox Company, Mt. Vernon, Indiana - CO inspection was performed on March 30 through April 2 to examine the fabrication of reactor pressure vessels for the Crystal River 3, oconee 3 and Zion 1 facilities.
Final repairs and testing of the Zion 1 reactor vessel were found to be in accordance with ASME Section III code requirements (February Monthly
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Fabrication of the Crystal River vessel was complete and hydrostatic testing was scheduled for April 5 It was found that B&W had utilized European supplied parts for the Oconee 3 vessel.
Two items of nonconformance relating to radiography and record irregularities were identified.
These items are currently being reviewed by Compliance.
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