IR 05000329/1980009

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Corrected Pages 1 & 3 to IE Insp Repts 50-329/80-09 & 50-330/80-10 on 800201-29
ML19310A175
Person / Time
Site: Midland
Issue date: 05/09/1980
From: Cook R, Knop R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML19310A174 List:
References
50-329-80-09, 50-329-80-9, 50-330-80-10, NUDOCS 8006060226
Download: ML19310A175 (2)


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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT

REGION III

Report Nos. 50-329/80-09; 50-330/80-10 Docket Nos. 50-329; 50-330 License Nos. CPPR-81; CPPR-82 Licensee: Consumers Power Company 1945 West Parnall Road Jackson, MI 49201 Facility Name: Midland Nuclear Power Plant, Units 1 and 2 Inspection At: Midland Site, Midland, MI Inspection Conducted: February 1-29, 19S0

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Inspector:

R. J. Cook

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Approved by:

R. C. Knop, Chief

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Projects Section No. 1 Inspection Summary Inspection on February 1-29, 1980 (Report No. 50-329/80-09; 50-330/80-10 Areas Inspected: Assembly of Unit I reactor vessel internals, settlement of diesel generator foundations and structures and associated soil settle-ment, Class 1E battery rack seismic braces, failures of Unit I reactor vessel anchor bolts, 10 CFR Part 21 notifications associated with Ruskin fire dampers and American Warming and Ventilating milliampere hydramotor actuators, NDE associated with fabrication of the borated water storage tank, and peaceful anti-nuclear demonstration conducted at the Midland Site. This inspection effort involved a total of 72 inspector-hours by one hTC inspector.

Results: One item of noncompliance (deficiency, failure to sequentially proceed the Field Construction Procedure fer trial fit-up of internal core support assembly as written) was identified in one area of the eight areas reviewed.

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wasdeterminedthatthetotallevelliftrequiremenhsof0.003inchas stated in the procedure being used (Field Construction Procedure No.

  • 132) could not physically be maintained during core support assembly lifts when the reactor vessel alignment keys were engaged. Procedure sequential work continued for the fit-up of the core support assembly without formal relief from the 0.003 inch level lift requirements re-ferenced in the procedure being used.

Response to Site Problem Report (SPR) No. 13-12-144-00, which addresses the out of alignment condition, states that the 0.005 to 0.006 inch measured alignment was acceptable.

However, this was not reflected in the procedure being used. Consumers Power Company generated Nonconformance Report No. M-03-4-0-004 which addressed the inability of maintaining the 0.003 inch levelness require-ments referenced in step 230 of Field Construction Procedure No. 132 and were continuing through step 310 pending a written response to SPR No. 13-12-144-00.

Failure to comply with Quality Control Procedure No. 9-QPP-102, Field Construction Procedures, by sequentially proceeding through Field Con-struction Procedure No. 132, Trial Fit-Up of Internals Core Support Assembly, ar written, when the re~" ements of preceding steps as written could not be met is considered au em of noncompliance with 10 CFR 50, Appendix B, Critetion V.

This item of noncompliance is identified in Appendix A (329/80-09-01).

Reportable Deficiencies 50.55(e) Items Settlement of Diesel Generator Foundations and Structures (0 pen) Item No. (329/78-13-03; 330/78-13-03): On February 27 and 28, 1980, members of the NRC and consultants to the NRC met with members of the licensee and their consultants to discuss site soil settlement and to orientate the NRC consultants. Consultants retained by the NRC were representatives of U.S. Corps of Engineers, U.S. Navy Surface Weapons Center, and Energy Technology Engineering Center. Underpinning of valve pits at the auxiliary building, installation of pile supports at the surface water building, installation of permanent dewatering system, and settlement of the diesel generator building vere discussed during the meeting. The Resident Inspector attended selected portions of these meetings.

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Class IE Batterf Racks, Seismic Braces During the report period, the Resident Inspector was informed that some of the Class IE battery racks had been modified to limit horizontal momentum during a seismic event. However, plans are in the offing to change the mounting of the Class IE battery racks. This may necessitate further seismic analysis and perhaps modifications to the racks.

Failure of Reactor Vessel Anchor Bolts I-3-