IR 05000518/1981010
| ML20010A478 | |
| Person / Time | |
|---|---|
| Site: | Hartsville  |
| Issue date: | 07/13/1981 |
| From: | Swan W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20010A468 | List: |
| References | |
| 50-518-81-10, 50-519-81-10, 50-520-81-10, 50-521-81-10, NUDOCS 8108110463 | |
| Download: ML20010A478 (6) | |
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UNITED STATES O
NUCLEAR REGULATORY COMMISSION
j REGION ll U
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"d 101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGI A 30303
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Report Nos. 50-518/81-10, 50-519/81-10, 50-520/81-10, and 50-521/81-10 Licensee: Tennessee Valley Authority 500A Chestnut Street Chattanooga, TN 37401 Facility Name: Ha*'sville Nuclear Plant Docket Nos. 50-518, 50-519, 50-520, and 50-521 License Nos. CPPR-150, CPPR-151, CPPR-152, and CPPR-153 Inspector: I e,IE M
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Date Signed W.'B.
Swan
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Approved by: YMN
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F. 5. CsQrell, Secti6n#ief, Division of.
Date Signed Resident and Reactor' Project Inspection SUMfiARY Inspection on June 1-30, 1981 Areas Inspected This routine inspection involved 119 resident inspector-hours on site in the areas of structural concrete; plant B extended shutdown; A-1 and A-2 steel containments; A-2 biological shield wall around RPV; A-1 drywell wall; earthwork; open items and independent inspection effort.
Results Of the eight areas inspected, no violations or deviations were identified.
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8108110463 810720 '
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DETAILS 1.
Persons Contacted Licensee Employees
- R. T. Fnthcote, Site Project Manager W. T. I Jinn, Construction Engineer; Acting Project Manager R. E. toung, Assistant Construction Engineer, Project Engineerir.g J. T Dorman, Assistant Construction Engineer, Quality Control H. S. Sheppard, Assistant Construction Engineer, Quality Control P. F. Gillespie, Supervisor, Technical Services B. F. Huffaker, Supervisor, Materials QC Unit R. C. Nixon, Supervisor, Document Control Unit F. E. Laurent, Unit Supervisor, STRIDE Mechanical Project Engineering G. A. Gonzalves, QA Unit Supervisor M. U. Rudolphi, Unit Supervisor, Project Engineering, Hangers and Supports R. E. McClure, Unit Supervisor, Mechanical Quality Control Other licensee employees contacted included document control personnel, craftsmen, QC technicians, and project engineers.
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized with the Site Project Manager on June 5, 12, 23, and 29, 1981.
3.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item 518, 519, 520, 521/80-15-04 Stainless Steel Tanks
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Left Open While in Storage Effective closures have been maintained on subject tanks. The licensee has issued Revision 1 to Receipt, Storage and Preventive Maintenance Manual, dated Apr'.i 30, 1981, Section 6KC, paragraph 2, of the Preventive Maintenance, now requires:
Weekly - Verify that all openings and/or flange faces are protected by caps, flanges, blanks, plugst or seals (secured in place), in order to prevent damage and contamination. Visually inspect for tears, breakage, or penetra tion."
During recent insections and surveillance tours, the inspector has identified no violation of these requirements.
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Unresolved Items Unresolved items were not identified during this inspection.
5.
Independent Inspection Effort The inspector made surveillance tours during which the status of project work was noted, and construction activities were inspected on nuclear safety-related structures, systems and facilities. The inspection was concentratea on Plant A power block structures, but included outlying structures such as the Plant A essential service water pump stations, earthfill for the spray ponds, the intake pumping station, and circulating cooling water pump house.
Open Site Item Control: Newly issued Nonconformance Reports (NCRs),
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I significant Quality Control Inspection Reports (QCIRs) and QA Unit audit findings were reviewed for pertinence to the inspection program and for adequacy of corrective actions.
