IR 05000518/1980026
| ML19345E708 | |
| Person / Time | |
|---|---|
| Site: | Hartsville  |
| Issue date: | 12/30/1980 |
| From: | Cantrell F, Swan W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19345E707 | List: |
| References | |
| 50-518-80-26, 50-519-80-23, 50-520-80-26, 50-521-80-22, NUDOCS 8102050642 | |
| Download: ML19345E708 (5) | |
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UNITED STATES
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g NUCLEAR REGULATORY COMMISSION
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101 MARiETTA sT., N.W., sulTE 3100
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ATL ANTA, GEORGI A 30303
- ...a Report Nos. 50-518/80-26, 50-519/80-23, 50-520/80-26, and 50-521/80-22 Licensee: Tennessee Valley Authority 500A Chestnut Street Chattanooga, TN 37401 Facility Name:
Hartsville Nuclear Plant Docket Nos. 50-518, 50-519, 50-520, and 50-521 License Nos. CPPR-150, CPPR-151, CPPR-152, and CPPR-153 Inspection at Hartsville site near Hartsville, Tennesse Inspector:
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W. B. Swan Date Signed Approved by:
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F.S!Cantrell, Sectio}nyhief,RCESBranch Date S'igned SLT!ARY Inspection for period November 1,1980 through November 28, 1980 Areas Inspected This routine, announced inspection involved 68 inspector-hours on site by the resident inspector in the areas of structural concrete; A-1 drywell penetration frames; A-1 steel containment; A-2 reactor pressure vessel pedestal; A-1 biological shield wall; pipe system supports and hangers; rock excavation for A-2 diesel generator building foundation; open items; and independent inspection ef fort.
Results Of the areas inspected, no items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensce Employees
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T.-Hathcote, Site Project Manager W. T. Quinn, Construction Engineer J. T. Dorman, Assistant Construction Engineer, Second Shif t H. S. Sheppard Asst. Construction Engineer, Quality Control K. H. Stewart, Asst. Construction Engineer, Engineering Services B. F. Huffaker, Supervisor, Materials _ QC Unit-R. C. Nixon, Supervisor, Document Control Unit F. E. Laurent, Principal Mechanical Engineer,_ STRIDE E. D. Sweeney, 'dechanical Project Engineer G. A. Gonsalves, QA Unit Supervisor A. G. Debbage, QA Audit Supervisor R. E. Young, Asst. Construction Engineer, Project Engineering T. O. Wilkenson, Supervisor, Materials Services Other licensee employees contacted included two construction foreman, four document control personnel, two engineering services personnel, -
six QC technicians, and two QA unit auditors.
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized with the Project Manager on November 7,14, 21 and 26,1980.
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Licensee Action on Previous Inspection Findings (Open) Infraction 518, 519, 520, 521/80-18-01:
Failure to Take Timely.
Corrective Action on Drawing Control Findings.
TVA is continuing spot checks'of drawings in the hands of the using depart-ments. Revision of procedures for drawing control -is underway by a. site-team,. but revisions have not been approved and implemented.
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Unresolved Items Unresolved items were not identified during this inspectio.
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Independent Inspection Effort The ~ inspector made routine surveillance tours during which the status of proj ect work was noted, and construction activities were inspected on nuclear safety related structures, systems and facilities. Inspection effort was concentrated on Plant A areas.
Follow on inspections of structural concrete were made in the' Plant A power block structures. Forming, installation of rebar' and embedments, placements and post placement curing were inspected as work progressed for A-1 fuel'
building and auxiliary building. Activities prior to placement were inspected for the A-2 fuel building, reactor shield building and auxiliary building.
Structural concrete is nearly completed in the Plant A radwaste building below the (-) 12' level.
The inspectot visually-inspected the completed concrete and found it to be acceptable.
The inspector watched the placement of concrete in.the annular space of the first third of the-vent wall in Unit A-2, and the initial' placement of concrete in the A-1 biological shield wall. In both cases, curing activities were later inspected and found to be adequate.
Installation of the layers - of heavy rebar for the base mat of the A-2
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Control Building was inspected.
In the inspection of activ.' ties for structural concrete, conformance with the requirements of C-F Braun Specification 300-01, Revision 8 " Concrete",
TVA Construction Specification G-2 and QC procedures was verified. The.
inspector verified that required preheating was being=done for welding on the A-2 reactor-pressure vessel pedestal and for welding on the lower two rings of the A-1 bological shield around the reactor vessel ~and on the third ring on the assembly pa'.
d The inspector inspected the second tensioning of the hold down bolts-fors the A-1 steel containment. This work is completed for A-1 until the contain-ment vessel has ' been completed-and the additional footing stresses have been imposed by that additional ~1oad and loads from the shield wall and auxiliary structures and equipment.
