IR 05000518/1982009

IE Insp Repts 50-518/82-09,50-519/82-08,50-520/82-09 & 50-521/82-08 on 820601-04 & 28-30.No Noncompliance Noted. Major Areas Inspected:Seismic Category 1 Concrete,Open Items & Site Deferral Preparation

ML20062H771
Person / Time
Site:	Hartsville
Issue date:	07/16/1982
From:	Cantrell F, Schapker J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20062H757	List: IR 05000518/1982009 ML20062H754
References
50-518-82-09, 50-518-82-9, 50-519-82-08, 50-519-82-8, 50-520-82-09, 50-520-82-9, 50-521-82-08, 50-521-82-8, NUDOCS 8208160161
Download: ML20062H771 (4)

Text

{{#Wiki_filter:.. . . UNITED STATES ftCJ' "f Gof NUCLEAR REGULATORY COMMisslON

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Report Nos.. 50-518/82-09, 50-519/82-08, 50-520/82-0 9 and 50-521/82-08 Licensee: Tennessee Valley Authority 500A Chestnut Street Chattanooga, Tennessee 37401 Facility Name: Hartsville Nuclear Plant t'

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Docket Nos. 50-518, 50-519, 50-520 and 50-521

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' License Nos. CPPR-150, CPPR-151, CPPR-152 and CPPR-153 Inspection at Hartsville site near Hartsville, Tennessee Inspector: Onm /A Qke [n 7/ / (,/# Z -

  , F. Schapker  b  Bate Signed Approved by: '[ 4cv[ d F.S.Cantrell,SerAippChief,Divisionof 7///-[[(2-D&te Signed Resident and Reactor Inspection r

SUMMARY Inspection on June 1-4, 28-30, 1982 Areas Inspected This routine, announced inspection involved 37 inspector-hours on site in the i areas of seismic category 1 concrete (Unit A-1), open items (all units), independent inspection effort (A-1 and A-2), and site deferral preparation (A-1 - and A-2).

Results l Of the 4 areas inspected, no violations or deviations were identifie , l l

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' B208160161 820716 E PDR ADOCK 05000518  ; G PDR 1 !  ;

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DETAILS [ j Persons Contacted Licensee Employees

i * T. Quinn, Site Construction Engineer J. W. Henry, Unit Supervisor, QC Welding H. S. Sheppard, Assistant Construction Engineer, Quality Control F. E. Laurent, Unit Supervisor, STRIDE Mechanical Project Engineering G. A. Gonsalves, QA Unit Supervisor B. F. Huffaker, Supervisor, Materials QC Unit ' Other licensee employees contacted included document control personnel, construction craftsmen, QC technicians, and project engineer * Attended exit interview The inspection scope and findings were summarized with the Site Project

! Manager /or his representative on June 4, and 30,198 . Licensee Action on Previous Inspection Findings

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, These items were not reviewe . Unresolved Items Unresolved items were not identified during this inspectio t

> Independent Inspection Effort '

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The inspector made two surveillance tours during which the status of project ! work was noted, and construction and deferal activities were inspected on : nuclear safety-related structures, systems and component " The inspections included: , Open items control: Newly issued Nonconformance Reports (NCR's), and QA unit audit findings were reviewed for pertinence to the inspection program and for adequacy of corrective actio I Preventive maintenance and protection of safety-related equipment , installed and in plant storage was observed in plant A-1 auxiliary , building, fuel building and reactor building. Observations made ; included: electrical switchgear, transformers, electrically actuated l valves and pumps. These items were observed for adequacy of protective covers, heaters installed and actuated and periodic maintenance performed in accordance with applicable specification ;.

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,. 2 The inspector observed corrosion on tne reactor vessels carbon steel nozzles interior. The corrosion was discovered as a result of a question by the inspector as to the adequacy of the nozzle cover seals - which had visually deterioated on the outside diameter. (Reference report 50-518 thru 521/82-06). The licensee stated the seals are adequate and are only deterioated on the OD. The corrosion is due to inadequate storage procedures which have been_ revise The licensee has issued a nonconformance report and is consulting with the vendor supplier to effect corrective action. The inspector will review corrective action taken and has requested notification to witncss corrosion removal and application of protective coatings if applied. This item is identified as inspector follow up item (518, 519,520,521/82-09-01) Corrosion of Reactor Vessels Within the areas inspected no violations or deviations were identifie . Licensee Identified 50.55(e) Items The following interim reports were received from the licensee on previously identified items. The inspector reviewed these reports and found that none contained information that would permit closure. Follow on reports are scheduled at later date (0 pen) 518, 520/82-07; 519, 521/82-06 Regional quality engineering branch

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inspection office manpowe Next scheduled report September 16, 198 (0 pen)518,519,520,521/80-27-01 Link rod assembly - Delaval Diesels (NCR Delaval Diesels No. 1)

-Next scheduled report indefinite due to construction deferra (0 pen) CDR 518/81-15, 519/81-11, 520/81-13, 521/81-11 Reactor core isolation cooling steam line brea Next scheduled report indefinite due to construction deferra (0 pen)CDR 518/82-08, 519/82-07, 520/82-08, 521/82-07 Check Valve Leak in air start of standby diesel generator Next scheduled report indefinite due to construction deferra . Seismic Category 1 Concrete Forming, prepouring inspection, p'acercents and post placement curing were inspected as work continued in the A plant fuel building. Specific place-ments designations AIF-111 and AIF-40E, 20H for a total of 208 cubic yards place *

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Preplacement inspection was-indicated by the properly signed pour car Placement of reinforcing steel conformed to drawing and procedure require-ments. Placement activities pertaining to delivery time, freefall, flow distance, layer thickness and consolidation vibration practices conformed to specification Samples for temperature, slump, air content, unit weight and test cylinders were made in accordance with procedure requirements. Post placement inspection observations showed proper curing was in progres During observations of activities for structural concrete in these areas, conformance with the requirements of C. F. Braun Specification 300-0, Revision 8, " Concrete", TVA Construction Specification G-2, QCI C-201, Revision 4, and CEP 9.02, Revision 5, was verified by the inspecto Within the areas inspected no deviations or violations were identifie . Review of Deferral Activitie The inspector toured the site to observe activities for preservation of material and equipment during deferral. Protective sealing of concrete rubber or polyvinyl chloride (PVC) waterstops partially embedded in concrete and installed anchor bolts is in process. The temporary containment cover has been installed on Unit A-1, the cover for unit A-2 is in the process of fabrication. Concrete slurry application to exposed rebar (12 to 24 inches) was observed on Unit A-1 containment. A quality assurance program for the deferred nuclear units has been requested by the Division of Licensing staff, and is in the process of formulation by the Licensee. }}