Containment Erection: The inspector inspected fit-up of the ninth steel ring of the A-1 containment cylinder wall and the third ring of the A-2 wall. Joint tolerances were being assured by the steel strap inserts, and preheating was established for welding and weld repair. The applicable code i
i for the containment welding is the ASME Boiler and Pressure Vessel Code,Section III, Subsection NE, 1974 Edition, including Addenda through S74.
Welding joint preparation was performed by the fabricator of the preformed steel panels in conformance with the cooe requirements. Preheat adequacy was being checked by Tempstiks.
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In the areas inspected, no violations or deviations were identified.
A-2 Biologic Shield Wall:
The inspector inspected the first ring of the shield assembled on a welding jig from sections prefabricated by IEW. Welds were examined and found to be visually acceptable. The ring was ready to be removed from the jig for radiographic inspection. The controlling pro-cedures and inspection hold points are outlined in Work Package D-258-C1,
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Addendum 3, which includes weld maps, a sequence control chart and designated weld procedures. The inspector reviewed notations on Weld Map i
Sheets 1 & 2, RB-PSW-2R3 and RB-BSW-1R2.
I No violations or deviations were identified in the areas inspected.
The inspector discussed with the QA unit supervisor preliminary findings of drawings and engineering change control audit HT-G-81-14.
Drawing control appeared to be adequate, but preliminary findings indicated late processing of ECNs and FCRs (Engineering Change Notices and Field Change Requests) by the Document Control Unit and mishandling in the field stations. This matter is being followed under infraction 518, 519, 520, 521/80-18-01.
Plant B Extended Shutdown: The inspector inspected completed concrete repairs in Unit B-1 concrete containment shield building and contiguous
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structures and the nearly completed replacement of reinforced plastic coverings over installed rebars as required by Standard Operating Procedure SOP-58, Periodic Inspection of Delayed Portion of Plant B, R2, 10-14-80.
No violations or deviations were identified.
6.
Licensee Identified 50.55(e) Items a.
Previously Identified Items (0 pen) 518, 519, 520, 521/80-05-03 RPV Shield Wall Weld Deficiencies (NCR's HNPA-087, HNPA-108, HNPA-109, HNPA-115, SX-19) - TVA letters dated 3/13/80, 5/29/80, 9/24/80,12/20/80, 6/2/81 and 7/1/81. Welding deficiencies by the fabricator, Industrual Engineering Works (IEW), on the biological shield walls for Unit A-1 (lower two tiers) have been corrected by TVA.
The shield for Unit A-1 has been installed, filled with concrete and capped.
Assembly of the A-2 shield sections is under way at a site shop under the controls of Work Package 0-258-C1.
IEW weld defects on the first tier for A-2 shield were corrected by TVA, and repairs are nearing completion on the second tier. The operations check lists (Attachment A to CEP.9. 08) noted the welds to be repaired.
The repair procedure and the NDE test or tests for acceptance of the repair were noted at each point on the weld map, Attachment B of CEP.9.08.
IEW completed weld repairs on the upper two tiers of the A-1 and A-2 shields and all of the B-1 shield before the hardware was released for shipment. The inspector nade periodic inspections of the site repair work and reviewed completed NCR's HHPA-087, R2; HNPA-109, R2; and HNPA-115 which detailed the repair work to be performed on Unit A-1 shield sections and partially completed NCR HNPA-108 for A-2 shield repairs.
In the areas inspected no violations or deviations were identified.
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Newly Identified Items (0 pen) 518/81-10-01 Unfused Material In Drywell Vent Structure Frame No. 7 Closure Plate Weld-HTR0-50-518/81-10 - TVA letter dated 6/2/81.
Vendor weld was partially severed by TVA thermal cutting operation, leaving unfused material.
The TVA letter states that repair and other l
corrective actions "will be complete by July 1,1981".