No violation or' deviations were identified.
By November 26, final-michining pass on the top bolting face of the A-2:
Reactor Pressure Vessel (RPV) Pedestal was in progress. This final pass was-
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witnessed by the, resident inspector and by'TVA's Mechanical QC. inspectors and project engineers..The Lfinal pass was designed to bring the 23 foot; 0.D. surface within ten tousands of an inch of absolute flatness and level-Placement of concrete in the annular. space'of the~ pedestal remains to ness.
be completed prior to installation of tlie RPV. LThe Lreactor pressure' vessel is scheduled tc be placed on the pedestal beginnin.g December ~ 17,1980.
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3-t The resident inspector made one inspection of excavation of rock and cleaning of rock surfaces for placement of fill concrete for the foundation of the south diesel generator bui'. ding for Unit A-2. Blasting was not being used at that time.
No violations or deviations with excavation procedure requirements were identified.
Follow on inspections were made of the installation of #18 rebar attachments
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to massive penetrations frames for the " drywall" above the vent wall foc Unit A-1, and installation activities on frame No. 7 which had been positioned in the wall. Installation of Cadweld joints on rebar connections to frames
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was being performed in accordance with TVA' Cadwelding procedures. The j
work was being monitored by TVA's civil QC inspectors, and was intermittently
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inspected by the resident inspector.
No violations or deviations with Cadwelding requirements were identified. During this period Erico advised
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Th not to use oil: soaked rags or burlap to mitigate corrosion in cartially -
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installed Cadweld sleeves due to the difficulty of ensuring clear. out when
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the joint is to be completed.
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Licensee Identified 50.55(e) item
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Previously Identified Item (Closed) 518, 519, 520, 521/79-27-05 Rebar Bending In Accordar., e with Specifications (NCR HT-C-79-04) '
The inspector verified that the licensee is obtaining approval of the-
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design agency, C. F. Braun, for proposed bending of _ rebar _ to accommcdate a
construction interferences in accordance with civil engineering proceoure, CEP 9.01, Rev 9, Attachment B.
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Inspector Followup Item (Closed) 518/80-18-02, 520/80-18-02:_ Batch Plant Back-up Measures. Regu-latory fuide 1.55 paragraph C.3.d addresses itself to the availability of proper equipment in good operating condition and in the sizes and quantities
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j needed : vibrators, chutes, etc) and to sufficient spare parts and equipment j
readily available so that loss or breakdown of equipment will not interrupt -
l the plt.cing of concrete and result in unplanned cold joints.
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The licensee's ongoing maintenance program for the batch plant and stockof
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spare parts to insure expedited repairs in the event'of breakdown serve to minimize the occurrance of unplanned cold joints.
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L Treatment of unplanned cold joints is provided for in TVA General Construction l
Specification. G-2 " Plain and. Reinforced Concrete"'.. Paragraph' 14.4
Emergency Joints, provides that 'whenever placing is -interrupted for an'-
extended time the working face 'is to be formed and finished to - provide suitable union with re-established placement. By these means'the licensee avoids. the economic burden of. maintaining an ever-ready' duplicate batch'
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Safety Related Pipe Support and Restraint Systems The licensee has installed approximately 25% of uiping over 2 inches in diameter for Unit A-1 and 14% for Unit A-2.
Most of this piping is being supported by structural steel beams and by temporary steel cable. The installation of U-clamps, hydraulic supports, spring supports and seismic restraints has not commenced.
Less than 5% of the supports, hangers and restraints needed for Plant A have been installed and less than 10% of the individual C.
R. Braun drawings which indicate the location and type for each hanger and work packages have been issued.
The inspector reviewed a sampling of the configuration centrol packages prepared for individual supports and restraints and the controlling procedure,
~ NP SOP-44 " STRIDE Component Support Program, Revision 3 supplemented by n
its referenced documents and SOP-27 "HNP ASME III PIPING PROGRAM". The inspector reviewed a computer readout of the computerized program for tracking the design; material control, fabrication, installation and inspec-tion of each of the more than 50,000 supports and " hangers". The liceusee has established a separate section of the site project engineering group for the required design effort.
Within the areas examined, no items of noncompliance or deviations were found.