(0 pen) 518, 519, 520, 521/81-10-02 Inconsistent Establishment of Inspection Program - HTP0-50-518/81-12, 519, 520, 521/81-10 -TVA letters dated 4/23/81 and 6/9/81 OEDC QA Program Requirements Manual (PRM) requires that ENDES supply inspection requirements to co,nstruction ENDES has failed to develop a comprehensive, documented progrsm to implement the PRM requirement and has failed ~to consistently supply inspection requirements to constructio.
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The licensee's second interim report states that: applicability of a program to be developed and tested at Watts Bar will be addressed following completion of the Watts Bar program.
TVA is to submit another report by Decembt
., 1981.
(0 pen) 518, 520/81-10-03 Review of Purchasa Request Forms Initiated by Construction - HTRD-50-518/81-14, 520/81-12 -TVA letter dated 6/19/81 Purchase forms initiated by construction have not been reviewed and completed by ENDES as required by CEP 4.01.
All previously initiated forms are to be reviewed for negative QA impact.
Followup licensee report is scheduled for August 28, 1981.
(0 pen) 518, 520/81-10-04 Drywell Framed Embedments - QA Documentation -
HTRD-50-518/81-13, 520/81-11 - TVA letter dated 6/17/81. Q screpancies were found by TVA in QA documentation supplied by Atlas Machine and Iron Works pertaining to.amed embedments. TVA is in process of evaluating and resolving discrepancies in the data packages, and is to file a progress report by October 30, 1981.
7.
Seismic Category I Concrete Forming, installation of rebar, positioning of embedments, placements and post placement curing were inspected as work progressed in the Plant A containments, fuel buildings, auxiliary buildings, control buildings, and essential service water pump houses.
Specific placements inspected included pour AIR-23A 300 cubic yards in a 210 segment of the A-1 drywell wall; pour A2D-IA & IB 1,259 cubic yards for lower section of the foundation of diesel generator building DG Division 2-1; AIR-2NB in the 14th ring of the A-1 containment shield building wall; and A2KESW V/1 for the foundation of the valving building for essatial service water on the westerly outboard slope of the A-2 spray pond. Additional inspections were made of installations of rebar for the foundations and sump areas of emergency diesel generator building DG Div.1-1 at the south side of Unit A-1.
During inspection of activities for structural concrete in these areas, the conformance with the requirements of C. F. Braun Specifkation 300-01, Revision 8 " Concrete", TVA Construction Specification G-2, QCI C-201, Rev.
4, and CEP 9.02, Revision 5, was verified by the inspector.
In the areas inspected, no violations or deviations were identified.
8.
Earthfill and Compaction For Plant A Spray Ponds Placement and compaction of earth fill for the peripheral dikes around the spray ponds is controlled by Specification N6C-875 Earth and Rock Founda-tions and Fills. By surveillance inspections of earth fill operations, inspection of soil compaction test No. 345 at Coordinates N1+77, W71+04, elevation 5336 feet northeast of A-1 spray pond, and by review of calcula-tions for this and other tests, the inspector verified compliance with
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Specification N6C-875 and with quality control procedure QCI C-102, Foundation and Fill, Earthfill Control Testing.
In the areas inspected, no violations or deviations were identified.
9.
Status of IE Circulars (0 pen) 81-08 Foundation Materials At the Hartsville site, the base mats of the nuclear island structures are founded on thick limestone rock substrata; except that control building A-1 has a #1032 crushed rock compacted fill between the focadation rock and the base mat. No settling of these nuclear island structures, or of the site pump stations is postulated.
Fill concrete was used under the electrical vault and large valve complex building for the Plant A essential service water system west of the A-2 spray pond.
Plant B structure work is under extended shutdown status.
The compacted earth fill for the A-1 and A-2 spray ponds is being constructed using a variety of soils and procured from nearby farms. These materials are selected and tested individually for their compactability.
The inspector has inspected placement and testing in several areas. This circular will be kept open pending additional inspections.
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